IAEA Safety Standards

Environmental andSource Monitoring forPurposes of RadiationProtection

for protecting people and the environment

No. RS-G-1.8Safety Guide

IAEA SAFETY RELATED PUBLICATIONS

IAEA SAFETY STANDARDS

Under the terms of Article III of its Statute, the IAEA is authorized to establish or adopt standards of safety for protection of health and minimization of danger to life and property, and to provide for the application of these standards.

The publications by means of which the IAEA establishes standards are issued in the IAEA Safety Standards Series. This series covers nuclear safety, radiation safety, transport safety and waste safety, and also general safety (i.e. all these areas of safety). The publication categories in the series are Safety Fundamentals, Safety Requirementsand Safety Guides.

Safety standards are coded according to their coverage: nuclear safety (NS), radiation safety (RS), transport safety (TS), waste safety (WS) and general safety (GS).

Information on the IAEAs safety standards programme is available at the IAEA Internet site

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

The site provides the texts in English of published and draft safety standards. The texts of safety standards issued in Arabic, Chinese, French, Russian and Spanish, the IAEA Safety Glossary and a status report for safety standards under development are also available. For further information, please contact the IAEA at P.O. Box 100, A-1400 Vienna, Austria.

All users of IAEA safety standards are invited to inform the IAEA of experience in their use (e.g. as a basis for national regulations, for safety reviews and for training courses) for the purpose of ensuring that they continue to meet users needs. Information may be provided via the IAEA Internet site or by post, as above, or by e-mail to Official.Mail@iaea.org.

OTHER SAFETY RELATED PUBLICATIONS

The IAEA provides for the application of the standards and, under the terms of Articles III and VIII.C of its Statute, makes available and fosters the exchange of information relating to peaceful nuclear activities and serves as an intermediary among its Member States for this purpose.

Reports on safety and protection in nuclear activities are issued in other publications series, in particular the Safety Reports Series. Safety Reports provide practical examples and detailed methods that can be used in support of the safety standards. Other IAEA series of safety related publications are the Provision for the Application of Safety Standards Series, the Radiological Assessment Reports Series and the International Nuclear Safety Groups INSAG Series. The IAEA also issues reports on radiological accidents and other special publications.

Safety related publications are also issued in the Technical Reports Series, the IAEA-TECDOC Series, the Training Course Series and the IAEA Services Series, and as Practical Radiation Safety Manuals and Practical Radiation Technical Manuals. Security related publications are issued in the IAEA Nuclear Security Series.

ENVIRONMENTAL AND SOURCE

MONITORING FOR PURPOSES OF RADIATION PROTECTION

Safety standards survey

The IAEA welcomes your response. Please see: http://www-ns.iaea.org/standards/feedback.htm

The following States are Members of the International Atomic Energy Agency:

The Agencthe IAEA held atThe Headquartersenlarge the contrib

AFGHANISTANALBANIAALGERIAANGOLAARGENTINAARMENIAAUSTRALIAAUSTRIAAZERBAIJANBANGLADESHBELARUSBELGIUMBENINBOLIVIABOSNIA AND HERBOTSWANABRAZILBULGARIABURKINA FASOCAMEROONCANADACENTRAL AFRICA REPUBLICCHILECHINACOLOMBIACOSTA RICACTE DIVOIRECROATIACUBACYPRUSCZECH REPUBLICDEMOCRATIC RE OF THE CONGODENMARKDOMINICAN REPECUADOREGYPTEL SALVADORERITREAESTONIAETHIOPIAFINLANDFRANCEGABONGEORGIAGERMANYGHANA

GREECEGUATEMALAHAITIHOLY SEEHONDURASHUNGARYICELANDINDIAINDONESIAIRAN, ISLAMIC REPUBLIC OF IRAQIRELANDISRAEL

PAKISTANPANAMAPARAGUAYPERUPHILIPPINESPOLANDPORTUGALQATARREPUBLIC OF MOLDOVAROMANIARUSSIAN FEDERATIONSAUDI ARABIASENEGALys Statute was approved on 23 October 1956 by the Conference on the Statute of United Nations Headquarters, New York; it entered into force on 29 July 1957. of the Agency are situated in Vienna. Its principal objective is to accelerate and ution of atomic energy to peace, health and prosperity throughout the world.

ZEGOVINA

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PUBLIC

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ITALYJAMAICAJAPANJORDANKAZAKHSTANKENYAKOREA, REPUBLIC OFKUWAITKYRGYZSTANLATVIALEBANONLIBERIALIBYAN ARAB JAMAHIRIYALIECHTENSTEINLITHUANIALUXEMBOURGMADAGASCARMALAYSIAMALIMALTAMARSHALL ISLANDSMAURITANIAMAURITIUSMEXICOMONACOMONGOLIAMOROCCOMYANMARNAMIBIANETHERLANDSNEW ZEALANDNICARAGUANIGERNIGERIANORWAY

SERBIA AND MONTENEGROSEYCHELLESSIERRA LEONESINGAPORESLOVAKIASLOVENIASOUTH AFRICASPAINSRI LANKASUDANSWEDENSWITZERLANDSYRIAN ARAB REPUBLICTAJIKISTANTHAILANDTHE FORMER YUGOSLAV REPUBLIC OF MACEDONIATUNISIATURKEYUGANDAUKRAINEUNITED ARAB EMIRATESUNITED KINGDOM OF GREAT BRITAIN AND NORTHERN IRELANDUNITED REPUBLIC OF TANZANIAUNITED STATES OF AMERICAURUGUAYUZBEKISTANVENEZUELAVIETNAMYEMENZAMBIAZIMBABWE

ENVIRMONOF R

IN

IAEA SAFETY STANDARDS SERIES No. RS-G-1.8ONMENTAL AND SOURCE ITORING FOR PURPOSES ADIATION PROTECTION

SAFETY GUIDE

TERNATIONAL ATOMIC ENERGY AGENCY

VIENNA, 2005

IAEA

EnvirpA

nSII

1I. InRS

IAE

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p. ; 24 cm. (IAEA Safety standards series, ISSN 1020525X ; o. RS-G-1.8)TI/PUB/1216SBN 9201134045ncludes bibliographical references.

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FOREWORD

by Mohamed ElBaradeiDirector General

The IAEAs Statute authorizes the Agency to establish safety standards to protect healthe IAEA musof its regulatorbody of safetassistance in tregime.

In the mprogramme wasystematic appstandards thatMember Statethe IAEA is wstandards.

Safety stain practice. Tengineering sato regulatory States in applyservices enablMember State

Regulatinmany Memberuse in their nainternational smeans of ensurThe standardsaround the womedicine, indu

The IAEeverywhere: thmaterials and for the benefiIAEA safety sth and minimize danger to life and property standards which t use in its own operations, and which a State can apply by means y provisions for nuclear and radiation safety. A comprehensive

y standards under regular review, together with the IAEAs heir application, has become a key element in a global safety

id-1990s, a major overhaul of the IAEAs safety standards s initiated, with a revised oversight committee structure and a roach to updating the entire corpus of standards. The new

have resulted are of a high calibre and reflect best practices in s. With the assistance of the Commission on Safety Standards, orking to promote the global acceptance and use of its safety

ndards are only effective, however, if they are properly applied he IAEAs safety services which range in scope from fety, operational safety, and radiation, transport and waste safety matters and safety culture in organizations assist Member ing the standards and appraise their effectiveness. These safety e valuable insights to be shared and I continue to urge all s to make use of them.g nuclear and radiation safety is a national responsibility, and States have decided to adopt the IAEAs safety standards for tional regulations. For the Contracting Parties to the various

afety conventions, IAEA standards provide a consistent, reliable ing the effective fulfilment of obligations under the conventions. are also applied by designers, manufacturers and operators rld to enhance nuclear and radiation safety in power generation, stry, agriculture, research and education.A takes seriously the enduring challenge for users and regulators at of ensuring a high level of safety in the use of nuclear

radiation sources around the world. Their continuing utilization t of humankind must be managed in a safe manner, and the tandards are designed to facilitate the achievement of that goal.

