标准编号:	HAD002/07-2019
中文名称:	核燃料循环设施营运单位的应急准备和应急响应
英文名称:	Emergency Preparedness and Emergency Response of Nuclear Fuel Cycle Facility Operating Entities
行业分类:	HAD    核电行业标准
发布机构:	国家核安全局
发布日期:	2019-11-29
实施日期:	2020-1-1
标准状态:	现行
替代旧标准:	HAD002/07-2010 核燃料循环设施营运单位的应急准备和应急响应 （报批稿）
翻译语言:	英文
文件格式:	PDF
中文字符数:	30000 字
翻译价格(元):	4500.00 元
交付时间:	付款后 1 个工作日

1 Introduction



1.1 Purpose



The site selection, design, construction, operation and decommissioning of nuclear fuel cycle facilities must be carried out in strict accordance with nuclear safety regulations. After taking various preventive measures, the possibility that nuclear fuel cycle facilities enter the emergency status of nuclear accident due to mistakes or accidents is very small, but it cannot be completely ruled out. Nuclear accidents may result in unacceptable release of radioactive materials or unacceptable exposure to personnel. In order to strengthen and maintain the emergency response capability, thereby control the accident, once happening, quickly and effectively and mitigate its consequences, every nuclear fuel cycle facility operator shall have a thorough on-site nuclear accident emergency response plan (hereinafter referred to as emergency response plan) and adequate preparation for emergency.



This guide provides guidance to civil nuclear fuel cycle facility operators for developing emergency response plans and carrying out emergency preparation and response actions.



1.2 Scope



This guide is applicable to the nuclear accident emergency preparation and response of operators of civil nuclear fuel cycle facilities (including nuclear fuel production, processing, storage and post-processing facilities) except nuclear reactors as well as the supervision and administration of emergency preparation and response of operators by the nuclear safety supervision and administration department of the State Council and specifies the specific requirements on emergency preparation and response of nuclear fuel cycle facility operators at different stages.



For different types of nuclear fuel cycle facilities, there may be considerable differences in the nature of nuclear accidents and their radiation consequences as a result of the great differences in the quantity, physical and chemical forms, nuclide composition, radioactivity and characteristics of nuclear materials and other radioactive materials processed, treated or stored thereby and their respective characteristics in process technology, engineering safety facilities and operation mode. Therefore, the operator shall, when using this guide, develop emergency response plans and implementation procedures according to the nature and risk degree of nuclear fuel cycle facilities.



2 Development of emergency response plans and relevant documents



2.1 Requirements on emergency preparation and response at different stages



2.1.1 Siting stage



The feasibility of implementing the emergency response plan shall be assessed in the site area within the whole expected life when demonstrating the suitability of the nuclear fuel cycle facility site. The documents submitted to the nuclear safety supervision and administration department of the State Council at the site selection stage shall cover the content of feasibility analysis on the implementation of emergency response plan at the site.



2.1.2 Design and construction stage



In this stage, the operator shall analyze the accident status of nuclear fuel cycle facilities (including beyond design basis accident) and the consequences and arrange the emergency facilities, emergency equipment and emergency evacuation routes in the site.



In the chapter on operation management of preliminary safety analysis report (PSAR), the preliminary scheme of emergency response plan shall be put forward, covering the purpose of emergency response plan, the laws it complies with and the applicable scope, the framework of emergency organization to be set up by the operator and its responsibilities, the preliminary calculation and environmental (population, roads, traffic, etc.) profile of the scope of emergency planning zone (if any), the basic functions and locations of main emergency facilities and equipment, the evacuation routes, and the arrangement of on-site and off-site emergency organization, resources and interface.



If there are already nuclear fuel cycle facilities in running in or near the site area where nuclear fuel cycle facilities are under construction, the safety of the workers of the nuclear fuel cycle facility under construction shall be ensured. For the expansion of nuclear fuel cycle facilities, the operator shall add the content of newly-built facility conditions on the basis of its original emergency response plan; for newly-built nuclear fuel cycle facilities, the operator shall develop corresponding emergency response plans and make corresponding emergency preparations for potential accidents of nuclear fuel cycle facilities in operation nearby.



