序言这是CSA N288的第二版。核设施、铀矿和工厂的环境风险评估。它取代了2012年出版的前一版。它是CSA N288系列核设施环境管理标准和指南的一部分。本版本的主要变化包括:a）与CSA N288系列标准一致；b）改进指导和清晰性。CSA N系列标准为核设施和活动的管理提供了一套相互关联的要求。CSA N286-12《核电厂管理体系要求》为管理层制定和实施健全的管理实践和控制提供了总体指导，而其他CSA核标准则提供了支持管理体系的具体技术要求和指导。 本标准涉及环境风险评估计划的设计、实施和管理，该计划包含加拿大和国际上使用的最佳实践，与CSA N286协调一致，不重复CSA N286的一般要求；然而，它可能会为这些需求提供更具体的指导。提醒本标准的用户，联邦、省/地区或市政当局可能会规定额外的和特定于现场的要求。本标准不应被视为替代任何a）适用的联邦或省/地区法规中的要求，包括《核安全与控制法》；或b）根据适用法规颁发的法规、执照或许可证。范围1。1设施1。1.1设施类型1。1.1.1本标准涉及一级核设施、铀矿和铀矿厂的电子逆向拍卖。 这些设施包括a）核反应堆；b） 铀矿、磨坊、炼油厂和转化厂；c） 铀燃料制造厂；d） 同位素处理设施；e） 束流能量等于或大于50 MeV的粒子加速器；f）废物管理设施。注:在本标准中，所有这些设施都包含在术语“核设施”中。1.1.1.2本标准的部分内容也可能与其他设施的电子逆向拍卖有关，例如a）II类核设施；b） 在核物质和辐射装置许可证授权下运营的机构；c）使用或储存天然放射性物质的设施。然而，在这些情况下，设施许可证持有人负责确定本标准的适用性和适用性。1.1.2设施生命周期设施生命周期期间，ERA的性质和范围可能会发生变化。 本标准涉及a）现场准备、施工和调试期间执行的ERA；b） 运营；c） 退役；以及d）设施关闭后可能出现的任何机构控制期。1.2操作条件本标准中描述的ERA过程适用于人类和/或非人类生物群可能经常暴露于a）由于核设施正常运行（定义见第3.1条）而释放到环境中的低水平废水和核有害物质排放的情况；或b）由于核设施的正常运行而对环境施加的物理压力。本标准不涉及事故（包括泄漏）可能导致的急性或高水平暴露。在这些情况下，设施许可证持有人负责确定本标准的适用性。 注:历史污染，包括过去的泄漏，被认为是现场现有环境条件的一部分，其影响在一个ERA中考虑。然而，通常不需要在ERA中包含泄漏风险评估。1.3排放本标准适用于常规废水和排放，包括可合理预见的不稳定事件产生的废水和排放。本标准也适用于定期短期释放，前提是释放受到控制并与正常操作相关。1.4归宿和迁移理解环境中污染物的归宿和迁移对于执行ERA是必要的；然而，关于命运和运输模式的详细讨论不在本标准的范围内。风险评估师应咨询CSA N288。1获取有关这些概念的信息。第6条提供了其他型号的示例。 3.7.1.5污染物和物理应力本标准中涉及的核设施ERA中包含的污染物和物理应力可包括以下一种或多种:a）非放射性污染物（例如有毒、腐蚀性或对环境有害的物质）；b） 放射性污染物；和c）身体应激源（例如，噪音、热量、野生动物车辆/鸟类结构死亡和取水口冷却水）。本标准中未提及的其他身体应激源，如果在特定场所或设施的基础上被确定为对人类或生态受体重要，则可纳入ERA。1.6受体本标准适用于受核设施释放的污染物和物理应激源影响的受体。本标准包括人类和非人类生物群（生态受体）。 VCs有时可能包括环境中的非生物成分（例如娱乐设施或历史遗址），但就本标准而言，这些成分不被视为受体。HHRA通常适用于场外受体（公众成员）。附件H涉及居住在设施附近的土著社区，如果这些社区依赖传统的狩猎、捕鱼和食物采集活动以及仪式和医疗实践。此外，根据现场和ERA目标，可以评估设施辐射防护计划和健康与安全计划未涵盖的现场非核能工人（非新闻）。该设施的辐射防护计划和健康与安全计划涵盖了相关新闻，因此本标准不考虑这些新闻。1.7风险管理本标准提供了评估和描述因暴露于核设施释放的污染物而对受体造成的风险的指南。 这包括识别、评估和优先考虑环境风险。ERA流程的输出可作为后续风险管理流程的输入；然而，关于风险可接受性或不可接受性的管理决策以及将采取的进一步措施不在本标准的范围内。第9.3条涉及根据ERA流程的结果向风险经理提供建议。1.8报告本标准提供了报告ERA结果的指南。然而，风险评估人员应注意，管理核设施运行的法规、法规、许可证和许可证可能会施加不同于本标准所述的报告要求。核设施运营商负责确定向监管机构提交报告所需的频率和内容，以确保遵守管理核设施运营的法规、条例、许可证或许可证。 1.9本标准中的术语“应”用于表示要求，即用户为遵守本标准而有义务满足的规定；“应该”用于表示建议或建议但不需要的建议；“可”用于表示一个选项或在标准范围内允许的选项。注释随附条款不包括要求或替代要求；随附条款的注释的目的是将解释性或信息性材料与文本分开。表和图的注释被视为表或图的一部分，可以作为要求编写。附件被指定为规范性（强制性）或信息性（非强制性）以定义其应用。

PrefaceThis is the second edition of CSA N288.6, Environmental risk assessments at nuclear facilities and uranium mines and mills. It supersedes the previous edition published in 2012. It is part of the CSA N288 series of Standards and guidelines on environmental management of nuclear facilities. The major changes in this edition include the following: a) alignment with the CSA N288 series of Standards; and b) improved guidance and clarity. The CSA N series of Standards provides an interlinked set of requirements for the management of nuclear facilities and activities. CSA N286-12, Management system requirements for nuclear power plants, provides overall direction to management to develop and implement sound management practices and controls, while the other CSA nuclear Standards provide specific technical requirements and guidance that support the management system. This Standard, which addresses the design, implementation, and management of an environmental risk assessment program that incorporates best practices used in Canada and internationally, works in harmony with CSA N286 and does not duplicate the generic requirements of CSA N286; however, it might provide more specific direction for those requirements. Users of this Standard are reminded that additional and site-specific requirements might be specified by federal, provincial/territorial, or municipal authorities. This Standard should not be considered a replacement for the requirements contained in any a) applicable federal or provincial/territorial statute, including the Nuclear Safety and Control Act; or b) regulation, licence, or permit issued pursuant to an applicable statute.Scope1.1 Facilities1.1.1 Types of facilities1.1.1.1 This Standard addresses ERAs for Class I nuclear facilities and uranium mines and mills. These facilities include a) nuclear reactors; b) uranium mines, mills, refineries, and conversion plants; c) uranium fuel fabrication plants; d) isotope processing facilities; e) particle accelerators with a beam energy equal to or greater than 50 MeV; and f) waste management facilities. Note: In this Standard, all of these facilities are included in the term "nuclear facilities".1.1.1.2 Parts of this Standard might also be relevant to ERAs for other facilities such as a) Class II nuclear facilities; b) institutions operating under the authority of a Nuclear Substances and Radiation Devices licence; and c) facilities that use or store naturally occurring radioactive materials. However, in these cases, the holder of the facility licence is responsible for determining the applicability and suitability of this Standard.1.1.2 Facility lifecycleThe nature and extent of an ERA might