标准编号:	HAD002/07-2010
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 （报批稿）
英文名称:	Emergency Preparedness and Emergency Response of Nuclear Fuel Cycle Facility Operating Entities (Draft for Approval)
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:	2010-08-20
实施日期:	2010-8-20
标准状态:	被替代
被新标准替代:	HAD002/07-2019 核燃料循环设施营运单位的应急准备和应急响应
被替代日期:	2020-1-1
翻译语言:	英文
文件格式:	PDF
中文字符数:	30000 字
翻译价格(元):	1000.00 元
交付时间:	付款后 1 个工作日

1 Introduction



1.1 Purpose

This Guideline is formulated according to Regulation on the Safety Supervision and Management of Civil Nuclear Facilities of the People's Republic of China and Regulation on Emergency Management of Nuclear Accidents at Nuclear Power Plants as well as other laws and regulations of nuclear safety with a view to providing guidance for civil nuclear fuel cycle facilities (hereinafter referred to as nuclear fuel cycle facilities) operating entities formulating emergency plan, carrying out emergency preparedness and conducting emergency response actions in case of accident.

This Guideline is guidance document; when formulating emergency plan and conducting emergency response actions, the operating entities may not adopt the scheme and method recommended in this Guideline, but they must prove that the adopted scheme and method have the safety level not inferior to that of this Guideline to the national nuclear safety supervision and control department.

1.2 Scope

This Guideline is applicable to emergency plan, emergency preparedness and emergency response of entities operating civil nuclear fuel cycle facilities (including facilities for uranium mining and metallurgy, conversion, isotope separation, element manufacture and fuel reprocessing as well as radioactive waste treatment and disposal facilities) excepting nuclear reactor as well as examination and evaluation of national nuclear safety supervision and control department on the emergency plan of operating entities.

This Guideline proposes basic requirements on the emergency plan formulation of the nuclear fuel cycle facilities operating entities and guiding suggestions on emergency plan contents and compiling format as well as emergency preparedness and emergency response capability maintenance of operating entities, and it also provides guiding principle for emergency plan implementation procedure compilation.

As for different types of nuclear fuel cycle facilities, vast differences exist in quantity, physical chemistry form, nuclide composition, radioactive activity and characteristic of nuclear material and other radioactive substances processed, treated or stored by them, and the characteristics of their process technology, work engineering facilities and operation mode are different, therefore, the property of the possible nuclear accident existing in them and the radiological consequence may be very different. Thus, the requirements of their emergency plan, emergency preparedness and emergency response are different. This Guideline will not specially discuss the above-mentioned differences. In case the operating entities use this Guideline, they must carry out threat assessment and analysis in combination with the characteristics of the nuclear fuel cycle facilities and formulate emergency plan and emergency response scheme taking evaluation on various possible nuclear and radiation accident consequences as basis and referring to this Guideline.



2 Emergency Plan Formulation



2.1 Requirements of Emergency Preparedness and Emergency Response in Different Stages

2.1.1 Plant site selection stage

As for evaluation on the suitability of nuclear fuel cycle facility plant site, the emergency plan implementation capacity and feasibility of emergency plan implementation within the whole predicted lifetime of the nuclear fuel cycle facility plant site area shall be demonstrated according to the natural and social characteristics of the plant site.

2.1.2 Design and construction stage

In design and construction stage, the operating entities and organizations concerned shall analyze the accidental state (including severe accident) and its consequence of nuclear fuel cycle facility, arrange the emergency facilities, emergency equipment and emergency evacuation route in the plant, compile in-site emergency plan and implementation procedure, carry out corresponding emergency preparedness works (including completing construction of emergency facilities) and make emergency exercise plan.

In the chapters relevant to operation and management in Preliminary Safety Analysis Report (PSAR), preliminary scheme of emergency plan shall be proposed, and the contents are as follows: emergency plan purpose, laws and regulations it based on and application scope, frame of emergency organizations set by operating entities and their responsibilities, emergency planning zone preliminary measurement & calculation and its environment (population, road, traffic, etc.) overview, basic function and position of main emergency facilities and equipment and evacuation route; emergency resource and interface arrangement shall be described.

In case there is other nuclear facility in operating in the newly-built nuclear fuel cycle facility plant site, newly-built nuclear fuel cycle facilities operating entities and organizations concerned shall compile corresponding emergency preparedness procedure and carry out proper emergency preparedness in allusion to the potential accident of the nuclear facility in running.

2.1.3 Stage before initial charge

Emergency plan of operating entities shall serve as independent document after being examined by the competent departments, and it shall be submitted to the national nuclear safety supervision and control department for examination and approval together with final safety analysis report before initial trial run, and carried out with emergency exercise before charging according to those specified in this Guideline. Before operation, nuclear fuel cycle facilities operating entities shall complete all emergency preparedness.

2.1.4 Operation stage

Within the whole operation stage of the nuclear fuel cycle facility, emergency preparedness shall be always kept; in emergency state, the necessary facilities, equipment and communication systems shall be properly maintained and ready for use at any time; the nuclear emergency exercise shall be carried out periodically and the emergency plan shall be rechecked and revised.

In case the nuclear fuel cycle facility enters into emergency state, effectively implement the emergency response, timely report the accident conditions to the national nuclear safety supervision and control department and coordinate and cooperate with off-site emergency organizations so as to ensure the safety of workers, publics and environment.

2.1.5 Decommissioning stage

There shall be emergency plan contents in the Nuclear Fuel Cycle Facility Decommissioning Report, describing the possible emergency state and corresponding countermeasures during decommissioning period, considering the radiation hazards possibly generated by to-be-decommissioned nuclear fuel cycle facility and specifying that the operating entities are responsible for organization and emergency facilities controlling such hazards. Once accident occurs during decommissioning period, effectively implement emergency response so as to ensure the safety of workers, publics and environment.

2.2 Emergency Plan Formulation

Nuclear fuel cycle facilities operating entities must formulate the emergency plan according to the characteristics of this nuclear facility and the environmental conditions surrounding the plant site. The main contents of operating entities emergency plan include:

(1) General characteristics of nuclear fuel cycle facility (construction purpose; installation type; operation plan for permitted nuclear activity; main facilities and functions, etc.);

(2) General conditions of the plant site (geographical location and site area plan layout; population distribution surrounding the plant site; meteorological conditions of the plant site, traffic conditions, etc.);

(3) Emergency organization;

(4) Emergency state and emergency action level;

(5) Emergency planning zone;

(6) Emergency response facilities, equipment and apparatus;

(7) Emergency response and protective measures;

(8) Emergency termination and restoration action;

(9) Maintenance of emergency response capability;

(10) Record and report.

Appendix A of this Guideline proposes requirements and suggestions for format and content of nuclear fuel cycle facilities operating entities emergency plan, and the operating entities may compile emergency plan according to these suggestions. Due to the big difference of types, characteristics and surrounding environment of nuclear fuel cycle facilities, the operating entities may properly change the content and format specified in this Guideline, but it shall be ensured that emergency plan covers the main contents specified in this Guideline and that the changed content and format have been approved by the national nuclear safety supervision and control department.

