Emergency Planning & Response

  • ANS-3.8.1, Properties of Radiological Emergency Response Functions and Organizations for Nuclear Facilities
    Scope: This standard establishes properties for identifying emergency response functions and subsequently developing an overall pre-planned emergency response organization for nuclear facilities. The properties address a) basic emergency response functions, b) emergency response support functions, c) emergency response organization, and d) personnel responsibilities.
  • ANS-3.8.2, Properties of Functional and Physical Characteristics of Radiological Emergency Response Facilities at Nuclear Facilities
    Scope: This standard establishes functional and physical properties for facilities needed to provide an adequate overall emergency response. The properties address a) emergency response facilities, b) facility features and requirements, and c) parameters needed to provide a basis for determining an adequate inventory of equipment and supplies for anticipated emergency responses.
  • ANS-3.8.3, Properties of Radiological Emergency Response Plans and Implementing Procedures and Maintaining Emergency Response Capability for Nuclear Facilities
    Scope: This standard establishes properties for developing a radiological emergency response plan, emergency plan implementing procedures, and emergency plan administrative procedures for nuclear facilities. Properties include exercises, drills, surveillance, and training.
  • ANS-3.8.6, Properties of the Conduct of Offsite Radiological Assessment for Emergency Response and Emergency Radiological Field Monitoring, Sampling and Analysis for Nuclear Facilities
    Scope: This standard establishes properties for consequence assessment properties, as well as field monitoring, and sampling and analysis strategy during all phases of and after an emergency to be used for Protective Action Recommendations for nuclear facilities.
  • ANS-3.8.7, Properties of Planning, Development, Conduct, and Evaluation of Drills and Exercises for Emergency Preparedness at Nuclear Facilities
    Scope: This standard establishes properties for the planning, development, conduct and evaluation of radiological emergency response drills and exercises in support of emergency preparedness at nuclear facilities. In addition, this standard will incorporate the requirements for the conduct of Hostile Action-Based Emergency Response drills.
  • ANS-GD-3.8, Guidance for Risk-Informing Emergency Preparedness Programs for Nuclear Facilities
    Scope: The guidance document provides recommended practices for using risk analysis methods and insights to influence the properties of emergency preparedness and response functions for nuclear power plants and non-power nuclear facilities. Initial work products will focus on risk-informing development of site Emergency Response Organizations (e.g., identification of necessary functions, positions and response times) and technical bases for sizing Emergency Planning Zones (including the selection of accident sequences).This guidance may be provided as a logically integrated set of work products rather than a single document.