BLAN

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IAEA SAFETY STANDARDS

SAFETY THROUGH INTERNATIONAL STANDARDS

While safety is a national responsibility, international standards and approaches to safety promote consistency, help to provide assurance that nuclear and radiation related technologies are used safely, and facilitate international technical coope

The standobligations. Onactivities that Contracting Stinternationallydemonstrate th

THE IAEA ST

The IAEwhich authorizradiation relate

The safeta high level of s

They arecategories:

Safety FundamPresentin

and provi

Safety RequireEstablish

people anwhich areconcepts measuresSafety Rincorpora

Safety GuidesProviding

Safety Rexpressedstated orinternatioration and trade.ards also provide support for States in meeting their international e general international obligation is that a State must not pursue cause damage in another State. More specific obligations on ates are set out in international safety related conventions. The agreed IAEA safety standards provide the basis for States to at they are meeting these obligations.

ANDARDS

A safety standards have a status derived from the IAEAs Statute, es the Agency to establish standards of safety for nuclear and d facilities and activities and to provide for their application.y standards reflect an international consensus on what constitutes afety for protecting people and the environment. issued in the IAEA Safety Standards Series, which has three

entalsg the objectives, concepts and principles of protection and safety ding the basis for the safety requirements.

mentsing the requirements that must be met to ensure the protection of d the environment, both now and in the future. The requirements, expressed as shall statements, are governed by the objectives, and principles of the Safety Fundamentals. If they are not met, must be taken to reach or restore the required level of safety. The equirements use regulatory language to enable them to be ted into national laws and regulations.

recommendations and guidance on how to comply with the equirements. Recommendations in the Safety Guides are as should statements. It is recommended to take the measures equivalent alternative measures. The Safety Guides present nal good practices and increasingly they reflect best practices to

help users striving to achieve high levels of safety. Each Safety Requirements publication is supplemented by a number of Safety Guides, which can be used in developing national regulatory guides.

The IAEA safety standards need to be complemented by industry standards and must be implemented within appropriate national regulatory infrastructures to be fully effective. The IAEA produces a wide range of technical publications to help States in d

MAIN USERS

As well aand agencies, ththe nuclear indand radiation rof various typematerial in mengineers, scieby the IAEA itcourses.

DEVELOPME

The prepSecretariat andsafety (NUSSC(WASSC) andCommission ostandards progsafety standardmembership ofgovernment of

For Safetthe Commissiofor publicationGeneral.

Through the IAEAs MCommittee onrecommendatioCommission odeveloping theother bodies inthe Food and Aeveloping these national standards and infrastructures.

OF THE STANDARDS

s by regulatory bodies and governmental departments, authorities e standards are used by authorities and operating organizations in

ustry; by organizations that design, manufacture and apply nuclear elated technologies, including operating organizations of facilities s; by users and others involved with radiation and radioactive

edicine, industry, agriculture, research and education; and by ntists, technicians and other specialists. The standards are used self in its safety reviews and for developing education and training

NT PROCESS FOR THE STANDARDS

aration and review of safety standards involves the IAEA four safety standards committees for safety in the areas of nuclear ), radiation safety (RASSC), the safety of radioactive waste

the safe transport of radioactive material (TRANSSC), and a n Safety Standards (CSS), which oversees the entire safety ramme. All IAEA Member States may nominate experts for the s committees and may provide comments on draft standards. The the CSS is appointed by the Director General and includes senior ficials having responsibility for establishing national standards.y Fundamentals and Safety Requirements, the drafts endorsed by n are submitted to the IAEA Board of Governors for approval . Safety Guides are published on the approval of the Director

this process the standards come to represent a consensus view of ember States. The findings of the United Nations Scientific the Effects of Atomic Radiation (UNSCEAR) and the ns of international expert bodies, notably the International

n Radiological Protection (ICRP), are taken into account in standards. Some standards are developed in cooperation with the United Nations system or other specialized agencies, including

griculture Organization of the United Nations, the International

Labour OrganHealth Organiz

The safetare reviewed to

APPLICATIO

The IAErelation to its othe IAEA. Aconcerning anrequirements oagreement.

Internatiosafety standardFundamentals Nuclear SafetManagement a

Outline and work plan prepared by the Secretariat;

review by the safety standards committees and the CSS

The proceization, the OECD Nuclear Energy Agency, the Pan American ation and the World Health Organization.y standards are kept up to date: five years after publication they determine whether revision is necessary.

N AND SCOPE OF THE STANDARDS

A Statute makes the safety standards binding on the IAEA in wn operations and on States in relation to operations assisted by

ny State wishing to enter into an agreement with the IAEA y form of Agency assistance is required to comply with the f the safety standards that pertain to the activities covered by the

nal conventions also contain similar requirements to those in the s, and make them binding on contracting parties. The Safety

were used as the basis for the development of the Convention on y and the Joint Convention on the Safety of Spent Fuel nd on the Safety of Radioactive Waste Management. The Safety

Secretariat and consultants: drafting of new or revision of existing safety standard

Review by safety standards

committee(s)

Endorsement by the CSS

Draft

Draft

Final draft

Comments

Member States

ss for developing a new safety standard or revising an existing one.

Requirements on Preparedness and Response for a Nuclear or Radiological Emergency reflect the obligations on States under the Convention on Early Notification of a Nuclear Accident and the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency.

The safety standards, incorporated into national legislation and regulations and supplemented by international conventions and detailed national requirements, establish a basis for protecting people and the environment. However, thereby case at thparticularly thoapply primarirecommendatioat some facilitiare to be applie

INTERPRETA

The safeconsensus requnot addressed tor parties shoexpressed as snecessary to measures) for c

Safety reGlossary (htwords are usededition of The of the text is th

The backSeries and itsIntroduction, o

Material material that isof statements iprocedures or l

An appestandard. MateIAEA assumeincluded, are uexplanation. Apublished by tpublished in sannexes. Extranecessary to be will also be special aspects of safety that need to be assessed case e national level. For example, many of the safety standards, se addressing planning or design aspects of safety, are intended to ly to new facilities and activities. The requirements and ns specified in the IAEA safety standards might not be fully met

es built to earlier standards. The way in which the safety standards d to such facilities is a decision for individual States.

TION OF THE TEXT

ty standards use the form shall in establishing international irements, responsibilities and obligations. Many requirements are o a specific party, the implication being that the appropriate party uld be responsible for fulfilling them. Recommendations are hould statements, indicating an international consensus that it is take the measures recommended (or equivalent alternative omplying with the requirements.lated terms are to be interpreted as stated in the IAEA Safety tp://www-ns.iaea.org/standards/safety-glossary.htm). Otherwise, with the spellings and meanings assigned to them in the latest

Concise Oxford Dictionary. For Safety Guides, the English version e authoritative version.ground and context of each standard within the Safety Standards objective, scope and structure are explained in Section 1, f each publication.for which there is no appropriate place in the main text (e.g. subsidiary to or separate from the main text, is included in support n the main text, or describes methods of calculation, experimental imits and conditions) may be presented in appendices or annexes.ndix, if included, is considered to form an integral part of the rial in an appendix has the same status as the main text and the s authorship of it. Annexes and footnotes to the main text, if sed to provide practical examples or additional information or n annex is not an integral part of the main text. Annex material he IAEA is not necessarily issued under its authorship; material tandards that is under other authorship may be presented in neous material presented in annexes is excerpted and adapted as generally useful.