2.3 Accident Considered in Emergency Plan

The emergency plan of the nuclear fuel cycle facilities operating entities is mainly in allusion to the potential nuclear accidents causing or possibly causing lose-control of radioactive substance release and thereby endangering worker or public health or environmental security or resulting in property loss. The range of the considered accidents shall cover expected operation conditions and accident conditions as well as the accident with lower occurrence probability while more serious consequence (including the severe accidents with environmental consequence more serious than that of the design basis accident). The operating entities shall carry out overall safety analysis and determine hypothetical accident spectrum (especially serious accident) and corresponding source term size suitable to this facility and used for emergency plan. Determination of accident range used for emergency plan may be partially based on the safety analysis report of the facilities, and further analysis shall be carried out as a supplementary. In the complementary analysis, it may be supposed that partial design and operating performances failure occurs, although such failure is improbable. Appendix C provides reference accidents of each main nuclear fuel cycle facility, which may be referred to by the operating entities during emergency plan formulation.

2.4 Emergency Plan Implementation Procedure

The operating entities shall compile various necessary emergency plan implementation procedures by reference to the guiding principles provided in Appendix B in this Guideline, including implementation procedures for implementing emergency response action and support procedures for properly carrying out emergency preparedness. These procedures shall provide the emergency work personnel with comprehensive and specific methods and procedures for implementing emergency plan and ensure that the emergency preparedness is carried out normatively and orderly and that the emergency plan is implemented concertedly and effectively.

It is not required to incorporate the implementation procedure into the emergency plan text; generally, the implementation procedure is not required to be provided to the national nuclear safety supervision and control department for examination and evaluation, either. But during emergency plan examination and evaluation as well as nuclear safety inspection, the national nuclear safety supervision and control department may inspect these procedure texts.



3 Emergency Organization



3.1 Emergency Organization of Operating Entities

3.1.1 The operating entities shall establish in-site emergency organization in line with the principle "active and compatible" on the basis of facility conventional operation organization, and the main responsibilities of the in-site emergency organization are as follows:

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

(2) Formulating, revising and implementing in-site nuclear emergency plan and properly carrying out nuclear emergency preparedness;

(3) Determining the nuclear emergency state class and uniformly commanding the nuclear emergency response actions of the entity;

(4) Taking measures immediately in case of accident to relieve the accident consequence;

(5) Protecting the safety of the workers within the site area;

(6) Carrying out radiation monitoring;

(7) Timely reporting accident conditions to national and provincial (municipal) nuclear emergency organizations, competent departments and national nuclear safety supervision and control departments as well as the specified departments, and keeping close connection during the accident;

(8) Where it is possible that the nuclear facility is in off-site emergency state, suggesting entering into off-site emergency state and adopting off-site emergency protective measures;

(9) Cooperating with and helping the provincial (municipal) nuclear emergency organization to properly carry out nuclear emergency response works, as necessary.

3.1.2 Emergency organization of operating entities includes emergency command and all emergency action teams. The operating entities shall make clear the personnel composition, the task and the responsibility of each emergency response team participating in such actions as emergency preparedness, emergency response and emergency restoration in their emergency plans.

3.1.3 Emergency organization of operating entities shall possess the capacity for continuously working for 24-hour under all levels of emergency states.

3.2 Emergency Command

3.2.1 Emergency command is the leading and command organization of in-site emergency preparedness and emergency response and is responsible for contacting off-site emergency organization, superior competent department and national nuclear safety supervision and control department. Emergency command consists of main executives and technical directors as well as responsible persons from relevant departments (operation, maintenance, security & protection, safeguard, logistics, etc.) of the operating entities. A chief emergency commander (legal representative of the operating entity or its designated personnel) and several deputy chief commanders shall be arranged.

3.2.2 The emergency plan of operating entities shall explicitly specify the highest authority and the specific responsibility of the emergency command, including:

(1) Organizing to formulate and modify the emergency plan;

(2) Organizing to implement and inspect the emergency preparedness works of the operating entities;

(3) Announcing and terminating the emergency states other than the off-site emergency;

(4) Commanding to implement in-site emergency response actions; including

——Taking actions for controlling and relieving the accident;

——Adopting emergency protective actions for protecting in-site workers;

——Suggesting whether an off-site protective action for protecting the public is necessary;

——Reporting or announcing the nuclear emergency information to off-site emergency organizations at all levels, superior competent departments and national nuclear safety supervision and control departments, asking for nuclear emergency support or providing nuclear emergency support for off-site emergency organizations.

——Organizing and commanding in-site restoration actions.

3.3 Emergency Action Team

3.3.1 The operating entities shall establish emergency action teams with their responsibilities covering the following aspects according to the facility characteristics:

——Operation and manipulation of in-site systems;

——Evaluation of radiation measurement and consequence;

——Criticality safety evaluation;

——Protective action implementation (shelter, evacuation as well as personnel check, rescue and search, etc.);

——Medical rescue;

——Emergency communication;

——Fire protection and defense;

——Logistical support such as transportation as well as apparatus and material supply.

3.3.2 As for the emergency plan of the operating entities, it shall explicitly specify the emergency responsible person as well as his/her authority and responsibility of each emergency action team, and it shall also explicitly specify the replacement person of emergency responsible person as well as the replacement sequence, and list his/her name, telephone number and home address in relevant implementation procedure table.

3.4 Interface with Off-site Emergency Organization

3.4.1 The interfaces between emergency organizations of operating entities and off-site emergency organizations and their relevant departments (such departments as public security, fire protection, environment protection, emergency management, hygiene, civil defense and disaster relief management) shall be specified in the emergency plan, responsibility assignment shall be made clear, and special department or special personnel shall be arranged to be the liaison man contacting local emergency organizations.

3.4.2 If necessary, the emergency organization of the operating entities shall provide support to the local emergency organizations, including providing the data related to nuclear facility conditions, radiation monitoring and accident consequence prediction, suggest off-site protective action and provide other technical consultation according to the requirements of local emergency organizations.

3.4.3 If necessary, the emergency organization of operating entities may request the local emergency organizations to provide supports in such aspects as fire protection, public security, medical care and radiation monitoring to in-site emergency organization.

3.4.4 Interface to each technical support organization shall be properly carried out, the interrelationship and responsibility assignment shall be made clear, and, if necessary, specify the requirements on the technical support organization and the supports they shall provide in an agreement.



4 Emergency State and Emergency Action Level



4.1 Emergency State Classification

4.1.1 Four emergency classes

The emergency state is classified into four classes according to the severity of radiological consequence of event or accident possibly caused by the nuclear fuel cycle facility and the emergency response action need to be adopted, i.e., emergency standby, plant emergency, site area emergency and off-site emergency:

(1) Emergency standby: appear some specific conditions or events possibly hazarding to the nuclear facility safety, which indicates that the facility safety level is in uncertain or possibly obvious reduction state, and the facility relevant personnel are in alert positions.

(2) Plant emergency: facility safety level actually or potentially reduces largely, but the influence of event is limited to partial area within the plant or the site area and will not threat the off-site area; after announcing plant emergency, the operating entities implement emergency response actions according to the requirements of the emergency plan and the off-site emergency response organization is notified.

(3) Site area emergency: as for the facility, serious failure of the engineering safety facility may occur, the safety level reduces significantly, and the accident influence expands to the whole site area, while the off-site radiation exposure level will not exceed the intervention level except the area near the site area boundary. After announcing site area emergency, the operating entities shall rapidly take action to relieve the accident consequence and protect the personnel in the site area; the off-site emergency organization possibly adopts some emergency response actions (such as carrying out radiation monitoring) and properly carries out preparation for protective action implementation as required.

