EN ISO 16639:2019
(Main)Surveillance of the activity concentrations of airborne radioactive substances in the workplace of nuclear facilities (ISO 16639:2017)
Surveillance of the activity concentrations of airborne radioactive substances in the workplace of nuclear facilities (ISO 16639:2017)
ISO 16639:2017 provides guidelines and performance criteria for sampling airborne radioactive substances in the workplace. Emphasis is on health protection of workers in the indoor environment.
ISO 16639:2017 provides best practices and performance-based criteria for the use of air sampling devices and systems, including retrospective samplers and continuous air monitors. Specifically, this document covers air sampling program objectives, design of air sampling and monitoring programs to meet program objectives, methods for air sampling and monitoring in the workplace, and quality assurance to ensure system performance toward protecting workers against unnecessary inhalation exposures.
The primary purpose of the surveillance of airborne activity concentrations in the workplace is to evaluate and mitigate inhalation hazards to workers in facilities where these can become airborne. A comprehensive surveillance program can be used to
- determine the effectiveness of administrative and engineering controls for confinement,
- measure activity concentrations of radioactive substances,
- alert workers to high activity concentrations in the air,
- aid in estimating worker intakes when bioassay methods are unavailable,
- determine signage or posting requirements for radiation protection, and
- determine appropriate protective equipment and measures.
Air sampling techniques consist of two general approaches. The first approach is retrospective sampling, in which the air is sampled, the collection medium is removed and taken to a radiation detector system and analysed for radioactive substance, and the concentration results made available at a later time. In this context, the measured air concentrations are evaluated retrospectively. The second approach is continuous real-time air monitoring so that workers can be warned that a significant release of airborne radioactivity may have just occurred. In implementing an effective air sampling program, it is important to achieve a balance between the two general approaches. The specific balance depends on hazard level of the work and the characteristics of each facility.
A special component of the second approach which can apply, if properly implemented, is the preparation of continuous air monitoring instrumentation and protocols. This enables radiation protection monitoring of personnel that have been trained and fitted with personal protective equipment (PPE) that permit pre-planned, defined, extended stay time in elevated concentrations of airborne radioactive substances. Such approaches can occur either as part of a planned re-entry of a contaminated area following an accidental loss of containment for accident assessment and recovery, or part of a project which involves systematic or routine access to radioactive substances (e.g. preparing process material containing easily aerosolized components), or handling objects such as poorly characterized waste materials that may contain radioactive contaminants that could be aerosolized when handled during repackaging. In this special case, the role of continuous air monitoring is to provide an alert to health physics personnel that the air concentrations of concern have exceeded a threshold such that the planned level of protection afforded by PPE has been or could be exceeded. This level would typically be many 10's or 100's of times higher than the derived air concentration (DAC) established for unprotected workers. The mo
Überwachung der Aktivitätskonzentrationen von luftgetragenen radioaktiven Substanzen an Arbeitsplätzen kerntechnischer Einrichtungen (ISO 16639:2017)
Dieses Dokument stellt Leitlinien und Leistungskriterien für die Probenentnahme luftgetragener radioaktiver Stoffe am Arbeitsplatz zur Verfügung. Der Schwerpunkt liegt dabei auf dem Gesundheitsschutz der Arbeits-kräfte in Innenräumen.
Dieses Dokument enthält bewährte Verfahren und leistungsbezogene Kriterien für den Einsatz von Geräten und Einrichtungen für die Luftprobenentnahme, einschließlich retrospektiver Sammler und kontinuierlicher Luftmonitore. Insbesondere deckt diese Norm die Ziele eines Luftprobenentnahmeprogramms, die Planung von Probenentnahme- und Messprogrammen zum Erreichen dieser Programmziele, die Verfahren zur Pro-benentnahme und Messung von Luft am Arbeitsplatz und die Qualitätssicherung zur Sicherstellung der Leis-tungsfähigkeit des Systems zum Schutz der Arbeitskräfte vor unnötiger Strahlenbelastung durch Inhalation ab.
Der primäre Zweck der Überwachung der Aktivitätskonzentrationen luftgetragener radioaktiver Stoffe am Ar-beitsplatz ist die Bewertung und Minimierung der Inhalationsgefahr für Arbeitskräfte in Einrichtungen, in denen diese Stoffe in die Luft gelangen können. Ein umfassendes Überwachungsprogramm kann verwendet werden, um:
– die Wirksamkeit administrativer und technischer Kontrollen für den Einschluss festzulegen;
– die Aktivitätskonzentrationen radioaktiver Stoffe zu messen;
– die Arbeitskräfte vor hohen Aktivitätskonzentrationen in der Luft zu warnen;
– die Abschätzung der Aktivitätszufuhr für die Arbeitskräfte zu unterstützen, falls biologische Testverfahren nicht zur Verfügung stehen;
– Anforderungen an die Beschilderung und Kennzeichnung für den Strahlenschutz festzulegen;
– geeignete Schutzausrüstung und Schutzmaßnahmen festzulegen.
Die Verfahren zur Luftprobenentnahme bestehen aus zwei allgemeinen Ansätzen. Der erste Ansatz ist die retrospektive Probenentnahme. Dabei werden Bestandteile der Luft zunächst gesammelt. Das Sammelme-dium wird anschließend entnommen, zu einem Strahlungsdetektor gebracht und auf radioaktive Stoffe hin analysiert. Die ermittelten Aktivitätskonzentrationen stehen erst zu einem späteren Zeitpunkt zur Verfügung, d. h. ihre Bewertung erfolgt retrospektiv. Der zweite Ansatz ist die kontinuierliche Echtzeit-Messung. Hierbei werden die Aktivitätskonzentrationen kontinuierlich gemessen, so dass die Arbeitskräfte bei einer möglicher-weise gerade aufgetretenen, signifikanten Freisetzung luftgetragener Aktivität gewarnt werden können. Bei der Implementierung eines effektiven Luftprobenentnahmeprogramms ist es wichtig, ein ausgewogenes Ver-hältnis zwischen beiden generellen Ansätzen zu erzielen. Dieses hängt insbesondere vom Gefährdungsgrad der Arbeit und den charakteristischen Eigenschaften jeder einzelnen Einrichtung ab.
Surveillance de l’activité volumique des substances radioactives dans l’air des lieux de travail des installations nucléaires (ISO 16639:2017)
ISO 16639:2017 fournit des lignes directrices et des critères de performance pour l'échantillonnage des substances radioactives dans l'air des lieux de travail. L'accent est mis sur la protection de la santé des travailleurs dans l'environnement intérieur.
ISO 16639:2017 fournit les meilleures pratiques et les critères basés sur les performances pour l'utilisation de dispositifs et de systèmes d'échantillonnage, y compris les dispositifs d'échantillonnage pour mesurage rétrospectif de la radioactivité et les dispositifs de surveillance en continu de l'air. Plus spécifiquement, le présent document couvre les objectifs et la conception des programmes d'échantillonnage et de surveillance de l'air visant à satisfaire les objectifs des programmes, les méthodes d'échantillonnage et de surveillance de l'air sur le lieu de travail, et l'assurance qualité visant à garantir les performances du système destiné à protéger les travailleurs contre les expositions inutiles par inhalation.
