Energy

1.1

This Standard specifies mechanical and electrical requirements for dispensers of compressed hydrogen gas intended for fuel storage systems integral to hydrogen powered vehicles at pressures of 25, 35, 50, and 70 MPa.

Dispensing systems covered by this Standard include

a)    HGV dispensers that integrate all dispensing system components in a single unit, as needed, fuel metering and registering, flow control and safety management devices, heat exchangers, and vehicle fuel cylinder over-fill and over-pressure protection with listed hoses with nozzles (see Figure A.1); or

b)   HGV dispensers that are primarily the customer facing unit with components, as needed, fuelling hose assembly listed hoses, nozzles, and operator interface, and where the key components of flow metering and over-pressure and over-fill protection are located in a separate unit or part of the hydrogen fuelling station system (see Figure A.2).

The following service pressures are applicable: 25, 35, 50, and 70 MPa.

Each dispensing system could have multiple valve trains allowing fuelling of multiple vehicles.

1.2

Dispensing systems covered by this Standard are intended for use with fuel meeting the requirements in SAE J2719 and ISO 14687, Grades D and F.

1.3

This Standard applies to dispensers that protect the vehicle storage for over-pressure, over-temperature, and over-fill (i.e., over-density) situations.

1.4

This Standard also applies to dispensing systems that are part of a modular fuelling station with remote fuel metering, registering, control and management devices, and vehicle fuel storage over-fill and over-pressure protection included in an integrated fuelling station control system. For these applications, refer to CSA HGV 4.9.

1.5

This Standard does not apply to dispensers intended for the refuelling of hydrogen-powered industrial trucks.

Note: CSA HPIT 2 addresses dispensers intended for the refuelling of hydrogen-powered industrial trucks.

1.6

All references to pressure throughout this document Standard are to be considered gauge pressures unless otherwise specified in this Standard.

1.7

These requirements are not intended to prevent the design and construction of a dispensing system not specifically prescribed in this Standard. In considering alternative designs or construction, the materials used shall be evaluated as to their ability to yield equivalent performance to that prescribed by this Standard.

1.8

In this Standard, “shall” is used to express a requirement, i.e., a provision that the user is obliged to satisfy in order to comply with the standard; “should” is used to express a recommendation or that which is advised but not required; “may” is used to express an option or that which is permissible within the limits of the standard; and “can” is used to express possibility or capability.

Notes accompanying clauses do not include requirements or alternative requirements; the purpose of a note accompanying a clause is to separate from the text explanatory or informative material.

Notes to tables and figures are considered part of the table or figure and may be written as requirements.

Annexes are designated normative (mandatory) or informative (non-mandatory) to define their application.

1.9

The values given in SI units are the units of record for the purposes of this Standard. The values given in parentheses are for information and comparison only.

1.1 

This Standard describes the investigations required to obtain the seismological and geological information necessary to determine the seismic ground motion that will be used in seismic qualification of safety-related nuclear power plant structures, systems, and components (SSCs), and the potential for secondary earthquake effects (e.g., tsunami, seiche, volcanism, slope instability, surface faults, surface instability, and dam failures) that can have a direct or indirect effect on plant safety or operation.

Notes:

1)This Standard establishes the basis for a family of seismic hazard results that can be used as input to CSA N289Series of Standards. This Standard does not specify

a)ground motion parameters to be used in design;

b)probability level; or

c)degree of confidence to be achieved.

2)The investigations specified in this Standard should be updated periodically to reflect gained knowledge and modern requirements. The investigations may be conducted independently or as part of the periodic safety review (refer to REGDOC-2.3.3, CSA N289.1, and CSA N290.18).

1.2 

This Standard was developed for the determination of ground motions for Eastern North American regions of low to moderate seismic hazard, comparable to the levels near Canada’s existing nuclear power plants. In regions of higher seismic hazard, the assessment of strong earthquake shaking can be more complex due to near-fault and other effects that are beyond the scope of this Standard. Therefore, while the provisions of this Standard can be applied to any nuclear power plant site, additional provisions might be required for high seismic hazard sites.

