F09 卫生、安全、劳动保护 标准查询与下载

NB/T 20037.4-2013 应用于核电厂的概率安全评价.第4部分:火灾

本部分规定了核电厂功率运行火灾一级概率安全评价(PSA)的要求。本部分适用于压水堆核电厂功率运行内部火灾一级PSA,其他堆型的核电厂可参照执行。本部分中不考虑防爆方面的因素。

Probabilistic safety assessment for nuclear power plant applications.Part 4: Fire

DIN 25475-1:2013 核设施.操作监控.第1部分:松动部件检测用结构噪声监测

Nuclear facilities.Operational monitoring.Part 1: Monitoring of structure-borne sound for loose parts detection

KS A ISO 7753:2012 核能.临界探测和报警系统的性能和检验要求

이 표준은 임계검출과 경보시스템을 위한 성능 및 시험요건을 기술하며, 플루토늄, 우라늄 2

Nuclear energy－Performance and testing requirements for criticality detection and alarm systems

KS A ISO 1709:2012 核能.贮存.装卸和加工易裂变材料的临界安全原则

이 표준은 핵분열성 물질 운용을 관리하는 기본원칙 및 제한사항을 기술한다. 이 표준은 장비

Nuclear energy－Fissile materials－Principles of criticality safety in storing, handling and processing

DL/T 256-2012 城市电网供电安全标准

本标准给出了供电企业应该满足的城市电网供电安全准则。 本标准适用于我国按行政建制的城市电网规划和改造工作。

Security of supply for urban electric network

DL/T 518-2012 电力生产人身事故伤害分类与代码

本标准规定了电力生产信息管理用的人身事故分类与代码。 本标准适用于电力生产安全运行、管理和科研的信息处理和信息交换。

Personal injury accident classification and code for electricity production

NB/T 20014-2010 核电厂放射工作人员健康监护

本标准规定了核电厂放射工作人员健康监护的基本内容和要求。 本部门适用于核电厂放射工作人员;核反应堆和相关核设施单位的放射工作人员也可参照执行。

Health surveillance for radiological workers in nuclear power plant

ANSI/ASME RA-Sa-2009 核动力设备用1级/大型早期释放频率概率风险评估标准

This Standard sets forth the requirements for probabilistic risk assessments (PRAs) used to support risk-informed decisions for commercial light water reactor nuclear power plants and prescribes a method for applying these requirements for specific applications.

Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications

ASTM D5498-09 为执行核设施喷涂工作检验的人员制定培训方案的标准指南

Personnel trained for coating work inspection are required to perform examination/inspection tasks to verify conformance of coating work to written requirements. This guide provides guidance for development of an indoctrination and training program for training of personnel performing coating work inspection. Certification/qualification of personnel performing coating work inspection is addressed in Guide D 4537.1.1 This guide is intended to assist those responsible for developing a program for the indoctrination and training of personnel performing coating inspection work for nuclear facilities. 1.2 It is recognized that organizations and job responsibilities vary widely among utilities and also among various support and service companies. It is the responsibility of the user of this guide to identify the appropriate subject matter for its program and its specific needs. 1.3 Users of this guide must ensure that coatings work complies not only with this guide, but also with the licensee's plant-specific quality assurance program and licensing commitments.

Standard Guide for Developing a Training Program for Personnel Performing Coating Work Inspection for Nuclear Facilities

KS A ISO 14943:2008 核原料技术.核界限安全相关的行政标准

이 표준은 원자로 밖에서 발생하는 작업과 잠재적 임계사고가 존재하는 핵임계 안전 관련 활동

Nuclear fuel technology－Administrative criteria related to nuclear criticality safety

EJ 275-2008 铀矿地质勘查安全生产规程

本标准规定了铀矿地质勘查工作野外地质作业、钻探工程、坑探工程、地质实验测试等方面的安全要求。 本标准适用于核工业铀矿地质勘查工作设计、生产和安全评价、管理。

Safety regulations for uranium exploration

ANSI/ASME N511-2007 核气体处理、加热、通风和空气调节系统在用测试标准

This standard covers the requirements for in-service testing of nuclear safety-related air treatment, heating, ventilating, and air conditioning systems in nuclear facilities.

Standard for In-Service Testing of Nuclear Air Treatment, Heating, Ventilating, and Air Conditioning Systems

EJ/T 1217-2007 核动力厂火灾危害性分析指南

本标准规定了全面实施核动力厂火灾危害性分析的框架结构，并为确定核动力厂防火安全充分性提供详细描述，包括数据采集、火势增长分析、火灾效应分析、防火安全措施恰当性评价、防火安全改进前的考虑、迭代分析等。 本标准适用于陆上固定式热中子反应堆核动力厂的火灾危害性分析，这些核动力厂包括轻水堆、重水堆和气冷堆核动力厂。也可适用于研究堆和其它核设施的火灾危害性分析。本标准既可以用于新建核动力厂又可以用于已有的核动力厂。本标准适用于核动力厂的所有区域，包括非核设施。 本标准不适用于液态金属冷却反应堆核动力厂中液态金属设施防火区火灾危害性分析。