L'objectif premier de la surveillance des activités volumiques dans l'air sur les lieux de travail est d'évaluer et d'atténuer les risques par inhalation auxquels sont exposés les travailleurs dans les lieux où elles peuvent être présentes dans l'air. Un programme de surveillance complet peut être utilisé pour:
- déterminer si les contrôles administratifs et techniques du confinement sont efficaces;
- mesurer les activités volumiques des substances radioactives;
- alerter les travailleurs d'activités volumiques élevées dans l'air;
- aider à estimer les incorporations par les travailleurs en l'absence de méthodes d'analyse radiotoxicologique;
- déterminer les exigences en matière de signalisation ou d'affichage pour la protection au rayonnement; et
- déterminer l'équipement de protection et les mesures appropriés.
Les techniques d'échantillonnage de l'air consistent en deux approches générales. La première approche est l'échantillonnage rétrospectif qui consiste à prélever des échantillons de l'air, à retirer le milieu de prélèvement, à le soumettre à un système de détection des rayonnements et à analyser les substances radioactives, et enfin à mettre à disposition ultérieurement les résultats de concentrations. Dans ce contexte, les concentrations mesurées dans l'air sont évaluées rétrospectivement. La deuxième approche est une surveillance de l'air en continu et en temps réel pour que les travailleurs puissent être avertis lorsqu'un important rejet de radioactivité dans l'air vient juste de se produire. Pour l'implémentation d'un programme d'échantillonnage de l'air efficace, il est important d'atteindre un équilibre correct entre les deux approches générales. L'équilibre spécifique dépend du niveau de risque du travail et des caractéristiques de chaque installation.
Un composant spécial de la deuxième approche qui peut être appliqué s'il est implémenté correctement est la préparation des instruments de détection et des protocoles de surveillance continue de l'air. Cela permet le suivi de la protection contre les rayonnements du personnel qui a été formé et équipé d'un équipement de protection individuelle (EPI) qui les rend en mesure de séjourner pendant une durée étendue définie et préprogrammée dans les concentrations élevées de substances radioactives dans l'air. De telles approches peuvent avoir lieu soit dans le cadre d'une réentrée programmée dans une zone contaminée suite à une perte accidentelle de confinement afin d'évaluer l'
Nadzorovanje koncentracije aktivnosti radioaktivnih snovi v zraku na delovnem mestu v jedrskih postrojih (ISO 16639:2017)
Standard ISO 16639:2017 podaja najboljše prakse in merila, ki temeljijo na učinkovitosti, za uporabo naprav ter sistemov za vzorčenje zraka, vključno z retrospektivnimi vzorčevalniki in napravami za stalen nadzor zraka. Natančneje, ta dokument zajema cilje programa vzorčenja zraka, snovanje programov za vzorčenje in nadzor zraka, ki ustrezajo ciljem programa, metode za vzorčenje in nadzor zraka na delovnem mestu ter zagotavljanje kakovosti z namenom delovanja sistema v smeri zaščite delavcev pred nepotrebno izpostavljenostjo vdihavanju.
Prvotni namen nadzorovanja koncentracije aktivnosti v zraku na delovnem mestu je ocenjevanje in zmanjšanje nevarnosti vdihavanja za delavce v obratih, kjer lahko snovi lebdijo v zraku. Celovit program nadzorovanja se lahko uporabi za:
– določanje učinkovitosti administrativnega in inženirskega nadzora za osamitev,
– merjenje koncentracije aktivnosti radioaktivnih snovi,
– opozarjanje delavcev na visoko koncentracijo aktivnosti v zraku,
– pomoč in ocenjevanje količine vdihanih snovi, kadar biološke metode niso na voljo,
– določanje znakov ali objavljanje zahtev za zaščito pred sevanjem ter
– določanje primerne zaščitne opreme in zaščitnih ukrepov.
Tehnike vzorčenja zraka zajemajo dva splošna pristopa. Prvi pristop je retrospektivno vzorčenje, pri katerem se zrak vzorči, ko je medij za zbiranje odstranjen in se vzorec analizira za radioaktivne snovi v sistemu za odkrivanje sevanja, rezultati koncentracije pa so na voljo naknadno. V tem kontekstu so izmerjene koncentracije aktivnosti v zraku vrednotene retrospektivno. Drugi pristop je stalen sprotni nadzor, ki omogoča pravočasno obveščanje delavcev ob morebitnem pomembnem izpustu sevanja v zrak. Pri izvajanju učinkovitega programa vzorčenje zraka je pomembno, da se vzpostavi ravnovesje med obema pristopoma. To ravnovesje je odvisno od stopnje nevarnosti pri delu in značilnosti vsakega obrata.
Posebna komponenta drugega pristopa, ki lahko velja, če je pravilno izvedena, je pripravljenost instrumentov in protokolov za stalni nadzor zraka. To omogoča nadzor zaščite pred sevanjem za osebje, ki je bilo usposobljeno in uporablja osebno zaščitno opremo (PPE), ki dovoljuje predhodno načrtovan, določen ter podaljšan čas čakanja v zvišanih koncentracijah radioaktivnih snovi v zraku. Takšni pristopi se lahko zgodijo kot del načrtovanega ponovnega vstopa v onesnaženo območje po naključnem izpustu za namene ocenjevanja in odpravljanja posledic nesreče ali kot del projekta, ki vključuje sistematičen ali rutinski dostop do radioaktivnih snovi (npr. pripravljanje proizvodnega materiala, ki vsebuje komponente, ki lahko prehajajo v zrak), ali za rokovanje s predmeti, kot je slabo označen odpadni material z morebitnimi radioaktivnimi onesnaževali, ki pri vnovičnem pakiranju zlahka prehajajo v zrak. V tem posebnem primeru je vloga stalnega nadzora zraka to, da medicinski fiziki prejmejo alarm zaradi preseženega praga ustrezne koncentracije v zraku, ki lahko pomeni, da je načrtovana raven zaščite z osebno zaščitno opremo presežena ali pa bi lahko bila presežena. Ta raven bi običajno bila 10- ali 100-krat višja, kot je izpeljana koncentracija v zraku (DAC), ki velja za nezaščitene delavce. Nadzorni alarm ali opozorilo bi bila torej načrtovana tako, da se ju ne zamenja z običajnim nadzornim alarmom, in ukrepi kot odziv nanj bi bili podobno usmerjeni na določeno mesto in vpleteno osebje.
Strategija vzorčenja zraka bi morala biti načrtovana tako, da zmanjša notranjo izpostavljenost in da je v ravnovesju s socialnimi, tehničnimi, ekonomskimi, praktičnimi ter javnimi dejavniki, ki so povezani z rabo radioaktivnih snovi.
General Information
- Status
- Published
- Publication Date
- 11-Jun-2019
- Withdrawal Date
- 30-Dec-2019
- Current Stage
- 6060 - Definitive text made available (DAV) - Publishing
- Start Date
- 12-Jun-2019
- Due Date
- 28-Nov-2020
- Completion Date
- 12-Jun-2019
Overview
EN ISO 16639:2019 (ISO 16639:2017) provides guidelines and performance-based criteria for the surveillance of activity concentrations of airborne radioactive substances in the workplace of nuclear facilities. The standard focuses on protecting workers from inhalation hazards by defining best practices for air sampling programs, including the use of retrospective samplers and continuous air monitors (CAM), program design, sampling methods, and quality assurance.
