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Foreword In order to implement the "Environmental Protection Law of the People's Republic of China", "Nuclear Safety Law of the People's Republic of China", "Radioactive Pollution Prevention Law of the People's Republic of China" and other relevant laws and regulations, to protect the environment and safeguard human health, this standard is formulated. Prevention and Control Law" and other relevant provisions of laws and regulations, to protect the environment and protect human health, the development of this standard. This standard specifies the purpose, content and requirements of radiation environmental monitoring at different stages of the near-surface disposal site of radioactive solid waste. This standard is a revision of the "general requirements for environmental radiation monitoring of low and medium level radioactive waste near-surface disposal sites" (GB/T 15950-1995). This standard was first published in 1995, and the original standard drafting unit is the Institute of Nuclear Industry Standardization of China National Nuclear Corporation. This is the first revision. The main content of this revision. -The standard name is revised to "radioactive solid waste near-surface disposal site radiation environmental monitoring requirements"; increased the "preface" "preliminary survey of the radiation environment background", "environmental monitoring outline " and "monitoring of passive monitoring period", etc. In the terminology of "near-surface disposal site", "investigation level", "reporting level" and "active monitoring period The definition of "near-surface disposal site", "investigation level", "reporting level" and "active monitoring period" are given in the terminology; the radiation environment monitoring of the near-surface disposal site of radioactive solid waste is divided into "pre-operational phase", "operational phase" and "closure After the phase" three stages, and detailed additional requirements: - in Chapter 5 and Chapter 6 were added to the pre-operation phase and operation phase of the radiation monitoring program table. From the date of implementation of this standard, "General requirements for environmental radiation monitoring of low and medium level radioactive waste near surface disposal sites" GB/T 159501995) is repealed. This standard by the Ministry of Ecology and Environment, the Department of radiation source safety supervision, regulations and standards organization. The main drafting unit of this standard: China National Nuclear Power Engineering Corporation, Beijing Institute of Nuclear Industry Chemical Processing Institute This standard was approved by the Ministry of Ecology and Environment on February 2, 2023. This standard has been implemented since June 1, 2023. This standard is interpreted by the Ministry of Ecology and Environment. 1 Scope of application This standard specifies the radioactive solid waste near-surface disposal site pre-operational phase, operational phase and post-closure phase of the radiation environment monitoring requirements. This standard applies to the radiation environment monitoring of the near-surface disposal site of radioactive solid waste, and does not apply to the radiation environment monitoring of the cavern disposal site. 2 normative reference documents This standard cites the following documents or provisions therein. Where the date of the cited document is indicated, only the dated version is applicable to this standard. Where the reference document is not dated, its latest version (including all the revision sheets) is applicable to this standard. GB 8999 General requirements for quality assurance of ionizing radiation monitoring GB 9132 low and medium level radioactive solid waste near-surface disposal safety requirements GB 18871 Basic standards for ionizing radiation protection and radiation source safety HJ 61 Technical Specification for Radiation Environmental Monitoring EJ 428 General Provisions for the Collection and Preparation of Soil Samples in Environmental Nuclear Radiation Monitoring EJ 527 Basic Provisions for Biological Sampling in Environmental Radiation Monitoring 3 Terminology and definitions The following terms and definitions are applicable to this standard. 