CONTENTS

1. INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1

Background (1.11.6). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1Objective (1.71.9) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3Scope (1.Structure

2. MEETINMONITO

Legal conGeneral

3. RESPON

ResponsiResponsiResponsiReportin

4. GENER

General Human eExposureTypes of

5. PROGRAND IN

General MonitoriMonitoriMonitori

exposuSupporti101.15) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 (1.16) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5

G REGULATORY REQUIREMENTS FOR RING IN PRACTICES AND INTERVENTIONS . . . . . 5

text (2.12.8) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5conditions for monitoring (2.92.24) . . . . . . . . . . . . . . . . . . . 9

SIBILITIES FOR MONITORING . . . . . . . . . . . . . . . . . . . 14

bilities of the operator (3.13.3) . . . . . . . . . . . . . . . . . . . . . . . 14bilities of the regulatory body (3.43.7). . . . . . . . . . . . . . . . . 15bilities of other agencies (3.83.11) . . . . . . . . . . . . . . . . . . . . 16g of monitoring results (3.123.18) . . . . . . . . . . . . . . . . . . . . . 18

IC ASPECTS OF MONITORING PROGRAMMES . . . . 20

(4.14.3) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20xposure pathways (4.44.11) . . . . . . . . . . . . . . . . . . . . . . . . . . 21 groups (4.124.17). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 24radiation monitoring (4.184.31) . . . . . . . . . . . . . . . . . . . . . . 25

AMMES FOR MONITORING IN PRACTICES TERVENTIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 29

(5.15.4) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 29ng of radioactive discharges within practices (5.55.63) . . . 30ng in emergency exposure situations (5.645.117) . . . . . . . . 47ng in situations of chronic (prolonged) re (5.185.132). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 59ng monitoring programmes (5.1335.138) . . . . . . . . . . . . . . . 62

6. TECHNICAL CONDITIONS FOR MONITORING PROCEDURES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 64

Sampling strategy (6.16.22) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 64Strategy for measurements (6.236.29) . . . . . . . . . . . . . . . . . . . . . . . . . 71Uncertainties in monitoring data (6.306.35) . . . . . . . . . . . . . . . . . . . . 75

7. CONSID

General AssessmeDose asseDose asse

exposuUncertai

8. INTERP

General Complian

for pubAssessme

of emeAssessme

(prolon

9. QUALIT

Quality aQuality a

10. RECOR

RecordinRetentio

11. EDUCA

REFERENCEGLOSSARY ERATIONS IN DOSE ASSESSMENT . . . . . . . . . . . . . . . 76

concepts (7.17.6) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 76nt of doses from normal discharges (7.77.16). . . . . . . . . . . 77ssment in emergencies (7.177.27) . . . . . . . . . . . . . . . . . . . . . 80ssment for situations of chronic (prolonged)

re (7.287.46) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 83nties in dose assessments (7.477.55) . . . . . . . . . . . . . . . . . . . 87

RETATION OF MONITORING RESULTS . . . . . . . . . . . 89

considerations (8.18.12) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 89ce within practices with reference levels and criteria lic exposure (8.138.26) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 92nt of protective actions in situations

rgency exposure (8.278.45) . . . . . . . . . . . . . . . . . . . . . . . . . . 95nt of remedial actions in situations of chronic ged) exposure (8.468.54) . . . . . . . . . . . . . . . . . . . . . . . . . . . . 100

Y ASSURANCE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 102

ssurance for monitoring (9.19.5). . . . . . . . . . . . . . . . . . . . . . 102ssurance for dose assessment (9.69.7). . . . . . . . . . . . . . . . . 103

DING OF RESULTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 104

g monitoring data (10.110.11) . . . . . . . . . . . . . . . . . . . . . . . . 104n of records (10.12) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 106

TION AND TRAINING (11.111.4) . . . . . . . . . . . . . . . . . . 107

S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 108. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 111

CONTRIBUTORS TO DRAFTING AND REVIEW . . . . . . . . . . . . . . . . 116BODIES FOR THE ENDORSEMENT

OF IAEA SAFETY STANDARDS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 117

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1. INTRODUCTION

BACKGROUND

1.1. The controlled release of radionuclides to the atmospheric and aquatic environments is a legitimate waste management practice in the nuclear industry and itand particulatalthough for sworking hoodvia pipelines inormal sewer element in thesource of the protection of t

1.2. The uncoterrestrial envaccident. Mondirect monitornecessary for tlonger term coprotection. Inhistorically confor the protect

1.3. In 1995, Principles of Rconcepts and othe environmelead to adversterm and in the1

s related facilities [1]. Typically, controlled discharges of gaseous e material containing radionuclides are made through stacks, mall facilities they may be made through discharge vents or

s, for example. Controlled liquid discharges are typically made nto rivers, lakes or the sea, but they may also be made via the systems from small establishments. An important and essential control of the discharges is regular monitoring both at the discharge and in the receiving environment to ensure the he public and the environment.

ntrolled release of radionuclides to the atmospheric, aquatic and ironments may occur as a result of a nuclear or radiological itoring of the accidental release at its source, and especially the ing of the environmental contamination with radionuclides, is he assessment and execution of actions for public protection and untermeasures as well as of emergency occupational radiation

such cases individual monitoring may be justified. In areas taminated with long lived radionuclides, monitoring is essential

ion of the public and as a basis for restoration activities.

the IAEA published a Safety Fundamentals publication on The adioactive Waste Management [1]. This establishes principles, bjectives for measures for the protection of human health and nt, since the improper management of radioactive waste could e effects on human health or the environment both in the short future.

21.4. In 1996, the IAEA, jointly with five other international sponsoring organizations,1 published the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (hereinafter referred to as the Basic Safety Standards (BSS)) [2]. The BSS establish the requirements for protection against the risks associated with exposure to ionizing radiation and, in particular, they establish requirements for radiation monitoring in the context of discharge control to check for compliance westimation ofrequirements fconditions, whpublication [3]

1.5. The safetwaste, includinsafety standarRadioactive Wpurpose of dem

1.6. This SafeRefs [25]. ItCommission o[6]. It accompDischarges toconsiderationsfor the dischartwo earlier Saf

1 The fivOrganization of(ILO), the NucleDevelopment (OWorld Health O

2 INTERof EnvironmentNo. 41, IAEA, Vfrom Nuclear Faith the authorized limits on discharges and to permit the the exposure of critical groups. The BSS also establish or radiation monitoring and assessment in emergency exposure ich are elaborated on in a separate Safety Requirements

.

y requirements for the predisposal management of radioactive g the discharge of radionuclides, are established in another

d [4]. The Safety Requirements on Near Surface Disposal of aste [5] include requirements for radiation monitoring for the onstrating compliance with safety standards.

ty Guide elaborates on relevant requirements established in also takes account of the guidance of the International n Radiological Protection on the issue of radiation monitoring anies the Safety Guide on Regulatory Control of Radioactive the Environment [7], which is mainly concerned with the and the procedures to be followed in establishing authorizations ge of radioactive material. The present Safety Guide supersedes ety Guides.2

e other sponsoring organizations were the Food and Agriculture the United Nations (FAO), the International Labour Organisation ar Energy Agency of the Organisation for Economic Co-operation and ECD/NEA), the Pan American Health Organization (PAHO) and the

rganization (WHO).NATIONAL ATOMIC ENERGY AGENCY, Objectives and Design al Monitoring Programmes for Radioactive Contaminants, Safety Series ienna (1975); Monitoring of Airborne and Liquid Radioactive Releases cilities to the Environment, Safety Series No. 46, IAEA, Vienna (1978).

