标准编号:	GB/T 17680.8-2003
中文名称:	核电厂应急计划与准备准则 场内应急计划与执行程序
英文名称:	Criteria or emergency planning and preparedness for nuclear power plants--On-site emergency planning and implementing procedures
中标分类:	F77    核辐射事故应急与处理
行业分类:	GB    国家标准
ICS分类:	27.120.20 27.120.20    核电站、安全 27.120.20
发布机构:	国家质量技术监督局
发布日期:	2003-03-24
实施日期:	2003-12-1
标准状态:	现行
替代旧标准:	EJ/T 880-1994
翻译语言:	英文
文件格式:	PDF
中文字符数:	10000 字
翻译价格(元):	600.00 元
交付时间:	付款后 1 个工作日

Foreword



GB/T 17680 consists of the following 10 parts under the general title Criteria for emergency planning and preparedness for nuclear power plants.



——GB/T 17680.1 Criteria for emergency planning and preparedness for nuclear power plants - The dividing of emergency planning zone;



——GB/T 17680.2 Criteria for emergency planning and preparedness for nuclear power plants - Off-site emergency functions and organization;



——GB/T 17680.3 Criteria for emergency planning and preparedness for nuclear power plants - Functional and physical characteristics of off-site emergency facilities;



——GB/T 17680.4 Criteria for emergency planning and preparedness for nuclear power plants - The off-site emergency planning and implementing procedures;



——GB/T 17680.5 Criteria for emergency planning and preparedness for nuclear power plants - Maintenance of off-site emergency response capacity;



——GB/T 17680.6 Criteria for emergency planning and preparedness for nuclear power plants - On-site emergency response functions and organizations;



——GB/T 17680.7 Criteria for emergency planning and preparedness for nuclear power plants - Function and physical characteristics for on-site emergency facilities;



——GB/T 17680.8 Criteria or emergency planning and preparedness for nuclear power plants - On-site emergency planning and implementing procedures;



——GB/T 17680.9 Criteria for emergency planning and preparedness for nuclear power plants - Maintenance of on-site emergency response capacity;



——GB/T 17680.10 Criteria for emergency planning and preparedness for nuclear power plants - Criteria for emergency radiological field monitoring, sampling and analysis conducted by nuclear power plant operating organizations.



This is Part 8 of GB/T 17680, which is revised on the basis of EJ/T 880-1994 Emergency planning and procedures of nuclear power plant operating organizations and formulated based on the requirements of current nuclear emergency regulations in China, in combination with the experience and actual situation of emergency work in nuclear power plants in China, and with reference to relevant national standards in the United States.



EJ/T 880-1994 shall be abolished from the implementation date hereof.



The following main changes have been made with respect to the nuclear industry standard EJ/T 880-1994:



——Special requirements and related contents are added for the preparation of emergency plans by operating organization of nuclear power plants at multi-reactor site;



——Some new nuclear emergency concepts or terms are included, such as: generic intervention level, generic action level and operational intervention level;



——The contents pertaining to training, exercise and plan revision, which were presented as separate clauses in the original industry standard, are merged into a single clause titled "maintenance of emergency response capability";



——The implementing procedures are divided into two categories: emergency response procedures and emergency preparedness support procedures.



This part was proposed by the National Nuclear Emergency Office and the National Technical Committee on Nuclear Energy of Standardization Administration of China.



This part is under the jurisdiction of National Technical Committee on Nuclear Energy of Standardization Administration of China.



Drafting organization of this part: Chinese Nuclear Society.



Chief drafters of this part: Chen Zhuzhou and Bai Guang.



Criteria for emergency planning and preparedness for nuclear power plants - On-site emergency planning and implementing procedures



1 Scope



This part of GB/T 17680 specifies the criteria to be followed in preparing the on-site emergency plan for nuclear power plants and corresponding emergency implementing procedures, and puts forward requirements and recommendations on the format and content of the emergency plan and implementing procedures.



This part is applicable to emergency preparedness and response of various land-based fixed nuclear power plants, and may be used as a reference for other nuclear facilities.



2 Terms and definitions



For the purposes of this part of GB/T 17680, the following terms and definitions apply.