2.1.3 Operation stage



The operator shall develop an emergency response plan which, serving as one of the application materials for operation and together with the final safety analysis report, shall be submitted to the nuclear safety supervision and administration department of the State Council for review before first loading (charging). Before first loading (charging), the nuclear fuel cycle facility operator shall complete the emergency preparation, and conduct the on-site pre-loading (charging) comprehensive emergency exercises.



During the whole operation stage of the nuclear fuel cycle facility, the emergency preparation shall be kept constantly on the alert; facilities, equipment and communication systems used in emergency status must be properly maintained and available at any time. The emergency exercise as well as recheck and revision of emergency response plan shall be conducted periodically.



When the nuclear fuel cycle facility enters an emergency status, the emergency response shall be implemented effectively, the accident conditions shall be reported to the competent department of nuclear industry and the nuclear safety supervision and administration department of the State Council, and the departments designated by the people's governments of provinces, autonomous regions and municipalities directly under the Central Government, and the operator shall coordinate with the off-site nuclear emergency organization to ensure the safety of the workers, the public and the environment.



2.1.4 Decommissioning stage



The decommissioning report of nuclear fuel cycle facilities shall cover the contents of the emergency response plan, indicating the possible emergency status and its countermeasures during decommissioning, taking into account the possible radiation hazards of nuclear fuel cycle facilities to be decommissioned, and making arrangements for the organizations and emergency facilities of the operators responsible for controlling these hazards. In case of an accident during the decommissioning, the emergency response shall be effectively implemented to ensure the safety of workers, the public and the environment.



2.2 Development of emergency response plan



2.2.1 Accident considered in emergency response plan



The operators shall, when developing the emergency response plan, take into account not only the expected operating conditions and accident conditions, but also those accidents with low occurrence probability but more serious consequences, including the beyond design basis accident with the environmental consequences beyond the design basis accidents (including serious accidents). The emergency response plan shall also consider the emergency status formed by the simultaneous occurrence of non-nuclear hazards and nuclear hazards, such as the simultaneous occurrence of fire and serious radiation hazards or contamination and the coexistence of toxic gas or asphyxiating gas with radiation and contamination, and the specific site conditions.



The major reference accidents of nuclear fuel cycle facilities are given in Annex A, which can be used as a reference for the operator when developing the emergency response plan.



2.2.2 Content of the emergency response plan



The emergency response plan shall at least include the following basic contents: the purpose, basis and scope of emergency response plan; the nuclear fuel cycle facilities and the environmental profile; emergency planning zone (if any); emergency status classification and emergency action level; emergency organization and responsibilities; emergency facilities and equipment; emergency communication, report and notification; accident consequence assessment; emergency environmental monitoring; emergency protective measures, emergency exposure control; medical rescue; emergency remedial actions; emergency termination and restoration actions; public information communication and public opinion response; record and report; and maintenance of emergency response capability.



The emergency response plan, if submitted to the nuclear safety supervision and administration department of the State Council for recheck, shall include detailed revision note.



The emergency response plan submitted by the operator before the first loading (charging) shall also include the technical documents of the following special subjects: emergency action level, habitability of main emergency facilities, emergency environmental monitoring scheme and emergency planning zone (if any). In principle, the above technical documents are no longer required to be submitted for recheck, but the revised technical documents shall still be submitted when the relevant contents are affected by changes in the nuclear facilities themselves or in the environment.



See Annex B for the format and content of on-site nuclear accident emergency response plan of nuclear fuel cycle facility operator.



2.3 Emergency response plan implementation procedure



The operators shall develop corresponding emergency preparation and response implementation procedures according to their emergency response plans. The implementation procedure list shall be included in the emergency response plan. The nuclear safety supervision and administration department of the State Council may inspect the texts of these procedures when reviewing the emergency response plans or conducting nuclear safety supervision and inspection.



The emergency response plan implementation procedures shall provide comprehensive and specific methods and steps for emergency workers to implement the emergency response plan, so as to ensure coordinated, timely and effective actions. The emergency response plan implementation procedures shall be revised in time according to the changes of the emergency response plan and other related factors to ensure its accuracy and operability.



See Annex C for examples for the implementation procedure list of emergency response plan of the operator.



2.4 Coordination of emergency response plans



For multi-facility sites, the same operator shall develop a unified emergency response plan covering all facilities, and the emergency response plans of different operators shall be coordinated with each other.



 

The on-site nuclear accident emergency response plan shall be coordinated with other emergency response plans for other emergencies of the operator.