3.1 Near surface disposal sitenear surface disposal repository Radioactive solid waste disposal facilities within a few tens of meters below or on the surface of the ground and with an engineered barrier, the facility has defined boundaries and is subject to organized control, the near surface disposal site generally consists of a number of disposal units, structures and buffers, etc. 3.2 Investigation levelinvestigation level When a measured quantity (such as dose rate, activity concentration, etc.) is higher than this level, it is necessary to investigate the causes and consequences of its occurrence. 3.3 Report levelreport level When a measured quantity (such as dose rate, activity concentration, etc.) is higher than this level, it should be reported to the relevant department. 3.4 Active guard periodinitiative guard period The period when facility maintenance and monitoring activities continue in an organized manner after the disposal site is closed. 4 General requirements 4.1 Radioactive solid waste near-surface disposal site of the radiation environment monitoring should be consistent with GB 9132, HJ61, GB18871 and other standards, sampling methods for various types of environmental media should be consistent with the requirements of HJ61, EJ428, EJ527 and other relevant standards and specifications, quality assurance should be consistent with the requirements of GB8999 and other standards. 4.2 The radiation environment monitoring of the near-surface disposal site of radioactive solid waste is divided into the pre-operation phase, operation phase and post-closure phase. 4.3 radiation environment monitoring range to the disposal site as the center, a radius of 3km ~ 5km, focusing on groundwater and other environmental media, and according to the environmental characteristics of the disposal site in the region, the appropriate adjustment. 4.4 disposal site radiation environment monitoring of the three stages are required to develop the corresponding monitoring outline. Monitoring outline should be in line with the requirements of this standard, and give full consideration to the source of radioactive solid waste items, disposal site characteristics and site environmental characteristics and other factors. 5 pre-operation phase 5.1 Monitoring purpose The purpose of radiation environmental monitoring in the pre-operation phase is to collect background information on site characteristics and to obtain background data on the radiation environment. 5.2 Monitoring auxiliary parameters acquisition Collect information on the radiation environment, meteorology, hydrology, geology, geochemistry and water chemistry, natural resources, population and its distribution within 5km of the site, as well as the operation of other nuclear facilities that may affect the site within 5km, and the distribution of radiation sources, to provide a basis for the development of the monitoring outline. 5.3 Preliminary survey of radiation environment background Disposal site in the site selection stage need to carry out preliminary investigation of the radiation environment background. New site site selection stage of the radiation environment background preliminary survey should be carried out a necessary site monitoring, monitoring content including instantaneous environmental γ radiation dose rate and environmental media (aerosol, soil, sediment, surface water, groundwater) in the radionuclide activity concentration level, monitoring projects and deployment requirements refer to Table 1. If the concentration of artificial radionuclide activity in the above environmental media is found to be abnormal