Key topics
- Program objectives and design - establish goals for measuring airborne activity concentrations, graded approaches based on hazard level, and frequency of sampling (grab vs continuous).
- Sampling methods - guidance on aerosol and gas sampling techniques, use of portable samplers, and placement of samplers for dose estimates, containment evaluation, and area posting.
- Continuous monitoring - performance criteria and protocols for CAMs used for real‑time warning, including integration with PPE and planned extended stays in elevated concentrations.
- Evaluation of results - calculation of average activity concentrations, uncertainty analysis, time‑trend evaluation, and correcting for radon progeny interference.
- Dose-based assessments - using sampling data to support intake estimates and to evaluate whether sampling program sensitivity is adequate to detect exposures of concern.
- Quality assurance / quality control - requirements for equipment performance, air in‑leakage testing, sample handling, documentation, and record keeping.
- Annexes and tools - informative examples for uncertainty and detection limit calculations (linked to ISO 11929), radon progeny correction methods, and sample program sensitivity examples.
Practical applications
EN ISO 16639:2019 is used to:
- Design and validate workplace air surveillance programs in nuclear power plants, fuel cycle facilities, laboratories and waste handling sites.
- Select and position samplers and CAMs to detect excursions and to assess containment effectiveness.
- Support occupational dose assessments when bioassay is unavailable.
- Define posting/signage, respiratory protection requirements, and emergency re‑entry strategies based on measured air concentrations.
- Establish QA/QC protocols for vendors, instrumentation, and in‑house monitoring teams.
Who uses this standard
- Radiation protection officers and health physics teams
- Nuclear facility operations and safety managers
- Environmental and occupational hygiene professionals
- Instrument manufacturers and service providers for air sampling/CAM systems
- Regulators and auditors assessing compliance with workplace radiological protection
Related standards
- ISO 11929 (decision threshold and detection limit calculations) - referenced in Annex A.
- EN ISO 16639:2019 is the CEN-adopted version of ISO 16639:2017 for European national standards bodies.
Keywords: EN ISO 16639:2019, ISO 16639:2017, surveillance airborne radioactive substances, workplace air monitoring, air sampling, continuous air monitors, radiation protection, nuclear facilities.
Frequently Asked Questions
EN ISO 16639:2019 is a standard published by the European Committee for Standardization (CEN). Its full title is "Surveillance of the activity concentrations of airborne radioactive substances in the workplace of nuclear facilities (ISO 16639:2017)". This standard covers: ISO 16639:2017 provides guidelines and performance criteria for sampling airborne radioactive substances in the workplace. Emphasis is on health protection of workers in the indoor environment. ISO 16639:2017 provides best practices and performance-based criteria for the use of air sampling devices and systems, including retrospective samplers and continuous air monitors. Specifically, this document covers air sampling program objectives, design of air sampling and monitoring programs to meet program objectives, methods for air sampling and monitoring in the workplace, and quality assurance to ensure system performance toward protecting workers against unnecessary inhalation exposures. The primary purpose of the surveillance of airborne activity concentrations in the workplace is to evaluate and mitigate inhalation hazards to workers in facilities where these can become airborne. A comprehensive surveillance program can be used to - determine the effectiveness of administrative and engineering controls for confinement, - measure activity concentrations of radioactive substances, - alert workers to high activity concentrations in the air, - aid in estimating worker intakes when bioassay methods are unavailable, - determine signage or posting requirements for radiation protection, and - determine appropriate protective equipment and measures. Air sampling techniques consist of two general approaches. The first approach is retrospective sampling, in which the air is sampled, the collection medium is removed and taken to a radiation detector system and analysed for radioactive substance, and the concentration results made available at a later time. In this context, the measured air concentrations are evaluated retrospectively. The second approach is continuous real-time air monitoring so that workers can be warned that a significant release of airborne radioactivity may have just occurred. In implementing an effective air sampling program, it is important to achieve a balance between the two general approaches. The specific balance depends on hazard level of the work and the characteristics of each facility. A special component of the second approach which can apply, if properly implemented, is the preparation of continuous air monitoring instrumentation and protocols. This enables radiation protection monitoring of personnel that have been trained and fitted with personal protective equipment (PPE) that permit pre-planned, defined, extended stay time in elevated concentrations of airborne radioactive substances. Such approaches can occur either as part of a planned re-entry of a contaminated area following an accidental loss of containment for accident assessment and recovery, or part of a project which involves systematic or routine access to radioactive substances (e.g. preparing process material containing easily aerosolized components), or handling objects such as poorly characterized waste materials that may contain radioactive contaminants that could be aerosolized when handled during repackaging. In this special case, the role of continuous air monitoring is to provide an alert to health physics personnel that the air concentrations of concern have exceeded a threshold such that the planned level of protection afforded by PPE has been or could be exceeded. This level would typically be many 10's or 100's of times higher than the derived air concentration (DAC) established for unprotected workers. The mo
ISO 16639:2017 provides guidelines and performance criteria for sampling airborne radioactive substances in the workplace. Emphasis is on health protection of workers in the indoor environment. ISO 16639:2017 provides best practices and performance-based criteria for the use of air sampling devices and systems, including retrospective samplers and continuous air monitors. Specifically, this document covers air sampling program objectives, design of air sampling and monitoring programs to meet program objectives, methods for air sampling and monitoring in the workplace, and quality assurance to ensure system performance toward protecting workers against unnecessary inhalation exposures. The primary purpose of the surveillance of airborne activity concentrations in the workplace is to evaluate and mitigate inhalation hazards to workers in facilities where these can become airborne. A comprehensive surveillance program can be used to - determine the effectiveness of administrative and engineering controls for confinement, - measure activity concentrations of radioactive substances, - alert workers to high activity concentrations in the air, - aid in estimating worker intakes when bioassay methods are unavailable, - determine signage or posting requirements for radiation protection, and - determine appropriate protective equipment and measures. Air sampling techniques consist of two general approaches. The first approach is retrospective sampling, in which the air is sampled, the collection medium is removed and taken to a radiation detector system and analysed for radioactive substance, and the concentration results made available at a later time. In this context, the measured air concentrations are evaluated retrospectively. The second approach is continuous real-time air monitoring so that workers can be warned that a significant release of airborne radioactivity may have just occurred. In implementing an effective air sampling program, it is important to achieve a balance between the two general approaches. The specific balance depends on hazard level of the work and the characteristics of each facility. A special component of the second approach which can apply, if properly implemented, is the preparation of continuous air monitoring instrumentation and protocols. This enables radiation protection monitoring of personnel that have been trained and fitted with personal protective equipment (PPE) that permit pre-planned, defined, extended stay time in elevated concentrations of airborne radioactive substances. Such approaches can occur either as part of a planned re-entry of a contaminated area following an accidental loss of containment for accident assessment and recovery, or part of a project which involves systematic or routine access to radioactive substances (e.g. preparing process material containing easily aerosolized components), or handling objects such as poorly characterized waste materials that may contain radioactive contaminants that could be aerosolized when handled during repackaging. In this special case, the role of continuous air monitoring is to provide an alert to health physics personnel that the air concentrations of concern have exceeded a threshold such that the planned level of protection afforded by PPE has been or could be exceeded. This level would typically be many 10's or 100's of times higher than the derived air concentration (DAC) established for unprotected workers. The mo
EN ISO 16639:2019 is classified under the following ICS (International Classification for Standards) categories: 13.040.30 - Workplace atmospheres; 13.280 - Radiation protection. The ICS classification helps identify the subject area and facilitates finding related standards.