2.1

emergency

status in which certain immediate actions beyond normal working procedures are required to avoid nuclear accidents at nuclear power plants or to mitigate the consequences of accidents, sometimes referred to as emergency status; it also generally refers to taking immediate actions beyond normal working procedures

2.2

emergency plan

approved document that comprehensively describes the emergency response functions, organizations, facilities and equipment of the nuclear power plant operating organization, as well as the coordination and mutual support relationships with external emergency organizations; this document must be supplemented by special implementing procedures

2.3

site

area where a nuclear power plant with legal boundaries and under the effective control of the nuclear power plant operating organization is located

 

2.4

off-site

area excluding the site

2.5

on-site

area where the operating organization is responsible for making emergency plans and responding to emergencies

2.6

emergency facility

facility for emergency response purposes, which will be arranged in accordance with relevant regulatory requirements and the principle of active compatibility; it includes places for emergency response purposes, and emergency response systems and equipment therein



Note: On-site emergency response facilities generally include: control room, backup control point, technical support center, operation support center, emergency command center, emergency communication facilities, emergency monitoring and evaluation facilities, medical rescue facilities, and public information center.

2.7

emergency classification

classification of emergency statuses; the emergency statuses of nuclear power plants are divided into the following four classes:



Emergency standby: some specific working conditions or external events that may endanger the safety of the plant occur; the relevant personnel of the plant are on standby, and some emergency organizations outside the plant may be notified



Plant emergency: the radiation consequences are limited to some areas of the plant; the on-site personnel take actions according to the emergency plan of the operating organization, and relevant emergency organizations outside the plant are notified



Site emergency: the radiation consequences are limited to the site; the on-site personnel take actions, and off-site emergency organizations are notified, some of which may also take actions



Off-site emergency: the radiation consequences have exceeded the boundary of the site; the on-site and off-site personnel take actions, and the general emergency plan shall be implemented

 

2.8

corrective actions

measures and actions taken at or near the area of accident leading to emergency for the purpose of terminating or mitigating the consequences brought by emergency status, such as mitigation controls for core damage, emergency overhaul, fire extinguishing, flooding treatment in plant building, typhoon impact resistance and earthquake disaster resistance

2.9

emergency action level

parameters or criteria used as the basis for emergency classification, which are generally predetermined, site-specific and observable thresholds corresponding to a certain emergency status

2.10

emergency planning zone

zone established in advance around a nuclear power plant for the purpose of taking timely and effective protective actions to protect the public in the event of an accident, which is provided with a developed emergency plan and for which emergency preparedness has be made; at present, the emergency planning zones in China are divided into plume emergency planning zone for plume exposure pathway and ingestion emergency planning zone for ingestion exposure pathway

2.11

emergency protective action

protective action taken in emergency status, with an aim to avoid or reduce doses that may be received by staff and the public

2.12

intervention level

dose level expressed in terms of preventable dose in the case of emergency exposures, at which specific protective or remedial action shall be taken

2.13

generic intervention level

internationally recommended intervention level with certain generality

2.14

generic action level

internationally recommended generic intervention level for controlling food under continuous or emergency exposure, expressed as activity concentrations in food, milk, and water

 

2.15

operational intervention level

measurable amount of radioactivity equivalent to an intervention level expressed in avertable dose, expressed as a radionuclide level or a measurable dose rate in an environmental or food sample



3 Emergency plan

3.1 Preparation of on-site emergency plan for nuclear power plant



The nuclear power plant operating organization shall prepare its emergency plan as per the format specified in 3.6 and the contents specified in 3.7 of this part, in which the personnel, organizations, facilities, equipment and other resources that the operating organization may use for emergency purposes, and other emergency preparedness to be carried out shall be highlighted, and the emergency response actions that may be taken under emergency status, as well as the connection, coordination and support with other off-site emergency organizations shall also be described.

3.2 Expression of emergency plan



The on-site emergency plan of nuclear power plant is a working document for performing emergency preparedness and implementing emergency response by operating organizations, which shall be concise, focused, comprehensive, informative and with good operability. Supporting documents and information related to the emergency plan shall be incorporated in the plan or annexes to the plan as much as possible.