during the preliminary survey, additional biological media survey should be considered or focused on during the pre-operation survey. If the site is located within the environmental monitoring range of other nuclear facilities, the environmental monitoring data of other nuclear facilities can be used directly as the background preliminary survey data. 5.4 Radiation environment background survey 5.4.1 The background data of the radiation environment around the site should be obtained for the last two consecutive years before the operation of the disposal site, as the basic data for the environmental impact evaluation and safety analysis during the operation and after the closure of the disposal site. 5.4.2 The survey includes the ambient γ radiation level and the activity concentration of the main radionuclides in the environmental media related to the operation of the disposal site. 5.4.3 The scope of the survey of the radiation environment background to the disposal site as the center, the radius is generally taken 5km. 5.4.4 The radiation environment background survey should follow the following principles of deployment: (a) should follow the provisions of the relevant standards and norms, and combined with the environmental characteristics of the survey area to consider point placement; (b) close to the dense far away, taking into account all directions; (c) in the main settlements, agriculture, animal husbandry and fishery concentrated areas, environmentally sensitive areas (in addition to the main settlements), the dominant wind downwind of the deployment of points; (d) sparsely populated and inaccessible areas can be appropriately reduced monitoring points; (e) As far as possible, choose the location that is less likely to be disturbed and damaged in the future, so that the operational phase and long-term use after closure; f) The selected points should be representative and avoid being affected by disturbing factors as far as possible; (g) set at least one control point in the area that can be negligibly affected by the disposal site and can maintain the original environmental characteristics in the long term. 5.4.5 Disposal site pre-operation phase of the radiation environment background survey program reference table 1 implementation. Monitoring projects can be adjusted according to the main radionuclides involved in the disposal site, site characteristics and monitoring method maturity. Table 1 pre-operational phase of the radiation environment background survey program 5.4.6 If the site is located within the influence of the surrounding nuclear facilities, it is also necessary to consider increasing the monitoring of the release of major artificial radionuclides from the nuclear facilities. 5.4.7 In the background survey of the radiation environment in the pre-operational phase of the disposal site, the nuclides to be concerned about in the γ-spectrum nuclide analysis should be set according to the source items of the disposal waste, including at least 137Cs, 60Co, 134Cs, 54Mn, etc.. The activity concentrations of238U,232Th,226Ra,40K in soil and substrate should also be concerned. 5.4.8 Indicator biological deployment points can be set with reference to the recommendations of EJ527. If the disposal site is in an area without the recommended range of species, it is appropriate to recommend possible indicator organisms through the pre-operational environmental background survey for monitoring during operation. 5.4.9 If the source item of the disposal waste contains transuranic nuclides and their content may have an impact on the environment, these nuclides need to be added to the monitoring items of soil, aerosol, sediment, and groundwater. 5.5 Environmental monitoring outline The environmental monitoring outline contains at least the following elements: a) the organizational structure and its responsibilities for carrying out environmental monitoring tasks; b) the basis for the development of the monitoring outline; c) details of the monitoring program; d) description of measurement methods, equipment and detectable limits; e) data processing methods; f) Quality assurance measures. 