F68 核电厂退役 标准查询与下载

NF M60-571*NF EN ISO 16647:2021 核设施. 核工地和退役核设施限制系统的设计和运行标准

Nuclear facilities - Criteria for design and operation of confinement systems for nuclear worksite and for nuclear installations under decommissioning

EJ/T 20049-2014 核设施退役质量保证要求

本标准规定了民用核设施退役策划管理过程和退役活动实施过程的质量保证基本要求。本标准适用于民用核设施营运单位及退役实施组织关于退役的质量保证大纲的建立和实施。它也适用于退役时对安全质量有重要影响的活动,如设计、试验、拆除、辐射防护及放射性废物管理等。其它核设施相关活动可参照执行。

Quality assurance requirements on decommissioning for nuclear facilities

NB/T 20271-2014 核电厂退役需要的文件和记录的维护与保存要求

本标准规定了收集、筛选、保存和维护核电厂退役需要的文件和记录的方法及一般要求。本标准主要适用于核电厂业主和(或)营运单位对核电厂退役需要的文件和记录的管理,其他核设施退役可参照执行。

Requirements of documents and records keeping and maintaining for the decommissioning of nuclear power plants

IEEE 1205-2014 核电站和其它核设施用电气设备老化影响的评价、监视和减轻指南

Guide for Assessing, Monitoring, and Mitigating Aging Effects on Electrical Equipment Used in Nuclear Power Generating Stations and Other Nuclear Facilities

ASTM E1281-10 核设备退役计划标准指南

The standardization of decommissioning plans will provide the nuclear facility owner with a greater assurance that all basic planning elements and requirements have been identified, examined, and addressed. In applying the guidance contained in this standard, the nuclear facility owner will address the significant subject areas necessary to describe a comprehensive decommissioning plan. Additional guidance on the planning of decommissioning projects, and the preparation of decommissioning plans can be found in such references as NUREG-1757 on decommissioning standard review plans, and Regulatory Guide 1.179 on the format and content of license termination plans. Recent new guidance on all aspects of decommissioning is contained in an ASME publication titled The Decommissioning Handbook. 1.1 This guide applies to decommissioning plans for any nuclear facility whose operation was (is) governed by Nuclear Regulatory Commission (NRC) or Agreement State license, or under Department of Energy (DOE) orders. 1.2 The guide applies to the preparation and content of the decommissioning plan document itself. 1.3 The detailed description and development of implementation plans identified in Section 4 is outside the scope of this guide. Note 18212;Nuclear facilities operated by the U.S. DOE are not licensed by the U.S. NRC, nor are other nuclear facilities which may come under the control of the U.S. Department of Defense or individual agreement states. The references in this guide to licensee, U.S. NRC Regulatory guides, and Title 10 of the U.S. Code of Federal Regulations are to imply appropriate alternative nomenclature with respect to DOE, DOD, or agreement state nuclear facilities. This distinction should not alter the content of decommissioning plans for nuclear facilities. 1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

Standard Guide for Nuclear Facility Decommissioning Plans

ASTM E1819-10 核设备退役的环境监测计划标准指南

Use of this guide will ensure that the potential impact on the surrounding environment from planned decommissioning activities has been properly assessed. Use of this guide will ensure that the adequacy of environmental sampling has been assessed for location, frequency, analytical techniques, and media type to monitor the environment and to detect site-related releases and their impact.1.1 This guide covers the development or assessment of environmental monitoring plans for decommissioning nuclear facilities. This guide addresses: (1) development of an environmental baseline prior to commencement of decommissioning activities; (2) determination of release paths from site activities and their associated exposure pathways in the environment; and (3) selection of appropriate sampling locations and media to ensure that all exposure pathways in the environment are monitored appropriately. This guide also addresses the interfaces between the environmental monitoring plan and other planning documents for site decommissioning, such as radiation protection, site characterization, and waste management plans, and federal, state, and local environmental protection laws and guidance. This guide is applicable up to the point of completing D&D activities and the reuse of the facility or area for other purposes.