3.3 Changes in the format and content of emergency plan



Considering the different characteristics of each nuclear power plant and its surrounding environment, the nuclear power plant operating organization may make appropriate changes to the format and content specified in 3.6 and 3.7 when preparing the emergency plan, but it shall ensure that the emergency plan has covered the main contents specified in this part, and the changed writing format and content have been approved by relevant departments.

3.4 Revision of emergency plan



To ensure the continuous improvement and effectiveness of the emergency plan, it shall be reviewed every 2~3 years, and revised based on the results of the review and the problems identified in training and exercises. The plan shall also be revised in time in case of major accidents or major changes in national laws and regulations. The revised emergency plan shall be submitted for approval following the legal procedures.

 

3.5 On-site emergency plan for nuclear power plants at multi-reactor site



The operating organization of nuclear power plants at multi-reactor site shall fully consider the following issues when preparing an emergency plan:



a) Impact of the accident occurring in the unit (or power plant) on the unit (or power plant) where the accident does not occur;



b) Making full use of and sharing emergency resources for emergency preparedness and response, and avoiding the focused arrangements of emergency organizations and emergency facilities and equipment;



c) It is necessary to not only adhere to the principle of unified command and active coordination, but also require the owner to fulfill nuclear safety responsibilities and obligations for nuclear emergency preparedness. Under this principle, a unified emergency organization and a unified emergency planning zone shall be established for the site area.

Foreword i
1 Scope
2 Terms and definitions
3 Emergency plan
4 Emergency plan implementing procedures

ICS 27.120.20
F 77
GB
中华人民共和国国家标准
GB/T 17680.8—2003



核电厂应急计划与准备准则
场内应急计划与执行程序
Criteria for emergency planning and preparedness for nuclear power plants—
On-site emergency planning and implementing procedures