(4) Off-site emergency: accident influence exceeds the site area boundary, and the radiation exposure level of certain off-site area is greater than the intervention level. After off-site emergency is announced, take immediate actions to relieve the accident influence, implement in-site and off-site emergency protective actions and protect the workers and the public.

4.1.2 Basic characteristics and examples of emergency standby

4.1.2.1 This emergency state class means that the nuclear facility is with specific situation possibly causing potential accident hazard, and the protection level to workers is uncertain or possibly dramatically reduced. But generally, there is no radioactive release with obviously abnormality, and the operating entities have sufficient time to adopt organized preventative procedures and measures so as to prevent event from further deteriorating or escalating and avoid possible accident or relieve the influence.

4.1.2.2 Some equipment failures, internal or external human induced events (such as entity protection of facility is threatened or damaged due to explosive or riot) or severe natural disaster (flood, earthquake, typhoon, tsunami, tornado, etc.) may possibly cause the state of emergency standby.

4.1.2.3 After announcing that it is in emergency standby, the main response actions the emergency organization of the operating entities shall rapidly adopts are assessing and relieving accident and its consequence as well as properly improving the emergency preparedness level (such as: personnel related to the facility entering into preparedness state, stopping some unimportant routine works or activities in the facility temporarily, and properly carrying out various prevention works necessary for coping with event escalation); meanwhile, report the event property and severity to the national nuclear safety supervision and control department according to the established procedures.

4.1.3 Basic characteristics and examples of plant emergency

4.1.3.1 This emergency state class means that certain kind of accident has occurred or is expected to occur, and radiological consequence has been generated or expected to be generated in partial zone of site area. It means that the facility is in the state with very low protection level to workers; however, the evaluation indicates that the radiation hazards are limited to partial zone of site area (e.g. in some plants) and do not expanded to the whole site area, and they will not threat the off-site areas.

4.1.3.2 Accident analyzed in final safety analysis report and with the expected radiological consequence limited in plant or partial zone of the site area may possibly cause plant emergency state; fire or explosion occurred in plant and without radiological consequence out of the workshop belongs to this emergency state class.

4.1.3.3 After announcing that it is in plant emergency state, the emergency organization of operating entities shall firstly take such response actions as improving the facility operation state and effectively control and relieve accident and its consequence. Meanwhile, report the event property and severity to the national nuclear safety supervision and control department according to the established procedures, and inform the relevant off-site technical support organizations. Under the emergency state of this class, some protective actions may also be taken, e.g. evacuation or shelter of personnel near the accident site as well as access control of affected area.

4.1.4 Basic characteristics and examples of site area emergency

4.1.4.1 The emergency state of this class means that certain kind of accident has occurred or is expected to occur, and the radiological consequence has expanded or expected to expand to the whole site area, and it is expected that the dose nearby the site area boundary will reach the intervention level for which emergency protective action is adopted. It means that the facility is in the state with very low protection level to workers; however, the evaluation indicates that the radiation hazards are limited in the site area and the area nearby the site area boundary, and they will not threat the off-site areas.

4.1.4.2 Accident analyzed in final safety analysis report with the expected radiological consequence possibly involving the whole site area may possibly cause site area emergency state.

4.1.4.3 After announcing that it is in site area emergency state, the emergency organization of operating entities shall firstly take such response actions as improving the facility operation state and effectively control and relieve accident and its consequence. Meanwhile, report the event property and severity to the national nuclear safety supervision and control department and local government according to the established procedures, and inform the relevant off-site technical support organization. The necessary protective actions may possibly include immediately evacuating the personnel in the site area except those in control room or emergency command center, controlling incoming/outgoing and carrying out radiological consequence evaluation action (including monitoring the environment out of the site area).

4.1.5 Basic characteristics and examples of off-site emergency

4.1.5.1 The emergency state of this class means that certain kind of accident has occurred or is expected to occur, and the radiological consequence has expanded or expected to expand to the area out of the site area, and it is expected that the dose nearby the site area boundary will exceed the intervention level for which emergency protective action is adopted. Evaluation indicates that radiation hazards have threatened or expect to threaten the off-site area.

4.1.5.2 After announcing that it is in off-site emergency state, the emergency organization of operating entities shall firstly take such response actions as taking effective measures to control and relieve accident and its consequence. Meanwhile, report the event property and severity to the national nuclear safety supervision and control department and local government according to the established procedures, and inform the relevant off-site technical support organizations; suggest the local government to enter into off-site emergency and adopt protective actions for protecting the public. The necessary protective actions may possibly include immediately evacuating the personnel in the site area except those in control room or emergency command center, controlling incoming/outgoing and carrying out radiological consequence evaluation action (including monitoring the environment out of the site area).

4.2 Determination of Emergency State Class of Nuclear Fuel Cycle Facilities

Emergency state class of nuclear fuel cycle facilities may include two classes (emergency standby and plant emergency), three classes (emergency standby, plant emergency and site area emergency) and even four classes (emergency standby, plant emergency, site area emergency and off-site emergency), because such conditions as type and characteristic of nuclear fuel cycle facilities are different. Therefore, the emergency state class possibly presenting of nuclear fuel cycle facilities must be determined through analysis and evaluation on nuclear accident possibly caused by this nuclear facility and its radiological consequence. It must be ensured that the established emergency state classification system can cover all the emergence states that the facility possibly presents.

As for the majority of Chinese nuclear fuel cycle facilities, generally, off-site emergency may not be considered; but as for facility with large potential hazards, off-site emergency may be necessary; refer to Appendix D for details.

As for nuclear fuel cycle facilities possibly releasing large amount of UF6, during determining the emergency state classification system, the chemical toxicity hazard of HF generated through the action of UF6 and air shall be considered.

4.3 Emergency Action Level

In the emergency plan or the emergency plan implementation procedure of the operating entities, various initial conditions possibly causing nuclear fuel cycle facilities presenting emergency states of all classes shall be proposed according to the design characteristics of nuclear fuel cycle facilities and the environmental characteristics of the plant site, and the criteria and standards for judging each emergency state shall be indicated.

The operating entities shall establish emergency action levels corresponding to emergency states at all levels according to the parameters relevant to facility and environment and influencing the security function of the nuclear fuel cycle facilities (e.g., safety of nuclear material system boundary, criticality safety characteristic, radiation level within site area and various natural disaster phenomena) and effluent emission level. And the operating entities shall propose preliminarily formulated emergency action level in initial charge approval letter application and submit revised emergency action level for examination and evaluation in operating license application. See Appendix D for partial examples of emergency action levels for judging emergency state of the nuclear fuel cycle facilities.