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Standards Content (Sample)
SLOVENSKI STANDARD
01-september-2019
Nadzorovanje koncentracije aktivnosti radioaktivnih snovi v zraku na delovnem
mestu v jedrskih postrojih (ISO 16639:2017)
Surveillance of the activity concentrations of airborne radioactive substances in the
workplace of nuclear facilities (ISO 16639:2017)
Überwachung der Aktivitätskonzentrationen von luftgetragenen radioaktiven Substanzen
an Arbeitsplätzen kerntechnischer Einrichtungen (ISO 16639:2017)
Surveillance de l’activité volumique des substances radioactives dans l’air des lieux de
travail des installations nucléaires (ISO 16639:2017)
Ta slovenski standard je istoveten z: EN ISO 16639:2019
ICS:
13.040.30 Kakovost zraka na delovnem Workplace atmospheres
mestu
13.280 Varstvo pred sevanjem Radiation protection
27.120.20 Jedrske elektrarne. Varnost Nuclear power plants. Safety
2003-01.Slovenski inštitut za standardizacijo. Razmnoževanje celote ali delov tega standarda ni dovoljeno.
EN ISO 16639
EUROPEAN STANDARD
NORME EUROPÉENNE
June 2019
EUROPÄISCHE NORM
ICS 13.280
English Version
Surveillance of the activity concentrations of airborne
radioactive substances in the workplace of nuclear
facilities (ISO 16639:2017)
Surveillance de l'activité volumique des substances Überwachung der Aktivitätskonzentrationen von
radioactives dans l'air des lieux de travail des luftgetragenen radioaktiven Substanzen an
installations nucléaires (ISO 16639:2017) Arbeitsplätzen kerntechnischer Einrichtungen (ISO
16639:2017)
This European Standard was approved by CEN on 8 March 2019.
CEN members are bound to comply with the CEN/CENELEC Internal Regulations which stipulate the conditions for giving this
European Standard the status of a national standard without any alteration. Up-to-date lists and bibliographical references
concerning such national standards may be obtained on application to the CEN-CENELEC Management Centre or to any CEN
member.
This European Standard exists in three official versions (English, French, German). A version in any other language made by
translation under the responsibility of a CEN member into its own language and notified to the CEN-CENELEC Management
Centre has the same status as the official versions.
CEN members are the national standards bodies of Austria, Belgium, Bulgaria, Croatia, Cyprus, Czech Republic, Denmark, Estonia,
Finland, Former Yugoslav Republic of Macedonia, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Latvia, Lithuania,
Luxembourg, Malta, Netherlands, Norway, Poland, Portugal, Romania, Serbia, Slovakia, Slovenia, Spain, Sweden, Switzerland,
Turkey and United Kingdom.
EUROPEAN COMMITTEE FOR STANDARDIZATION
COMITÉ EUROPÉEN DE NORMALISATION
EUROPÄISCHES KOMITEE FÜR NORMUNG
CEN-CENELEC Management Centre: Rue de la Science 23, B-1040 Brussels
© 2019 CEN All rights of exploitation in any form and by any means reserved Ref. No. EN ISO 16639:2019 E
worldwide for CEN national Members.
Contents Page
European foreword . 3
European foreword
The text of ISO 16639:2017 has been prepared by Technical Committee ISO/TC 85 "Nuclear energy,
nuclear technologies, and radiological protection” of the International Organization for Standardization
(ISO) and has been taken over as EN ISO 16639:2019 by Technical Committee CEN/TC 430 “Nuclear
energy, nuclear technologies, and radiological protection” the secretariat of which is held by AFNOR.
This European Standard shall be given the status of a national standard, either by publication of an
identical text or by endorsement, at the latest by December 2019, and conflicting national standards
shall be withdrawn at the latest by December 2019.
Attention is drawn to the possibility that some of the elements of this document may be the subject of
patent rights. CEN shall not be held responsible for identifying any or all such patent rights.
According to the CEN-CENELEC Internal Regulations, the national standards organizations of the
following countries are bound to implement this European Standard: Austria, Belgium, Bulgaria,
Croatia, Cyprus, Czech Republic, Denmark, Estonia, Finland, Former Yugoslav Republic of Macedonia,
France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Latvia, Lithuania, Luxembourg, Malta,
Netherlands, Norway, Poland, Portugal, Romania, Serbia, Slovakia, Slovenia, Spain, Sweden, Switzerland,
Turkey and the United Kingdom.
Endorsement notice
The text of ISO 16639:2017 has been approved by CEN as EN ISO 16639:2019 without any modification.
INTERNATIONAL ISO
STANDARD 16639
First edition
2017-01
Surveillance of the activity
concentrations of airborne radioactive
substances in the workplace of
nuclear facilities
Surveillance de l’activité volumique des substances radioactives dans
l’air des lieux de travail des installations nucléaires
Reference number
ISO 16639:2017(E)
©
ISO 2017
ISO 16639:2017(E)
© ISO 2017, Published in Switzerland
All rights reserved. Unless otherwise specified, 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.
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ii © ISO 2017 – All rights reserved
ISO 16639:2017(E)
Contents Page
Foreword .v
Introduction .vi
1 Scope . 1
2 Normative references . 2
3 Terms and definitions . 2
4 Symbols . 5
5 Developing the surveillance program . 5
5.1 Reasons for conducting a surveillance programme . 5
5.1.1 General. 5
5.1.2 Sampling when respiratory protective equipment is used . 6
5.1.3 Sampling to establish air contamination areas . 6
5.1.4 Air sampling as a basis for determining worker intakes. 6
5.1.5 Air monitoring for early warning of elevated air concentrations . 6
5.2 Graded approach to sampling . 7
5.3 Frequency of sampling . 8
5.3.1 General. 8
5.3.2 Grab vs. continuous sampling . 8
5.3.3 Continuous monitoring of activity concentrations . 8
5.3.4 Prompt analysis of certain samples . 9
5.4 Substitutes for air sampling . 9
6 Location of samplers and monitors . 9
6.1 General . 9
6.2 Types of air flow studies . 9
6.2.1 General. 9
6.2.2 Qualitative airflow studies . 9
6.2.3 Quantitative airflow studies .10
6.3 Location of samplers for estimating committed effective dose .10
6.4 Location of samplers for evaluating effectiveness of containment.11
6.5 Location of samplers for posting of air contamination areas .11
6.6 Location of portable samplers .12
6.7 Location of CAM for continuous monitoring of the activity concentration .12
7 Collection of samples .12
7.1 General .12
7.2 Sampling of aerosol particles .12
7.3 Gas Sampling .13
8 Evaluation of sampling results .14
8.1 Determining the average activity concentration .14
8.2 Uncertainty .14
8.3 Techniques for correcting for radon progeny interference .15
8.4 Evaluating changes in activity concentration over time .15
8.5 Review of sampling results.15
9 Evaluating the effectiveness of the sampling program .16
9.1 General .16
9.2 Dose-based assessment of the adequacy of the sampling program.16
10 Quality assurance and quality control .17
10.1 General .17
10.2 Sample identification, handling, and storage .17
10.3 Sampling and monitoring equipment .17
10.3.1 General.17
10.3.2 Performance of measuring instruments .18
ISO 16639:2017(E)
10.3.3 Air in-leakage testing .18
10.4 Documentation and record keeping .18
Annex A (informative) Examples for the determination of uncertainty, decision threshold
and detection limit according to ISO 11929 .20
Annex B (informative) Correcting for the interference of radon progeny.27
Annex C (informative) Normalized concentration and exposure .29
Annex D (informative) Example applications of evaluating sampling program sensitivity
from the viewpoint of potential missed exposure .30
Bibliography .32
iv © ISO 2017 – All rights reserved
ISO 16639:2017(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 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 . i so .org/ iso/ foreword .html.