Standard Guide for Environmental Monitoring Plans for Decommissioning of Nuclear Facilities

ASTM E1892-09 核设备退役准备计划的标准指南

Knowledge of the nature and extent of contamination in a nuclear facility to be decommissioned is crucial to choosing the optimum methods for decontamination and decommissioning, and estimating the resulting waste volumes and personnel exposures. Implementing a characterization plan, developed in accordance with this standard, will result in obtaining or deriving the above information. Information on the proposed decommissioning methods, waste volumes, and estimated personnel radiation exposures can be used to define the overall work scope, costs, schedules, and manpower needs for the decommissioning project. This information may be included in the Decommissioning Plan. The extent of over- or under-estimating these project parameters will be a function of the sampling plan and statistical designs, described in Sections 6.1.4 and 6.1.5.1.1 This standard guide applies to developing nuclear facility characterization plans to define the type, magnitude, location, and extent of radiological and chemical contamination within the facility to allow decommissioning planning. This guide amplifies guidance regarding facility characterization indicated in ASTM Standard E 1281 on Nuclear Facility Decommissioning Plans. This guide does not address the methodology necessary to release a facility or site for unconditional use. This guide specifically addresses: 1.1.1 the data quality objective for characterization as an initial step in decommissioning planning. 1.1.2 sampling methods, 1.1.3 the logic involved (statistical design) to ensure adequate characterization for decommissioning purposes; and 1.1.4 essential documentation of the characterization information. 1.2 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

Standard Guide for Preparing Characterization Plans for Decommissioning Nuclear Facilities

EJ/T 1200-2006 生产堆退役设计安全准则

本标准规定了生产堆退役设计（堆芯拆除设计除外）中的基本安全准则，以保障退役活动的安全性。 本标准适用于生产堆的退役设计，其他类型反应堆的退役设计也可参照使用。

Safety criteria for decommissioning design of production reactor

ASTM E2216-02(2008) 核设施退役区混凝土处理方案的评估标准指南

This standard guide applies to concrete that is still in place with a defined geometry and known, documented history. It is not intended for use on concrete that has already been rubbelized where it is difficult to measure the radiation levels and not easy to remove surface contamination to reduce radiation levels after concrete has been rubbelized. This standard guide applies to surface or volumetrically contaminated concrete, where the depth of contamination can be measured or estimated based on the history of the concrete. This standard guide does not apply to the reinforcement bar (rebar) found in concrete. Although most concrete contains rebar, it is generally removed before the concrete is dispositioned. In addition, rebar may be activated, and is covered under procedures for reuse of scrap metal. General unit-dose and unit-cost data to support the calculations is provided in the appendices of this standard guide. However, if site-specific data is available, it should be used instead of the general information provided here. This standard guide helps determine estimated doses to the public during disposal of concrete and to future residents of disposal areas. It does not include dose to radiation workers already involved in a radiation control program. It is assumed that the dose to radiation workers is already tracked and kept within acceptable levels through a radiation control program. The cost and dose to radiation workers could be added in to find an overall cost and dose for each option.1.1 This standard guide defines the process for developing a strategy for dispositioning concrete from nuclear facility decommissioning. It outlines a 10-step method to evaluate disposal options for radioactively contaminated concrete. One of the steps is to complete a detailed analysis of the cost and dose to nonradiation workers (the public); the methodology and supporting data to perform this analysis are detailed in the appendices. The resulting data can be used to balance dose and cost and select the best disposal option. These data, which establish a technical basis to apply to release the concrete, can be used in several ways: (1) to show that the release meets existing release criteria, (2) to establish a basis to request release of the concrete on a case-by-case basis, (3) to develop a basis for establishing release criteria where none exists. 1.2 This standard guide is based on the “Protocol for Development of Authorized Release Limits for Concrete at U.S. Department of Energy Sites,” (1) from which the analysis methodology and supporting data are taken. 1.3 Guide E 1760 provides a general process for release of materials containing residual amounts of radioactivity. In addition, Guide E 1278 provides a general process for analyzing radioactive pathways. This standard guide is intended for use in conjunction with Guides E 1760 and E 1278, and provides a more detailed approach for the release of concrete.

Standard Guide for Evaluating Disposal Options for Concrete from Nuclear Facility Decommissioning

DIN 25454:2000 核设施和粒子加速器发出的放射性成份退役过程中的遥控操作

The document is to be applied for remotely controlled operations of radioactive components and steel including concrete structures during decommissioning of nuclear plants. It is not valid for nuclear power plants.

Remotely controlled operations during decommissioning of radioactive components from nuclear facilities and particle accelerators

IEEE 1205-2000 核电站用1E级设备老化影响的评价、监视和减轻

This document provides the guidelines for assessing, monitoring, and mitigating aging degradation effects on Class 1E equipment used in nuclear power generating stations. It also includes informative annexes on aging mechanisms, environmental monitoring, condition monitoring, aging program essential attributes, and example assessments for five types of equipment (including electric cable).