2003-03-24发布 2003-12-01实施
中华人民共和国
国家质量监督检验检疫总局 发布

前言
GB/T 17680《核电厂应急计划与准备准则》分为以下10个部分：
——GB/T 17680.1 核电厂应急计划与准备准 则应急计划区的划分；
——GB/T 17680.2 核电厂应急计划与准备准则 场外应急职能与组织；
——GB/T 17680.3 核电厂应急计划与准备准则 场外应急设施功能与特性；
——GB/T 17680.4 核电厂应急计划与准备准则 场外应急计划与执行程序；
——GB/T 17680.5 核电厂应急计划与准备准则 场外应急响应能力的保持；
——GB/T 17680.6 核电厂应急计划与准备准则 场内急响应职能与组织机构；
——GB/T 17680.7 核电厂应急计划与准备准则 场内应急设施功能与特性；
——GB/T 17680.8 核电厂应急计划与准备准则 场内应急计划与执行程序；
——GB/T 17680.9 核电厂应急计划与准备准则 场内应急响应能力的保持；
——GB/T 17680.10 核电厂应急计划与准备准则 核电厂营运单位应急野外辐射监测、取样与分析准则。
本部分是GB/T 17680的第8部分，是根据我国现行核应急法规的要求，结合我国核电厂应急工作的经验和实际情况，参考美国的有关国家标准，在核行业标准EJ/T 880—1994《核电厂营运单位的应急计划与程序准则》基础上制定而成的。
本标准自实施之日起EJ/J 880—1994废止。
本部分与核行业标准EJ/T 880—1994相比主要变化如下：
——增加了对多堆厂址的营运单位应急计划编制的特殊要求及相关内容；
——引入了某些新的核应急概念或术语，如：通用干预水平、通用行动水平、操作干预水平等；
——将原行业标准各单列为一章的培训、演习和计划修改三章合并为一章：应急响应能力的维持；
——将执行程序划分为两大类：应急响应程序和应急准备支持程序。
本部分由国家核应急办和全国核能标准化技术委员会提出。
本部分由全国核能标准化技术委员会归口。
核电厂应急计划与准备准则
场内应急计划与执行程序
1 范围
GB/T 17680的本部分规定了编制核电厂场内应急计划及相应的应急执行程序应遵循的准则，对应急计划及执行程序的格式与内容提出了要求和建议。
本部分适用于各种陆地固定式核电厂的应急准备和响应，其他核设施可参照采用。
2 术语和定义
下列术语和定义适用于GB/T 17680的本部分。
2.1
应急 emergency
需要立即采取某些超出正常工作程序的行动，以避免核电厂核事故发生或减轻事故后果的状态，有时称为紧急状态。也是泛指立即采取超出正常工作程序的行动。
2.2
应急计划 emergency plan
一份经过审批的文件，它全面描述了核电厂营运单位的应急响应功能、组织、设施和设备，以及和外部应急组织间的协调和相互支持关系。该文件必须有专门的执行程序加以补充。
2.3
场区 site
具有法定边界，受核电厂营运单位有效控制的核电厂所在区域。
2.4
场外 off-site
场区以外的区域。
2.5
场内 on-site
营运单位负责制定应急计划和进行应急响应的区域内。
2.6
应急设施 emergency facility
用于应急响应目的的设施，它们将根据有关法规要求和积极兼容的原则设置。它包括用于应急响应目的的场所及其中的应急响应系统和设备。
注：场内应急响应设施一般包括：控制室、备用控制点、技术支持中心、运行支持中心、应急指挥中心、应急通讯设施、应急监测与评价设施、医学教护设施，以及公众信息中心等。
2.7
应急状态分级emergency classification
应急状态级别的划分。我国将核电厂应急状态划分为下列四种等级：
应急待命(emergency standby)：出现可能危及工厂安全的某些特定工况或外部事件。工厂有关人员进入待命状态，场外某些应急组织可能得到通知。
厂房应急(plant emergency)：辐射后果仅限于工厂部分区域，按营运单位应急计划，厂内人员行动，场外有关应急组织得到通知。
场区应急(site emergency)：辐射后果限于场区内。场区人员行动，场外应急组织得到通知，某些场外应急组织也可能行动。
场外应急(off site emergency)：辐射后果已超越场区边界。场内场外人员行动，需实施总体应急计划。
2.8
纠正行动 corrective actions
为终止或缓解应急状态的后果，在导致应急的出事点或其附近所采取的措施和行动，例如堆芯损坏缓解控制、紧急检修、灭火、厂房内水淹处理以及抗风灾、地震灾害等等。
2.9
应急行动水平 emergency action level
用作应急状态分级基础的参数或判据，这一般是预先确定的、基于特定厂址和可观测的对应某一应急状态的阈值。
2.10