OBJECTIVE

1.7. The purpose of this Safety Guide is to provide international guidance, coherent with contemporary radiation protection principles and accounting for experience gained since the previous publication of guidance (see footnote 2), on the strategy of monitoring in relation to: (a) the control of radionuclide discharges under the conditions of practices, and (b) situations requiring intervention, contaminationmonitoring ar(hereinafter c(environment(individual mo

1.8. The Safedoses to criticmaterial or dufrom the normfrom a nuclearwith long livedthe results ofmonitoring or

1.9. This Safebodies that havany practice imonitoring pronational systeminstallations anare treated and

3 In the cthe public againapplied to radiousual terminologhalf-lives of 10003

such as a nuclear or radiological emergency or the past of areas with long lived radionuclides.3 Three categories of e discussed: monitoring at the source of the discharge alled source monitoring), monitoring in the environment al monitoring) and monitoring of individual exposure nitoring).

ty Guide also provides general guidance on the assessment of the al groups of the population due to the presence of radioactive e to radiation fields in the environment, which may arise both al operation of nuclear and other related facilities (practices) or or radiological emergency or the past contamination of areas radionuclides (interventions). The dose assessment is based on source monitoring, environmental monitoring or individual on combinations of these.

ty Guide is primarily intended for use by national regulatory e responsibilities for regulating the introduction and conduct of nvolving sources of radiation and for appropriate radiation cedures. It will also be valuable to other agencies involved in s for radiation monitoring as well as to operators of nuclear

d other facilities in which natural or human made radionuclides monitored.

ontext of this Safety Guide, which concerns the radiation protection of st both present and future exposure, the term long lived radionuclide is nuclides with half-lives of 30 years or more (e.g. 137Cs), in contrast to the y in waste safety, where this term is usually used for radionuclides with years or more.

4SCOPE

1.10. This Safety Guide is primarily concerned with source monitoring and environmental monitoring of discharges from authorized (registered or licensed) practices under normal operating conditions and during the decommissioning of facilities. The practices considered in this Safety Guide include the operation of nuclear power plants and research reactors, reprocessing pmining and mwaste, and faciare used (med

1.11. The guidwaste emplacesites) or near sand for borehoand specificallwould not be e

1.12. General accident are almonitoring du

1.13. This Safelived radionucaccident, or asthe content oespecially in fo

1.14. This Safeworkplace, althoccupational p

4 The refTechniques andAccident in a Na Radioactive MIAEA, Vienna (Radioactive MaNo. 91, IAEA, Vlants and nuclear fuel production plants, uranium and thorium illing facilities, near surface disposal facilities for radioactive lities of other types where natural or human made radionuclides ical, radiopharmaceutical, research, educational and others).

ance presented here applies for planning monitoring during ment in surface (uranium and thorium ore mining and milling urface (for low and intermediate level waste) disposal facilities le and deep underground (geological) waste disposal facilities,

y for post-closure monitoring although radionuclide releases xpected from such facilities under normal circumstances.

issues of emergency monitoring in the aftermath of a radiation so considered in this publication. More detailed information on ring emergencies is presented in Refs [812].4

ty Guide also addresses general aspects of monitoring for long lides widely dispersed in the environment following a radiation residual waste from past practices. This includes monitoring of f natural and human made radionuclides in commodities, odstuffs and drinking water.

ty Guide does not address the monitoring of workers and the ough its recommendations and guidance may be useful for the rotection of emergency workers in the event of an accident

erences cited supersede the following IAEA safety standards: Decision Making in the Assessment of Off-site Consequences of an uclear Facility, Safety Series No. 86, IAEA, Vienna (1987); Response to aterials Release Having a Transboundary Impact, Safety Series No. 94, 1989); Emergency Planning and Preparedness for Accidents Involving

terials Used in Medicine, Industry, Research and Teaching, Safety Series ienna (1989).

accompanied by the release of radionuclides to the environment. More detailed guidance on the occupational monitoring of workers and the workplace is provided in Refs [1316]. Neither does the Safety Guide address monitoring for research purposes, which is not for the purposes of radiation protection, or monitoring of the global fallout of radionuclides released during past nuclear weapon tests, which are unamenable to control.

1.15. A generathe presence oSafety Guide,However, operto combine che

STRUCTURE

1.16. Section 2radionuclides registrants, licegeneric aspectdetailed objectpractices and some specific assessment meare discussed. results. SectioSection 10 is dspecifies requi

2. MEETMONITO

LEGAL CON

2.1. Exposurepractice, an undirect emission5

l surveillance and monitoring programme for the release to, or f toxic chemicals in, the environment is not addressed in this

which is devoted to the monitoring of radionuclides only. ators and other responsible organizations may find it convenient mical and radiological monitoring programmes.

discusses some general international guidance for monitoring in the environment. Section 3 outlines the responsibilities of nsees and regulatory bodies with regard to monitoring. Most

s of monitoring programmes are discussed in Section 4, and ives and different types of design of monitoring programmes for interventions are presented in Section 5. Section 6 addresses technical features of monitoring procedures. In Section 7 dose thods as they relate to different types of monitoring programmes Section 8 contains guidance on the interpretation of monitoring n 9 describes the appropriate quality assurance programme. evoted to the recording of monitoring results and Section 11

rements for education and training.

ING REGULATORY REQUIREMENTS FOR RING IN PRACTICES AND INTERVENTIONS

TEXT

s of members of the public from a controlled discharge in a controlled release or past area contamination may arise from the of radiation at the source of the discharge or from the dispersal

6of radionuclides in the environment. For the latter case the more likely pathways are external exposure due to radionuclides in a plume and on the ground as well as the ingestion of contaminated food. The inhalation of airborne radionuclides in a plume or from the resuspension of ground deposits may also be of importance. In the case of practices, the monitoring of radiation dose rates around the source, of discharge levels and of the levels of radionuclides in the environment is necessary to verify compliance with authorized limdose to membesource and of on protective aremedial actio

2.2. The concRefs [2, 3, 5, 7,

2.3. With regarequire that establishment, equipment ansatisfaction of according to thlicensees shall,

(a) establishthe requiof extern

(b) establishthe requsubstance[regulatothat the remain vestimated

(c) keep app(d) report a

approved(e) report p

environmto the radresponsibits on discharges and to facilitate the assessment of radiation rs of the public. In case of interventions, monitoring of a release environmental contamination is necessary for decision making ctions and longer term countermeasures in an emergency, or on

ns in areas contaminated with long lived radionuclides.

epts underlying the requirements for monitoring are set out in 17].

rd to the monitoring of controlled discharges in practices, the BSS Registrants and licensees shall be responsible for the implementation, and maintenance of appropriate monitoring

d surveillance programmes to assess public exposure to the the [regulatory body] (Ref. [2], para. III.2(f)). In particular, e Basic Safety Standards (Ref. [2], para. III.13), Registrants and if appropriate:

and carry out a monitoring programme sufficient to ensure that rements of the Standards regarding public exposure to sources al irradiation be satisfied and to assess such exposure; and carry out a monitoring programme sufficient to ensure that irements of the Standards for discharges of radioactive s to the environment and the requirements established by the

ry body] in granting the discharge authorization be satisfied and conditions assumed in deriving the authorized discharge limits alid and sufficient to enable the exposures to critical groups to be ;

ropriate records of the results of the monitoring programmes;summary of the monitoring results to the [regulatory body] at intervals;

romptly to the [regulatory body] any significant increase in ental radiation fields or contamination that could be attributed iation or radioactive discharges emitted by sources under their ility;

(f) establish and maintain a capability to carry out emergency monitoring, in case of unexpected increases in radiation fields or radioactive contamination due to accidental or other unusual events affecting sources under their responsibility; and

(g) verify the adequacy of the assumptions made for the prior assessment of radiological consequences of the discharges.

2.4. With regsituations the B

V.23. All reamembers of thassessments sh

V.24. The asshall be prompsubstantially m

V.25. Comprupdates, and environment.

2.5. For the psituations, theNuclear or Ra

(a) In responand envirto identif(Ref. [3],

(b) To ensurarrangecontaminof decidifollowing

(c) To ensurterm profor grounand wate7

ard to assessment and monitoring in emergency exposure SS (Ref. [2], paras V.23V.25) require that:

sonable steps shall be taken to assess exposure incurred by e public as a consequence of an accident, and the results of the all be made publicly available.

sessments shall be based on the best available information, and tly updated in the light of any information that would produce ore accurate results.

ehensive records shall be maintained of assessments and their of monitoring results for workers, the public and the

urpose of assessment and monitoring in emergency exposure Safety Requirements on Preparedness and Response for a diological Emergency [3] further require that:

se to the initial phase of the emergency, Radiation monitoring onmental sampling and assessment shall be carried out in order y new hazards promptly and to refine the strategy for response. para. 4.67.)e preparedness to respond to the initial phase of the emergency, ments shall be made for promptly assessing any radioactive ation, releases of radioactive material and doses for the purpose ng on or adapting the urgent protective actions to be taken a release. (Ref. [3], para. 4.71.)

e preparedness to take agricultural countermeasures and longer tective actions, arrangements shall include timely monitoring d contamination in the field; the sampling and analysis of food r. (Ref. [3], para. 4.89.)