6 Operational phase 6.1 Monitoring purpose The purpose of radiation environmental monitoring during the operation phase is to continuously obtain monitoring data of the radiation environment around the disposal site, to grasp the level of the radiation environment and its changing trends, to evaluate the radiation impact of the operation of the disposal site on the surrounding environment, and to provide data support for the assessment of public exposure dose and evaluation of the inclusive performance of the facilities during the operation of the disposal site. 6.2 Monitoring focus The radiation environment monitoring should focus on the main emission source items of the disposal site, the environmentally sensitive points within the survey area and the relevant pathways of potential leakage, and should also fully integrate the findings of the background survey of the radiation environment before operation. 6.3 Layout principles In order to make the sampling and monitoring points are selected with sufficient representation, the sampling and monitoring points should be laid out considering the following principles: (a) to meet the relevant standards and technical specifications requirements; (b) focus on monitoring the area near the site, focusing on the main residential points and other environmentally sensitive points within the survey area, and increase the monitoring points for dense residential areas as appropriate; (c) fully integrated with the pre-operational radiation environment background survey of the deployment program, and according to the findings of the survey appropriate adjustments; (d) should set up environmental control points, it is appropriate to set up in the same point with the background survey; (e) in addition to the above requirements, should also meet the relevant requirements in Table 2. 6.4 Groundwater 6.4.1 groundwater monitoring is the focus of the disposal site radiation environment monitoring. Monitoring wells for groundwater sampling is generally not less than four, of which one is set upstream as a comparison well, the rest are set in the downstream. The distribution of monitoring wells should be distributed in a fan shape in accordance with the direction of groundwater flow. Monitoring wells need to be monitored for a long period of time, and the changes in groundwater runoff should be taken into account. 6.4.2 Non-radioactive parameters (e.g. pH, conductivity, nitrate, fluoride, total organic carbon, etc.) can be used as auxiliary indicators to indicate potential problems. 6.5 Surface water If there are surface rivers within the survey area, a sampling point can be set up in the upstream and downstream of the river. If there are lakes and reservoirs within the survey area, one sampling point will be set up in each lake and reservoir. 6.6 Indicator organisms If there is no clear indicator organism in the monitoring area, if conditions are available, it is appropriate to plant one kind of indicator plant recommended by EJ527 near the plant area for sampling and measurement. 6.7 Monitoring program The radiation environment monitoring program of the operation phase of the disposal site is implemented with reference to Table 2 6.8 Environmental monitoring program The monitoring items, frequencies and points of the environmental monitoring outline in the operation phase should be consistent with Table 2, and other content requirements are the same as in section 5.5. The environmental monitoring program can be optimized periodically (usually 5 years) based on feedback from experience, advances in monitoring technology, changes in the characteristics of the received waste, and changes in the environment around the site. The environmental monitoring items, frequency, and locations can be adjusted appropriately during the closure process period from the time the disposal site stops receiving waste to the time of formal closure. 