The committee responsible for this document is ISO/TC 85, Nuclear energy, nuclear technologies, and
radiological protection, Subcommittee SC 2, Radiological protection.
ISO 16639:2017(E)
Introduction
Sampling of airborne radionuclides and monitoring of activity concentration in workplaces are critically
important for maintaining worker safety at facilities where dispersible radioactive substances are used.
Specifically, air sampling and monitoring are critical for evaluation of containment integrity, evaluation
of effectiveness of contamination control programs and work practices, providing measurements for
qualitative dose assessment, providing a general assessment of the level of the airborne hazard in a room,
and for providing workers an immediate warning when the activity concentration exceeds safe levels.
This document sets forth guidelines and performance criteria for sampling airborne radioactive
substances and monitoring activity concentration in the workplace of nuclear facilities. Emphasis is
on health protection for workers in indoor environments. This document provides best practices and
performance-based criteria for the use of sampling devices and systems, including delayed radioactivity
measurement samplers and continuous air monitors. Specifically, this document covers air sampling
program objectives, design of sampling and monitoring programs to meet program objectives, methods
for air sampling and monitoring in the workplace, and quality assurance to ensure system performance
toward protecting workers against unnecessary inhalation exposures. Taken together, these activities
constitute the sampling or surveillance program.
The primary purpose of the surveillance of airborne activity concentrations in the workplace is to
evaluate and mitigate inhalation hazards to workers in facilities where these may become airborne.
Results often provide the basis for development and evaluation of control procedures and may indicate
if engineering controls or operational changes are necessary.
The surveillance can consist of two general techniques. The first is retrospective sampling, in which
constituents of the air are sampled, the collection medium is removed and taken to a radiation detector
system and analysed for radioactive substances, and the activity concentration results made available
at a later time. In this context, the measured activity concentrations are evaluated retrospectively. The
second approach is real-time monitoring, in which activity concentrations are continuously monitored
so that workers can be warned that a significant release of airborne activity may have occurred. In
implementing an effective sampling program, it is important to achieve a proper balance between the
two general approaches of the program. The specific balance depends on the hazard level of the work
and the characteristics of each facility.
When designing a surveillance program, the optimization of worker protection minimizes internal
and external exposures while balancing social, technical, economic, practical, and public policy
considerations that are associated with the use of the radioactive substance.
A comprehensive surveillance program should also consider that the monitoring program is only one
element of a comprehensive radiation protection program. Therefore, individuals involved with the
monitoring program should interact with personnel working in the other elements of the radiation
protection program, such as contamination control and internal dosimetry.
vi © ISO 2017 – All rights reserved
INTERNATIONAL STANDARD ISO 16639:2017(E)
Surveillance of the activity concentrations of airborne
radioactive substances in the workplace of nuclear
facilities
1 Scope
This document provides guidelines and performance criteria for sampling airborne radioactive
substances in the workplace. Emphasis is on health protection of workers in the indoor environment.
This document provides best practices and performance-based criteria for the use of air sampling
devices and systems, including retrospective samplers and continuous air monitors. Specifically, this
document covers air sampling program objectives, design of air sampling and monitoring programs
to meet program objectives, methods for air sampling and monitoring in the workplace, and quality
assurance to ensure system performance toward protecting workers against unnecessary inhalation
exposures.
The primary purpose of the surveillance of airborne activity concentrations in the workplace is to
evaluate and mitigate inhalation hazards to workers in facilities where these can become airborne. A
comprehensive surveillance program can be used to
— determine the effectiveness of administrative and engineering controls for confinement,
— measure activity concentrations of radioactive substances,
— alert workers to high activity concentrations in the air,
— aid in estimating worker intakes when bioassay methods are unavailable,
— determine signage or posting requirements for radiation protection, and
— determine appropriate protective equipment and measures.
Air sampling techniques consist of two general approaches. The first approach is retrospective sampling,
in which the air is sampled, the collection medium is removed and taken to a radiation detector system
and analysed for radioactive substance, and the concentration results made available at a later time.
In this context, the measured air concentrations are evaluated retrospectively. The second approach
is continuous real-time air monitoring so that workers can be warned that a significant release of
airborne radioactivity may have just occurred. In implementing an effective air sampling program, it is
important to achieve a balance between the two general approaches. The specific balance depends on
hazard level of the work and the characteristics of each facility.
A special component of the second approach which can apply, if properly implemented, is the preparation
of continuous air monitoring instrumentation and protocols. This enables radiation protection
monitoring of personnel that have been trained and fitted with personal protective equipment (PPE)
that permit pre-planned, defined, extended stay time in elevated concentrations of airborne radioactive
substances. Such approaches can occur either as part of a planned re-entry of a contaminated area
following an accidental loss of containment for accident assessment and recovery, or part of a project
which involves systematic or routine access to radioactive substances (e.g. preparing process material
containing easily aerosolized components), or handling objects such as poorly characterized waste
materials that may contain radioactive contaminants that could be aerosolized when handled during
repackaging. In this special case, the role of continuous air monitoring is to provide an alert to health
physics personnel that the air concentrations of concern have exceeded a threshold such that the
planned level of protection afforded by PPE has been or could be exceeded. This level would typically be
many 10’s or 100’s of times higher than the derived air concentration (DAC) established for unprotected
workers. The monitoring alarm or alert would therefore be designed not to be confused with the normal
ISO 16639:2017(E)
monitoring alarm, and the action taken in response would be similarly targeted at the specific site and
personnel involved.
The air sampling strategy should be designed to minimize internal exposures and balanced with social,
technical, economic, practical, and public policy considerations that are associated with the use of the
radioactive substance.
A comprehensive air sampling strategy should also consider that the air sampling program is only
one element of a broader radiation protection program. Therefore, individuals involved with the air
sampling program should interact with personnel working in other elements of the radiation protection
program, such as contamination control and internal dosimetry.
This document does not address outdoor air sampling, effluent monitoring, or radon measurements.
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 11929, Determination of the characteristic limits (decision threshold, detection limit and limits of the
confidence interval) for measurements of ionizing radiation — Fundamentals and application
3 Terms and definitions
For the purposes of this document, the following terms and definitions apply.