1 Introduction
1.1 Purpose
1.2 Scope
2 Emergency Plan Formulation
2.1 Requirements of Emergency Preparedness and Emergency Response in Different Stages
2.2 Emergency Plan Formulation
2.3 Accident Considered in Emergency Plan
2.4 Emergency Plan Implementation Procedure
3 Emergency Organization
3.1 Emergency Organization of Operating Entities
3.2 Emergency Command
3.3 Emergency Action Team
3.4 Interface with Off-site Emergency Organization
4 Emergency State and Emergency Action Level
4.1 Emergency State Classification
4.2 Determination of Emergency State Class of Nuclear Fuel Cycle Facilities
4.3 Emergency Action Level
5 Emergency Planning Zone
5.1 General Requirements for Emergency Planning Zone Establishment
5.2 Determination of Emergency Planning Zone
6 Emergency Facilities and Emergency Equipment
6.1 Overview
6.2 Emergency Control Center
6.3 Control Room
6.4 Communication System
6.5 Monitoring and Evaluating Facilities and Equipment
6.6 Protective Equipment and Apparatus
6.7 First-Aid and Medical Facilities
6.8 Other Emergency Equipment and Goods and Materials
6.9 Emergency Evacuation Routes and Emergency Assembly Points
7 Emergency Response and Protective Measures
7.1 General
7.2 Intervention Principle and Intervention Level
7.3 Emergency Response Actions
7.4 Emergency Response Actions in Emergency States of All Classes
7.5 Evaluation Activity
7.6 Remedial Action
7.7 Protective Action
7.8 Emergency Exposure Control
7.9 Medical Rescue
8 Emergency Termination and Restoration Action
8.1 Termination of Emergency State
8.2 Restoration Actions
9 Maintenance of Emergency Response Capability
9.1 Training
9.2 Exercise
9.3 Maintenance of Emergency Facilities and Equipment
9.4 Deliberation and Modification of Emergency Plan
10 Record and Report
10.1 Record
10.2 Emergency Announcement and Report
10.3 Final Evaluation Report of Accident
Terminologies
Appendix A Brief Introduction of the Standard Format and Content for In-site Emergency Plan of Nuclear Fuel Cycle Facilities
A.1 General Provisions
A.2 Overview of the Facilities and Their Environment
A.3 Emergency State Classification and Emergency Action Level
A.4 Emergency Organization
A.5 Emergency Planning Zone
A.6 Emergency Facilities and Equipment
A.7 Emergency Response and Protective Measures
A.8 Emergency Termination and Restoration Action
A.9 Maintenance of Emergency Capability
A.10 Record and Report
A.11 Appendix
Appendix B Brief Introduction of Execution Procedure for In-site Emergency Plan of Nuclear Fuel Cycle Facilities
B.1 Emergency Starting Procedure
B.2 Procedure for Emergency Action
B.3 Auxiliary Procedure
Appendix C Reference Accidents for Emergency Plan of Nuclear Fuel Cycle Facilities
Appendix D Examples of Nuclear Fuel Cycle Facilities Emergency Action Level

