EN ISO 12807:2021

Safe transport of radioactive materials - Leakage testing on packages (ISO 12807:2018)

This document specifies gas leakage test criteria and test methods for demonstrating that packages used to transport radioactive materials comply with the package containment requirements defined in the International Atomic Energy Agency (IAEA) Regulations for the Safe Transport of Radioactive Material for:
—          design verification;
—          fabrication verification;
—          preshipment verification;
—          periodic verification;
—          maintenance verification.
This document describes a method for relating permissible activity release of the radioactive contents carried within a containment system to equivalent gas leakage rates under specified test conditions. This approach is called gas leakage test methodology. However, in this document it is recognized that other methodologies might be acceptable, provided that they demonstrate that any release of the radioactive contents will not exceed the regulatory requirements, and subject to agreement with the competent authority.
This document provides both overall and detailed guidance on the complex relationships between an equivalent gas leakage test and a permissible activity release rate. Whereas the overall guidance is universally agreed upon, the use of the detailed guidance shall be agreed upon with the competent authority during the Type B(U), Type B(M) or Type C packages certification process.
It should be noted that, for a given package, demonstration of compliance is not limited to a single methodology.
While this document does not require particular gas leakage test procedures, it does present minimum requirements for any test that is to be used. It is the responsibility of the package designer or consignor to estimate or determine the maximum permissible release rate of radioactivity to the environment and to select appropriate leakage test procedures that have adequate sensitivity.
This document pertains specifically to Type B(U), Type B(M) or Type C packages for which the regulatory containment requirements are specified explicitly.

Kernbrennstofftechnologie - Sicherer Transport von radioaktivem Material - Dichtheitsprüfung der Verpackung (ISO 12807:2018)

Dieses Dokument legt Prüfkriterien und Prüfverfahren für die Messung der Gasleckage fest, um nachzuweisen, dass Versandstücke für den Transport radioaktiven Materials die Anforderungen an sichere Verpackungen im Dokument Regulations for the Safe Transport of Radioactive Material der International Atomic Energy Agency (IAEA) erfüllen, für die
- Designverifizierung,
- Verifizierung bei der Fertigung,
- Verifizierung vor Versand,
- regelmäßige Verifizierung, und
- Verifizierung bei Wartung.
Dieses Dokument beschreibt ein Verfahren, mit der die zulässige Aktivitätsfreisetzung radioaktiven Inhalts in einem Umschließungssystem unter vorgegebenen Prüfbedingungen zu äquivalenten Gasleckageraten in Bezug gesetzt werden kann. Dieser Ansatz wird als die Gasleckage-Prüfmethodik bezeichnet. Jedoch wird in diesem Dokument anerkannt, dass auch andere Verfahren zulässig sein könnten, sofern mit ihnen nachgewiesen werden kann, dass eine Freisetzung des radioaktiven Inhalts die behördlichen Anforderungen nicht übersteigt und diese mit der zuständigen Behörde abgestimmt werden.
Dieses Dokument stellt sowohl eine allgemeine als auch eine detaillierte Anleitung zu den komplexen Beziehungen zwischen einer Prüfung der äquivalenten Gasleckage und einer zulässigen Aktivitäts-freisetzungsrate bereit. Während die allgemeine Anleitung allgemein anerkannt ist, muss die Anwendung der detaillierten Anleitung mit der zuständigen Behörde während der Zertifizierung von Versandstücken Typ B(U), Typ B(M) oder Typ C vereinbart werden.
Es wird darauf hingewiesen, dass der Nachweis der Erfüllung der Anforderung nicht auf eine einzelne Methodik beschränkt ist.
Dieses Dokument verlangt keine bestimmten Prüfverfahren für Gasleckagen, legt jedoch Mindestanforderungen für jede Prüfung fest, die angewandt wird. Der Konstrukteur oder Lieferant des Versandstücks ist für die Abschätzung oder Bestimmung der maximal zulässigen Freisetzungsrate von Radioaktivität in die Umgebung und für die Wahl der geeigneten Leckage-Prüfverfahren, die eine angemessene Empfindlichkeit aufweisen, verantwortlich.
Dieses Dokument bezieht sich gezielt auf Versandstücke Typ B(U), Typ B(M) oder Typ C, für die die behördlich festgesetzten Anforderungen an eine dichte Umschließung explizit festgelegt sind.