Reactor and Plant Systems and Support

  • ANS-18.1, Radioactive Source Term for Normal Operation of Light Water Reactors
    Scope: This standard provides a set of typical radionuclide concentrations for estimating the radioactivity in the principal fluid systems of light water reactors and for projecting the expected releases of radioactivity from nuclear plants. It is not Intended that the values be used as the sole basis for design, but be used in environmental reports and elsewhere where expected operating conditions over the life of the plant would be appropriate.
  • ANS-51.10, Auxiliary Feedwater System for Pressurized Water Reactors
    Scope: This standard sets forth the nuclear safety-related functional requirements, performance requirements, design criteria, design requirements for testing and maintenance, and interfaces for the nuclear safety-related portion of the auxiliary feedwater system (AFS) of pressurized water reactor (PWR) plants.
  • ANS-56.1, Containment Hydrogen Control
    Scope: The scope of this project is being drafted. Contact standards@ans.org for the status of this new project.
  • ANS-56.2, Containment Isolation Provisions for Fluid Systems After a LOCA
    Scope: This standard specifies minimum design, actuation, testing, and maintenance requirements for the containment isolation of fluid systems that penetrate the primary containment of nuclear power plants and include piping systems (including instrumentation and control) for all fluids entering or leaving the containment. Electrical systems are not included. This standard does not consider any isolation requirements that may exist for controlled leakage areas either enclosing the primary containment or contiguous to the primary containment. Also, this standard does not address containment isolation requirements for events other than LOCAs.
  • ANS-58.2, Design Basis for Protection of Light Water Nuclear Power Plants Against the Effects of Postulated Pipe Rupture
    Scope: This standard addresses the design basis for the protection of light water reactor nuclear power plants from the potentially adverse effects of postulated pipe ruptures.
  • ANS-58.3, Physical Protection for Nuclear Safety-Related Systems and Components
    Scope: This standard sets forth physical protection criteria for nuclear safety-related systems and components in stations using light water reactors (LWRs). This standard includes an identification of potential hazards to nuclear safety-related systems and components and acceptable means of ensuring the protection of this equipment from these hazards.
  • ANS-58.6, Criteria for Remote Shutdown for Light Water Reactors
    Scope: This standard provides design criteria for controls and monitoring instrumentation necessary to shut down a reactor and maintain it in a safe shutdown condition from outside the control room. The design criteria require that: (a) specific controls and monitoring instrumentation be provided; (b) these controls be installed at a location (or locations) that is physically separate from the control room and cable spreading areas; (c) simultaneous control from both locations be prevented by devices for transfer of control from the control room to the remote location(s); and (d) the remote controls be used as a defense-in-depth measure in addition to the control room shutdown controls and as a minimum provide for one complete channel of shutdown equipment.
  • ANS-58.9, Single Failure Criteria for Light Water Reactor Safety-Related Fluid Systems
    Scope: This standard provides criteria for the designer which interpret the requirements of Title 10, Code of Federal Regulations, Part 50, "Licensing of Production and Utilization Facilities," Appendix A, "General Design Criteria for Nuclear Power Plants," with respect to design against single failures in safety-related Light Water Reactor (LWR) fluid systems. Means of treating both active and passive failures are addressed for safety-related fluid systems following various initiating events. Current acceptable practice is used as a basis for these criteria.
  • ANS-58.11, Design Criteria for Safe Shutdown Following Selected Design Basis Events in Light Water Reactors
    Scope: This standard provides design criteria for systems that perform the safety-related functions necessary to shut down a reactor and maintain it in a safe shutdown condition for selected design basis events; i.e., any design basis events that do not require operation of engineered safety features. For design basis events that require operation of engineered safety features, this standard can be selectively applied because of plant features specifically designed for these conditions. For systems that serve multiple functions, the design criteria associated with the most limiting function shall be applied. The following safety-related functions are required for safe shutdown and are addressed in this standard: (1) Reactor core reactivity control, (2) Reactor core heat removal, (3) Reactor coolant pressure boundary integrity provided by: (a) Temperature control, (b) Pressure control, and (c) Inventory control.
  • ANS-58.14, Safety and Pressure Integrity Classification Criteria for Light Water Reactors
    Scope: This standard specifies deterministic criteria for the safety classification of items (i.e., SSCs and parts (including consumables)) in a LWR NPP as either safety-related (Q), supplemented grade (S), or non-safety-related (N). Criteria provide and establish a procurement subclassification within Class Q, called commercial grade (C). In addition, pressure integrity classification criteria provide for the assignment of Classes 1 to 5 to the pressure-retaining portion of items.
  • ANS-59.3, Nuclear Safety Criteria for Control Air Systems
    Scope: This standard provides criteria for the control air system that furnishes compressed air to nuclear safety-related components and other equipment that could affect any nuclear safety-related function in nuclear power plants. This standard provides: (1) the system nuclear safety design requirements and the non-nuclear safety design recommendations for equipment, piping, instruments, and controls that constitute the control air system; and (2) the nuclear safety design requirements and the non-nuclear safety design recommendations to accommodate the testing and maintenance necessary to ensure adequate performance of the control air system. This standard applies only to the control air system and does not apply to air-operated devices or the emergency diesel generator starting air system.
  • ANS-59.51, Fuel Oil Systems for Safety-Related Emergency Diesel Generators
    Scope: This standard provides functional, performance, and initial design requirements for the fuel oil system for diesel generators that provide safety-related emergency onsite power for light water reactor nuclear power plants. This standard addresses the mechanical equipment associated with the fuel oil system, with the exception of the engine mounted components. These components, which are mounted directly to the engine structure itself, are excluded except to define interface requirements. It also includes the instrumentation and control functional requirements. The standard excludes motors, motor control centers, switchgear, cables, and other electrical equipment used in the operation of the fuel oil system, except to define interface requirements.
  • ANS-59.52, Lubricating Oil Systems for Safety-Related Emergency Diesel Generators
    Scope: This standard provides functional, performance, and design requirements for lubricating oil systems for diesel generators that provide emergency onsite power for light water reactor nuclear power plants. The standard addresses all mechanical equipment associated with the lubricating oil system, with the exception of engine mounted components. These components, which are mounted directly to engine structure itself, are excluded, except to define interface requirements. This standard also includes the lubricating oil system instrumentation and control functional requirements. It excludes motors, motor control centers, switchgear, cables, and other electrical equipment used in the operation of the lubricating oil system, except to define interface requirements.
  • ANS-60.1, Nuclear Export Control Standard
    Scope: This standard provides criteria for export control of nuclear technology, equipment, and materials. This includes information regarding various types of exports, what information is required by each agency, and what reporting requirements exist after an export has occurred.