本导则自2010年8月20日起实施
本导则由国家核安全局负责解释
本导则是指导性文件。在实际工作中可以采用不同于本导则的方法和方案，但必须证明所采用的方法和方案至少具有与本导则相同的安全水平。
本导则的附录为参考性文件。
1引言
1.1目的
依据《中华人民共和国民用核设施安全监督管理条例》和《核电厂核事故应急管理条例》以及其他核安全法规文件制定本导则，目的是为民用核燃料循环设施(以下简称核燃料循环设施)营运单位制定应急计划、进行应急准备及事故时开展应急响应行动提供指导。
本导则是指导性文件，营运单位在制定应急计划及开展应急响应行动时，可以不采用本导则推荐的方案和方法，但必须向国家核安全监管部门证明其所采用的方案和方法具有不低于本导则的安全水平。
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(包括铀矿冶、转化、同位素分离、元件制造、燃料后处理设施，以及放射性废物处理处置设施)营运单位的应急计划、应急准备和应急响应，以及国家核安全监管部门对营运单位应急计划的审评。
本导则对核燃料循环设施营运单位应急计划的制定提出了基本要求；对营运单位应急计划的内容与编写格式以及应急准备与应急响应能力的保持提出了比较详细的指导性建议；此外，还对应急计划实施程序的编制提供了指导原则。
对于不同类型的核燃料循环设施，由于它们加工、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颇大，它们的工艺技术、工程安全设施和运行方式等亦各有特点，从而使它们之中潜在的核事故的性质及其辐射后果可能存在相当大的差别。因此，对它们的应急计划、应急准备和应急响应的要求也有所不同。本导则将不对上述这些差别进行专门讨论。营运单位在使用本导则时，必须结合本核燃料循环设施的特点，开展威胁评估分析，以各种可能发生的核与辐射事故后果的评价为基础，参照本导则，制定应急计划和应急响应方案。
2应急计划的制定
2.1不同阶段应急准备和应急响应的要求
2.1.1厂址选择阶段
在评价核燃料循环设施厂址适宜性时，应根据厂址自然与社会特征，论证核燃料循环设施厂址区域在整个预计寿期内执行应急计划的能力和实施应急计划的可行性。
2.1.2设计建造阶段
在设计建造阶段，营运单位及有关单位应对核燃料循环设施事故状态(包括严重事故)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，并编制场内应急计划和执行程序，开展相应的应急准备工作(包括完成应急设施的建设)，编写应急演习计划。
在初步安全分析报告(PSAR)有关运行管理的章节中，应提出应急计划的初步方案，其内容包括：应急计划的目的，依据的法规和适用范围，营运单位所设置的应急组织及其职责的框架，应急计划区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；说明应急资源及接口的安排。
若新建核燃料循环设施厂址内已有正在运行的其他核设施，则新建的核燃料循环设施营运单位及有关单位应针对正在运行的核设施潜在事故，编制相应的应急准备程序并进行适宜的应急准备。
2.1.3首次装料前阶段
营运单位的应急计划应在经主管部门审查后作为独立文件，于首次投料试车前与最终安全分析报告一并报国家核安全监管部门审批，并按本导则的规定，进行投料前的应急演习。在运行开始前核燃料循环设施营运单位应作好全部应急准备。
2.1.4运行阶段
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为维护，处于随时可用状态；应定期进行核应急演习和对应急计划进行复审和修订。
在核燃料循环设施进入应急状态时，应有效实施应急响应，及时向国家核安全监管部门报告事故情况并与场外应急机构协调配合，以保证工作人员、公众和环境的安全。
2.1.5退役阶段
在核燃料循环设施退役报告中应有应急计划的内容，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，规定营运单位负责控制这些危害的组织和应急设施。在退役期间一旦发生事故，应有效实施应急响应，以保证工作人员、公众和环境的安全。
2.2应急计划的制定
核燃料循环设施营运单位必须根据本核设施特点和所在厂址周围的环境条件，制定营运单位的应急计划。营运单位的应急计划的主要内容包括：
(1)核燃料循环设施的一般特性(建造目的；设施类型；许可进行的核活动的运行计划；主要设施和功能等)；
(2)厂址的一般情况(地理位置和场区平面布置；厂址周围人口分布；厂址的气象条件、交通条件等)；
(3)应急组织；
(4)应急状态及应急行动水平；
(5)应急计划区；
(6)应急响应设施、设备和器材；
(7)应急响应和防护措施；
(8)应急终止和恢复行动；
(9)应急响应能力的保持；
(10)记录和报告。
本导则附录A对核燃料循环设施营运单位应急计划的格式和内容提出了要求与建议，营运单位可根据这些建议编写应急计划。考虑到核燃料循环设施的类型、特点及周围环境条件的差异很大，营运单位在制定应急计划时可对本导则规定的内容、格式做适当变动，但应保证，应急计划已覆盖了本导则规定的主要内容，且变动后的内容、格式已经国家核安全监管部门认可。
2.3应急计划考虑的事故
核燃料循环设施营运单位应急计划主要针对那些导致或可能导致放射性物质释放失控，从而危及工作人员或公众健康或环境安全或财产损失的潜在核事故。所考虑的事故范围不仅要包括预期的运行工况和事故工况，而且应考虑那些发生概率更低，但后果更严重的事故，包括环境后果比设计基准事故更严重的严重事故。营运单位应开展全面的安全分析，确定适合本设施的用于应急计划的假想事故谱(特别是严重事故)及相应的源项大小。在确定用于应急计划的事故范围时，可部分基于设施的安全分析报告，并补充做进一步的分析。补充分析中可假设部分设计和运行性能失效，尽管这种失效是不大可能的。附录C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计划时参考。
2.4应急计划执行程序
营运单位应参照本导则附录B提供的指导原则编写各种必要的应急计划执行程序，包括实施应急响应行动的执行程序和为做好应急准备的应急准备支持程序。这些程序应为应急工作人员执行应急计划提供全面、具体的方法和步骤，保证应急准备规范、有序地进行和应急计划协调有效地实施。
不要求将执行程序纳入应急计划文本，一般也不要求将它们提供国家核安全监管部门审评。但国家核安全监管部门在审评应急计划或进行核安全检查时，可能会对这些程序文本进行检查。
3应急组织
3.1营运单位的应急组织
3.1.1营运单位应本着“积极兼容”的原则，在设施常规运行组织的基础上，成立场内应急组织。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计划，做好核应急准备；
(3)确定核应急状态等级，统一指挥本单位的核应急响应行动；
(4)发生事故时立即采取措施，缓解事故后果；
(5)保护场区内的工作人员的安全；
(6)进行辐射监测；
(7)及时向国家和省(自治区、直辖市)核应急组织、主管部门和国家核安全监管部门及规定的部门报告事故情况，并保持在事故过程中的紧密联系；
(8)当核设施可能存在场外应急状态时，提出进入场外应急状态和采取场外应急防护措施的建议；
(9)根据需要，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。
3.1.2营运单位的应急组织包括应急指挥部和各应急行动小组。营运单位应在其应急计划中明确参加应急准备、应急响应和应急恢复等活动的各应急小组的人员组成及任务与职责。
3.1.3营运单位的应急组织应具备在各级应急状态下昼夜24小时连续工作的能力。
3.2应急指挥部
3.2.1应急指挥部是场内应急准备和应急响应的领导和指挥机构，并负责与场外应急组织、上级主管部门及国家核安全监管部门的联系。应急指挥部由营运单位的主要行政与技术负责人及各相关部门(运行、维修、安防、保卫、后勤等)负责人组成。设应急总指挥一人(由营运单位的法人代表或其指定的人员担任)，副总指挥若干人。
3.2.2营运单位的应急计划应明确规定应急指挥的最高权限和具体职责，包括：
(1)组织制定和修改应急计划；