6.9 Emergency environmental monitoring The operating unit needs to develop an emergency environmental monitoring program based on the accident analysis of the facility before the disposal site is put into use, and equipped with the appropriate personnel and equipment, and organize regular drills. Emergency environmental monitoring should be able to quickly provide relevant environmental monitoring data under abnormal conditions to provide data support for emergency response. 6.10 Other auxiliary parameters acquisition 6.10.1 Hydrological parameters During the operation phase of the disposal site, the groundwater flow and water level should be evaluated in a five-year cycle. 6.10.2 Geological parameters For the settlement, deformation, cracks of disposal units, slopes (if any), interceptor ditches (if any), as well as the surface deformation and soil erosion of the whole site should be monitored or inspected annually during the reception of waste at the facility to assess the environmental safety of the site, and the disposal site constructed in phases should be evaluated after The cycle of monitoring or inspection can be lengthened after the completion of capping and surface backfill of the previous phase. 6.11 Investigation level The survey level should be linked to a multiple of background concentration or a share of the dose limit and used as a management standard for the disposal site, and the following actions should be taken when a physical quantity is found to reach the survey level: a) Review laboratory procedures; b) Inspection for contamination; c) resampling; d) radionuclide analysis; e) Increased sampling frequency; f) Monitoring outline extension. 6.12 Reporting Levels When a measured quantity reaches or exceeds the reporting level, then the monitoring results and mitigation measures taken to resolve the problem should be reported to the regulatory authority. 7 Post-Closure Phase 7.1 Purpose of monitoring After closure of the disposal site in accordance with statutory procedures and conditions, appropriate environmental monitoring functions are retained based on the operational history of the disposal site and the closure and stabilization situation as part of the safe guardianship program for the closure of the disposal site. The purpose is to evaluate the stability performance of the facility after closure of the disposal site by detecting radioactive material in the environment that may come from the disposal site, to provide early warning of abnormal radionuclide releases from the disposal waste and to provide data support for assessing the long-term environmental impact of radiation. 7.2 Active monitoring of the custody period 7.2.1 General requirements The environmental monitoring medium during the active guardianship period should be mainly groundwater samples from the monitoring wells of the site, with appropriate retention of some ambient γ radiation levels and plant samples for monitoring, and continuous attention should be paid to surface movement and soil erosion of the disposal site. 7.2.2 Groundwater and Plant Samples In the initial period after site closure, groundwater monitoring should be continued to analyze whether it contains radioactive materials that may come from the disposal site, so as to indirectly judge the integrity of the engineering barrier. If no potential problems are confirmed after a period of monitoring, the frequency of groundwater monitoring can be gradually reduced. Plant samples (especially deep-rooted plants) within the disposal site (focusing on the disposal unit area) should be collected regularly during the active monitoring period to analyze whether the samples contain radioactive substances that may come from the disposal site and judge the environmental impact. 