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Working Group

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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-2.10, Criteria for Retrieval, Processing, Handling, and Storage of Records from Nuclear Facility Seismic Instrumentation

Scope: This standard provides criteria for the timely retrieval and the subsequent processing, handling, and storage of data obtained from nuclear power plant and non-power nuclear facility strong-motion analog and digital seismic instrumentation. ) Nuclear power plant seismic instrumentation requirements are specified in ANSI/ANS-2.2-2016. Non-power nuclear facility seismic instrumentation, if required, is specified in facility-specific regulations, standards, and/or guidance documents.

ANS-2.23, Nuclear Power Plant Response to an Earthquake

Scope: This standard specifics actions that the owner of a nuclear power plant shall take to prepare for and respond to a felt earthquake at the plant(s), including the need for plant shutdown; actions to determine the readiness of the plant to resume operation; and those evaluations necessary to verify the long-term integrity of safety-related (SR) and important structures, systems, and components (SSCs). It also includes a consensus definition of operating basis earthquake (OBE) exceedance, beyond which U.S. regulations require plant shutdown. Application of this revised standard provides a comprehensive, balanced plan for the response of a nuclear power plant to an earthquake. This standard does not cover those operator actions that are performed in connection with safe operation and control of the nuclear power plant during and following an earthquake. These operations are specified in plant operating procedures, emergency procedures, alarm response procedures, and other conditions of the plant's license. Likewise, it does not cover required reporting and communications with the U.S. Nuclear Regulatory Commission (NRC). It is not applicable to nuclear facilities other than licensed nuclear power plants.

ANS-2.26, Categorization of Nuclear Facility Structures, Systems, and Components For Seismic Design

Scope: This standard provides: (a) criteria for selecting the seismic design category1) (SDC) for nuclear facility structures, systems, and components (SSCs) to achieve earthquake safety and (b) criteria and guidelines for selecting Limit States for these SSCs to govern their seismic design. The Limit States are selected to ensure the desired safety performance in an earthquake. 1) The SDCs used in this standard are not the same as the SDCs referred to in the International Building Code (IBC).

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-2.29, Probabilistic Seismic Hazard Analysis

Scope: This standard provides criteria to establish the probabilistic basis for various levels of natural phenomena hazards at nuclear materials facility sites

ANS-2.30, Criteria for Assessing Tectonic Surface Fault Rupture and Deformation at Nuclear Facilities

Scope: This standard provides criteria and guidelines for assessing permanent ground deformation (PGD) hazard due to tectonic surface fault rupture and deformation at nuclear facilities. Specifically, the purpose of this standard is to provide an outline of procedures and methods for performing probabilistic fault displacement hazard analysis (PFDHA for surface rupture hazard) and probabilistic tectonic deformation hazard analysis (PTDHA for surface deformation due to displacements along blind [buried faults]). Probabilistic approaches for assessing surface fault displacement and tectonic deformation hazard are relatively new and so criteria and guidelines have not been defined previously. PGD due to fault rupture is a potential hazard for nuclear facilities founded across or near a fault. In this standard, only coseismic PGD hazard related to movement on crustal faults is addressed. Deformation in the form of creep or afterslip and uplift and subsidence during subduction zone earthquakes is not addressed.

ANS-2.34, Characterization and Probabilistic Analysis of Volcanic Hazards

Scope: This standard provides criteria and guidance for performing a probabilistic volcanic hazard analysis (PVHA) for the design and construction of nuclear facilities. Criteria provided in this standard address several aspects of conducting PVHAs, including 1) selection of the methodology and level of volcanic hazard analysis appropriate for a facility, including a deterministic screening; 2) characterization of the hazards posed by existing volcanic vents and potential newly emerging volcanic vents; and 3) characterization of the unique hazards posed by several volcanic phenomena including ashfall, lava flows, lahars, and asphyxiating gases.

Last modified July 21, 2016, 1:57pm CDT