(2)组织落实和检查营运单位的应急准备工作；
(3)宣布和终止除场外应急外的其他应急状态；
(4)指挥实施场内应急响应行动，包括
——采取控制、缓解事故的行动；
——采取保护场内工作人员的应急防护行动；
——对场外是否需要采取保护公众的防护行动提出建议；
——向场外各级应急组织、上级主管部门和国家核安全监管部门报告或通报核应急信息，请求核应急支援或向场外应急组织提供核应急支援；
——组织指挥场内恢复行动。
3.3应急行动小组
3.3.1营运单位应根据本设施特点建立其职责可以涵盖下述各方面的应急行动小组：
——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、营救与寻找等)；
——医学救护；
——应急通讯；
——消防与保卫；
——交通运输与器材、物资供应等后勤保障。
3.3.2营运单位的应急计划应明确规定各应急行动小组的应急负责人及其权限和责任；还应明确应急负责人的替代人员及替代顺序，并在相关的执行程序中列表给出他们的名字、电话号码和家庭住址。
3.4与场外应急组织的接口
3.4.1应在应急计划中明确营运单位应急组织与场外应急组织及其有关部门(如公安、消防、环保、应急管理、卫生、民防和救灾管理等部门)的接口，明确职责分工，并安排专门部门或专人担任与地方应急组织联系的联络员。
3.4.2必要时营运单位应急组织应当向地方应急组织提供支援，包括提供有关核设施状况、辐射监测和事故后果预测方面的资料；提出场外防护行动的建议；根据地方应急组织的要求提供其他的技术咨询。
3.4.3必要时营运单位应急组织可以请求地方应急组织向场内应急组织提供有关消防、公安、医疗、辐射监测等方面的支援。
3.4.4应做好与各技术支持单位的接口，明确相互关系和职责分工，必要时，以协议的形式明确对技术支持单位的要求及它们应提供支持的内容。
4应急状态及应急行动水平
4.1应急状态分级
4.1.1四个应急等级
核燃料循环设施按其可能出现的事件、事故的辐射后果的严重程度和需要采取的应急响应行动，将应急状态划分为四级，依次为应急待命、厂房应急、场区应急和场外应急：
(1)应急待命 出现可能危及核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，设施有关工作人员处于戒备状态。
(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。宣布厂房应急后，营运单位按应急计划要求实施应急响应行动，场外应急响应组织得到通知。
(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，但除了场区边界附近，场外放射性照射水平不会超过干预水平。宣布场区应急后，营运单位应迅速采取行动缓解事故后果，保护场区人员；场外应急组织可能采取某些应急响应行动(如开展辐射监测)，并视情况做好实施防护行动的准备。
(4)场外应急事故后果超越场区边界，场外某个区域的放射性照射水平大于干预水平。宣布场外应急后，应立即采取行动缓解事故后果，实施场内、场外应急防护行动，保护工作人员和公众。
4.1.2应急待命基本特征及实例
4.1.2.1该级应急状态意味着核设施已出现可能引发潜在事故危险的特定事态，对工作人员的防护水平不确定或可能明显下降，但一般而言，尚无明显异常的放射性释放发生，营运单位有足够的时间采取有组织的预防性步骤和措施，防止事件进一步恶化或升级，避免可能发生的事故或减轻其后果。
4.1.2.2某些设备故障、内部或外部人为事件(如设施的实体保护因爆炸物或骚乱而受到威胁或破坏)或严重的自然灾害(洪水、地震、台风、海啸、龙卷风等)均可能导致应急待命状态。
4.1.2.3宣布处于应急待命后，营运单位应急组织应迅速采取的主要响应行动是评估和缓解事故及其后果和适当提高应急准备水平(如：设施有关人员进入准备状态、尽可能停止设施内暂不重要的某些常规工作或活动、做好应对事件升级所需要的各种预防工作)；同时按规定程序将事态的性质和严重程度报告国家核安全监管部门。
4.1.3厂房应急基本特征及实例
4.1.3.1该级应急状态意味着已发生或预计要发生某种事故，而且在场区的局部区域已产生或预计产生辐射后果，说明设施处于对工作人员防护水平严重下降的状态，但评价表明，辐射危害仅限于场区的局部区域(如某些厂房内)，并未扩大到整个场区，更不会对场外构成威胁。
4.1.3.2在最终安全分析报告中分析的、预期辐射后果仅限于厂房内或场区局部区域的事故可能导致厂房应急状态，厂房内发生的不具有厂房外辐射后果的火灾或爆炸属于这一级应急状态。
4.1.3.3宣布处于厂房应急状态后，营运单位应急组织应当首先采取的响应行动是改善设施的运行状态，有效控制与缓解事故及其后果；同时按规定程序将事态的性质和严重程度报告国家核安全监管部门，并通报相关的场外技术支持单位；在这级应急状态下，可能还需要采取某些防护行动，例如事故现场附近人员的撤离或隐蔽，以及受影响区的出入控制。
4.1.4场区应急基本特征及实例
4.1.4.1该级应急状态意味着已发生或预计要发生某种事故，而且事故的辐射后果已经或预计会扩大到整个场区，场区边界附近的剂量预计会达到采取紧急防护行动的干预水平，说明设施处于对工作人员防护水平严重下降的状态，但评价表明，辐射危害仅限于场区内及场区边界附近，不会对场外构成威胁。
4.1.4.2在最终安全分析报告中分析的、预期辐射后果可能涉及整个场区范围的事故可能导致场区应急状态。
4.1.4.3宣布处于场区应急状态后，营运单位应急组织应当首先采取的响应行动是改善设施的运行状态，有效控制与缓解事故及其后果；同时按规定程序将事态的性质和严重程度报告国家核安全监管部门和地方政府，并通报相关的场外技术支持单位；需要采取的防护行动可能包括立即撤离除控制室或应急指挥中心以外的场区人员，实施进出入控制及开展辐射后果评价行动，包括进行场区外环境的监测。
4.1.5场外应急基本特征及实例
4.1.5.1该级应急状态意味着已发生或预计要发生某种事故，而且事故的辐射后果已经或预计会扩大到场外，场区边界附近的剂量预计会超过采取紧急防护行动的干预水平。评价表明，辐射危害已经或预期会对场外地区构成威胁。
4.1.5.2宣布处于场外应急状态后，营运单位应急组织应当首先采取的响应行动是采取有效措施控制与缓解事故及其后果；同时按规定程序将事态的性质和严重程度报告国家核安全监管部门和地方政府，并通报相关的场外技术支持单位；向地方政府提出进入场外应急及采取保护公众的防护行动的建议。需要采取的防护行动可能包括立即撤离除控制室或应急指挥中心以外的场区人员，实施进出入控制及开展辐射后果评价行动，包括进行场区外环境的监测。
4.2核燃料循环设施应急状态级别的确定
核燃料循环设施的应急状态可能包含两级(应急待命、厂房应急)，也可能包含三级(应急待命、厂房应急和场区应急)，甚至包含四级(应急待命、厂房应急、场区应急和场外应急)，因核燃料循环设施的类型、特征等条件而异。因此，核燃料循环设施可能出现的应急状态级别，必须通过对该核设施可能发生的核事故及其辐射后果的分析评价确定。必须保证所建立的应急状态分级系统能覆盖其设施中可能出现的所有紧急状态。
对我国大多数核燃料循环设施，一般可不考虑场外应急，但潜在危险较大的设施。有可能需要实施场外应急，具体可参照附录D。
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系统时需考虑UF6与空气作用产生的HF等的化学毒性的危害。
4.3应急行动水平
营运单位的应急计划或应急计划执行程序中应根据核燃料循环设施的设计特征和厂址的环境特征提出可能导致核燃料循环设施出现各级应急状态的各种初始条件，说明判定每种应急状态的判据和准则。
营运单位应根据影响核燃料循环设施安全功能的设施和环境相关参数(例如，核材料系统边界的安全性、临界安全特征、场区辐射水平及各种自然灾害现象等)和流出物排放水平建立对应各级应急状态的应急行动水平，并在申请首次装料批准书时，提出初步制定的应急行动水平；在申请运行许可证时，提交经修订的应急行动水平供审评。判定核燃料循环设施应急状态的应急行动水平的部分实例见附录D。
5应急计划区
5.1对建立应急计划区的一般要求
5.1.1营运单位应基于可能发生的事故及其辐射后果的分析，在其应急计划中明确需要建立的应急计划区类型以及应急计划区的范围大小。