Simulators, Instrumentation, Control Systems, Software & Testing

  • ANS-3.1, Selection, Qualification, and Training of Personnel for Nuclear Power Plants
    Scope: This standard provides criteria for the selection, qualification, and training of personnel for nuclear power plants. The qualifications of personnel in the operating organizations appropriate to safe and efficient operation of a nuclear power plant are addressed in terms of the minimum education, experience, and training requirements.
  • ANS-3.2, Managerial, Administrative, and Quality Assurance Controls for the Operational Phase of Nuclear Power Plants
    Scope: This standard provides requirements and recommendations for managerial and administrative controls to ensure that activities associated with operating a nuclear power plant are carried out without undue risk to the health and safety of the public. This standard provides requirements for implementing managerial and administrative controls consistent with requirements of 10 CFR 50, Appendix B [1]. ) This standard is not specifically intended for application to test, mobile, or experimental reactors, nor reactors not subject to U.S. Nuclear Regulatory Commission (NRC) licensing. Although this standard is based on NRC requirements, the approach is applicable with modifications to reflect the regulatory requirements in the country of application. Applicable sections of this standard may be used in those cases for activities similar to those addressed herein.
  • ANS-3.4, Medical Certification and Monitoring of Personnel Requiring Operator Licenses for Nuclear Power Plants
    Scope: This standard defines the medical and psychological requirements for licensing of nuclear power plant reactor operators and senior operators. It also addresses the content, extent, and methods of examination. This standard has been reviewed and reaffirmed by the ANS Nuclear Facilities Standards Committee (NFSC) with the recognition that it may reference other standards and documents that may have been superseded or withdrawn. The requirements of this document are met by using the version of the standards and documents referenced herein. It is the responsibility of the user to review each of the references cited and to determine whether the use of the original references or more recent versions is appropriate for the facility. Variations from the standards and documents referenced in this standard should be evaluated and documented. The standard does not necessarily reflect recent industry initiatives for risk informed decision-making or a graded approach to quality assurance. Users should consider the use of these industry initiatives in the application of this standard.
  • ANS-3.5, Nuclear Power Plant Simulators for Use in Operator Training and Examination
    Scope: This standard establishes the functional requirements for full-scope nuclear power plant control room simulators for use in operator training and examination. The standard also establishes criteria for the scope of simulation, performance, and functional capabilities of simulators. This standard does not address simulators for reactors not subject to U.S. Nuclear Regulatory Commission licensing. This standard does not establish criteria for the use of simulators in training programs.
  • ANS-3.5.1, Nuclear Power Plant Simulators for Use in Simulation Assisted Engineering and Non-Operator Training
    Scope: This standard will provide minimum requirements for use of simulators for other applications such as plant engineering design Verification and Validation (V&V), plant engineering modifications V&V, optimization of engineering designs, optimization of plant performance, control loops tuning through different power levels, reducing trip risks, power uprates/downrates, pre-testing, human factors engineering, safety assessment studies, plant procedures development and verification, testing and commissioning procedures development and verification, training of plant personnel other than operators, etc.
  • ANS-3.13, Nuclear Facility Reliability Assurance Program (RAP) Development
    Scope: This standard provides criteria to describe nuclear facility reliability assurance programs and to perform scheduled maintenance and/or monitoring of operating conditions. This standard identifies and provides for scheduled maintenance based upon design principles. It provides guidance on how to select components' failure modes and maintenance requirements.
  • ANS-3.15, Risk-Informing Critical Digital Assets (CDAs) for Nuclear Power Plant Systems
    Scope: This standard provides a risk-informed, performance-based process for assessing the safety significance of plant digital assets. This risk-informed, performance-based process is in lieu of the deterministic methods currently in use. This standard applies to both new and operating plants.
  • ANS-56.8, Containment System Leakage Testing Requirements
    Scope: This standard specifies acceptable primary containment leakage rate test requirements to assure valid testing. The scope includes (1) Leakage test requirements; (2) Test instrumentation; (3) Test procedures; (4) Test methods; (5) Acceptance criteria; (6) Data analysis; (7) Inspection and recording of test results.
  • ANS-58.8, Time Response Criteria for Manual Actions at Nuclear Power Plants
    Scope: This standard establishes criteria and methods for identifying, calculating, validating, tracking, and documenting time requirements for the performance of nuclear power plant time-limited manual actions that are associated with either design-basis events or licensing basis.