If the off-site emergency status is involved, the on-site and off-site nuclear accident emergency response plans shall be mutually complementary and coordinative. In case that the consequences of the accident may exceed the boundary of the site area, the operator shall estimate the possible release amount of radioactive materials, and provide corresponding suggestions on the contents and methods of implementing public protective measures to the off-site nuclear emergency organization.



3 Emergency organization



3.1 General



The operator shall list in the emergency response plan the emergency preparation responsibilities of the normal operation organization and the emergency response responsibilities of the on-site emergency organization.



3.2 Main responsibilities and basic organizational structure of emergency organization



3.2.1 The operator shall set up a unified on-site emergency organization, whose main responsibilities are:



(1) Implementing the national guidelines and policies on nuclear emergency response works;



(2) Developing, revising and implementing the on-site nuclear emergency response plan and the implementation procedure, and making good preparations for nuclear emergency;



(3) Specifying the tasks and interfaces of emergency action organizations;



(4) Taking timely measures to mitigate the consequences of the accident;



(5) Protecting the safety of personnel in the site and in the area controlled by the operator;



(6) Reporting the accident conditions to the competent department of nuclear industry and the nuclear safety supervision and administration department of the State Council, and the departments designated by the people's governments of provinces, autonomous regions and municipalities directly under the Central Government in a timely manner and coordinating with the off-site nuclear emergency organization.



3.2.2 The emergency organization of the operator shall include emergency headquarters and several emergency action groups. The emergency response plan of the operator shall clearly specify the responsibilities of the emergency headquarters and each emergency action group, set up corresponding emergency posts and provide nominated and authorized qualified personnel.



3.2.3 The emergency organization of the operator shall have the ability to start timely and work continuously under emergency status.



3.3 Emergency headquarters



3.3.1 The operator shall set up an emergency headquarters as its leading and commanding organization for emergency response under emergency status. The emergency headquarters shall consist of the chief commander and other members. The emergency chief commander shall be the legal representative of the operator or the agent designated by the legal representative. The emergency response plan shall clearly specify the replacement of emergency chief commander and the replacement sequence. The emergency chief commander and his replacement shall have more than 5 years of relevant management experience in the production of nuclear fuel cycle facilities.



3.3.2 The responsibilities of the emergency headquarters are as follows:



(1) The emergency chief commander shall be responsible for uniformly commanding the on-site response actions in the emergency status, approving the entry and terminating the emergency standby, plant emergency and on-site emergency status (in case of emergency, before the start of emergency headquarters, the person in charge on duty for operation shall act as the emergency chief commander);



(2) Reporting the accident conditions to the competent department of nuclear industry and the nuclear safety supervision and administration department of the State Council, and the departments designated by the people's governments of provinces, autonomous regions and municipalities directly under the Central Government in a timely manner and maintaining close connection during the accident;



(3) Putting forward suggestions on entering the off-site emergency status and taking emergency protective measures off-site;



(4) Cooperating with and assist the nuclear emergency organizations of provinces, autonomous regions and municipalities directly under the Central Government in doing well in nuclear emergency response;



(5) Requesting support from the off-site nuclear emergency organization when necessary.



3.4 Emergency action groups



3.4.1 The operator shall set up several emergency action groups according to the principle of active compatibility, and allocate appropriate personnel. The emergency action groups generally include technical support group, radiation protection group, accident rescue group, logistics support group and public information group. The operator may adopt different schemes when establishing emergency organizations, but they shall cover the following responsibilities: running and operation of various systems in the site; radiation measurement and consequence assessment; critical safety assessment, implementation of protective actions (taking cover, evacuating and personnel counting, missing persons searching and rescuing, etc.); medical rescue; emergency communication; emergency exposure control; fire protection and defense; transportation, equipment and material supply and logistics support, and public information and public opinion response. In case of emergency, each emergency action group shall keep smooth communication with emergency headquarters and other relevant emergency action groups.



3.4.2 The main responsibilities of the technical support group are:



(1) Making a preliminary assessment of the emergency status, and proposing the emergency status level to the emergency headquarters;



(2) Grasping the accident status, analyzing and assessing the accident, and providing the accident rescue group with suggestions and guidance on diagnosing the accident and taking countermeasures;



(3) Recommending feasible emergency response actions to the emergency headquarters, or putting forward suggestions on protective actions ought to be taken according to accident diagnosis and assessment.