Note: Guidance regarding additional provisions for high seismic hazard sites may be obtained from IAEA Specific Safety Guide SSG-9, and relevant codes of other countries.

1.3 

This Standard may be applied, as appropriate, to other nuclear facilities under the jurisdiction of the Government of Canada’s Nuclear Safety and Control Act.

1.4 

In this Standard, “shall” is used to express a requirement, i.e., a provision that the user is obliged to satisfy in order to comply with the Standard; “should” is used to express a recommendation or that which is advised but not required; and “may” is used to express an option or that which is permissible within the limits of the Standard.

Notes accompanying clauses do not include requirements or alternative requirements; the purpose of a note accompanying a clause is to separate from the text explanatory or informative material.

Notes to tables and figures are considered part of the table or figure and may be written as requirements.

Annexes are designated normative (mandatory) or informative (non-mandatory) to define their application. 

1.1

Cette norme décrit les études exigées pour obtenir les informations sismologiques et géologiques nécessaires en vue de déterminer les mouvements sismiques du sol qui seront utilisés lors de la qualification sismique des structures, systèmes et composants (SSC) de centrales nucléaires liés à la sûreté, et le risque d’effets secondaires du séisme (p. ex., tsunami, seiche, activité volcanique, instabilité de pente, défauts de surface, instabilité de surface et défaillances de barrage) susceptibles d’avoir un effet direct ou indirect sur la sécurité ou l’exploitation de la centrale.

Notes :

1) Cette norme présente un ensemble de résultats associés aux aléas sismiques qui sont susceptibles d’être utilisés pour la série de normes CSA N289. Cette norme ne prescrit pas ce qui suit :

a) les paramètres de mouvement du sol à utiliser pour la conception;

b) le niveau de probabilité; ou

c) le degré de confiance nécessaire.

2) Les études spécifiées dans cette norme devraient être mises à jour périodiquement pour tenir compte des connaissances acquises et des exigences modernes. Les études peuvent être menées indépendamment ou dans le cadre de la revue de sûreté périodique (voir REGDOC-2.3.3, CSA N289.1 et CSA N290.18).

1.2

Cette norme a été élaborée en vue de permettre la détermination des mouvements du sol pour des régions de l’est de l’Amérique du Nord où les aléas sismiques sont faibles à moyens, comparables aux niveaux qui existent près des centrales nucléaires existantes du Canada. Dans les régions qui présentent un plus grand aléa sismique, l’évaluation des fortes secousses sismiques risque d’être plus compliquée en raison des quasi-failles et autres effets qui dépassent le cadre de cette norme. Donc, bien que les dispositions de cette norme sont susceptibles de s’appliquer à tout site de centrale nucléaire, des exigences supplémentaires pourraient être requises pour les sites à plus grand aléa sismique.

Note : Des lignes directrices additionnelles visant les sites à haut aléa sismique peuvent être obtenues dans le Specific Safety Guide SSG-9 de l’IAEA, et dans les codes pertinents d’autres pays.

1.3

Cette norme peut s’appliquer, s’il y a lieu, à d’autres installations nucléaires visées par la Loi sur la sûreté et la réglementation nucléaires du gouvernement du Canada.

1.4

Dans cette norme, le terme « doit » indique une exigence, c.-à-d., une prescription que l’utilisateur est obligé de respecter pour assurer la conformité à la norme; « devrait » indique une recommandation ou ce qu’il est conseillé mais non obligatoire de faire; et « peut » indique une possibilité ou ce qu’il est permis de faire dans les limites de la norme.

Les notes qui accompagnent les articles ne comprennent pas de prescriptions ni de recommandations. Elles servent à séparer du texte les explications ou les renseignements de nature informative qui ne font pas proprement partie de la norme.

Les notes au bas des figures et des tableaux font partie de ceux-ci et peuvent être rédigées comme des prescriptions.

Les annexes sont qualifiées de normatives (obligatoires) ou d’informatives (facultatives) pour en préciser l’application.