Preparation of fire hazard analyses for nuclear power plants

BS IEC 60671:2007 核电站.对安全性重要的仪器装置和控制系统.监督测试

Where functional reliability is required by general safety standards, one aspect of demonstrating this reliability is testing performed on-line during plant operation or during plant shutdown in preparation for return to power operation. This standard lays down principles for testing I&C systems performing category A, B and C functions, per IEC 61226, during normal power operation and shutdown, so as to check the functional availability especially with regard to the detection of faults that could prevent the proper operation of the functions important to safety. It covers the possibility of testing at short intervals or continuous surveillance, as well as periodic testing at longer intervals. It also establishes basic rules for the design and application of the test equipment and its interface with the systems important to safety. Further, the effect of any test equipment failure on the reliability of the I&C systems is considered. Types of surveillance tests may include: – self-tests for I&C equipment; – test of a group of equipment or components to confirm properties that support the safety function (continuity, power availability, etc.); – test based on information redundancy or comparison of control signatures (consistency checking for redundant sensors, CRC-checking, Checksum, etc.); – periodic testing which is related to the correctness of functional behaviour of an I&C system. The dependability targets of any I&C system is reached using an appropriate combination of tests of the form indicated above. The extent of the I&C system to be tested is from the interface of the sensors with the process through to the actuation devices. It is applicable to the installed I&C systems as well as to temporary installations which are part of those I&C systems important to safety (for example, auxiliary equipment for commissioning tests and experiments). This standard also applies to individual electromechanical equipment, such as relays and solenoid actuators. Additional testing and inspections may be performed on I&C equipment for purposes other than the demonstration of functional capability, such as to optimise preventive maintenance, etc. Such tests are beyond the scope of this standard; however, they may be combined with the surveillance testing discussed herein. For any on-line tests the potential interaction and fault dependencies between the part of the system under test and the testing part, have to be carefully studied and their influences have to be fully integrated into the reliability assessment of the functions important to safety (in accordance with IEC 61513). This standard applies to the I&C of new nuclear power plants as well as to I&C upgrading or back-fitting of existing plants. For I&C upgrades, only a subset of the requirements may be applicable; this subset is to be identified at the beginning of any project.

Nuclear power plants - Instrumentation and control systems important to safety - Surveillance testing

BS IEC 62397:2007 核电站.对安全性重要的仪器装置和控制系统.电阻温度探测器

This International Standard describes the requirements for resistance temperature detectors (RTDs) suitable for nuclear power plant (NPP) services. The requirements of RTDs include design, materials, manufacturing, testing, calibration, procurement, and inspection. In nuclear application, both “direct-immersion” and “thermowell-mounted” RTD are commonly used; however, this standard does not exclude any other design of RTD which may be required for certain special applications in various types of reactors. RTDs can be supplied in different internal constructions, which depend on the manufacture, qualifications, and applications. For RTD being used in an NPP, the design and structure of the RTD should consider the environmental conditions in which the detector is being used under normal operating and under design basis accident conditions, as well as the qualification tests specified by the user 1. The use of a flexible mineral-insulated (MI) cable between the RTD and the connector is commonly adopted, and the user may also adopt any other construction. A variation of this design may include a rigid exterior sheath over the MI cable between the RTD and the connector, these being welded to each other. The scope of this standard does not cover the design, material selection, and construction of the thermowell, the guide tube, the extension cable, and the temperature transmitter or bridge which may be associated with the RTD.

Nuclear power plants - Instrumentation and control important to safety - Resistance temperature detectors

DIN 25474:2007 对于除反应堆外的核技术装备保持临界安全的管理措施

Measures of administrative character for conservation of criticality safety in nuclear facilities excluding reactors

IEC 62385:2007 核电站.仪器和控制对安全的重要性.安全系统测量途径的性能评估用方法

The purpose of this International Standard is to define the requirements for demonstrating acceptable performance of safety system instrument channels through response time testing, calibration verification, and other means. The same requirements may be adopted for demonstrating the acceptable performance of non-safety systems and other instrument channels. This Standard contains the main topics in its body and includes annexes to provide further information. The annexes are for information only and contain a selection of the available methods. The methods described in this Standard are used to check instrument calibration for accuracy and time response. It covers direct methods used to set calibration within required tolerances and indirect methods to indicate a need for a direct calibration. The use of the indirect methods allows for longer periods between the routine direct calibrations.

Nuclear power plants - Instrumentation and control important to safety - Methods for assessing the performance of safety system instrument channels

ANSI/ANS 8.23-2007 核危险事故应急计划和响应

This standard provides criteria for minimizing risks to personnel during emergency response to a nuclear criticality accident outside reactors. This standard applies to those facilities for which a criticality accident alarm system, as specified in American National Standard Criticality Accident Alarm System, ANSI/ANS-8.3-1997 (R2003) is in use. This standard does not apply to nuclear power plant sites or to licensed research reactor facilities, which are addressed by other standards.

Nuclear Criticality Accident Emergency Planning and Response

DB11/ 383-2006 建设工程施工现场安全资料管理规程

为加强北京市建设工程施工现场安全资料的规范化管理，提高工程施工现场安全管理水平，防止和减少生产安全事故，保障人民群众生命和财产安全，特制定本规程。本规程适用于北京市行政区域内新建、扩建、改建和拆除的建设工程施工现场安全资料管理。凡在北京市行政区域内参与工程建设的建设、施工、监理等单位均应执行本规程。

Management specification of construction engineering safety document

ANSI/ANS 8.19-2005 核临界安全.管理规程

This standard provides criteria for the administration of a nuclear criticality safety program for outside-of-reactor operations in which there exists a potential for nuclear criticality accidents. Responsibilities of management, supervision, and the nuclear criticality safety staff are addressed. Objectives and characteristics of operating and emergency procedures are included.

Nuclear Criticality Safety – Administrative Practices