 

3.4.3 The main responsibilities of the radiation protection group are:



(1) Being responsible for on-site radiation and chemical monitoring, and investigating, assessing, classifying, marking and controlling the contaminated areas in the site;



(2) Carrying out necessary off-site radiation investigation, sampling, analysis and assessment;



(3) Putting forward suggestions on on-site and off-site radiation protection actions, and determining the requirements for workers taking stable iodine and stable iodine distribution;



(4) Organizing appropriate personnel and providing relevant equipment to support radiation protection emergency response actions, and supervising, assessing and controlling the exposure dose of emergency workers;



(5) Other radiation protection.



3.4.4 The main responsibilities of the accident rescue group are:



(1) Managing the emergency design, build, construction and engineering rescue works required under emergency status;



(2) Being responsible for professional maintenance, organizing teams, allocating enough professionals, timely inputting, supplementing and replacing personnel, maintaining and repairing systems and equipment, and troubleshooting.



3.4.5 The main responsibilities of the logistics support group are:



(1) Providing communication equipment to ensure smooth communication;



(2) Ensuring the office conditions of all emergency organizations and personnel, and providing office supplies and equipment;



(3) Being responsible for the accommodation and living arrangements and material supply of emergency workers and temporary contingent workers;



(4) Being responsible for on-site safety protection, fire control, traffic management and emergency medical rescue;



(5) Being responsible for purchasing and supplying equipment, materials, medical equipment and medicines;



(6) Being responsible for processing, archiving and saving the documents, data and correspondence;



(7) Being responsible for organizing personnel evacuation and personnel search and rescue.



3.4.6 The public information group, usually under the direct leadership of the emergency chief commander, manages the public information during the emergency. The main responsibilities of the public information group are:



(1) to know the accident information in time;



(2) Collecting the reflection from the public and society, so as to carry out proper communication;



(3) Preparing and providing relevant data;



(4) Making preparations for the press conference according to the authorization.



3.5 Interface to off-site nuclear emergency organization



3.5.1 The operator shall clearly specify in the emergency response plan the interface to the off-site nuclear emergency organization and relevant departments, and state the names and functions of the off-site nuclear emergency organization and relevant departments.



3.5.2 The operator shall coordinate the on-site emergency organization with the off-site nuclear emergency organization and backup organization, clarify the division of responsibilities and, if necessary, sign relevant written agreements.



4 Emergency status and emergency action level



4.1 Emergency status classification



The emergency status of nuclear facilities is generally divided into emergency standby, plant emergency, on-site emergency and off-site emergency. The operator shall determine the emergency status level according to the type and design characteristic of nuclear fuel cycle facilities, assumed accident types and severity of accident consequences.



For nuclear fuel cycle facilities where a large amount of UF6 is likely to be released, it is necessary to consider the hazard of chemical toxicity of HF generated by UF6 interacting with water or vapour in the air when determining the emergency status classification.



(1) For emergency standby, certain specific working conditions or incidents that may endanger the safety of facilities appear in, indicating that the safety level of facilities is uncertain or may be significantly reduced.



(2) For plant emergency, the safety level of facilities has actually or potentially been greatly reduced, but the consequences of the incident are limited to local areas of the plant or site area, and will not pose a threat to the off-site.



(3) For on-site emergency, the engineering safety facilities for the facilities in the site area may be seriously failed, with the safety level greatly reduced, and the consequences of the accident extended to the whole site area; except near the boundary of the site area, the off-site radioactive irradiation level will not exceed the intervention level of emergency protective actions or the hazard of chemical toxicity caused by nuclear accidents will not affect off-site; early information and assessment show that there is no need to take protective measures off-site.



(4) For off-site emergency, a large amount of radioactive materials or toxic materials may be released or likely to be released, and the accident consequences is beyond of the boundary of the site area, resulting in the off-site radioactive irradiation level beyond the intervention level of emergency protective actions or the hazard of chemical toxicity caused by nuclear accidents affecting off-site, thus it is necessary to take off-site protective measures.

