For nuclear power plants, ISO 26802:2010 addresses only reactors that have a secondary confinement system based on IAEA recommendations.

For research reactors, ISO 26802:2010 applies specifically to reactors for which accidental situations can challenge the integrity or leak-tightness of the containment barrier, i.e. in which a high-pressure or -temperature transient can occur and for which the isolation of the containment building and the shut-off of the associated ventilation systems of the containment building is required.

The requirements of ISO 26802:2010 apply to research reactors in which the increase of pressure or temperature during accidental situations do not risk damaging the ventilation systems, although the requirements applicable for the design and the use of ventilation systems are given in ISO 17873.

The method can be applied for heavy water isotopic purity measurements in a heavy water reactor power plant or research reactor, heavy water production factory and heavy water related areas.

[1] This edition is based on ANSI/ANS-6.1.2-2013^[1].

An in-service eddy current test of steam generator heating tube plugs as a component of the primary circuit is not an object of this document. Owing to the different embodiments of steam generator heating tube plugs, the use of specially adapted test systems to be qualified is necessary.

Test systems for the localisation of inhomogeneities (surface) and requirements for test personnel, test devices, the preparation of test and device systems, the implementation of the testing as well as the recording are defined.

NOTE Data concerning the test section, test extent, inspection period, inspection interval and evaluation of indications is defined in the nuclear safety standards.

It is recommended that the technical specifications are based on experience on U-tube bends with even bend radius (similar to the S/KWU design). To test other kind of tube bends (e.g. U-tube bends with two 90° bends) further qualifications will be provided.

— general visual testing (overview), or

— selective visual testing (specific properties).

This document is also applicable to other components of nuclear installations. The requirements in this document focuses on remote (mechanized) visual testing, but also specifies global requirements for direct visual testing. For specific requirements for direct visual testing of welds see ISO 17637.

This document is not applicable to tests in respect to the general state that are carried out in conjunction with pressure and leak tests and regular plant inspections.

This document specifies test methods that allow deviations from the expected state to be recognised, requirements for the equipment technology and test personnel, the preparation and performance of the testing as well as the recording.

NOTE Data concerning the test section, test extent, inspection period, inspection interval and evaluation of indications is defined in the applicable national nuclear safety standards.

This document specifies the test technique, the requirements for measuring equipment and additional devices, the preparation and performance of the test as well as the recording and documentation, for the purpose to ensure the reliability and comparability of tests.

NOTE Data on (test) pressure, (test) temperature, scope of testing, rates of change of pressure and temperature, test schedule and inspection intervals can be obtained from the applicable national nuclear codes.

Test systems for the localisation of surface inhomogeneities and requirements for test personnel, test devices, test media, accessories as well as optical auxiliaries, the preparation and implementation of the test as well as the recording are defined.

NOTE 1 Data concerning the test section, test extent, inspection period, inspection interval and evaluation of indications are defined in the applicable national nuclear safety standards.

NOTE 2 In general, this document is in accordance with ISO 3452 and ISO 9934 series. This document provides details to be considered in the standard test procedure (see Annex A).

Mechanized ultrasonic inspections are carried out in order to enable an evaluation in case of

— fault indications (e.g. on austenitic weld seams or complex geometry),

— indications due to geometry (e.g. in case of root concavity),

— complex geometries (e.g. fitting weld seams), or

— if a reduction in the radiation exposure of the test personnel can be attained in this way.

Ultrasonic test methods are defined for the validation of discontinuities (volume or surface open), requirements for the ultrasonic test equipment, for the preparation of test and device systems, for the implementation of the test and for the recording.

This document is applicable for the detection of indications by UT using normal-beam probes and angle-beam probes both in contact technique. It is to be used for UT examination on ferritic and austenitic welds and base material as search techniques and for comparison with acceptance criteria by the national referencing nuclear safety standards. Immersion technique and techniques for sizing are not in the scope of this document and are independent qualified.

NOTE Data concerning the test section, test extent, inspection period, inspection interval and evaluation of indications is defined in the applicable national nuclear safety standards.

Unless otherwise specified in national nuclear safety standards the minimum requirements of this document are applicable. This document does not define:

— extent of examination and scanning plans;

— acceptance criteria;

— UT techniques for dissimilar metal welds and for sizing (have to be qualified separately);

— immersion techniques;

— time-of-flight diffraction technique (TOFD).

It is recommended that UT examinations are nearly related to the component, the type and size of defects to be considered and are reviewed in specific national inspection qualifications.

NOTE Ces données d'irradiation peuvent être la fluence neutronique ou les déplacements par atome (dpa), et la production d'Hélium.

Cette évaluation s'appuie à la fois sur des calculs de flux de neutrons et sur des données de mesures de dosimétrie à l'intérieur de la cuve et de la cavité, selon les cas. Le présent document s'applique aux réacteurs à eau sous pression (Pressurized Water Reactors, PWR), aux réacteurs à eau bouillante (Boiling Water Reactors, BWR) et aux réacteurs à eau lourde pressurisée (Pressurized Heavy Water Reactors, PHWR).

Le présent document donne également une procédure d'évaluation des endommagements dus aux neutrons sur la cuve sous pression du réacteur et les composants internes des PWR, BWR et PHWR. Les endommagements sont axés sur les dommages de déplacements atomiques causés par le déplacement direct des atomes dû aux collisions avec les neutrons, et sur les dommages indirects causés par la production de gaz, les deux types de dommages étant fortement dépendants du spectre d'énergie des neutrons. Pour une fluence neutronique et un spectre d'énergie des neutrons donnés, le calcul du nombre cumulé total de déplacements atomiques est donc une donnée importante à utiliser pour la gestion de la durée de vie du réacteur.