Sûreté des transports de matières radioactives - Contrôle de l'étanchéité des colis (ISO 12807:2018)

Le présent document donne les critères applicables aux essais d'étanchéité au gaz et les méthodes de contrôle permettant de vérifier que les colis utilisés pour transporter les matières radioactives sont conformes aux exigences pour le confinement définies dans le Règlement de transport des matières radioactives de l'Agence internationale de l'énergie atomique (AIEA), du point de vue des:
—          contrôles à la conception;
—          contrôles en cours de fabrication;
—          contrôles avant expédition;
—          contrôles périodiques;
—          contrôles de maintenance.
Le présent document décrit une méthodologie qui permet d'établir une relation entre le relâchement d'activité admissible du contenu radioactif transporté dans une enveloppe de confinement et les flux de fuite équivalents d'un gaz, dans des conditions d'essai données. II s'agit de la méthodologie de contrôle d'étanchéité au gaz. Cependant, le présent document admet que d'autres méthodologies puissent être suivies, avec l'accord de l'autorité compétente, à condition qu'elles démontrent que toute perte de contenu radioactif n'excédera pas les exigences réglementaires.
Le présent document fournit des lignes directrices à la fois générales et détaillées sur les relations complexes entre un essai de flux de fuite équivalent et le taux admissible de relâchement d'activité. Étant donné que les lignes directrices générales sont reconnues universellement, l'utilisation des lignes directrices détaillées doit faire l'objet d'un accord avec l'autorité compétente lors de la certification des colis de type B(U), B(M) ou C.
II convient de noter que la démonstration de la conformité d'un colis donné n'est pas limitée à la mise en œuvre d'une seule méthodologie.
Bien que le présent document n'impose pas de méthode spécifique d'essai d'étanchéité au gaz, il indique des exigences minimales pour toute méthode susceptible d'être utilisée. II incombe au concepteur, ou à l'expéditeur du colis, d'estimer ou de déterminer, le taux de relâchement maximal admissible de matière radioactive dans l'environnement et de choisir des procédures d'essai d'étanchéité appropriées qui présentent la sensibilité requise.
Le présent document s'applique tout particulièrement aux colis de type B(U), B(M) ou C pour lesquels les exigences réglementaires pour le confinement sont spécifiées explicitement.

Varen prevoz radioaktivnih snovi - Preskušanje tesnjenja embalaže (ISO 12807:2018)

General Information

• Status: Published
• Publication Date: 09-Feb-2021
• Withdrawal Date: 30-Aug-2021
• ICS: 13.280 - Radiation protection
• ICS: 27.120.30 - Fissile materials and nuclear fuel technology
• Technical Committee: CEN/TC 430 - Nuclear energy, nuclear technologies, and radiological protection
• Drafting Committee: CEN/TC 430 - Nuclear energy, nuclear technologies, and radiological protection
• Current Stage: 6060 - Definitive text made available (DAV) - Publishing
• Start Date: 10-Feb-2021
• Due Date: 22-Sep-2022
• Completion Date: 10-Feb-2021
• Ref Project: SIST EN ISO 12807:2021 - Safe transport of radioactive materials - Leakage testing on packages (ISO 12807:2018)

Standards Content (Sample)

SLOVENSKI STANDARD
01-april-2021
Varen prevoz radioaktivnih snovi - Preskušanje tesnjenja embalaže (ISO
12807:2018)
Safe transport of radioactive materials - Leakage testing on packages (ISO 12807:2018)
Kernbrennstofftechnologie - Sicherer Transport von radioaktivem Material -
Dichtheitsprüfung der Verpackung (ISO 12807:2018)
Sûreté des transports de matières radioactives - Contrôle de l'étanchéité des colis (ISO
12807:2018)
Ta slovenski standard je istoveten z: EN ISO 12807:2021
ICS:
13.280 Varstvo pred sevanjem Radiation protection
27.120.30 Cepljivi materiali in jedrska Fissile materials and nuclear
gorivna tehnologija fuel technology
2003-01.Slovenski inštitut za standardizacijo. Razmnoževanje celote ali delov tega standarda ni dovoljeno.

EN ISO 12807
EUROPEAN STANDARD
NORME EUROPÉENNE
February 2021
EUROPÄISCHE NORM
ICS 13.280; 27.120.30
English Version
Safe transport of radioactive materials - Leakage testing on
packages (ISO 12807:2018)
Sûreté des transports de matières radioactives - Kernbrennstofftechnologie - Sicherer Transport von
Contrôle de l'étanchéité des colis (ISO 12807:2018) radioaktivem Material - Dichtheitsprüfung der
Verpackung (ISO 12807:2018)
This European Standard was approved by CEN on 18 January 2021.