1 Introduction
1.1 Purpose
1.2 Scope
2 Development of emergency response plans and relevant documents
2.1 Requirements on emergency preparation and response at different stages
2.2 Development of emergency response plan
2.3 Emergency response plan implementation procedure
2.4 Coordination of emergency response plans
3 Emergency organization
3.1 General
3.2 Main responsibilities and basic organizational structure of emergency organization
3.3 Emergency headquarters
3.4 Emergency action groups
3.5 Interface to off-site nuclear emergency organization
4 Emergency status and emergency action level
4.1 Emergency status classification
4.2 Emergency action level
5 Emergency planning zone
5.1 Principles for determining emergency planning zone
5.2 Determination of emergency planning zone
6 Emergency facilities and equipment
6.1 General
6.2 Emergency control center
6.3 Control room
6.4 Communication system
6.5 Assessment facilities and equipment
6.6 Radiation monitoring facilities and equipment
6.7 Radiation protection facilities and equipment
6.8 First aid and medical facilities and equipment
6.9 Emergency evacuation routes and assembly points
6.10 Other emergency equipment and materials
6.11 Habitability requirements
7 Emergency response and protective measures
7.1 General
7.2 Intervention principles and intervention levels
7.3 Response actions in emergency status
7.4 Emergency notice
7.5 Emergency monitoring
7.6 Assessment activities
7.7 Remedial actions
7.8 Emergency protective measures
7.9 Control of emergency exposure
7.10 Medical rescue
8 Emergency termination and restoration actions
8.1 Termination of emergency status
8.2 Restoration actions
9 Maintenance of emergency response capability
9.1 Training
9.2 Exercises
9.3 Emergency facilities and maintenance of equipment
9.4 Recheck and revision of emergency response plan
10 Records and reports
10.1 Records
10.2 Reports
Terms and definitions
Annex A Reference accidents of nuclear fuel cycle facilities
Annex B Format and content of on-site nuclear accident emergency response plan of nuclear fuel cycle facilities operator
Annex C Examples for implementation procedure list of on-site nuclear accident emergency response plan of nuclear fuel cycle facilities operator
Annex D Example for initial conditions and emergency action level matrix

1 引言

1.1 目的
核燃料循环设施的选址、设计、建造、运行和退役均需严格按照核安全法规 进行。在采取种种预防性措施后，核燃料循环设施因失误或事故进入核事故应急 状态的可能性虽然很小，但仍不能完全排除。核事故可能导致放射性物质不可接 受的释放，或对人员造成不可接受的照射。为了加强并维持应急响应能力，以便 在一旦发生事故时能快速有效地控制事故，并减轻其后果，每一个核燃料循环设 施营运单位应有周密的场内核事故应急预案（以下简称应急预案）和充分的应急 准备。
本导则为民用核燃料循环设施营运单位制定应急预案，开展应急准备和应急 响应行动提供指导。
1.2 范围
本导则适用于除核反应堆外的民用核燃料循环设施（包括核燃料生产、加工、 贮存和后处理设施等）营运单位的核事故应急准备和应急响应，以及国务院核安 全监督管理部门对营运单位应急准备和应急响应工作的监督管理，给出了在不同 阶段对核燃料循环设施营运单位应急准备和应急响应的具体要求。
对于不同类型的核燃料循环设施，由于其加工、处理或贮存的核材料及其他 放射性物质的数量、物理化学形态、核素组成、放射性活度和特性等差别较大， 且其工艺技术、工程安全设施和运行方式等各有特点，导致核事故的性质及其辐 射后果可能存在相当大的差别。因此营运单位在使用本导则时，应根据核燃料循 环设施的性质和风险程度，制定应急预案及执行程序。

2 应急预案及相关文件的制定
2.1 不同阶段应急准备和应急响应要求
2.1.1 厂址选择阶段 论证核燃料循环设施厂址适宜性时，应评价厂址区域在整个预计寿期内实施
应急预案的可行性。在厂址选择阶段向国务院核安全监督管理部门提交的文件