ISO and IEC maintain terminological databases for use in standardization at the following addresses:
— IEC Electropedia: available at http:// www .electropedia .org/
— ISO Online browsing platform: available at http:// www .iso .org/ obp
3.1
accuracy
closeness of agreement between a measured value and a true value
3.2
aerodynamic diameter
D
a
-3
diameter of a sphere with density 1 000 kg·m that has the same sedimentation velocity in quiescent
air as the actual particle of arbitrary shape and density
3.3
aerosol
dispersion of solid or liquid particles in air or other gas
Note 1 to entry: An aerosol is not only the aerosol particles.
3.4
airborne radioactive substance
radioactive substance dispersed in the air in the form of dusts, fumes, particulates, mists, vapours,
or gases
3.5
air contamination area
area accessible to individuals where the measured activity concentrations of an airborne radioactive
substance exceeds or is likely to exceed the applicable national criteria
2 © ISO 2017 – All rights reserved
ISO 16639:2017(E)
3.6
air sampler
device designed to pass a known volume of air containing a radioactive substance through a filter or
other media and thereby trapping the airborne radioactive substance on the sampling media
3.7
annual limit on intake
ALI
derived limit for the amount of radioactive substance (in Bq) taken into the body of an adult worker by
inhalation or ingestion in a year
3.8
breathing zone
BZ
uniform description of the volume of air directly around the worker‘s upper body and head, which may
be drawn into the lungs during the course of breathing
Note 1 to entry: An air sample representative of the breathing zone is usually considered to be representative if
drawn from within about 30 cm of the worker’s head.
3.9
breathing zone sampler
BZA
air sampler located in the breathing zone
Note 1 to entry: Other common terms include “personal air sampler” (PAS), “personal air monitor” (PAM), “lapel
air samplers” or “fixed air sampler”.
Note 2 to entry: In the case of workers using PPE which includes full face (or even whole body suit) respirator
equipment and supplied air, as when preparing for entry into high levels of airborne radioactive substances,
special BZA or protective equipment samplers may be needed. Such BZAs are not always mandated then, but the
decision should be based on the contaminant levels and types of PPE involved and the potential for contamination
entering the suit or air immediately surrounding the suit just as PPE are being doffed.
3.10
continuous air monitor
CAM
instrument that continuously monitors the airborne activity concentration on a near real-time basis
3.11
continuous monitoring
active and continual monitoring of activity concentration in room air in near real time
Note 1 to entry: This approach uses continuous air monitors to assess activity concentration in air and can alarm
when predetermined levels are exceeded.
3.12
derived air concentration
DAC
concentration of a radionuclide in air that, if breathed over the period of a work year, would result in the
intake of one ALI for that radionuclide
Note 1 to entry: The DAC is calculated by dividing the ALI by the volume of air breathed by reference man under
-3
light-activity work during a working year (in Bq·m ).
Note 2 to entry: The parameter values recommended by the International Commission on Radiological Protection
3 -1 3
for calculating the DAC are a breathing rate of 1,2 m ·h and a working year of 2 000 h (i.e. 2 400 m ).
Note 3 to entry: The air concentration can be expressed in terms of a number of DAC. For example, if the DAC
-3 -3
for a given radionuclide in a particular form is 0,2 Bq·m and the observed concentration is 1,0 Bq·m , then the
observed concentration can also be expressed as 5 DAC (i.e. 1,0 divided by 0,2)
ISO 16639:2017(E)
Note 4 to entry: The derived air concentration-hour (DAC-h) is an integrated exposure and is the product of the
concentration of a radioactive substance in air (expressed as a fraction or multiple of DAC for each radionuclide)
and the time of exposure to that radionuclide, in hours.
[SOURCE: References [5] and [10], modified]
3.13
detection limit
L
D
smallest true value of the measurand which ensures a specified probability of being detectable by the
measurement procedure
Note 1 to entry: For a given type-I error (or false alarm probability, i.e. typically 0,05), L is the lowest net count
D
(or rate) with the desired probability of detection, i.e. typically 0,95 (otherwise stated as a type-II error of 0,05 or
a missed detection probability of 5 %).
Note 2 to entry: The measurand is the quantity subject to measurement.
3.14
grab sample
air sample of a sufficient volume drawn over a relatively short duration
3.15
intake
activity of a radionuclide taken into the body in a given time period or as a result of a given event
[SOURCE: ISO 20553:2006, 3.10]
3.16
personal air monitor
personal air sampler
breathing zone sampler
3.17
personal protective equipment
PPE
equipment designed to limit worker exposure to contaminants in the air or that are easily resuspended
from contaminated surfaces
Note 1 to entry: Includes partial or full-face respirators, face masks, gloves, boots, whole body anti-contamination
coveralls, and self-contained breathing apparatus (SCBA), depending on conditions.
3.18
potential missed exposure
PME
time-integrated activity concentration or maximum activity concentration, as applicable, that can
acceptably be missed
Note 1 to entry: The detection limit of the method of measuring the activity concentration shall be less than or
equal to the selected PME, which is defined according to ALARA/ALARP principles, and below legal limits.
3.19
sampling
collection of a radioactive substance on media such as filters, absorbers or adsorbers that is analysed
for radioactive content after collection
3.20
standard reference conditions
conditions of temperature and pressure to which measurements are referred for standardization
Note 1 to entry: For this document, the standard reference conditions are 25 °C temperature and 101 325 Pa
pressure.
4 © ISO 2017 – All rights reserved
ISO 16639:2017(E)
Note 2 to entry: Used to convert air densities to a common basis. Other temperature and pressure conditions may
be used and should be applied consistently.
3.21
surveillance
air monitoring and sampling, and the evaluation of the activity concentration measurement
4 Symbols
A activity, in Bq
-3
C activity concentration, defined as activity per volume, in Bq·m
D aerodynamic aerosol particle diameter, in μm
a
E(τ) committed effective dose, in Sv
-1
e dose coefficient for inhalation, in Sv·Bq (committed effective dose per unit intake
inh
such as those in Reference [9])
L annual dose limit, in Sv (an annual limit on the total effective dose equivalent to an
individual)
3 -1 3 -1
q flowrate, in m ·s or m ·h
3 -1 3 -1
Q breathing rate, in m ·s or m ·h
B
-1
R net count rate from the assay system, in s
N
T annual exposure time, in s
E
T sampling time span, in s
S
ε collection efficiency
C
ε counting (measurement) efficiency of the assay system for a reference standard, in
r
-1 -1
Bq ·s
ε efficiency modification factor for counting (measuring) an actual sample as opposed
S
to the reference standard (e.g. the dimensionless alpha self-absorption factor for
particulate alpha on glass fiber filters)
5 Developing the surveillance program
5.1 Reasons for conducting a surveillance programme
5.1.1 General
The specific techniques used in a sampling or surveillance program are based on the purpose(s) of the
sampling. Even if airborne concentrations are very low, sampling may be conducted routinely due to
the potential for high exposures and doses, should releases occur (e.g. in facilities with glove boxes).
