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ANS > Standards > Get Involved > Volunteer Opportunities > NFSC > ANS-25 |
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ANS-25, Siting: Environmental and Emergency Preparedness If you are interested in participating in the following standards, complete and submit the Standards Volunteer Form. ANS-2.2, Earthquake Instrumentation Criteria for Nuclear Power Plants  Scope: This standard specifies the required earthquake instrumentation for the site and structures of light water cooled, land based nuclear power plants. It may be used for guidance at other types of nuclear facilities. This standard does not address the following: (a) Instrumentation to automatically shut down a nuclear power plant at a predetermined ground acceleration. (b) Procedures for evaluating records obtained from seismic instrumentation and instructions for the treatment of data. These procedures and instructions are specified in American National Standard, "Criteria for the Handling and Initial Evaluation of Records from Nuclear Power Plant Seismic Instrumentation," ANSI/ANS 2.10-2003. ANS-2.3, Determining Tornado and Other Extreme Wind Characteristics at Nuclear Facility Sites Scope: The purpose of this standard is to specify guidelines to determine the wind velocity, atmospheric pressure change, missile type, size and velocity that result from tornadoes, hurricanes and other extreme winds to be used in nuclear facility design. The standard does not treat forces that result from these natural events. ANS-2.6, Guidelines for Estimating Present and Forecasting Future Population Distributions Surrounding Power Reactor Sites Scope: This standard provides guidance on suitable methodologies for developing estimates and forecasts of human population distribution around civilian and Federal nuclear facility sites. The standard is intended to provide applicants and DOE/NNSA professionals with methodologies that are generally acceptable in the demographic community and to facilitate the NRC review of site suitability relative to population considerations. ANS-2.8, Determining Design Basis Flooding at Power Reactor Sites Scope: This document presents criteria to establish design basis flooding for nuclear safety-related features at power reactor sites. Methodology is described to evaluate the flood having virtually no risk of exceedance that can be caused by precipitation and snowmelt and any resulting dam failures; seismically induced dam failures; surge or seiche and attendant wind-generated wave activity; or a reasonable combination of these events. ANS-2.9, Evaluation of Ground Water Supply for Nuclear Facilities Scope: This standard provides criteria for the determination of the availability of ground water supplies for nuclear facilities with respect to both safety and non-safety related aspects. ANS-2.17, Evaluation of Radionuclide Transport in Ground Water for Nuclear Facilities Scope: This standard provides criteria for the determination of the concentration of radionuclides in the ground water resulting from both postulated accidents and routine releases from nuclear facilities. ANS-2.18, Standards for Evaluating Radionuclide Transport in Surface Water for Nuclear Power Sites Scope: This standard presents guidelines for the determination of the transport of radionuclides in surface water resulting from both postulated accidental and routine releases from nuclear power plants and other nuclear facilities. ANS-2.21, Criteria for Assessing Atmospheric Effects on the Ultimate Heat Sink Scope: This standard establishes criteria for use of meteorological data collected at nuclear facilities to evaluate the atmospheric effects from meteorological parameters (e.g., dry-bulb temperature/wet-bulb temperature differential, precipitation, wind speed, short wave radiation, incoming solar (short wave) radiation, surface water temperature, and atmospheric pressure) on ultimate heat sinks. ANS-2.22, Environmental Radiological Monitoring at Nuclear Facilities Scope: This standard establishes criteria for use in developing and implementing an integrated radiological environmental monitoring program focusing on ambient air, surface water, and biota. It also provides criteria on the use of resultant environmental data collected near nuclear facilities to evaluate the impact of facility operations on the surrounding population and environment. ANS-2.25, Surveys of Terrestrial Ecology Needed to License Thermal Power Plants Scope: This standard discusses the need developers of thermal power plants and their associated facilities have for information on the terrestrial environment. Utilities and regulatory agencies must collect information to predict and assess real and potential environmental impacts, and to site and design generating plants that avoid or reduce adverse effects. Users of this standard will be guided through each stage of a survey with its corresponding requirements, the relationship of the terrestrial ecologist and other specialists in a major project, sources of information, and the governing laws and regulations. ANS-2.27, Criteria for Investigations of Nuclear Facility Sites for Seismic Hazard Assessments Scope: This standard provides requirements and recommended practices for conducting investigations and acquiring data sets needed to evaluate seismic source characterization for probabilistic seismic hazard analysis (PSHA), site response and soil structure interaction (SSI) effects, and liquefaction. These data also are used to evaluate fault rupture and associated secondary deformation, and other seismically-induced ground failure hazards (i.e., ground settlement, slope failure, and subsidence and collapse). ANS-2.30, Assessing Capability for Surface Faulting at Nuclear Facilities Scope: This standard provides criteria and guidelines for investigations to assess potential for surface and near-surface faulting and associated near-fault deformation at nuclear facilities, referencing considerable new experience. The standard is an up-to-date compilation of techniques to evaluate fault offset potential and a valuable resource for