中，应包括关于厂址执行应急预案可行性分析的内容。
2.1.2 设计建造阶段 在设计建造阶段，营运单位应对核燃料循环设施事故状态（包括超设计基准
事故）及其后果作出分析，对场内的应急设施、应急设备和应急撤离路线作出安 排。在初步安全分析报告（PSAR）有关运行管理的章节中，应提出应急预案的 初步方案，其内容包括：应急预案的目的，依据的法规和适用范围，营运单位拟 设置的应急组织及其职责的框架，应急计划区（如有）范围的初步测算及其环境
（人口、道路、交通等）概况，主要应急设施与设备的基本功能和位置，撤离路 线，场内、外应急组织、资源及接口的安排。
若正在建设的核燃料循环设施场区内或附近已有正在运行的核燃料循环设 施，应保证正在建设的核燃料循环设施工作人员的安全。对于扩建核燃料循环设 施，营运单位应在其原应急预案的基础上增加针对新建设施情况的内容；对于新 建核燃料循环设施，新建核燃料循环设施营运单位应针对附近正在运行的核燃料 循环设施潜在事故，制定相应的应急预案，并进行相应的应急准备。
2.1.3 运行阶段 营运单位应制定应急预案，并作为运行申请材料之一于首次装（投）料前与
最终安全分析报告一并报国务院核安全监督管理部门审查。在首次装（投）料前， 核燃料循环设施营运单位应完成应急准备工作，并进行装（投）料前场内综合应 急演习。
在整个核燃料循环设施运行阶段，应急准备应做到常备不懈；应急状态下需 要使用的设施、设备和通信系统等必须妥善维护，处于随时可用状态。应定期进 行应急演习和对应急预案进行复审和修订。
在核燃料循环设施进入应急状态时，应有效实施应急响应，按规定向国务院 核工业主管部门、核安全监督管理部门和省、自治区、直辖市人民政府指定的部 门报告事故情况并与场外核应急组织协调配合，以保障工作人员、公众和环境的 安全。
2.1.4 退役阶段 在核燃料循环设施退役报告中应有应急预案的内容，说明在退役期间可能出
现的应急状态及其对策，考虑待退役的核燃料循环设施可能产生的辐射危害，对


营运单位负责控制这些危害的组织和应急设施作出安排。在退役期间一旦发生事 故，应有效实施应急响应，以保障工作人员、公众和环境的安全。
2.2 应急预案的制定
2.2.1 应急预案考虑的事故 营运单位在制定应急预案时，不仅要考虑预期的运行工况和事故工况，而且
应考虑那些发生概率很小且后果更为严重的事故，包括其环境后果大于设计基准 事故的超设计基准事故（包括严重事故）。应急预案还应考虑到非核危害与核危 害同时发生所形成的应急状态，诸如火灾与严重辐射危害或污染同时发生、有毒 气体或窒息性气体与辐射和污染并存等，同时要考虑特定的厂址条件。
附录A给出了各主要核燃料循环设施的参考事故，可供营运单位制定应急预 案时参考。
2.2.2 应急预案的内容 应急预案应至少包括以下基本内容：制定应急预案的目的、依据、范围，核
燃料循环设施及其环境概况，应急计划区（如有），应急状态分级及应急行动水 平，应急组织与职责，应急设施与设备，应急通信、报告与通知，事故后果评价， 应急环境监测，应急防护措施，应急照射控制，医学救护，应急补救行动，应急 终止和恢复行动，公众信息沟通与舆情应对，记录和报告，应急响应能力的保持。
应急预案提交国务院核安全监督管理部门复审时，应包含详细的修订说明。 营运单位在首次装（投）料前提交的应急预案还应包括如下专题的技术文件： 应急行动水平、主要应急设施可居留性、应急环境监测方案、应急计划区（如有）
等。复审时，原则上不再要求提交上述技术文件，但在核设施本身或环境发生的 改变对相关内容造成影响时，仍应提交修订后的技术文件。
核燃料循环设施营运单位场内核事故应急预案的格式和内容见附录B。

2.3 应急预案执行程序
营运单位应根据其应急预案制定相应的应急准备和应急响应执行程序。执行 程序清单应列入应急预案中。国务院核安全监督管理部门在审查应急预案或进行 核安全监督检查时，可对这些程序文本进行检查。
应急预案执行程序应为应急工作人员执行应急预案提供全面的、具体的方法


和步骤，以保证协调一致和及时有效的行动。应急预案执行程序应根据应急预案 及其他相关因素的变化及时修订，保证其准确性及可操作性。
营运单位应急预案执行程序清单示例见附录C。

2.4 应急预案的协调
对于多设施厂址，同一营运单位的应制定涵盖各设施的统一的应急预案，不 同营运单位的应急预案应相互协调。
场内核事故应急预案应与营运单位其他突发事件应急预案相协调。 如涉及到场外应急状态，场内核事故应急预案和场外核事故应急预案应相互
补充和协调。在事故后果可能超越场区边界的情况下，营运单位应估算可能的放 射性物质的释放量，并向场外核应急组织提供相应的实施公众防护措施的内容和 方法的建议。