7.2.3 Ambient γ radiation level Retain one continuous monitoring point of ambient γ radiation air absorbed dose rate set during operation to continue continuous monitoring, and retain periodic γ radiation air absorbed dose rate instantaneous measurement at some points. 7.2.4 Other monitoring Conduct regular monitoring or inspection of surface movement and soil erosion of the disposal site, and analyze the possible impact of changes on the disposal unit in time when obvious changes are found, and judge whether engineering measures are needed. 7.3 Environmental monitoring outline The implementation period of the environmental monitoring outline of the post-closure phase should cover the active monitoring period after the closure of the disposal site. The monitoring items, frequency and points in the outline should be set according to the requirements of section 7.2, and other content requirements should be the same as section 5.5. 7.4 Monitoring of the passive monitoring period The monitoring results of the active monitoring period to determine whether to continue to carry out monitoring of the radiation environment during the passive monitoring period. If you need to continue to carry out the radiation environment monitoring, passive monitoring period 8 Data processing and monitoring reports 8.1 Data processing and preservation 8.1.1 It is appropriate to carry out data processing in accordance with the relevant requirements of HJ61 and other standards and specifications, and the final results of radiation environmental monitoring should be scientific and reasonable. 8.1.2 It is recommended that the construction of the disposal site radiation environment information management system to save all environmental monitoring process and results data, to provide data support for the entire life of the disposal site. 8.2 Monitoring report requirements 8.2.1 Monitoring report should be prepared to comprehensively introduce the monitoring process and results, and the format and frequency of the report should be decided according to the purpose of the report. 8.2.2 The content of the monitoring report should include at least a) A comprehensive description of the monitoring task or plan; b) Detailed site surroundings associated with the measurement program; c) detailed description of the sample collection process, giving a clear layout map of each monitoring item, giving the sample type, sampling process, sampling equipment, sampling volume, sampling location and frequency; (d) give the analytical nuclides, analytical methods, analytical instruments and minimum detection limits; (e) a detailed description of the sample preparation and measurement process, measurement results, including measured values and standard deviations, measurement results should be scientific and reasonable; (f) a detailed description of quality assurance measures and their effects; (g) combined with the collected monitoring data to evaluate in detail the state of the radiation environment around the site, for the existence of abnormal data, should be a detailed analysis of the reasons for the abnormal;; (h) operation phase and post-closure monitoring should also be compared with the data of the pre-operation radiation environment background survey and control point data to analyze the environmental impact and change trends; i) According to the current radiation environment monitoring results on the subsequent radiation environment monitoring work to make recommendations. 9 Quality assurance 9.1 Quality assurance should be throughout all stages of the disposal site radiation environment monitoring, and should be throughout the process from the development of the monitoring outline to the evaluation of the monitoring results. 9.2 Each stage of radiation environmental monitoring work undertaken by the unit should establish a quality assurance system and make it continuous, compliant and effective operation. 