Guide for Assessing, Monitoring, and Mitigating Aging Effects on Class 1E Equipment Used in Nuclear Power Generating Stations

STAS 11115/15-1992 机载设备的环境条件和试验程序．第15节．磁效应

Aceast? ?ncercare determin? influen?a magnetic? a echipamentului pentru a ajuta pe cel care proiecteaz? instala?ia ?n alegerea pozi?ion?rii corecte a echipamentului ?n aeronav?.

Environmental condition and test procedures for airborne equipment. Section 15: Magnetic effect

STAS 11115/11-1992 机载设备的环境条件和试验程序．第11节．流体敏感度

Aceste ?ncerc?ri stabilesc dac? materialele folosite la fabricarea echipamentului pot s? reziste la efectele de deteriorare ale fluidelor contaminante. Aceste gen de ?ncercare nu trebuie s? se efectueze dec?t dac? echipamentul este instalat ?n zone ?n car

Environmental condition and test procedures for airborne equipment. Section 11: Fluids susceptibility

STAS 12865-1990 飞行器用可修理的电流接触器（非密封）一般质量技术要求

Prezentul standard stabile?te condi?iile tehnice generale de calitate, precum ?i regulile ?i metodele de verificare a calit??ii contractoarelor reparabile, neermetice, pentru aeronave.

Repairable contactors (Nothermetically sealed) for aircraft General technical requirements for quality

ASTM E1281-89(1996)e1 核设备退役计划的标准指南

1.1 This guide applies to decommissioning plans for any nuclear facility whose operation was (is) governed by Nuclear Regulatory Commission (NRC) or Agreement State license, or under Department of Energy (DOE) orders. 1.2 The guide applies to the preparation and content of the decommissioning plan document itself. 1.3 The detailed description and development of implementation plans identified in Section 4 is outside the scope of this guide.Note 1--Nuclear facilities operated by the U.S. DOE are not licensed by the U.S. NRC, nor are other nuclear facilities which may come under the control of the U.S. Department of Defense or individual agreement states. The references in this guide to licensee, U.S. NRC Regulatory guides, and Title 10 of the U.S. Code of Federal Regulations are to imply appropriate alternative nomenclature with respect to DOE, DOD, or agreement state nuclear facilities. This distinction should not alter the content of decommissioning plans for nuclear facilities. 1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

Standard Guide for Nuclear Facility Decommissioning Plans

ASTM E1281-89(2005) 核设备退役计划的标准指南

The standardization of decommissioning plans will provide the nuclear facility owner with a greater assurance that all basic planning elements and requirements have been identified, examined, and addressed. In applying the guidance contained in this standard, the nuclear facility owner will address the significant subject areas necessary to describe a comprehensive decommissioning plan. Additional guidance on the planning of decommissioning projects, and the preparation of decommissioning plans can be found in such references as NUREG-1727 on decommissioning standard review plans, and Regulatory Guide 1.179 on the format and content of license termination plans. Recent new guidance on all aspects of decommissioning is contained in an ASME publication titled The Decommissioning Handbook.6 This decommissioning plan will be developed to serve as the executive document that describes the objectives of the decommissioning program and identifies and defines the elements necessary to accomplish the program. A detailed implementation plan describing how the objectives of the decommissioning plan will be met should be prepared. Some of the documents or implementation plans that may be required to support the overall decommissioning program include an engineering plan; a cost, schedule, and financing plan; a field implementation plan; a health and safety plan; a quality assurance plan (for example, Guide E 1167); an emergency plan; an environmental report; a radiological protection plan; and a physical security plan. These implementation plans shall be separate from and consistent with the decommissioning plan.1.1 This guide applies to decommissioning plans for any nuclear facility whose operation was (is) governed by Nuclear Regulatory Commission (NRC) or Agreement State license, or under Department of Energy (DOE) orders.1.2 The guide applies to the preparation and content of the decommissioning plan document itself.1.3 The detailed description and development of implementation plans identified in Section is outside the scope of this guide. Note 18212;Nuclear facilities operated by the U.S. DOE are not licensed by the U.S. NRC, nor are other nuclear facilities which may come under the control of the U.S. Department of Defense or individual agreement states. The references in this guide to licensee, U.S. NRC Regulatory guides, and Title 10 of the U.S. Code of Federal Regulations are to imply appropriate alternative nomenclature with respect to DOE, DOD, or agreement state nuclear facilities. This distinction should not alter the content of decommissioning plans for nuclear facilities.1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

Standard Guide for Nuclear Facility Decommissioning Plans