3 应急组织
3.1 概述
营运单位应在应急预案中列出正常运行组织的应急准备职责和场内应急组 织的应急响应职责。
3.2 应急组织的主要职责和基本组织结构
3.2.1 营运单位应成立场内统一的应急组织，其主要职责是：
（1）执行国家核应急工作的方针和政策；
（2）制定、修订和实施场内核应急预案及其执行程序，做好核应急准备；
（3）规定应急行动组织的任务及相互间的接口；
（4）及时采取措施，缓解事故后果；
（5）保护场内和受营运单位控制的区域内人员的安全；
（6）及时向国务院核工业主管部门、核安全监督管理部门和省、自治区、 直辖市人民政府指定的部门报告事故情况并与场外核应急组织协调配合。
3.2.2 营运单位应急组织包括应急指挥部和若干应急行动组。营运单位的应 急预案应明确规定应急指挥部及各应急行动组的职责，设立相应的应急岗位，配 备经提名和授权的合格岗位人员。


3.2.3 营运单位的应急组织应具备在应急状态下及时启动及连续工作的能 力。
3.3 应急指挥部
3.3.1 营运单位应设立应急指挥部，作为本单位在应急状态下进行应急响应 的领导和指挥机构。应急指挥部由总指挥及其他成员组成。应急总指挥由营运单 位法定代表人或法定代表人指定的代理人担任。应急预案中应明确应急总指挥的 替代人及替代顺序。应急总指挥及其替代人应具备5年以上核燃料循环设施生产 相关管理经验。
3.3.2 应急指挥部的职责为：
（1）应急总指挥负责统一指挥应急状态下场内的响应行动，批准进入和终 止应急待命、厂房应急和场区应急状态（紧急情况下，在应急指挥部启动前，运 行值班负责人应代行应急总指挥的职责）；
（2）及时向国务院核工业主管部门、核安全监督管理部门和省、自治区、 直辖市人民政府指定的部门报告事故情况，并保持在事故过程中的紧密联系；
（3）提出进入场外应急状态和场外采取应急防护措施的建议；
（4）配合和协助省、自治区、直辖市核应急组织做好核应急响应工作；
（5）必要时向场外核应急组织请求支援。

3.4 应急行动组
3.4.1 营运单位应根据积极兼容的原则设置若干应急行动组，并配备合适的 人员。应急行动组一般包括技术支持组、辐射防护组、事故抢险组、后勤保障组、 公众信息组等。营运单位在建立应急组织时可采取不同的方案，但应涵盖下述职 责：场内各系统的运行、操作，辐射测量与后果评价，临界安全评价，防护行动 实施（隐蔽、撤离及人员清点、失踪人员搜救等），医学救护，应急通讯，应急 照射控制，消防与保卫，交通运输与器材、物资供应、后勤保障，公众信息与舆 情应对。应急状态下，各应急行动组应保持与应急指挥部及其他相关应急行动组 之间通畅的通信联系。
3.4.2 技术支持组的主要职责为：
（1）对应急状态进行初步评价，向应急指挥部提出应急状态等级的建议；


（2）掌握事故状态，分析、评价事故，向事故抢险组提供有关诊断事故、 采取对策方面的建议和指导；
（3）向应急指挥部推荐可行的应急响应行动，或者根据事故诊断、评价， 提出应采取的防护行动建议。
3.4.3 辐射防护组的主要职责为：
（1）负责场内辐射和化学监测，对场内污染区域进行调查、评价、划分、 标记和控制；
（2）开展必要的场外辐射调查、取样、分析和评价；
（3）提出场内、外辐射防护行动建议，确定工作人员服用稳定碘的要求和 发放；
（4）组织适当人员、提供相关设备支持辐射防护应急响应行动，监督、评 价和控制应急工作人员的受照剂量；
（5）其他辐射防护工作。
3.4.4 事故抢修组的主要职责为：
（1）管理应急状态下所需的应急设计、建造、施工和工程抢险工作；
（2）负责专业维修，组织队伍、配备足够的专业人员，并及时投入、补充、 替换人员，对系统、设备进行维护、修理、故障的排除。
3.4.5 后勤保障组的主要职责为：
（1）提供通信设备，保证通信畅通；
（2）保证各应急组织和人员的办公条件，提供办公用品、器材；
（3）负责应急工作人员和临时增援工作人员的食宿生活安排和物资供应；
（4）负责场内安全保卫、消防、交通管理、应急医疗救护；
（5）负责设备、材料、医疗设备、药品的采购供应；
（6）负责文件、资料、通信等的整理、归档、保存；
（7）负责组织人员撤离和人员搜救。
3.4.6 公众信息组通常在应急总指挥直接领导下，管理应急期间公众信息工 作。公众信息组的主要职责为：
（1）及时了解事故信息；
（2）收集公众、社会的反映，以便开展适当的沟通；