Sampling in the workplace can be used to determine the following parameters:
— effectiveness of engineering and administrative controls for the confinement of radioactive
substances;
ISO 16639:2017(E)
— measurement of activity concentrations of airborne radioactive substances in the workplace for
assessment of inhalation risk;
— estimation of worker intakes when bioassay methods are deficient or unavailable;
— confirmation of appropriate air contamination area posting requirements;
— appropriateness of PPE;
— provision of early warning or detection of the release of radioactive substances in the workplace.
5.1.2 Sampling when respiratory protective equipment is used
A special component of the second approach which can apply, if properly implemented, is the preparation
of continuous air monitoring instrumentation and protocols which enable radiation protection
monitoring of personnel that have been trained and are using PPE that permit pre-planned, defined,
extended stay time in elevated concentrations of airborne radioactive substances. Such applications
can occur either as part of a planned re-entry of a contaminated area following an accidental loss of
containment for accident assessment and recovery, or part of a project which involves systematic or
routine access to radioactive substances (e.g. preparing process material containing easily aerosolized
components), or handling objects such as poorly characterized waste materials that may contain
radioactive contaminants that could be aerosolized when handled during repackaging. In this special
case, the role of continuous air monitoring is to provide an alert to health physics personnel that the
air concentration(s) of concern have exceeded a threshold such that the planned level of protection
afforded by PPE has been or could be exceeded. This level would typically be 10’s or 100’s of DAC. The
monitoring alarm or alert would therefore be designed not to be confused with the normal monitoring
alarm, and the action taken in response would be similarly targeted at the specific site and personnel
involved.
5.1.3 Sampling to establish air contamination areas
Air samplers located to sample general room air or at a specific work location can be used as an aid to
evaluate the need for posting the area as an airborne radioactivity area. Areas should not be posted
as airborne radioactivity areas on the basis of unlikely accidents; rather, airborne radioactivity areas
should be established based on the radioactivity levels normally encountered or on levels that can
reasonably be expected to occur when work is being performed.
5.1.4 Air sampling as a basis for determining worker intakes
Air sampling is a tool for internal dosimetry primarily to help identify when an intake may have
occurred, and is an indication of the magnitude of an intake. It is not usually the primary tool for
individual worker intake and dose assessment, but may be used as such by internal dosimetry programs
in the absence of appropriate bioassay data. Specifically, the estimation of internal dose shall be based
on bioassay data rather than air concentration values unless bioassay data are 1) unavailable, 2)
inadequate, or 3) internal dose estimates based on air concentration values are demonstrated to be as
or more accurate. Some regulatory bodies accept air sample results as being appropriate for assigning
intakes when circumstances indicate that this would be the most reliable option. There is nothing in
this document that is contrary to this practice, provided that use of air sampling, which is generally less
accurate for assigning intakes than bioassay, is justified.
5.1.5 Air monitoring for early warning of elevated air concentrations
Air monitors can provide early warning to workers regarding elevated radioactivity concentrations.
This real-time monitoring can be an effective method to reduce or eliminate exposures to the airborne
radioactive substance or gas.
6 © ISO 2017 – All rights reserved
ISO 16639:2017(E)
5.2 Graded approach to sampling
The extent and type of sampling should be based on estimates of worker intakes and on estimated
activity concentrations of airborne radioactive substances as illustrated in Table 1. Estimates of intakes
and concentrations may be based on historical sampling or bioassay data if these data are available.
If the data are not available, a survey program should be established based on likely radiological
conditions, probability of change in conditions, and area occupancy factors. Considerations for this
evaluation may include the following:
a) quantity of radioactive substance being handled;
b) ALI of the substance;
c) release fraction for the radioactive substance based on its physical form and use;
d) type of confinement for the substance;
e) other factors appropriate for the specific facility (such as national regulations or license
requirements).
The estimated prospective intake levels given in Table 1 are an illustration that may be used to guide
decisions regarding sampling resources used in different situations. Alternatively, a sampling resource
[1] [3]
allocation scheme may be based on containment classes (see ISO 17873 and ISO 26802 ) or according
to other local or national guidelines. The person in charge of the radiation safety program should use
all appropriate information, professional judgment, and historical experience to perform sampling
appropriate for the specific situation in keeping with the as low as reasonably achievable/practicable
(ALARA/ALARP) principle.
Table 1 — Example of sampling recommendations based on ALI and airborne concentrations
expressed as fractions of the ALI
Annual intake
as a fraction of Sampling recommendations
ALI
Sampling is generally not necessary. However, monthly or quarterly grab
<0,02 samples or some other measurement (e.g. surface contamination) may be
appropriate to confirm that airborne levels are indeed low.
Sampling is appropriate. Intermittent or grab samples are appropriate
near the lower end of the range depending on the nature of the work being
performed.
Continuous sampling is appropriate if activity concentrations are likely
to cause an exposure exceeding 12 DAC-h during a time period of a week
≥0,02 and <1,0
or longer.
A demonstration that the samples are representative of the breathing zone
air is appropriate if intakes of record are based on sampling.
Additional investigation by bioassay methods may be considered.
Perform continuous monitoring with alarm capability, as necessary, provid-
ed there is a reasonable potential for concentrations to cause an exposure
exceeding 40 DAC-h during a time period of a week or less.
≥1,0
Samples should be analysed before work resumes the next day, and results
should be available before the next shift ends. Credit may be taken for pro-
tection factors if respiratory protection is used.
ISO 16639:2017(E)
5.3 Frequency of sampling
5.3.1 General
The frequency of sample collection should be based on occupancy rates, hazard levels, purposes of
sampling (e.g. worker protection and/or verifying containment), and requirements for minimum levels
of detection. Grab samples may be used in non-routinely occupied work rooms. Often, continuous
monitoring is also conducted in routinely occupied areas where workers are likely to be exposed to
an activity concentration exceeding 1-DAC over a 40-hour work week or 5-DAC in an 8-hour work day
(both typically called 40 DAC-h). The selected sampling approach and frequency should be designed to
ensure detection limits, as related to radiation protection goals are met.
5.3.2 Grab vs. continuous sampling
Air sampling may be continuous during work hours or intermittent (e.g. grab samples taken during part
of the work). The distinction between grab and continuous air sampling is the duration of collection. The
resultant data are an estimate of concentration (DAC, and hence potential exposure rate) averaged over
that time. With continuous air monitoring, a real-time detection device or system is active during the
sampling process, and the resultant data has the form of the product of concentration in air (fraction of
DAC) and duration of sampling or potential exposure (number of DAC-h). In the latter case an estimate
of a person’s dose can be determined. On the other hand, when continuous sampling during the work
day is performed, a weekly sample exchange period is generally acceptable (except for shorter-lived
radionuclides or when airb
...
The article discusses the guidelines and performance criteria outlined in EN ISO 16639:2019 for monitoring the activity concentrations of airborne radioactive substances in the workplace of nuclear facilities. The emphasis is on protecting the health of workers in indoor environments. The document provides best practices for air sampling programs, including the use of air sampling devices and systems. It covers the objectives and design of air sampling and monitoring programs, methods for air sampling and monitoring, and quality assurance measures to ensure worker safety. The primary purpose of surveillance is to evaluate and mitigate inhalation hazards for workers. The article mentions various uses of a comprehensive surveillance program, such as evaluating control measures, measuring activity concentrations, alerting workers to high concentrations, estimating worker intakes, determining requirements for radiation protection signage, and identifying appropriate protective equipment. The article also discusses two approaches to air sampling: retrospective sampling, where air samples are collected and analyzed at a later time, and real-time monitoring, which provides immediate warnings to workers. A balance between the two approaches is recommended based on the hazard level and facility characteristics. The article also mentions the special case of continuous air monitoring for personnel wearing personal protective equipment in elevated concentrations of airborne radioactive substances. This monitoring serves as an alert to health physics personnel when the air concentrations exceed a threshold for worker protection.