planning and conducting site characterization studies for future nuclear facilities. It supplements a group of standards (i.e., ANS-2.26, -2.27, -2.29, ASCE 43-05) whose focus is on vibratory ground motion rather than fault offset hazard. ANS-3.7.1, Facilities and Medical Care for On-Site Nuclear Power Plant Radiological Emergencies Scope: This standard provides criteria for developing plans, and for providing facilities and equipment, for the care and transportation of individuals exposed to unexpected radiation, or contaminated with radioactive materials either internally or externally, in nuclear power plants. The criteria address coordination of emergency response and first aid at the plant site; transportation to an offsite location, such as a local hospital; and care at the offsite location. Training of personnel in support of expected actions is also addressed. ANS-3.8.1, Criteria for Radiological Emergency Response Functions and Organizations Scope: This standard establishes criteria for developing an overall preplanned emergency response organization for commercial nuclear power plants. The criteria address: (1) basic emergency response functions (2) emergency response support functions to ensure that the basic functions are adequately implemented (3) emergency response organization (4) personnel responsibilities. ANS-3.8.2, Criteria for the Functional and Physical Characteristics of Radiological Emergency Response Facilities Scope: This standard establishes the criteria for facilities needed to provide an adequate overall emergency response. The standard addresses: (1) emergency response facilities (2) facility features and requirements, and (3) parameters needed to provide a basis for determining an adequate inventory of equipment and supplies for the anticipated emergency response. Normal plant equipment that is to be used during an emergency, such as sampling system equipment, safety-related systems, or system instrumentation, are not within the scope of this standard. ANS-3.8.3, Criteria for Radiological Emergency Response Plans and Implementing Procedures Scope: This standard establishes criteria for developing a radiological emergency response plan and implementing procedures necessary to coordinate an integrated emergency response at a commercial nuclear power plant. The radiological emergency response plan is the administrative document that establishes the licensee's commitments to emergency preparedness and response. The procedures are the licensee's documents that implement the radiological emergency response plan. Implementing procedures address the following areas: (1) emergency classification, (2) emergency response organization duties and responsibilities, (3) notification, (4) emergency response facilities activation and operation, (5) emergency teams, (6) personnel protection, (7) environmental , assessment, (8) public information, (9) de-escalation, (10) recovery planning, (11) maintaining emergency preparedness. ANS-3.8.4, Criteria for Maintaining Radiological Emergency Response Capability Scope: This standard provides criteria and recommendations for emergency preparedness exercises, drills, surveillance activities, and training. This standard does not address detailed accident scenarios, but provides criteria regarding the frequency, type, and scope of exercises, drills, and training needed, and the extent of the realism necessary for the exercise to be effective. This standard provides criteria for emergency exercises involving the facility and offsite support groups and criteria for evaluating exercises. ANS-3.8.6, Criteria for the Conduct of Offsite Radiological Assessment for Emergency Response for Nuclear Power Plants Scope: This standard describes the purpose of dose assessment and provides dose assessment criteria to be used when formulating protective action recommendations for the public. The standard describes the use of field monitoring data in support of dose assessment, and the integration of dose assessments with plant status assessments for protective action recommendations. ANS-3.8.7, Criteria for Planning, Development, Conduct, and Evaluation of Drills and Exercises for Emergency Preparedness Scope: This standard establishes criteria for the administration of a program of radiological emergency response drills and exercises in support of emergency preparedness at nuclear power plants. The topics discussed in this standard are applicable to both exercises and drills unless specifically identified otherwise. The standard addresses: (1) Types of emergency drills and exercises, and the reasons for each. (2) Planning activities associated with drills and exercises. (3) Development of scenarios for drills and exercises. (4) Conduct of drills and exercises. (5) Evaluation of drills and exercises. Simulator drills and exercises conducted as part of a larger emergency response exercise are within the scope of this standard. Simulator drills and exercises conducted as part of licensed operator training, and periodic retraining, are not within the scope of this standard. Exercise scenario artificialities needed to drive emergency response activities are often obtained by intentionally defeating operating actions or by inserting simulator manipulations. These actions or manipulations might produce responses which are in excess of the capabilities called for in American National Standard for Nuclear Power Plant Simulators for Use in Operator Training and Examination, ANSI/ANS-3.5-1993. Therefore, these exercises are not to be used to evaluate the adequacy of simulator performance or operator accident mitigation capability. ANS-40.21, Siting, Construction, and Operation of Commercial Low Level Radioactive Waste Burial Grounds Scope: This standard provides a matrix of minimum criteria to be met in determining the siting, construction and operation of a commercial low level radioactive waste burial ground. The standard will balance siting (i.e., natural criteria), construction (i.e., engineered safeguards) and operation (i.e., acceptance criteria) to provide a safety matrix that provides for the containment of the facility. |