82.6. In order to ensure proper monitoring and assessment during the operation of near surface waste disposal facilities and after their closure, the Safety Requirements publication on Near Surface Disposal of Radioactive Waste [5] requires that:

(a) The design of a near surface repository shall allow for implementation of a monitoring programme to verify the containment capability of the disposal repositorterm perf

(b) The reguenvironmand exteoperation

(c) The opemaintenaduring rethat the r[5], para.

(d) The respclosure regulatormonitorithe abserespect tpossible, 11.8.)

2.7. The SafeDesign [18] spearrangementsthe vicinity of

(1) pathways(2) the radio(3) the poss

environm(4) the possi

6.106.)system during operation and, as necessary, after closure of the y. Arrangements for monitoring shall not compromise the long ormance of the disposal system. (Ref. [5], para. 7.5.)latory body shall provide guidance necessary to establish an ental monitoring programme, including monitoring of releases rnal exposure, and to assess the environmental impact of s. (Ref. [5], para. 9.3.)

rator shall be responsible for ensuring the provision and nce of adequate monitoring to measure radioactive releases pository operation, and shall take necessary actions to ensure equirements established by national authorities are met. (Ref. 9.12.)onsible organization shall implement an appropriate post-

monitoring programme, which shall be approved by the y body. This programme shall deal with radiological and other ng of the repository and its surrounding area in order to verify nce of unacceptable radiological impacts (for example, with o the leachate limits, if appropriate), and to confirm, as far as the assumptions made in the safety assessment. (Ref. [5], para.

ty Requirements publication on Safety of Nuclear Power Plants: cifically requires that at the stage of nuclear power plant design, shall also be made to determine radiological impacts, if any, in

the plant, with particular reference to:

to the human population, including the food-chain;logical impact, if any, on local ecosystems;ible accumulation of radioactive materials in the physical ent; andbility of any unauthorized discharge routes. (Ref. [18], para.

2.8. For the stage of nuclear power plant operation, the Safety Requirements publication on Safety of Nuclear Power Plants: Operation [19] specifically requires that:

(a) The operating organization shall establish and implement procedures for monitoring and controlling discharges of radioactive effluents. A copy of these procedures shall be made available to the regulatory body.

(b) If requirestablishthe vicinradioacti

GENERAL C

2.9. The typebe commensurdischarge ratesdifferent expodoses to indivinstitutes usinprogramme fonuclear medicmay require roenvironmentalmedicine depaboth source anemergency mo

Conditions for

2.10. The requdirectly relatedThe internatiodescribed in th

2.11. Monitorithat give rise ttheir magnitudrequirements 9

ed by the regulatory body, the operating organization shall and implement a programme for monitoring the environment in ity of the plant in order to assess the radiological impacts of ve releases on the environment. (Ref. [19], paras 8.11 and 8.12.)

ONDITIONS FOR MONITORING

of monitoring programme, as well as its scale and extent, should ate with the source characteristics at the expected or current , the radionuclide composition, the comparative significance of sure pathways, and the magnitudes of expected and potential iduals. Some practices and sources (e.g. hospitals or research g short lived radionuclides) may not require a monitoring r the environment; some (e.g. small nuclear installations or ine departments using radionuclides for diagnostic purposes) utine monitoring at the source but only occasional checks on

levels; and others (e.g. most nuclear installations, large nuclear rtments) require continuous and comprehensive monitoring of d environment. Every facility should be prepared to conduct

nitoring at an appropriate level.

monitoring in practices

irements for the monitoring of discharges in a practice should be to the regulatory situation applying to the sources in question. nal requirements as they relate to monitoring actions are e following paragraphs.

ng is not required at the source or in the environment for sources o exposures that are excluded from regulatory control because e or likelihood is essentially unamenable to control through the of the BSS [2]. A relevant example in the context of this

10

publication is the gaseous discharge through a building ventilation system of radon and its decay products arising from the underlying soil.

2.12. Practices and sources can be exempted or materials cleared from the requirements for regulatory control if the associated radiation risks to individuals and populations are low enough to be of no regulatory concern and the exempted practices or sources are inherently safe [2]. For exempted practices and no requiremelaboratory thaactivity of a gexemption lev

2.13. Sources oare required totakes the formpractices are tusage of shortenvironment athese types is umonitoring at

2.14. Finally, tprogrammes alarge research this category. Ispecific safetymust comply, athe environmeprogramme maat facilities of monitoring capsource and the

Conditions for

2.15. Interventexposures can(prolonged) exto be necessaexceeded. Thesources or cleared materials that include discharges, there is nt for monitoring. An example of exemption is a small t utilizes amounts of radionuclides for which either the total iven radionuclide or the activity concentration is below the el [2].

r practices for which neither exclusion nor exemption is possible be authorized by the regulatory body [2, 7]. The authorization of either a registration or a licence. Examples of registered

hose at small research institutes and small hospitals, where the lived radionuclides and the corresponding discharges to the re low. Monitoring in the environment for registered practices of sually not required by the regulatory body, while some degree of

the source may be required.

here are several types of source for which routine monitoring re required. Most installations in the nuclear fuel cycle, some establishments and radioisotope production facilities fall under nstallations of this type are licensed by the regulatory body, have related requirements and conditions with which the licensee nd are always subject to monitoring, both at the source and in nt, as well as to public dose assessment. The routine monitoring y also form the basis for the emergency monitoring programme these types, although not all of them require a full emergency ability. Table 1 summarizes a relationship between the types of

necessary types of monitoring.

monitoring in intervention situations

ion situations requiring a response in order to reduce or avert be emergency exposure situations or situations of chronic posure. Protective and remedial actions are not normally likely

ry unless intervention levels or action levels are or may be initial input for decision making with regard to protective or

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12

remedial actions is usually based on monitoring. An overall monitoring strategy for emergencies and remedial actions should therefore be established; such a strategy should be site specific and should be based on detailed consideration of the sources and of possible pathways of human exposure.

Emergency exposure situations

2.16. Radiatioradiological emdetermined inaccident. The iof priorities inthat is to be pe

2.17. Emergenradioactive maconfinement. source monitoappropriate dothe emergency

2.18. With remeasurementsprotective andthe early deteworkers that a

2.19. In the denational and monitoring shoof accidentallywaters. The nenvironmentalthat occur in on monitoring should be performed in the event of any nuclear or ergency. The strategy for emergency monitoring should be

accordance with the possible radiological consequences of the ntended uses of the monitoring results should guide the selection monitoring and the technical details of the type of monitoring rformed.

cy exposure situations range from a spill of small amounts of terial in a laboratory to a major reactor accident with loss of

The methods and extent of emergency monitoring, including ring, environmental monitoring, individual monitoring and se assessment (see Table 1), should depend on the severity of and its potential or actual consequences.

gard to the timing, number and methods for radiation and environmental sampling, to ensure the timely execution of remedial actions, the monitoring strategy should be selected for ction of any exposures of the general public or of emergency re approaching the intervention levels or action levels.

velopment of a national strategy for emergency monitoring, both international aspects should be considered. Emergency

uld be aimed at receiving data relevant to the possible transfer released radioactive material to other States and international ational monitoring system should also be able to monitor radioactive contamination originating from accidental releases ther States.

2.20. Emergency monitoring may be terminated when control over the accidental source is restored or when radioactive conditions are not deteriorating and levels of human exposure and environmental contamination are substantially below the respective generic intervention levels and action levels [2] or the appropriate national levels.