5.1.2应急计划区划分为烟羽应急计划区和食入应急计划区。前者针对放射性烟羽产生的直接外照射、吸入放射性烟羽中放射性核素产生的内照射和沉积在地面的放射性核素产生的外照射；后者则针对摄入被事故释放的放射性核素污染的食物和水而产生的内照射。
5.1.3考虑到核燃料循环设施的类型、威胁等级、安全特征等差别颇大，从而使它们之中潜在的核事故的性质及其辐射后果可能存在相当大的差别。因此，对应急计划区类型和大小将因核燃料循环设施类型、规模、设计特征等情况的不同而有不同的要求。一般说，多数核燃料循环设施可能只需要建立一个应急计划区，且应急计划区的范围可能仅限于场区内。少量潜在危险较大且有可能需要实施场外应急的核燃料循环设施，有可能需要在其周围环境建立烟羽应急计划区和食入应急计划区。
5.1.4对于可能发生较大量UF6释放的核燃料循环设施，在确定应急计划区的范围时需考虑UF6与空气作用产生的HF等的化学毒性的危害。
5.2应急计划区的确定
5.2.1营运单位应在其应急计划中提供确定应急计划区所考虑的事故及其源项、划定应急计划区的方法、安全准则。
5.2.2确定应急计划区大小的准则、方法，可参照国家标准GB/T 17680.1《核电厂应急计划与应急准备准则 第1部分：应急计划区的划分》。
5.2.3潜在危险较大且有可能需要实施场外应急的核燃料循环设施的营运单位，应在其安全分析报告和应急计划中提出需建立的应急计划区类型及大小的申请，并论证其合理性。
5.2.4确定核燃料循环设施应急计划区时，所考虑的事故及其源项应经国家核安全监管部门认可。
5.2.5确定应急计划区(特别是烟羽应急计划区)的实际边界时，除了遵循本节5.2.2和5.2.3要求外，还应考虑核燃料循环设施周围的具体环境特征(如地形、行政区划边界、人口分布、交通和通信)、社会经济状况和公众心理等因素，使划定的应急计划区实际边界(不一定是圆形)符合当地的实际情况，便于进行应急准备和应急响应。
6应急设施和应急设备
6.1概述
核燃料循环设施营运单位应根据日常运行和应急相兼容的原则，建立相应的应急设施，并在应急计划中对主要的应急设施(应急控制中心、控制室、通信系统、监测和评价设施、防护设施与设备、急救和医疗设施、其他必要的设备和物资等)做出必要的说明。
6.2应急控制中心
6.2.1营运单位应在其应急计划中明确应急控制中心的位置、功能和设计要求。
6.2.2营运单位应在场区适当的地点建立应急控制中心。在应急状态下，应急控制中心是营运单位实施应急响应的指挥场所，还可以是某些应急行动小组的集合与工作场所。
6.2.3应急控制中心应满足的主要设计要求有：
(1)在任何应急状态下都具有可居留性，采取防非法入侵的措施，保证应急指挥人员和应急工作人员在应急状态下可以在此中心安全地实施应急指挥与响应行动。因此，该中心应具有一定的屏蔽、密封与通风净化功能——视可能的事故后果而定；
(2)其位置应与可能的事故地点及其他应急活动场所保持适当的距离，以保证应急指挥中心内的指挥、响应人员能够安全和不受干扰地工作；
(3)应配置必要的接收、显示设备，以获得有关设施工况的重要参数和厂址环境辐射状况的相关信息；还需要配备必要的个人防护用品、个人剂量监测仪表与环境辐射监测仪表等；此外，还应配置应急计划及其他相关文件(各种应急行动的实施程序；最终安全分析报告和环境影响报告；场区平面布置图、厂址地理位置图和场区周围地形图；应急人员花名册及其电话号码和家庭住址等)。
6.2.4必要时建立备用应急控制中心。
6.3控制室
6.3.1营运单位应在其应急计划中明确控制室的位置、功能和设计要求。
6.3.2控制室的主要功能是对核燃料循环设施的运行实施控制，并用于探明应急状态及对其进行分级，执行缓解行动以及启动响应组织。
6.3.3控制室应满足应急状态下的可居留性要求，适当采取防非法入侵的措施，并配置有必要个人防护用品、辐射监测仪表、应急计划及其他相关文件(例如各种应急行动的实施程序)等。
6.4通信系统
6.4.1营运单位应配置必要的通信系统，满足场内应急通信(应急控制中心、生产调度室等各应急设施间的通信)、应急通知及场外应急通信(与国家和地方应急组织、上级主管部门、国家核安全监管部门以及技术支持单位等的通信)的要求。
6.4.2应急通信系统应具有一定的裕度，满足可靠性和多重性要求。
6.5监测、评价设施与设备
6.5.1营运单位应在其应急计划中列出可用于应急监测，包括场所监测、个人监测、流出物监测、环境监测以及气象观测的设施与设备，描述它们的功能(或性能)、用途、数量，以及设施位置和仪表设备贮存或安装的地点，并说明它们可以满足监测与评价的要求。
6.5.2营运单位应建立监测、诊断事故状态的手段和相应的事故(包括放射性释放与非放有害化学物质释放)后果评价系统。后果评价系统应能针对本燃料循环设施及其可能发生的事故特点，应用较快速简洁的模式开展事故后果评价(大气或水弥散估计和剂量估算，以及必要时进行核临界计算)。
6.6防护装备与器材
应按应急计划安排，准备好现场应急工作人员的辐射防护装备与器材，例如，呼吸防护用的口罩、配有滤毒罐的防毒面具以及防护衣、帽、手套、鞋等。
6.7急救和医疗设施
营运单位应在应急计划中明确营运单位所配备的现场人员去污、急救和医疗设施、设备与器材，可以提供支援的地方医院的名称、地点、功能和提供的服务项目，可以接收放射损伤救治的专科医院的名称、地点、功能和提供的服务项目。
6.8其他应急设备和物资
需要准备的其他应急设备和物资包括：
消防器材、交通控制与人员撤离路线使用的标识物、事故抢救用的物资等。
6.9应急撤离路线和应急集合点
营运单位应针对可能实施的人员撤离，设置具有醒目而持久标识的安全撤离路线和应急集合点，集合点应能抵御恶劣的自然条件，并配备为安全使用这些路线所必需的应急照明、通风和其他辅助设施。
7应急响应和防护措施
7.1概述
核燃料循环设施营运单位应在其应急计划中明确所遵循的干预原则、干预水平，及出现每级应急状态时应采取的响应行动、防护措施以及执行的应急行动的程序。
7.2干预原则和干预水平
7.2.1干预原则
在应急干预的决策中，应遵循下列干预原则：
(1)正当性原则——在干预情况下，只要采取防护行动或补救行动是正当的，则应采取这类行动；
所谓正当，指拟议中的干预应利大于弊，即由于降低辐射剂量而减少的危害，应当足以说明干预本身带来的危害与代价(包括社会代价在内)是值得的。
(2)最优化原则——任何这类防护行动或补救行动的形式、规模和持续时间均应是最优化的，使在通常的社会、经济情况下，从总体上考虑，能获得最大的净利益；
(3)应当尽可能防止公众成员因辐射照射而产生严重确定性健康效应。如果任何个人所受的预期剂量(而不是可防止的剂量)或剂量率接近或预计会接近可能导致严重损伤的阈值(如国标GB18871—2002附录E1所列)，则采取防护行动几乎总是正当的。
7.2.2干预水平
用于核燃料循环设施核应急状态下公众防护行动的干预水平和控制食品的行动水平，应采用国标GB18871—2002附录E2中规定的应急照射情况下的通用干预水平与通用行动水平值。
7.3应急响应行动
营运单位在应急状态下可能采取的应急响应行动有：
(1)应急启动与应急通知或报告；
(2)评价活动；
(3)补救行动；
(4)防护行动；
(5)应急照射的控制；
(6)医学救护。
7.4各级应急状态下的应急响应行动
7.4.1应急待命
(1)启动应急指挥中心；
(2)启动部分场内应急组织，通知必要的应急人员进入岗位，其他应急人员进入待命状态；
(3)实施部分应急响应行动，如运行人员应采取措施使核设施恢复和保持安全状态，并做好进一步行动准备；以及加强场区辐射监测等；
(4)按规定向国家核安全监管部门等有关机构报告。
7.4.2厂房应急
(1)启动场内各应急组织，通知全体应急人员进入应急岗位；
(2)按应急计划的要求实施相应的应急响应行动，包括评价行动、补救行动和局部区域的防护行动、应急照射的控制和医学救护行动；
(3)按规定向国家核安全监管部门等有关机构报告；
(4)向地方应急组织或地方有关应急机构报告核事故情况、应急响应行动和必要的数据资料；必要时向应急技术支持单位通报情况。
7.4.3场区应急
(1)应急工作人员全部到位，各应急行动组全面实施应急响应行动，包括评价行动、补救行动和防护行动，以及应急照射的控制和医学救护行动；
(2)适时实施场区内非应急工作人员的撤离；