应急计划区 emergency planning zone
为在事故时能及时、有效地采取保护公众的防护行动，事先在核电厂周围建立的、制定有应急计划并作好应急准备的区域。我国目前将应急计划区分为两类：针对烟羽照射途径的烟羽应急计划区和针对食入照射途径的食入应急计划区。
2.11
应急防护行动 emergency protective action
应急状态下为避免或减少工作人员和公众可能接受的剂量而采取的保护行动。
2.12
干预水平 intervention level
在应急照射情况下，用可防止剂量表示的应采取特定防护行动或补救行动的剂量水平。
2.13
通用干预水平 generic intervention level
国际上推荐的，具有一定通用性的干预水平。
2.14
通用行动水平 generic action level
国际上推荐的，在持续性照射或应急照射情况下，用于控制食品的通用的干预水平，表示为食物、牛奶、水中的活度浓度。
2.15
操作干预水平 operational intervention level
相当于用可防止剂量表示的干预水平的可测量的放射性量，表示为环境或食物样品中放射性核素水平或可测量的剂量率。
3 应急计划
3.1 核电厂场内应急计划的编制
核电厂营运单位应根据本部分3.6规定的格式和3.7规定的内容编制其应急计划。该计划应着重描述营运单位可能用于应急目的的人员、组织和设施、设备等资源保障以及应当进行的其他应急准备工作，也应当描述应急状态下将可能采取的应急响应行动，以及和其他场外应急组织的接口、相互协调与支援。
3.2 应急计划的表述
核电厂场内的应急计划是营运单位进行应急准备和实施应急响应的工作文件，应文字精练，重点突出，内容全面、翔实，有好的可操作性。与应急计划有关的支持性文件、资料等，应尽可能收入到计划或计划的附录之中。
3.3 应急计划格式和内容的变动
考虑到各核电厂及其周围环境的特点不同，核电厂营运单位在编制应急计划时，可对3.6和3.7规定的格式和内容作适当变动，但应保证：应急计划已覆盖了本部分规定的主要内容，且变动后的书写格式和内容已经有关部门认可。
3.4 应急计划的修改
为使应急计划不断改进和完善维持其有效性，每2～3年进行一次评议，并根据评议结果和培训与演习中发现的问题进行修改。在发生重大事故或国家法规有重大变化时也应及时修改。修改后的应急计划按法定程序报批。
3.5 多堆厂址的核电厂场内应急计划
多堆厂址的核电厂营运单位在编制应急计划时，应充分考虑如下事项：
a) 事故机组(或电厂)的事故对非事故机组(或电厂)的影响；
b) 用于应急准备和响应的应急资源的充分利用和共享，避免应急组织、应急设施设备的重点设置；
c) 既要坚持统一指挥，大力协同，又要求业主履行核安全责任和核应急准备义务，在此原则下建立厂址地区统一的应急组织和统一的应急计划区。
3.6 应急计划的格式
应急计划的格式列于表1。
表1 核电厂场内应急计划的格式
序号 内容
1 总则
2 核电厂及其环境概况
3 应急计划区
4 应急状态分级与应急行动水平
5 应急组织与职责
6 与其他应急组织的协调
7 应急设施与设备
8 应急通信报告与通知
9 应急运行控制与系统设备抢修
10 事故后果评价
11 应急防护行动
12 应急照射控制
13 医学救护
14 应急纠正行动
15 应急状态终止与恢复
16 公众信息与沟通
17 记录
18 应急响应能力的维持
19 术语
20 附件
3.7 应急计划的内容
3.7.1 总则
描述编制应急计划的目的，列出所依据的法规、规章标准和文件，说明应急计划的适用范围。
3.7.2 核电厂及其环境概况
描述厂址的地理位置(标出经纬度)，给出厂址地理位置图，标出场区边界、非居住区边界和规划限制区边界，并概要描述厂址周围的主要环境特征，包括地形、地貌、气候与气象、水体分布、工业、交通运输与农牧渔业，以及人口分布等。
给出核电厂的堆型、功率，概述其营运计划与发展规划，并简要描述主要设施的名称、功能与平面布置，专设安全设施的名称及其主要安全特性。附厂区平面图。
对于多堆厂址，简要描述同一厂址内的其他电厂的概况。
3.7.3 应急计划区
给出用于确定应急计划区大小的事故源项，描述核电厂厂址周围建立两个应急计划区(烟羽和食入应急计划区，前者又可划分为内区和外区，内区必须作好采取包括撤离的预防护措施的准备)的原则和方法，给出经批准的应急计划的大小，并在地图上标出两个应急计划区的边界，概述应急计划区内的人口分布，特别应说明特殊人群(例如医院、监狱和中、小学校等)的分布。此外，还应给出场区及其附近营运单位负责的应急责任区(包括场区、职工宿舍社区以及受营运单位委托为核电厂服务的单位的工作区与职工宿舍社区)的区划图。
3.7.4 应急状态分级与应急行动水平