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, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Latvia, Lithuania, Luxembourg, Malta, Netherlands, Norway,
Poland, Portugal, Republic of North Macedonia, 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
© 2021 CEN All rights of exploitation in any form and by any means reserved Ref. No. EN ISO 12807:2021 E
worldwide for CEN national Members.

Contents Page
European foreword . 3

European foreword
The text of ISO 12807:2018 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 12807:2021 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 August 2021, and conflicting national standards shall
be withdrawn at the latest by August 2021.
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, France, Germany, Greece, Hungary, Iceland,
Ireland, Italy, Latvia, Lithuania, Luxembourg, Malta, Netherlands, Norway, Poland, Portugal, Republic of
North Macedonia, Romania, Serbia, Slovakia, Slovenia, Spain, Sweden, Switzerland, Turkey and the
United Kingdom.
Endorsement notice
The text of ISO 12807:2018 has been approved by CEN as EN ISO 12807:2021 without any modification.

INTERNATIONAL ISO
STANDARD 12807
Second edition
2018-09
Safe transport of radioactive
materials — Leakage testing on
packages
Sûreté des transports de matières radioactives — Contrôle de
l'étanchéité des colis
Reference number
ISO 12807:2018(E)
©
ISO 2018
ISO 12807:2018(E)
© ISO 2018
All rights reserved. Unless otherwise specified, or required in the context of its implementation, no part of this publication may
be reproduced or utilized otherwise in any form or by any means, electronic or mechanical, including photocopying, or posting
on the internet or an intranet, without prior written permission. Permission can be requested from either ISO at the address
below or ISO’s member body in the country of the requester.
ISO copyright office
CP 401 • Ch. de Blandonnet 8
CH-1214 Vernier, Geneva
Phone: [phone]
Fax: [phone]
Email: [e-mail]
Website: www.iso.org
Published in Switzerland
ii © ISO 2018 – All rights reserved

ISO 12807:2018(E)
Contents Page
Foreword .v
Introduction .vi
1 Scope . 1
2 Normative references . 1
3 Terms and definitions . 1
4 Symbols and units . 4
5 Regulatory requirements . 7
5.1 Relevant regulations. 7
5.2 Regulatory containment requirements . 7
6 Procedure for meeting the requirements of this document . 7
6.1 General . 7
6.2 Quality management system . 8
6.3 Procedure . 8
6.3.1 General. 8
6.3.2 Determination of permissible activity release rates . 9
6.3.3 Determination of standardized leakage rates.10
6.3.4 Determination of permissible test leakage rates for each verification stage .10
6.3.5 Selection of appropriate test methods .10
6.3.6 Performance of test and record of results . .10
7 Determination of permissible activity release rates .10
7.1 Step 1: List the radioactive contents, A .
i 10
7.2 Step 2: Determine the total releasable activity, RI .
T 10
7.3 Step 3: Determine the maximum permissible activity release rates, R . 11
8 Determination of standardized leakage rates .11
8.1 General .11
8.2 Step 4: Determine the activity release rate due to permeation, RP . 12
8.3 Step 5: Determine the maximum permissible activity release rate due to leakage, RG . 12
8.4 Step 6: Determine the activity per unit volume of the containment system medium, C . 12
8.5 Step 7: Determine the maximum permissible volumetric leakage rate of the medium, L . 12
8.6 Step 8: Determine the maximum permissible equivalent capillary leak diameter, D . 12
8.7 Step 9: Determine the permissible standardized leakage rate, Q .
SLR 13
9 Containment-system verification requirements .13
9.1 Containment-system verification stages .13
9.1.1 General.13
9.1.2 Design verification .14
9.1.3 Fabrication verification .14
9.1.4 Preshipment verification .14
9.1.5 Periodic verification .15
9.1.6 Maintenance verification .15
9.2 Verification requirements .15
9.2.1 General.15
9.2.2 Step 10: Determine permissible test leakage rate for each verification
stage, Q , Q , Q Q Q and Q .
TDA TDN TF, TS, TP TM 15
9.2.3 Step 11: Select appropriate test methods .15
10 Leakage test procedure requirements .16
10.1 General .16
10.2 Step 12: Perform tests and record results .16
10.3 Test sensitivity .16
10.4 Test procedure requirements .16
10.4.1 General.16
ISO 12807:2018(E)
10.4.2 Testing .16
Annex A (infor
...