9.3 quality assurance both to ensure that the monitoring outline in the monitoring of the whole process of correct implementation and obtain credible monitoring results, but also to ensure that the evaluation of monitoring results in line with the quality assurance requirements. 9.4 Quality assurance measures should consider at least the following factors: a) operational procedures for sampling, transport, preservation, sample preparation and measurement of various types of samples are well documented; b) the quality of equipment, instruments, articles, apparatus, and reagents; c) Calibration and verification of equipment and instruments and ensuring that they are within the validity period; d) Training and qualification of personnel; e) confirmation of methods through routine analysis of control samples and application of standard analytical methods; f) traceability of monitoring results to national standards; g) data processing and uncertainty analysis; h) comparative measurement content with other laboratories; (i) to prove that the required quality is achieved and maintained and the need for document management and preservation. 9.5 disposal site operators need to save the pre-operational phase of the radiation environment background survey of soil, sediment and biological ash samples obtained. Properly preserve the original records and quality records of the survey to ensure the traceability of the survey. Pre-operation radiation environment background survey results and reports need to be kept permanently. Monitoring outline and monitoring report of each stage are included in the systematic analysis of the whole safety process. Foreword 1 Scope of application 2 normative reference documents 3 Terminology and definitions 4 General requirements 5 pre-operation phase 6 Operational phase 7 Post-Closure Phase 8 Data processing and monitoring reports 9 Quality assurance 前言 为贯彻《中华人民共和国环境保护法》《中华人民共和国核安全法》《中华人民共和国放射性污染 防治法》等法律法规的有关规定，保护环境，保障人体健康，制定本标准。本标准规定了放射性固体废物近地表处置场不同阶段辐射环境监测的目的、内容和要求。本标准是对《低、中水平放射性废物近地表处置场环境辐射监测的一般要求》(GB/T 15950-1995)的修订。 本标准首次发布于1995年，原标准起草单位为中核集团核工业标准化研究所。本次为第1次修订。本次修订的主要内容: -标准名称修改为《放射性固体废物近地表处置场辐射环境监测要求》;增加了“前言”“辐射环境本底初步调查”、“环境监测大纲”和“被动监护期的监测”等内容; 在术语中给出“近地表处置场”、“调查水平”、“报告水平”和“主动监护期”的定义;将放射性固体废物近地表处置场的辐射环境监测分为“运行前阶段”、“运行阶段”和“关闭 后阶段”三个阶段，并详细补充了相关要求:-在第5章和第6章分别增加了运行前阶段和运行阶段辐射环境监测方案表。自本标准实施之日起,《低、中水平放射性废物近地表处置场环境辐射监测的一般要求》GB/T 159501995)废止。 本标准由生态环境部辐射源安全监管司、法规与标准司组织制订。 本标准主要起草单位:中国核电工程有限公司、核工业北京化工治金研究院本标准生态环境部2023年2月2日批准。 本标准自2023年6月1日起实施。 本标准由生态环境部解释。 1适用范围 本标准规定了放射性固体废物近地表处置场运行前阶段、运行阶段和关闭后阶段的辐射环境监测要求。 本标准适用于放射性固体废物近地表处置场的辐射环境监测，不适用于岩洞处置场的辐射环境监测。 2规范性引用文件 本标准引用了下列文件或其中的条款。凡是注明日期的引用文件，仅注日期的版本适用于本标准。 凡是未注明日期的引用文件，其最新版本（包括所有的修改单）适用于本标准。 GB 8999电离辐射监测质量保证通用要求 GB 9132低、中水平放射性固体废物近地表处置安全规定 GB 18871电离辐射防护与辐射源安全基本标准 HJ 61辐射环境监测技术规范 EJ 428环境核辐射监测中土壤样品采集与制备的一般规定 EJ 527环境辐射监测中生物采样的基本规定 3术语和定义 下列术语和定义适用于本标准。 3.1 近地表处置场near surface disposal repository 在地表面或地表面下几十米深以内并设置工程屏障的放射性固体废物处置设施，该设施有确定的边界并受到有组织的控制，近地表处置场一般由若干处置单元、构筑物和缓冲区等组成。 3.2 调查水平investigation level 当被测量的一个量（如剂量率、放射性活度浓度等）高于此水平时，需要调查其发生原因和造成后果。 3.3 报告水平report level 当被测量的一个量（如剂量率、放射性活度浓度等）高于此水平时，需要向有关部门报告。 3.4 主动监护期initiative guard period 处置场关闭后继续有组织地开展设施维护和监测活动的阶段。 4总体要求 4.1放射性固体废物近地表处置场的辐射环境监测应符合GB 9132、HJ61、GB18871等标准，各类环境介质的采样方法应符合HJ61、EJ428、EJ527等有关标准规范的要求，质量保证应符合GB8999等标准的要求。 4.2放射性固体废物近地表处置场的辐射环境监测分为运行前阶段、运行阶段和关闭后阶段。 4.3辐射环境的监测范围以处置场为中心，半径3km～5km，重点关注地下水等环境介质，并根据处置场所在区域的环境特点，适当调整。 4.4处置场辐射环境监测的三个阶段均需制定相应的监测大纲。监测大纲应符合本标准的要求，并充分考虑放射性固体废物的源项、处置场特性和场址环境特点等因素。 5运行前阶段 5.1监测目的 运行前阶段开展辐射环境监测的目的是收集场址特性的背景资料，获得辐射环境本底数据。 5.2监测辅助参数获取 收集场址5km范围内辐射环境、气象、水文、地质、地球化学和水化学、自然资源、人口及其分布，以及可能对场址5km范围内造成影响的其他核设施运行情况、辐射源分布情况等资料，为制定监测大纲提供依据。 5.3辐射环境本底初步调查 处置场在选址阶段需开展辐射环境本底初步调查。新场址选址阶段的辐射环境本底初步调查应进行一次必要的现场监测，监测内容包括瞬时环境γ辐射剂量率和环境介质（气溶胶、土壤、沉积物、地表水、地下水）中的放射性核素活度浓度水平，监测项目和布点要求参考表1。如果在初步调查中发现上述环境介质中人工放射性核素活度浓度异常，应考虑补充生物介质的调查或在运行前调查时予以重点关注。若场址位于其他核设施环境监测范围内，可直接使用其他核设施的环境监测数据作为本底初步调查数据。 5.4辐射环境本底调查 5.4.1应获取处置场运行前最近连续两年的场址周围辐射环境本底数据，作为处置场运行期间和关闭后环境影响评价和安全分析的基础数据。 5.4.2调查内容包括环境γ辐射水平和环境介质中与处置场运行有关的主要放射性核素活度浓度。 