(3)按规定，向国家核安全监管部门等有关机构报告；
(4)保持与地方应急组织或地方有关应急机构或地方有关应急机构的信息交换与协调，必要时请求地方应急组织或地方有关应急机构以及应急技术支持单位的支援。
7.4.4场外应急
(1)实施7.4.3节的所有响应行动；
(2)加强场区外辐射监测和辐射后果评价工作；
(3)向场外应急组织提出进入场外应急和实施公众防护行动的建议；
(4)明确应急总指挥应负责将实行应急的决定立即通知有关组织和人员，并提出进行通知时的要求，如提供初始信息的内容等。
7.5评价活动
7.5.1应急评价(包括应急监测)是应急响应行动决策的基础，应急评价结果则是实施防护行动的依据。在每一级应急状态下，营运单位都必须开展评价活动，判断事故性质、发展趋势、可能的后果及严重程度，估算场内外人员可能受到的辐射剂量(包括预期剂量、可防止剂量和剩余剂量)，为确定是否采取校正行动和防护行动，以及采取什么校正行动和防护行动提供决策基础。
7.5.2需要采取的评价活动主要包括应急辐射监测和事故后果评价，主要工作内容有：
(1)工艺参数的监测；
(2)流出物监测和场区与工作场所辐射水平监测；
(3)环境辐射监测及必要时空气中HF浓度的监测；
(4)气象参数的获取；
(5)事故后果评价与发展趋势的预测。
7.5.3宜开发、使用与事故工况评价相结合的快速、简洁的事故后果评价模式(某些核燃料循环设施可能还需要建立临界安全评价模式)。通过评价获得场内外预期剂量、可防止剂量的分布，在与相应的干预水平比较的基础上，结合最优化分析，确定需要采取的应急防护行动。
7.5.4应制定具有可操作性的应急辐射监测方案和具体的实施程序或操作步骤。
7.6补救行动
7.6.1补救行动是应急状态下营运单位必须立即开展的最主要的响应行动之一，目的是控制和缓解事故，使核设施尽快和尽可能恢复到受控的安全状态，并减轻对工作人员和公众的辐射后果。
7.6.2可能采取的补救行动有工艺系统或整个设施的紧急停闭、灭火、抢修，或其他纠正与缓解事故、减轻事故后果的行动。
7.7防护行动
7.7.1营运单位应在应急计划中描述在各级应急状态下场内可能需要采取的应急防护行动和具体的实施方案。对于有可能出现场外应急状态的核燃料循环设施还应在应急计划中描述提出进入场外应急和实施场外应急防护行动建议的安排。
7.7.2场内可能采取的防护行动包括：
(1)非应急工作人员的部分或全部撤离。应在应急计划中对撤离条件、撤离路线和撤离方案做概要描述；
(2)人员集合、清点。应在应急计划中概要描述集合、清点方案，规定集合地点；
(3)受伤、受污染、受照射人员的现场医学救治和向地方或专科医院的转送；
(4)防止污染扩散和出入通道控制。应在应急计划中概要描述人员、车辆去污、污染区隔离及出入通道控制的安排；
(5)其他防护措施，如找寻失踪人员、使用个人防护用品等。
7.8应急照射的控制
必须控制应急工作人员受到的辐射照射。营运单位应在应急计划中描述控制应急工作人员辐射照射的基本原则，规定各类应急工作人员剂量控制水平及受照审批程序，并概要描述应急状态下需要采取的控制应急工作人员照射的措施。
7.9医学救护
7.9.1现场医学救护的首要任务是抢救生命和外伤救治，辐射损伤救治则是核与辐射应急响应中特有的医学救治问题。辐射损伤的现场医学救治的主要内容包括：受污染、受照射状况的评估与受照剂量的估算、体表或伤口去污、受伤受污染人员分类、处理及病人转送等。
7.9.2营运单位应建立现场医学救护和场外医学支持程序，并在应急计划中以附件形式给出与场外医学救护支持单位的协议及联系方式。
8应急终止和恢复行动
8.1应急状态的终止
8.1.1当核事故(或事件)的威胁和危害得到控制或消除，核设施已处于可控的安全状态，放射性物质的释放已停止或低于可接受的水平时，可以考虑终止应急状态。
8.1.2营运单位应在应急计划中规定终止应急状态的条件和判断满足应急状态终止条件的准则，以及批准与发布终止各级应急状态的程序。
8.1.3应急待命、厂房应急和场区应急状态终止的决定由营运单位应急组织决定，由应急指挥宣布，并报告国家核安全监管部门和地方政府；场外应急状态的终止由营运单位提出建议，由核设施所在省应急组织决定，报国家核应急组织批准后发布。
8.2恢复行动
8.2.1应急状态终止后营运单位应采取相应的恢复行动，使核设施及场区环境尽快恢复到正常的状态。
8.2.2营运单位的应急计划应提出应急状态终止后需要采取的恢复措施。应急状态终止后可能采取的主要恢复措施有：
(1)解除区域控制；
(2)评估设施、设备的损伤或破坏情况，对设施、设备做必要的检修；
(3)处理、处置放射性废物；
(4)继续开展辐射监测和放射性去污；
(5)必要时，评估核设施与重要核安全物项的安全功能，做好重新启动运行的相关准备，重新启动计划报国家核安全监管部门审评；
(6)开展事故总结与核应急响应工作总结。
9应急响应能力的保持
9.1培训
9.1.1为保持各类应急工作人员的应急响应能力，营运单位应制定各类应急工作人员的培训和定期再培训计划或大纲，明确应该接受培训的人员、培训的主要内容、培训和定期再培训的频度和学时要求、培训方法(授课、实际操作、考试等)，以及培训效果的评价等。
9.1.2需要接受培训的应急工作人员有：
(1)营运单位应急组织的负责人员；
(2)事故评价人员，包括控制室值班人员；
(3)辐射监测人员；
(4)消防与保卫人员；
(5)营救与医学救护人员；
(6)场外支援人员。
场区非应急工作人员，包括外来人员也应接受必要的培训。
9.1.3培训的主要内容包括：
(1)应急计划的基本内容和完成应急任务的基本知识和技能；
(2)应急执行程序；
(3)人员防护技能，包括个人防护衣具的使用；
(4)应急状态下应急人员的职责。
9.1.4在核燃料循环设施运行寿期内，营运单位对所有应急工作人员(包括应急指挥人员)，每年至少进行一次与他们预计要完成的应急任务相适应的再培训与考核。
9.2演习
9.2.1营运单位应通过经常和适时地组织应急演习检验和提高核应急组织的应急响应能力、核应急工作人员熟悉和胜任核应急工作的程度，以及核应急计划和应急执行程序的适宜性和有效性。
9.2.2应急演习分为三类，即场内外应急组织同时参加的联合演习、场内不同方面应急工作人员共同参加的综合演习和仅由场内某一方面的应急工作人员进行的单项演习。
9.2.3综合演习每2年进行1次，单项演习每年进行1次；涉及场外应急时，联合演习每5年进行1次。在核设施首次装料启动前，营运单位应进行一次全体应急人员共同参加的全面的综合演习(对可能出现场外应急状态的核燃料循环设施，则应开展有场内场外核应急组织共同参加的联合演习)。
9.2.4在每次演习之前应设计演习情景，编制演习计划。营运单位应将演习计划和演习情景事先报国家核安全监管部门。演习结束后，应对演习的效果、取得的经验和存在的问题等进行评价，并对应急计划提出修改意见。
9.2.5应不断提高演习的实效性。原则上要求演习情景在演习前对参演人员保密。
9.2.6营运单位对国家核安全监管部门在演习评估报告中提出的营运单位在应急准备中存在的问题，应及时加以纠正。
9.3应急设施、设备的维护
9.3.1营运单位应保证所有应急设施、设备和物资始终处于良好的备用状态，为此，应做好对应急设施、设备和物资的经常性保养、维护、检修和清点。
9.3.2营运单位应定期不定期地对应急设施、设备和物资进行检查，确定它们是否存在，是否可以正常使用或操作，以及是否满足应急响应功能的要求。
9.4应急计划的评议与修改
为使应急计划不断改进和完善，维持其有效性和可实施性，营运单位应根据设施及环境条件的变化，以及培训和演习中揭示的问题，每2年对应急计划及其执行程序进行评议和修订。修订后的应急计划应在原计划有效期满前三个月报国家核安全监管部门，经审评后方可生效。在发生重大核事故或国家相关法津、法规有重大变化时也应进行修订。修订后的应急计划应按规定程序报国家核安全监管部门审评。
10记录和报告
10.1记录
营运单位应把应急准备工作和应急期间的情况详细地进行记录并存档，其主要内容包括：
(1)培训和演习的内容，参加的人员和取得的效果等；
(2)应急设施的检查和维修，应急设备及其配件的清点、测试、标定和维修等情况；
(3)事故始发过程和演变过程；
(4)应急期间的评价活动、采取的补救措施、防护措施和恢复措施以及应急行动的程序等。