Situations of chronic (prolonged) exposure

2.21. Situationradioactive recaused by radifrom the past cof regulatoryradionuclides)

2.22. There is all States for exposure of poestablished bygenerally baseconcentrationsProtection (ICif the existingsources does n

2.23. Monitoriradionuclides wcomprised a sugeneric level aaction levels.

2.24. Monitoripurpose of theif the radionucaction levels fintervention or13

s of chronic (prolonged) exposure include exposure to sidues from past events, such as radioactive contamination ation accidents (post-emergency exposure situations), as well as onduct of practices and the use of sources not under the system control (sites contaminated with natural long lived .

no standard of radiation protection that is universally applied in intervention in situations of chronic (prolonged) radiation pulations. Appropriate intervention levels or action levels are national authorities, depending on the circumstances and

d on existing or averted doses, dose rates in air and radionuclide . According to the International Commission on Radiological RP), intervention (remedial actions) is not likely to be justifiable annual effective dose from all the environmental radioactive ot reach 10 mSv [20].

ng of environmental contamination with long lived ould generally be justified if the annual dose due to this source

bstantial fraction (one tenth or more, i.e. 1 mSv or above) of the s given in para. 2.22 or the appropriate national intervention or

ng of food contamination with long lived radionuclides for the substantiation of protective actions would generally be justified lide levels in food comprised a substantial fraction of the generic or radionuclides in foodstuffs [2] or the appropriate national action levels.

14

3. RESPONSIBILITIES FOR MONITORING

RESPONSIBILITIES OF THE OPERATOR

3.1. In relation to the control of discharge practices, operators should have the following general responsibilities:

(a) To prevepublic re

(b) To comp(c) To report

3.2. With regoperators:

(a) Should pappropri

(b) Should pmonitoriunexpectdemonstrestablish

(c) Should ror increabe attribu

3.3. On this bdefined along

(a) Source mpractice (licenseephases ofoperationhave the

5 In somethe regulatory bIAEA guidancent any unacceptable radiation or contamination hazard to the sulting from a discharge practice;ly with applicable regulatory requirements; to the regulatory body any changes to the discharge practice.

ard to specific responsibilities in the area of monitoring,

erform all necessary pre-operational investigations (including, as ate, pre-operational monitoring);rovide means and perform adequate source and environmental ng programmes during and after operation that will permit ed releases to be detected promptly and will provide the data to ate that doses to the public are below the dose criteria

ed by the regulatory body;eport to the regulatory body any significant changes in releases ses in environmental radiation fields or contamination that could ted to releases from the sources under their responsibility.

asis, the responsibilities of operators for monitoring should be the following lines5:

onitoring referred to a specific practice or source within a that is under the responsibility of the particular operator or registrant) should be carried out by that operator in all the programme, including monitoring in operational and post-al stages and in the event of an emergency. The operator should

responsibility of establishing, carrying out and maintaining the

States, the main responsibility for environmental monitoring lies with ody or with other governmental agencies, in general agreement with

[21].

appropriate equipment and programmes for the monitoring of discharges.

(b) Environmental monitoring referred to a given practice or source within a practice is only necessary for major practices and sources warranting a licence. The licensees should be generally responsible for such environmental monitoring in all its phases, including the pre-operational, operational and post-operational stages. The licensees should also establishmonitori

(c) The licenprior asse

RESPONSIBI

3.4. In relatiothe following g

(a) Ensuringregulatio

(b) Ensuringregulatorsource an

(c) Providingare based

3.5. With regregulatory bod

(a) Should eincludingand shou

(b) Should ch(c) Should p

sources o

3.6. On this bshould be alon

(a) Althoughenvironm15

and maintain an adequate capability to carry out environmental ng in emergency situations.sees should periodically check the assumptions made for the ssment of the radiological impact of the discharges.

LITIES OF THE REGULATORY BODY

n to the control of discharge practices, the regulatory body has eneral responsibilities:

, by means of establishing and implementing appropriate ns, that the public and the environment are protected; that the operator complies with the appropriate regulations and y requirements, including those in respect of carrying out such d environmental monitoring as may be necessary; assurance that judgements concerning the safety of the public upon valid information and sound methods.

ard to specific responsibilities in the area of monitoring, the y:

stablish technical requirements for monitoring arrangements, arrangements for emergency monitoring and quality assurance, ld regularly review them;eck the monitoring data provided by operators;rovide evidence that can satisfy the public that authorized f exposure are being suitably monitored and controlled.

asis, the allocation of responsibilities for the regulatory body g the following lines:

the licensees should be generally responsible for source and ental monitoring, in some cases (such as major practices or

16

sources) the regulatory body may carry out a limited confirmatory programme of environmental measurements to verify the quality of the results provided by the licensee and to confirm that the doses to members of the public are maintained below the constraints established in the licence [21].

(b) When several sources may have an impact on the same areas and population groups, an environmental monitoring programme should be carried odifferentlicenseesinformatby other regulator

(c) If the potensure throutinelymonitoridesignatethe reguenvironm

3.7. In rare individual memestimated on tlimit, a reassesthe registrant outlines the mregulatory bod

RESPONSIBI

3.8. The govresponsibilitiesgovernment mdirectly. The d

(a) Review, t(b) Review out in order to assess the cumulative radiological impacts of these sources. As it may be difficult for individual registrants or to undertake such monitoring, since they may not have ion about the radionuclide composition of materials discharged operators, this monitoring may be arranged or carried out by the y body.ential exists for a large scale accident, the regulatory body must at emergency preparedness arrangements are in place and are tested. This should include the ability for rapid, large scale ng under emergency conditions, which may be performed by a d responsible organization with the requisite capability or by

latory body itself. The required monitoring may include both ental monitoring and individual monitoring.

circumstances, if the assessed annual dose to the average ber of the critical group arising from all relevant practices,

he basis of environmental monitoring, is approaching the dose sment of the doses to the critical group should first be made by or licensee and then validated by the regulatory body. Table 2 ajor areas of responsibility for registrants, licensees and the y concerning the different types of monitoring.

LITIES OF OTHER AGENCIES

ernment or the regulatory body may delegate specific relevant to environmental monitoring to other agencies. The ay control this delegation through the regulatory body or

elegation of authority may concern:

esting and calibration of monitoring equipment;f the quality assurance programme;

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18

(c) The design and regular performance of the confirmatory programmes of environmental measurements or release measurements to verify the quality of the results provided by the licensee;

(d) The confirmatory assessment of the doses to members of the public to warrant that they are maintained below the limits established in licences;

(e) The environmental monitoring programme carried out in order to assess the cumulative radiological impact of multiple sources when they have an impact on

(f) Emergen

3.9. Other agmonitoring, su

(a) Collectiointernatio

(b) Nationwi(c) Establish

3.10. In decidiother agenciesthe availabilityequipment and

3.11. As a gento which resporemain indepeare responsiblregulated, as wradiation facili

REPORTING

3.12. In accorappropriate:

(d) report a approved

(e) report penvironm the same areas and the same population groups;cy response.

encies may also be responsible for other domains relating to ch as:

n and retention of data provided by operators, governmental or nal agencies;

de environmental monitoring;ing standards.

ng on the delegation of specific monitoring responsibilities to or companies, the regulatory body should pay due attention to in these organizations of appropriate analytical techniques, qualified personnel, and of a quality assurance system.

eral principle, the regulatory body, as well as any other agencies nsibilities have been delegated by the regulatory body, should ndent of any government department and of any agencies that e for the promotion and development of the practices being ell as of any registrant, licensee, designer or constructor of the

ties used in the practices being regulated.

OF MONITORING RESULTS

dance with the BSS, Registrants and licensees shall, if

summary of the monitoring results to the [regulatory body] at intervals;

romptly to the [regulatory body] any significant increase in ental radiation fields or contamination that could be attributed

to the radiation or radioactive discharges emitted by sources under their responsibility (Ref. [2], para. III.13).