change during the lifecycle of the facility. This Standard addresses ERAs performed during a) site preparation, construction, and commissioning; b) operations; c) decommissioning; and d) any period of institutional control that might follow closure of the facility.1.2 Operating conditionsThe ERA process described in this Standard is applicable where human and/or non-human biota might routinely be exposed to a) low-level effluents and emissions of nuclear and hazardous substances released to the environment as a result of the normal operation (as defined in Clause 3.1) of a nuclear facility; or b) physical stressors imposed on the environment as a result of the normal operation of a nuclear facility. This Standard does not address acute or high-level exposures that can result from accidents (including spills). In these cases, the holder of the facility licence is responsible for determining the applicability of this Standard.Note: Historical contamination, including past spills, is considered to be part of the existing environmental conditions of the site and its influence is accounted for in an ERA. However, the inclusion of a spills risk assessment in an ERA is generally not required.1.3 ReleasesThis Standard applies to routine effluents and emissions, including those resulting from reasonably foreseeable upset events. This Standard also applies to periodic short-term releases, provided that the releases are controlled and associated with normal operations.1.4 Fate and transportAn understanding of the fate and transport of contaminants in the environment is necessary for performing an ERA; however, a detailed discussion of fate and transport models is outside the scope of this Standard. The risk assessor should consult CSA N288.1 for information on these concepts. Examples of additional models are provided in Clause 6.3.7.1.5 Contaminants and physical stressorsContaminants and physical stressors to be included in an ERA for a nuclear facility, which are addressed in this Standard, can include one or more of the following: a) non-radioactive contaminants (e.g., toxic, corrosive, or environmentally deleterious substances); b) radioactive contaminants; and c) physical stressors (e.g., noise, heat, wildlife-vehicle/bird-structure mortalities, and intake cooling water withdrawal). Other physical stressors that are not addressed in this Standard can be included in the ERA if they are identified as important to human or ecological receptors on a site or facility-specific basis.1.6 ReceptorsThis Standard applies to receptors that can be affected by contaminants and physical stressors released from a nuclear facility. Human and non-human biota (ecological receptors) are included in this Standard. VCs can occasionally include abiotic components of the environment (e.g., recreational facilities or historical sites), but these are not considered receptors for the purposes of this Standard. HHRAs generally apply to off-site receptors (members of the public). Annex H addresses Indigenous communities living near the facility if those communities rely on traditional hunting, fishing, and food gathering activities as well as ceremonial and medicinal practices. In addition, on-site non-nuclear energy workers (non-NEWs) that are not covered under the facility's radiation protection program and health and safety program can be evaluated, as appropriate to the site and ERA objectives. NEWs are covered under the radiation protection program and health and safety program in place at the facility and therefore are not considered in this Standard.1.7 Risk managementThis Standard provides guidance on evaluating and characterizing risks to receptors resulting from exposure to contaminants released from nuclear facilities. This involves identifying, evaluating, and prioritizing risks to the environment. Outputs from the ERA process can be used as input into subsequent risk management processes; however, management decisions on acceptability or unacceptability of risk and further steps to be taken are outside the scope of this Standard. Clause 9.3 addresses the provision of recommendations to risk managers based on the results of the ERA process.1.8 ReportingThis Standard provides guidance on reporting the results of an ERA. However, risk assessors are cautioned that the statutes, regulations, licences, and permits that govern the operation of a nuclear facility can impose reporting requirements that differ from those described in this Standard. The operator of the nuclear facility is responsible for determining the required frequency and content of reports to regulatory agencies necessary to ensure compliance with the statutes, regulations, licences, or permits that govern the operation of the nuclear facility.1.9 TerminologyIn 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.