5.4.3辐射环境本底的调查范围为以处置场为中心，半径一般取5km。 5.4.4辐射环境本底调查应遵循如下布点原则： a）应遵循相关标准规范的规定，并结合调查范围内环境特征综合考虑点位布设； b）近密远疏、兼顾各方位； c）在主要居民点、农牧渔业集中区、环境敏感区（除主要居民点外）、主导风下风向布点； d）人口稀少且交通不便的区域可适当减少监测点位； e）尽可能选择未来被扰动和破坏可能性小的位置，以便运行阶段及关闭后长期使用； f）所选点位应具有代表性，尽量避免受到干扰因素影响； g）在受处置场影响可以忽略且能长期保持原有环境特征的区域，至少设置1个对照点。 5.4.5处置场运行前阶段辐射环境本底调查方案参考表1执行。监测项目可根据处置场涉及的主要放射性核素情况、场址特征和监测方法成熟性适当调整。 表1运行前阶段辐射环境本底调查方案 5.4.6若场址位于周边核设施影响范围内，还需考虑增加该核设施释放主要人工放射性核素的监测。 5.4.7处置场运行前阶段辐射环境本底调查中，γ谱核素分析需关注的核素应按照处置废物的源项设置，至少包括137Cs、60Co、134Cs、54Mn等。土壤和底泥中还需关注238U、232Th、226Ra、40K的活度浓度。 5.4.8指示生物布点可参考EJ527的推荐进行设置。如处置场所在地区无推荐范围内的物种，宜通过运行前环境本底调查推荐可能的指示生物，以便在运行期间开展监测。 5.4.9如处置废物源项中含有超铀核素且其含量可能对环境造成影响，需在土壤、气溶胶、沉积物、地下水的监测项目中增加这些核素。 5.5环境监测大纲 环境监测大纲至少包含以下内容： a）执行环境监测任务的组织机构及其职责； b）制定监测大纲的依据； c）监测方案的详细内容； d）测量方法、设备及可探测限的描述； e）数据处理方法； f）质量保证措施。 6运行阶段 6.1监测目的 运行阶段开展辐射环境监测的目的是持续获取处置场周围辐射环境监测数据，掌握辐射环境水平及其变化趋势，评价处置场运行对周围环境的辐射影响，同时为评估公众受照剂量和评价处置场运行期间设施的包容性能提供数据支持。 6.2监测重点 辐射环境监测应重点考虑处置场的主要排放源项、调查范围内的环境敏感点及潜在泄露的相关途径，还应充分结合运行前辐射环境本底调查的结论。 6.3布点原则 为了使采样和监测点的选取具有充分的代表性，采样和监测点的布设应考虑以下原则： a）满足相关标准及技术规范要求； b）重点监测场址附近的区域，重点关注调查范围内的主要居民点和其他环境敏感点，对居民密集地区适当增加监测点； c）充分结合运行前辐射环境本底调查的布点方案，并根据调查结论适当调整； d）应设置环境对照点，宜与本底调查时设置在同一点位； e）除以上要求外，还应满足表2中的有关要求。 6.4地下水 6.4.1地下水监测是处置场辐射环境监测的重点内容。用于地下水采样的监测井一般不少于4口，其中上游设置1口作为对比井，其余设置在下游。监测井的分布应按照地下水流向呈扇形分布。监测井需进行长期监测，并适当考虑地下水径流的变化。 6.4.2非放射性参数（如pH、电导率、硝酸盐、氟化物、总有机碳等）可作为辅助指标指示潜在问题。 6.5地表水 若在调查范围内存在地表河流，可在河流上游、下游各设置一个采样点。若在调查范围内存在湖泊、水库，在每个湖泊、水库各设置一个采样点。 6.6指示生物 监测范围内无明确的指示生物时，如具备条件，宜在厂区附近种植1种EJ527推荐的指示植物用于取样测量。 6.7监测方案 处置场运行阶段的辐射环境监测方案参考表2执行 6.8环境监测大纲 运行阶段环境监测大纲的监测项目、频次及点位宜与表2保持一致，其他内容要求与5.5节相同。 环境监测大纲可根据经验反馈、监测技术进步、接收废物的特性变化以及场址周围环境变化，定期（通常为5年）进行优化。 处置场停止接收废物至正式关闭前这段关闭过程时期的环境监测项目、频次、点位可适当调整。 6.9应急环境监测 营运单位需在处置场投入使用前根据设施的事故分析制定应急环境监测方案，并配备相应的人员和设备，组织定期演练。应急环境监测应能够在异常情况下快速提供相关环境监测数据，为应急响应提供数据支持。 6.10其他辅助参数获取 6.10.1水文参数 处置场运行阶段，应以五年为周期，对地下水流向、水位等进行评价。 6.10.2地质参数 对于处置单元、边坡（如有）、截洪沟（如有）的沉降、变形、裂缝以及整个场址的地表形变和土壤侵蚀情况在设施接收废物期间应每年进行监测或检查，以评估场址环境安全性，分期建设的处置场在 上一期工程完成封盖和地表回填后，监测或检查的周期可以加长。 6.11调查水平 应将调查水平与本底浓度的倍数或剂量限值的某一份额相联系，并作为处置场的管理标准，当发现某物理量达到调查水平时，应采取下列行动： a）审核实验室程序； b）检查污染； c）再采样； d）放射性核素分析； e）增加采样频率； f）监测大纲扩展。 6.12报告水平 当某被测定的量达到或超过报告水平时，则应向监管部门报告监测结果和为解决问题所采取的缓解措施。 7关闭后阶段 7.1监测目的 处置场依照法定的程序和条件关闭后，根据处置场的运行历史以及关闭和稳定化情况保留合适的环境监测功能，作为处置场关闭安全监护计划的组成部分，其目的是通过探测环境中可能来自处置场的放射性物质，评价处置场关闭后设施的稳定性能，为处置废物中放射性核素异常释放提供早期预警，并为评估长期的辐射环境影响提供数据支持。 7.2主动监护期的监测 7.2.1一般要求 主动监护期的环境监测介质应以场区的监测井地下水样品为主，适当保留部分环境γ辐射水平和植物样品监测，对处置场的地表运动和土壤侵蚀也应持续关注。 7.2.2地下水和植物样品 在场址关闭后的初期，应继续开展地下水监测，分析是否含有可能来自处置场的放射性物质，从而间接判断工程屏障的完整性。如经一段时期监测确认没有潜在问题，可逐渐减少地下水监测频率。 主动监护期应定期采集处置场范围内（重点是处置单元区域）的植物样品（特别是深根植物），分析样品中是否含有可能来自处置场的放射性物质，判断环境影响。 7.2.3环境γ辐射水平 保留一个运行期间设置的环境γ辐射空气吸收剂量率连续监测点位继续开展连续监测，保留部分点位的定期γ辐射空气吸收剂量率瞬时测量。 7.2.4其他监测 对处置场的地表运动和土壤侵蚀开展定期监测或检查，发现明显变化时应及时分析变化对处置单元可能造成的影响，判断是否需要开展工程措施。 7.3环境监测大纲 关闭后阶段环境监测大纲的执行期需涵盖处置场关闭后的主动监护期，大纲中的监测项目、频次及点位，根据7.2节的要求进行设置，其他内容要求与5.5节相同。 7.4被动监护期的监测 可根据主动监护期的监测结果情况确定被动监护期是否继续开展辐射环境监测。如需继续开展辐射环境监测，被动监护期的监测大纲可在主动监护期监测大纲基础上适当简化。 8数据处理与监测报告 8.1数据处理和保存 8.1.1宜按照HJ61等标准规范的有关要求进行数据处理，辐射环境监测的最终结果应科学合理。 8.1.2建议处置场建设辐射环境信息管理系统保存所有环境监测过程和结果数据，为处置场整个寿期提供数据支撑。 8.2监测报告要求 8.2.1应编制监测报告以全面介绍监测过程及成果，报告的格式及频度应根据报告的目的决定。 8.2.2监测报告的内容应至少包括： a）监测任务或计划的全面介绍； b）与测量方案相关的详细场址周围环境情况； c）详细描述样品采集过程，给出各监测项目清晰的布点图，给出样品类型、采样过程、采样设备、取样量、取样位置和频次； d）给出分析核素、分析方法、分析仪器及最小探测限； e）详细描述样品制样及测量过程，测量结果包括测量值和标准差，测量结果应科学合理； f）详细描述质量保证措施及效果； g）结合已收集的监测数据详细评价场址周围辐射环境状况，对于存在异常的数据，应详细分析异常原因； h）运行阶段及关闭后监测还应与运行前辐射环境本底调查的数据和对照点数据进行比较，分析环境影响及变化趋势； i）根据当前的辐射环境监测成果对后续的辐射环境监测工作提出建议。 9质量保证 9.1质量保证应贯穿于处置场辐射环境监测的所有阶段，并应贯穿于从监测大纲制定到监测结果评价的全过程。 9.2各阶段辐射环境监测工作的承担单位应建立质量保证体系并使其持续、合规、有效运转。 9.3质量保证既要保证监测大纲在监测全过程中正确地执行并取得可信的监测结果，也要保证监测结果评估工作符合质保要求。 9.4质量保证措施至少应考虑以下因素： a）各类样品采样、运输、保存、制样和测量的操作程序有据可依； b）设备、仪器、物品、器具、试剂的质量； c）设备和仪器的校准与检定并确保在有效期内； d）人员培训与资格； e）通过对控制样品的常规分析及标准分析方法的应用，对方法进行确认； f）监测结果对国家标准的溯源性； g）数据处理及不确定度分析； h）与其它实验室的比对测量内容； i）为证明达到并且保持了所要求的质量而需要的文档管理与保存。 9.5处置场营运单位需保存运行前阶段辐射环境本底调查获得的土壤、沉积物和生物灰等样品。妥善保存调查原始记录和质量记录，保证调查的可追溯性。运行前辐射环境本底调查结果和报告需永久保存。 各阶段监测大纲、监测报告纳入安全全过程系统分析中。
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