3.13. In addition, registrants and licensees should promptly report any discharges exceeding the authorized limits on discharges in accordance with criteria established by the regulatory body.

3.14. The perioresults of botmonitoring proallows the veriby the regulatoto the objectivbody. In somerates or activitit may be neceregulatory bodattached to diinterpretation

3.15. The perioresults and an appropriate mfor results thcontaminationuseful informaand the net equantities of fufuel reprocessi

3.16. The regimonitoring datnecessitate mooperation (e.gvariability of tas nuclear fuelradionuclides dlimits establish

3.17. The promradiation field19

dic summary report of the monitoring results should include the h the source monitoring programme and the environmental gramme. In all cases, results should be reported in a way that

fication of compliance with the limits on discharges authorized ry body. The way in which results are reported should be related es of the monitoring programme as defined by the regulatory circumstances it may be adequate to compare measured dose y concentrations with appropriate derived levels; in other cases, ssary to evaluate the doses to critical groups. As specified by the y, these doses should be compared with the dose constraints

scharge authorizations; the results of the comparison and their should be reported to the regulatory body.

dic summary report should also include an interpretation of the adequate explanation of their significance (e.g. with reference to odels or standards or to the uncertainty of the results), especially at show significant variations in the releases or in the

of the environment. The summary should also include other tion such as the weather conditions during the reported period lectrical energy production (for nuclear power plants) or the el produced (for a fuel fabrication facility) or reprocessed (for a ng plant) in the period concerned.

strant or licensee should present source and environmental a to the regulatory body at least annually, but other factors may re frequent reports. These factors could include the type of . registered or licensed sources or practices) and the time he quantities and rates of the discharge. Licensed practices such cycle facilities should specify in their reporting the quantities of ischarged to the environment in accordance with the authorized ed by the regulatory body.

pt report of a significant unplanned increase in environmental s or contamination should include a description of the

20

investigation that has been set up, its preliminary results if available, the immediate actions that have been taken in relation to discharge operations (e.g. stopping batch discharges) and the actions that are foreseen for the immediate future (e.g. resuming discharge operations).

3.18. In view of the increasing public awareness of environmental issues, the regulatory body together with the licensees and registrants should make available to thwith an adeqstandards or to

4. GENERI

GENERAL

4.1. The geneof the public an

(a) To verifyregulatorenvironma practice

(b) To proviassess thpopulatiofields in source w

(c) To checkdischargeunforeseenvironm

4.2. Some sumonitoring pro

(a) To provide public summary information on environmental monitoring uate explanation of its significance (e.g. with reference to the uncertainty of the results).

C ASPECTS OF MONITORING PROGRAMMES

ral objectives of any monitoring programme for the protection d the environment, as considered in this Safety Guide, are [6, 7]:

compliance with authorized discharge limits and any other y requirements concerning the impact on the public and the ent due to the normal operation of a practice or a source within ;

de information and data for dose assessment purposes and to e exposure or potential exposure of critical groups and ns due to the presence of radioactive materials or radiation

the environment from the normal operation of a practice or a ithin a practice and from accidents or past activities; the conditions of operation and the adequacy of controls on s from the source and to provide a warning of unusual or

en conditions and, where appropriate, to trigger a special ental monitoring programme.

bsidiary objectives, which should usually be fulfilled by a gramme, are [6, 7]:

e information for the public;

(b) To maintain a continuing record of the impacts of an installation or a practice on environmental radionuclide levels;

(c) To check the predictions of environmental models so as to modify them as appropriate in order to reduce uncertainties in the dose assessment.

4.3. In accordance with general and subsidiary objectives, the monitoring programmes should include radiation measurements and the collection of relevant suppogroups and poenvironment compliance wi

HUMAN EXP

4.4. One impanalysis and programmes fopathways of hsource of radiothrough mediapathway: exterthe body) anincorporated in

4.5. The mainare:

(a) Source oradiation

(b) Source ofdue to thwater;

(c) Source ocontact e

(d) Source oor buildradionucrivers, lavegetatio21

rting information as well as the assessment of doses to critical pulations due to the presence of radioactive material in the

from a practice or intervention and a demonstration of th authorized limits on discharges within a practice.

OSURE PATHWAYS

ortant purpose of monitoring is to provide data that permit the evaluation of human radiation exposure. For this purpose, r monitoring radionuclides in the environment should focus on uman exposure. An exposure pathway defines routes from a nuclides and/or radiation to a target individual or a population in the environment. There are two main categories of exposure nal exposure pathways (the source of exposure remains outside d internal exposure pathways (the source of exposure is to the body).

external exposure pathways considered in this Safety Guide

f radiation human: direct exposure from a source of ionizing ; radionuclides atmosphere or water body human: exposure e plume of radionuclides in the atmosphere (cloud shine) or

f radionuclides atmosphere or water body human skin: xposure from radionuclides on the skin;f radionuclides atmosphere or water body soil or sediment ing surface or vegetation human: exposure from the lides deposited on the ground or on sediments (on the shores of kes or the sea) or building surfaces (walls, roofs and floors) or n (trees, bushes and grass).

22

4.6. The main internal exposure pathways considered in this Safety Guide are:

(a) Source of radionuclides atmosphere human: inhalation of radionuclides in the plume;

(b) Source of radionuclides atmosphere or water body (soil or sediment) vegetation and/or meat, milk, eggs or marine food human: ingestion of radionuclides in food or beverages;

(c) Source ofabsorptio

(d) Soil or se

4.7. Figure 1 following the water or groun

4.8. The impo

(a) The radiobeta emit

(b) The phyinorganicand its m

(c) The dispmeteorolclimate, t

(d) The locapopulatio

4.9. Under copermanent ancontributions vpublic may beshould be consIn order to prfollowing majoemergencies frtherefore, the

4.10. At differdifferent moniprotective acti tritium atmosphere human: for tritium oxide in the plume, n through the skin;diment human: inhalation of resuspended radionuclides.

illustrates the pathways by which an individual may be exposed discharge of radionuclides to the atmosphere and the surface dwater, respectively.

rtance of the various exposure pathways depends on:

logical properties of the material released (e.g. gamma emitters, ters or alpha emitters; physical half-life);

sical (e.g. gas, liquid or solid) and chemical (e.g. organic or form, oxidation state, speciation, etc.) properties of the material igration characteristics;ersal mechanism and factors affecting it (e.g. stack height, ogical conditions, etc.) and environmental characteristics (e.g. ype of biota, agricultural production, etc.);tions, ages, diets and habits of the exposed individuals or n.

nditions of normal discharges the exposure pathways are usually d well defined. In the case of emergency releases, the ia different pathways to the doses received by workers and the different from the normal and transient. These differences idered when establishing the emergency monitoring programme. otect the public and workers from deterministic health effects r accidents, different radiological criteria may be applied in om those applied under conditions of normal discharges and,

collection of additional monitoring data may be necessary.

ent stages of an accident the exposure pathways may change and toring data may be necessary to support decision making on ons. Thus, at an early stage of an accidental atmospheric release,

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24

the monitoring should be focused on measurements of cloud shine and on the sampling of radionuclides from the plume to assess the contributions of external exposure and inhalation to doses. Once the release has been terminated and the radioactive cloud has passed, monitoring should be refocused on ground shine and food contamination to take into account the contributions of external exposure and ingestion to doses.

4.11. In situatusually well ddetermined bysediments, buingestion of amay contributlong lived ratherefore, of th

EXPOSURE G

4.12. One of tdischarges is tmembers of thstage to occurnormal operat

4.13. An impocritical group reasonably hosource and is equivalent dosage, diet or haestablished bycritical group. of critical grou

4.14. The criticcarefully. Adeqminorities as wpatterns and pathways and analysis.ions of chronic (prolonged) exposure, exposure pathways are efined and not likely to change rapidly. External exposure is the radiation from radionuclides deposited on the ground or ilding surfaces or vegetation and not by cloud shine. The gricultural and/or natural foodstuffs containing radionuclides e substantially to doses. Because of the gradual penetration of dionuclides into soil, the importance of resuspension and, e inhalation pathway decreases with time.