記事タイトル: EN ISO 16639:2019 - 原子力施設の職場における空気中放射性物質の活性濃度の監視 (ISO 16639:2017) 記事内容: ISO 16639:2017は、職場の空気中の放射性物質をサンプリングするためのガイドラインと性能基準を提供しています。重点は屋内環境での労働者の健康保護にあります。 ISO 16639:2017は、後戻り型のサンプラーや連続的な空気モニターを含む空気サンプリング装置とシステムの使用のためのベストプラクティスと性能基準を提供しています。具体的には、空気サンプリングプログラムの目標、目標を達成するための空気サンプリングとモニタリングプログラムの設計、職場での空気サンプリングとモニタリング方法、労働者が不必要な吸入曝露から保護されるためのシステムの性能保証について述べています。 職場での活性濃度の監視の主な目的は、空気中に移行しうる場所での労働者の吸入危険性を評価し、軽減することです。包括的な監視プログラムは、以下のような様々な用途に使用されます。 - 制御策の効果を評価するために - 放射性物質の活性濃度を測定するために - 空気中の高い活性濃度に労働者が警告を受けるために - 生体測定法が利用できない場合に労働者の摂取量を推定するために - 放射線防護のための標識や掲示要件を決定するために - 適切な保護具と措置を決定するために 空気サンプリング技術には、一般的に2つのアプローチがあります。最初のアプローチは後戻り型のサンプリングであり、空気をサンプリングし、収集媒体を取り除いて放射線検出器システムで分析し、濃度結果を後で利用できるようにします。この文脈では、測定された空気濃度は後戻り的に評価されます。二つ目のアプローチはリアルタイムで連続的に空気を監視することで、労働者に即時の警告を提供します。効果的な空気サンプリングプログラムの実施では、二つのアプローチのバランスを達成することが重要です。具体的なバランスは、作業のハザードレベルと施設の特性に基づいて決められます。 特定の状況では、適切に実施された場合には連続的な空気モニタリング装置とプロトコルの準備が適用されることがあります。これにより、訓練を受けた健康物理学のスタッフが個人防護具（PPE）を身に着け、空気中の高い放射能物質の濃度で予定された一定の長時間滞在が可能となります。このようなアプローチは、事故が発生した後の汚染地域への計画された再入場や清掃などの事故評価と回復、放射性物質への定期的なアクセス（例：容易にエアロゾル化される成分を含むプロセス材料の準備）や再パッケージング時の処理物品のような、放射性汚染物質を含む未評価の物品の処理時に適用されることがあります。この特殊なケースでは、連続的な空気モニタリングの役割は、PPEが提供する計画された保護レベルが超える可能性のある濃度の空気を健康物理学のスタッフに通知することです。このレベルは、通常、無防護の労働者に対して設定される導出空気濃度（DAC）よりもはるかに数十倍または数百倍高いことがあります。
기사 제목: EN ISO 16639:2019 - 핵시설 작업장의 공기 중 방사성 물질 농도 감시 (ISO 16639:2017) 기사 내용: ISO 16639:2017은 작업장에서 공기 중 방사성 물질을 채취하는 가이드라인과 성능 기준을 제공합니다. 주요한 것은 실내 환경에서 근로자의 건강 보호에 중점을 두고 있습니다. ISO 16639:2017은 후향적인 샘플러와 연속적인 공기 감시 장치를 포함한 공기 채취 장치와 시스템의 사용에 대한 최선의 방법 및 성능 기준을 제공합니다. 구체적으로, 이 문서는 공기 채취 프로그램의 목표, 프로그램 목표를 충족시키기 위한 공기 채취와 감시 프로그램의 설계, 작업장에서의 공기 채취와 감시 방법, 작업자의 불필요한 흡입 노출을 방지하기 위한 시스템의 성능에 대한 품질 보증을 다룹니다. 작업장에서의 공기 중 농도 감시의 주요 목표는 공기 중으로 이동할 수 있는 기반시설에서 근로자들에게 나타날 수 있는 흡입 위험을 평가하고 완화하는 것입니다. 포괄적인 감시 프로그램은 다음과 같은 용도로 사용될 수 있습니다. - 구획 제어의 효과성을 판단하기 위해, - 방사성 물질의 농도를 측정하기 위해, - 공기 중 높은 농도를 일으킬 수 있는 경우 근로자에게 경보를 발송하기 위해, - 생물 안전 테스트 방법을 사용할 수 없는 경우 근로자의 흡수량을 추정하기 위해, - 방사선 보호를 위한 표지판 또는 게시 요건을 결정하기 위해, - 적절한 보호 장비와 조치를 결정하기 위해. 공기 채취 기술은 일반적으로 두 가지 접근 방식으로 이루어집니다. 첫 번째 접근 방식은 후향적인 채취로서, 공기를 채취한 후 수집 매체를 제거하여 방사성 물질을 검출기로 운반하고 나중에 농도 결과를 제공합니다. 이 경우, 측정된 공기 농도는 후향적으로 평가됩니다. 두 번째 접근 방식은 연속적인 실시간 공기 감시로, 근로자들이 공기 중의 방사능 물질 높은 농도로 인해 경고를 받을 수 있도록 합니다. 효과적인 공기 채취 프로그램을 실행하기 위해서는 두 가지 접근 방식 사이에서 균형을 달성하는 것이 중요합니다. 특히 작업의 위험 수준과 각 시설의 특성에 따라 균형을 맞추는 것이 권장됩니다. 제대로 구현된 경우 가능한 특수한 접근 방식은 연속적인 공기 감시장비와 프로토콜 준비입니다. 이를 통해 훈련을 받고 개인 보호 장비를 착용한 건강물리학 인원들이 미리 계획된 상태로 공기 중 방사능 물질의 높은 농도에서 오랜 기간 머물 수 있게 됩니다. 이러한 접근 방식은 사고로 인한 방출 손실 후에 오염된 지역에 계획된 재진입 또는 청소 등을 위한 사고 평가 및 복구, 방사성 물질에 관련된 시스템적인 루틴 접근 (예: 쉽게 기화되는 구성 요소가 포함된 공정 물질을 준비하는 작업) 또는 다루는 물질을 재포장하는 동안 오염된 물질을 포함할 수 있는 특성을 가진 물체 다루기와 관련하여 발생할 수 있습니다. 이 특수한 경우에 연속적인 공기 감시의 역할은 헬스 물리학 인원에게 경고를 제공하여 개인 보호 장비로 제공되는 계획된 수준의 보호가 벗어날 수 있음을 알리는 것입니다. 이 수준은 일반적으로 보호되지 않은 근로자를 위해 설정된 유도 공기 농도(DAC)보다 훨씬 여러 개의 10~100 배 높을 수 있습니다.
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