描述四级应急状态的基本特征，并简要说明场内外应急组织应采取的相应响应行动，列表给出用于认识和判断应急状态的初始条件和应急行动水平。
对于多堆厂址的核电厂，还应说明事故电厂处于某一应急状态时非事故电厂可能受到的影响和应处的应急状态。
3.7.5 应急组织与职责
概述核电厂正常运行组织和应急响应组织，提供相应的组织框图，给出应急指挥部的组成及各成员的职责、替代顺序，描述各应急响应小组(其工作范围应覆盖通信、应急运行、堆安全分析、环境监测、事故后果评价、应急维修与工程抢险、治安保卫、后勤保证、消防、医学救护等方面)的组成及职责。
对于多堆厂址的核电厂，其应急指挥部的组成，应保证具有统一协调场区内应急响应行动的能力。
3.7.6 与其他应急组织的协调
详细说明核电厂应急指挥部与场外各应急组织，包括：国家核应急组织、地方核应急组织、核安全监督部门、核行业主管部门、上级主管部门及其他应急支援组织间的接口和协调，重点描述与地方应急组织的协调，包括接口、联络人、相互支援与责任分工等。
3.7.7 应急设施与设备
列出应设置的主要应急设施，包括控制室、备用或辅助控制室(点)、技术支持中心或支持点、应急指挥(或管理)中心、运行支持中心(或支持点)、监测与评价设施以及通信系统(重点在3.7.8中描述)等的位置，基本功能及应配置的主要设备与器材，同时说明某些设施是否能满足可居留性的要求。
概要描述公众信息中心，医学救护设施、淋浴与去污设施以及消防设备等应急辅助设施、设备的配置。
3.7.8 应急通信、报告与通知
描述对应急通信系统的基本要求(冗余性、多样性、畅通性、保密性以及抗干扰能力和覆盖范围)、所拥有的通信能力与系统(包括语音通信系统、数据收集和传输系统)；描述应急通知方法与程序，包括向国家核应急组织、地方核应急组织、核安全监督部门、核行业主管部门、上级主管单位等的应急报告，警报通知场内应急工作人员和非应急工作人员(包括承包商及外来参观人员)的方法和程序。
3.7.9 应急运行控制与系统设备抢修
描述应急状态下的运行控制(例如事故诊断与事故规程应用)及对系统设备抢修的工作安排。
3.7.10 事故后果评价
描述事故后果评价的目的、任务和主要工作内容：事故工况评价、堆芯损伤评价、工作场所与场内场外辐射水平监测与评估以及场外辐射后果的预测与评价，说明获取评价参数(预估源项、安全壳与流出物的辐射测量结果、气象参数、环境监测结果)的方法与安排，并重点描述场外辐射后果评价方法与应急环境监测内容及安排。
3.7.11 应急防护行动
列出经场内外协调一致的通用干预水平与通用行动水平，说明在应急状态下，如何根据监测结果对操作干预水平进行修改的原则与方法，并在附件中给出针对本核电厂及厂址特点建立的操作干预水平，描述有关场内防护行动决策的原则和实施场内防护行动(包括人员的通知、清点、隐蔽和撤离等)的计划；说明对场外实施防护行动所承诺的责任和提出公众防护行动建议的方法和程序。
3.7.12 应急照射控制
说明控制应急工作人员辐射照射的基本原则，给出应急工作人员在各类应急行动中的剂量控制水平；概述控制应急工作人员照射的方法和应急照射的批准程序。
3.7.13 医学救护
描述可用于应急状态下医学救护的设施、设备和能力，对受伤和受污染人员实施医学救护的计划安排，以及可以获得的外部医学救护支援及计划安排。
3.7.14 应急纠正行动
概述应急状态下可能采取的应急纠正行动、相应的计划安排、可获得的场外消防支援，抗其他自然灾害的能力与安排等。
3.7.15 应急状态终止与恢复
概述应急状态终止的条件，应急状态终止的批准与发布程序；给出场内恢复组织的组成和职责；说明应急组织向恢复组织的职责转移及拟采取的主要恢复措施。
3.7.16 公众信息与沟通
描述核电厂营运单位在与公众信息沟通中的职责，信息沟通的内容与方法，以及公众获得信息的渠道和新闻媒体信息传播的统一管理。
3.7.17 记录
描述对记录的基本要求和基本内容，包括制定、维持、修改应急计划的记录，应急响应的记录，以及应急终止与恢复阶段的记录。
3.7.18 应急响应能力的维持
应急响应能力的维持包括：
a) 培训：描述必须接受培训的各类工作人员，说明对他们培训和再培训的内容和计划安排；
b) 演习：说明各类演习的目的、类别、规模、频度和情景设计，以及对演习的评议要求。
c) 应急设施、设备的检查、测试和维护：描述对主要应急设施、设备的定期检查、测试及日常维护工作的安排；
d) 应急计划的评议与修改：概要说明对应急计划进行评议和修改的要求、频度和方法，以及修改后的应急计划的审批和发放。
3.7.19 术语
列出本应急计划中使用的、使用者并不十分熟悉的或为本核电厂及其营运单位专用的主要名词术语及其定义。
3.7.20 附件
列出与应急计划有关的各主要文件、资料的名称与内容，包括与各级应急组织及外部应急支援单位的协议文件、信件，以及操作干预水平与应急执行程序目录。