ROUPS

he primary purposes of monitoring in the context of normal o provide information and data for assessing the exposure of e public and for verifying the doses anticipated at the licensing as a consequence of discharges to the environment during

ion.

rtant concept for this purpose is that of the critical group. The is defined as a group of members of the public which is

mogeneous with respect to its exposure for a given radiation typical of individuals receiving the highest effective dose or

e (as applicable) from the given source because of their location, bits [2]. Dose constraints or, in some circumstances, dose limits the regulatory body generally apply to the mean dose to this The ICRP has provided guidance to assist in the determination ps [6]. This issue is discussed in more detail in Ref. [7].

al group for a particular set of circumstances should be selected uate attention should be paid to the habits of ethnic and cultural ell as those of indigenous people where applicable. Their living

habits of consumption of food and water could give rise to elevated exposure levels that are unanticipated by conventional

4.15. One of the major aspects of the selection is the size of the critical group, which is strongly influenced by the above mentioned requirement for homogeneity. In extreme cases, it may be convenient to define the critical group in terms of a single hypothetical individual. However, the critical group will not usually consist of a single individual, although it will rarely be a large group because homogeneity could then be lost. In practice, the size of the critical group is generally of the order of a few tens of individuals, except in cases in whichthrough the inga large reservo

4.16. There mapathways and In this situaticalculated sumwith the dose Some populatiwith time, creasome exposure

4.17. Whereasexposure grouemergencies aaccording to rebe used as a bactions and to defined shouldpatterns of defoodstuffs andaffected areas.

TYPES OF RA

4.18. Monitorithree types: menvironment (monitoring omeasurementsradiation or fr25

a large population is homogeneously exposed, for example, estion of widely distributed foodstuffs or of drinking water from ir.

y be different groups of the most exposed for different exposure some individuals may be members of more than one such group. on, the critical group should be defined on the basis of the of doses via all exposure pathways, which should be compared constraints or dose limits (e.g. in the case of multiple sources). on distributions or land use patterns near a facility may change ting a new critical group or changing the relative importance of pathways.

in the case of normal discharges the doses calculated for the ps are often conservative, the doses for exposure groups during nd situations of chronic (prolonged) exposure should be defined alistic habits so as to provide realistic dose assessments that can asis for making decisions on protective actions and remedial

ensure an adequate allocation of resources. The exposure groups be oriented on real individuals and on assumptions of real position and contamination of the environment and of the

feedstuffs that are produced and used by the population in the

DIATION MONITORING

ng for radiation protection of the public can be divided into onitoring at the source (source monitoring), monitoring in the environmental monitoring) and, in very rare cases, individual f members of the public. Source monitoring includes of radiation levels and radionuclides from a particular source of om a practice, environmental monitoring is conducted outside

26

the site giving rise to the exposure and individual monitoring is concerned with measurements carried out directly on people [6].

4.19. Environmental monitoring can be further subdivided into two categories: source related environmental monitoring and person related environmental monitoring (see Fig. 2). Source related environmental monitoring concerns the measurement of absorbed dose rates in air or activity concentrations resulting from a definnecessary to dunder investenvironmentalsources irradiadoses derivingcharacteristics

4.20. When boindividual monrespective moprogramme mait is preferablerather than onrather than ominimizing thecould provide group. Howev

Sourcemonitoring

FIG.ed source or practice; comparative measurements may be istinguish the contribution of the particular source or practice igation. Person related environmental monitoring is monitoring in circumstances in which there may be several ting the same group of people; the main objective is to assess the from all these sources [6]. The specific objectives and

of the different types of monitoring are discussed below.

th source and environmental monitoring or environmental and itoring are required, there should be good liaison between the

nitoring programmes, because information obtained from one y contribute to a better understanding of the other. In principle,

to base dose calculations on the results of individual monitoring environmental monitoring, and on environmental monitoring

n monitoring at source. This approach has the advantage of modelling uncertainties involved in the dose calculations and a firmer indication of the doses actually incurred by the critical er, low levels of activity and dose make individual monitoring

RADIATION MONITORING

Environmentalmonitoring

Individualmonitoring

Source relatedmonitoring

Person relatedmonitoring

2. Types of monitoring for radiation protection of the public.

and sometimes environmental monitoring impracticable for dose assessment purposes.

4.21. Individual monitoring for members of the public would only be necessary in the case of an intervention if the assessed average individual dose to members of a particular group of people is close to or could exceed a substantial fraction of an appropriate intervention level [2]. Such a situation is extremely rare

4.22. The folloany monitoring

Radioact Space an Authoriz Possible

pathwaysfeatures a

Significanenvironmpossible r

4.23. The routgood basis for considerable fand the calibraemergency moallow a prompprogramme. Thpossible emerg

Source monito

4.24. Source mthe discharge oin the design othe scale andprogrammes athe discharge nature of the airborne efflu27

.

wing conditions should be taken into account in the design of programme:

ive inventory and radionuclide composition at the source;d time features of the radiation fields around the source;ed discharges and discharge rates;contributions from any nearby practices or sources, discharge , exposure pathways, environmental features at the site, and nd habits of the population involved;ce of the annual average doses of the critical group(s) and the ental radiation levels from planned radioactive releases and eleases.

ine monitoring programme should also be designed to provide a emergency monitoring in the event of an accident. This requires lexibility in the monitoring arrangements (through the choice tion of appropriate equipment, applicable in both routine and nitoring, organizational provisions and personnel training) to t shift from normal to emergency operation in the monitoring orough preparation and planning for the monitoring relating to encies are essential.

ring

onitoring is the monitoring of a particular source of radiation or f radionuclides arising from a practice. The basic considerations

f source monitoring programmes are the same for all sources, but frequency of monitoring will differ. Source monitoring

re usually designed to measure dose rates at the source and/or rates of radionuclides. Dose rates will vary depending on the source and its condition. The mode of discharge will also vary: ents are most frequently discharged continuously during

28

operation, but the operation itself may be discontinuous, whereas liquid effluents may be discharged continuously or may be stored and subsequently discharged from tanks on a batch basis.

4.25. For each type of source and for each pathway of potential exposure it is necessary to consider the location of the measurement point, whether continuous monitoring is required, the frequency of sampling and/or measurement of radionuclidform, density hydrological d

Environmenta

4.26. Environmgiving rise to eenvironmentalfields and radrelevant to huproduce and nradionuclides a

4.27. Source rimpact of a pdetermine thepoints and sambe applied thaarising from th

4.28. Althoughdose rates arefocused on thdiffuse, which sources are micontribution fenvironmentalby a wide geradionuclides f

4.29. Environmfeatures of theand the requirements for additional information. For discharges es it may be necessary to obtain information on the chemical and flow rate of the discharge, as well as meteorological and ata and information relating to the receiving environment [6].

l monitoring

ental monitoring is conducted both on and outside the site xposure of the public and radionuclides in the environment. The monitoring programmes include measurements of radiation ionuclide activity concentrations in environmental samples man exposure, primarily in air, drinking water, agricultural atural foodstuffs, as well as in bioindicators that concentrate nd provide a measure of trends in activity levels.

elated environmental monitoring is carried out to assess the articular source of radiation and radionuclide discharge. To environmental impact of a particular source, measurement pling points should be selected and analytical methods should

t allow the detection of radiation and radioactive contamination e source under consideration.

many sources giving rise to radionuclide releases or external localized and environmental monitoring programmes can be em, there are also sources that are multiple, widespread or cannot be treated in this way. The radionuclides released by such xed in the environment, and there is a need to monitor the total rom multiple or widespread sources. The person related monitoring applied for these conditions is often characterized ographical coverage and by the capability of detecting most ound in the environment [6].

ental monitoring is always dependent on the site specific environment to be monitored. The monitoring should be done

to detect changes in long term trends in activity concentrations or dose rates in the environment. The other objectives of environment