（3）准备和提供有关资料；
（4）根据授权，做好新闻发布会的准备。

3.5 与场外核应急组织的接口
3.5.1 营运单位应在应急预案中明确与场外核应急组织及有关部门的接口， 说明场外核应急组织及有关部门的名称、职能。
3.5.2 营运单位场内应急组织应与场外核应急组织、后援组织相互协调，并 明确职责分工，必要时应签订有关书面协议。

4 应急状态及应急行动水平
4.1 应急状态分级
核设施应急状态一般分为应急待命、厂房应急、场区应急和场外应急。营运 单位应根据核燃料循环设施的类型、设计特征、所假定的事故类型以及事故后果 的严重程度来确定所达到的应急状态等级。
对于可能发生较大量UF6释放的核燃料循环设施，在确定应急状态分级时需 考虑UF6与空气中的水或水蒸气作用产生的HF等的化学毒性的危害。
（1）应急待命出现可能危及设施安全的某些特定工况或事件，表明设施安 全水平处于不确定或可能有明显降低。
（2）厂房应急设施的安全水平有实际的或潜在的大的降低，但事件的后果 仅限于厂房或场区的局部区域，不会对场外产生威胁。
（3）场区应急设施的工程安全设施可能严重失效，安全水平发生重大降低， 事故后果扩大到整个场区，除了场区边界附近，场外放射性照射水平不会超过紧 急防护行动干预水平或由核事故引发的化学毒性的危害不会影响到场外，早期的 信息和评价表明场外尚不必采取防护措施。
（4）场外应急发生或可能发生放射性物质或有毒物质大量释放，且事故后 果超越场区边界，导致场外的放射性照射水平超过紧急防护行动干预水平或由核 事故引发的化学毒性的危害影响到场外，以至于有必要采取场外防护措施。
4.2 应急行动水平
营运单位应根据核燃料循环设施的设计特征和厂址特征，确定用于应急状态


分级的初始条件及其相应的应急行动水平。在首次装（投）料前，申请运行许可 证时，应提交应急行动水平及编制说明；在运行阶段，应根据运行经验反馈，对 其进行持续修订完善。
应急行动水平应具有以下基本特征：
（1）一致性。在相类似的风险水平下，由应急行动水平可得出相类似的结 论。不同核燃料循环设施，只要应急状态等级相同，则其代表的风险水平和所需 要的应急响应水平是大致相同的。
（2）完整性。应急行动水平应包括可触发各个应急状态的所有适用条件。
（3）可操作性。应急行动水平应尽量使用客观、可观测的值，以便于快速、 正确地识别，并以此判断应触发的应急状态等级。
（4）逻辑性。在多重事件组合的分级中，应考虑事件进程的逻辑性。 应急行动水平一般采用初始条件和应急行动水平矩阵的形式。矩阵中应至少
包括识别类、应急状态、初始条件、应急行动水平等技术要素。识别类应便于操 作，并能够覆盖所有制定的应急行动水平。由于核燃料循环设施类型多，不同的 设施可有不同的识别类。一般可采用如下5种识别类：
（1）辐射水平或放射性流出物异常；
（2）影响核燃料循环设施安全的危害和其他事件；
（3）系统故障；
（4）放射性物质包容和屏蔽性能降低；
（5）考虑到核燃料循环设施的事故和特征，除上述4种识别类外，还可以事 件或事故始发作为初始条件。
制定的应急行动水平文件还应对应急状态等级的确定、升级、降级原则进行 规定。
核燃料循环设施初始条件和应急行动水平矩阵示例见附录D。