ML24355A028

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Mazzola - ANS Standards Supporting DOE and NRC Nph Design
ML24355A028
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Issue date: 10/29/2024
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ANS STANDARDS SUPPORTING DOE AND NRC NPH DESIGN DOE NPH Workshop Carl Mazzola (PEC) October 29, 2024

CONSENSUS STANDARD DEVELOPMENT PROCESSES Approved by a Balance of Interest (BOI) cross-section of industry and regulatory representatives using a consistent process Developed by Standards Development Organizations (SDOs) when industry identifies a need Often endorsed by a regulator (NRC) or state or federal entity (DOE); thus becoming a regulatory requirement in state or federal law Involves a process that takes many years to achieve consensus from many techniques, viewpoints, and opinions

STANDARDS DEVELOPMENT LEGISLATIVE AND EXECUTIVE DRIVERS

  • Legislative
  • PL 104-113: National Technology Transfer and Advancement Act (1995)
  • Executive
  • OMB Circular A-119 (Revised 2015)
  • DOE Technical Standards Project Office

NUCLEAR STANDARDS SDOS ANSI ACCREDITATION

  • American Nuclear Society (ANS)
  • American Concrete Institute (ACI)
  • American Society of Mechanical Engineers (ASME)
  • American Society for Testing & Materials (ASTM)
  • American Welding Society (AWS)
  • Health Physics Society (HPS)
  • Institute of Electrical and Electronics Engineers (IEEE)
  • Institute of Nuclear Materials Management (INMM)
  • Instrumentation Systems & Automation Society (ISA)
  • National Fire Protection Association (NFPA)

ANS ESCC MISSION AND SCOPE

  • Preparation/maintenance of 25 consensus standards
  • Nuclear power plant/DOE non-reactor nuclear facility siting, design, engineering and construction
  • Categorization and evaluation of site-specific NPHs
  • NEPA environmental impacts and assessments
  • Environmental surveillance and monitoring
  • Environmental remediation
  • Decommissioning and decontamination

ESCC SUBCOMMITTEES

  • Siting: Atmospheric
  • Siting: Hydrogeologic
  • Siting: Seismic
  • Siting: General & Monitoring
  • Environmental Impact Assessment and Analysis

ESCC STANDARDS SUPPORTING NRC

  • 10 CFR 50/10 CFR 52/10 CFR 53 early site selection
  • 10 CFR 50/10 CFR 52/10 CFR 53 environmental compliance &

environmental monitoring requirements

  • Operational environmental analyses
  • Groundwater and surface water transport of tritium
  • Atmospheric transport and diffusion of hazardous releases
  • Flooding and extreme precipitation hazard design criteria
  • Seismic hazard design criteria and monitoring
  • Volcanic dust design criteria

ESCC STANDARDS SUPPORTING DOE

  • 10 CFR 851 worker safety & health requirements
  • 10 CFR 1021 NEPA requirements
  • Operational environmental analyses
  • Groundwater and surface water transport of tritium
  • Atmospheric transport and diffusion of releases
  • Seismic, flooding, extreme precipitation and volcanic dust hazard protection
  • Seismic monitoring

ESCC STANDARDS SUPPORTING DOE

  • 10 CFR 830 Facility Safety NPH determinations to ensure design adequacy
  • Extreme straight-line winds, hurricanes, tornadoes, atmospheric pressure changes (WDC)
  • Floods, tsunamis, seiches, storm surges, dam failures (FDC)
  • Extreme precipitation at dry sites (PDC)
  • Volcanic dust impacts on HVAC systems (VDC)

ESCC STANDARDS AND PROJECTS

  • ANS-2.2 - Earthquake Instrumentation Criteria for Nuclear Power Plants
  • ANS-2.3 - Estimating Tornado, Hurricane, and Extreme Straight-Line Wind Characteristics at Nuclear Facility Sites
  • ANS-2.8 - Probabilistic Evaluation of External Flood Hazards for Nuclear Facilities
  • ANS-2.6 - Guidelines for Estimating Present and Projecting Future Population Distributions Surrounding Nuclear Facility Sites
  • ANS-2.9 - Evaluation of Ground Water Supply for Nuclear Facilities

ESCC STANDARDS AND PROJECTS

  • ANS-2.10 - Criteria for the Handling & Initial Evaluation of Records from Nuclear Power Plant Seismic Instrumentation
  • ANS-2.13 - Evaluation of Surface-Water Supplies for Nuclear Power Sites
  • ANS-2.15 - Criteria for Modeling and Calculating Atmospheric Dispersion of Routine Radiological Releases from Nuclear Facilities
  • ANS-2.17 - Evaluation of Subsurface Radionuclide Transport at Commercial Nuclear Power Plants

ESCC STANDARDS AND PROJECTS

  • ANS-2.23 - Nuclear Power Plant Response to an Earthquake
  • ANS-2.26 - Categorization of Nuclear Facility Structures, Systems, and Components for Seismic Design
  • ANS-2.27 - Criteria for Investigations of Nuclear Facility Sites for Seismic Hazard Assessments
  • ANS-2.29 - Probabilistic Seismic Hazard Analysis
  • ANS-2.18 - Standard for Evaluating Radionuclide Transport in Surface Water for Nuclear Power Sites
  • ANS-2.19 - Guidelines for Establishing Site-Related Parameters for Site Selection and Design of ISFSIs (Water Pool Type)

ESCC STANDARDS AND PROJECTS

  • ANS-2.30 - Criteria for Assessing Tectonic Surface Fault Rupture and Deformation at Nuclear Facilities
  • ANS-2.34 - Characterization and Probabilistic Analysis of Volcanic Hazards
  • ANS-3.11 - Determining Meteorological Information at Nuclear Facility Sites
  • ANS-2.32 - Guidance on the Selection and Evaluation of Remediation Methods for Subsurface Contamination
  • ANS-2.35 - Estimating the Socioeconomic Impacts of Construction, Operation and Decommissioning at a Nuclear Facility
  • ANS-16.1 - Measurement of the Leachability of Solidified Low-Level Radioactive Wastes by a Short-Term Test Procedure
  • ANS-41.5 - V & V of Radiological Data for Use in Waste Management and Environment

NPH DESIGN STANDARDS

  • ANS-2.2 - Earthquake Instrumentation Criteria for Nuclear Power Plants
  • ANS-2.10 - Criteria for the Handling & Initial Evaluation of Records from Nuclear Power Plant Seismic Instrumentation
  • ANS-2.23 - Nuclear Power Plant Response to an Earthquake
  • ANS-2.26 - Categorization of Nuclear Facility Structures, Systems, and Components for Seismic Design
  • ANS-2.27 - Criteria for Investigations of Nuclear Facility Sites for Seismic Hazard Assessments
  • ANS-2.29 - Probabilistic Seismic Hazard Analysis
  • ANS-2.30 - Criteria for Assessing Tectonic Surface Fault Rupture and Deformation at Nuclear Facilities

NPH DESIGN STANDARDS

  • EXTREME WIND NPH/WIND DESIGN CATEGORIZATION
  • ANS-2.3 - Standard for Estimating Tornado, Hurricane and Extreme Straight-Line Wind Characteristics at Nuclear Facility Sites
  • FLOOD NPH/FLOOD DESIGN CATEGORIZATION
  • ANS-2.8 - Probabilistic Evaluation of External Flood Hazards for Nuclear Facilities

ANS-2.2-2020: EARTHQUAKE INSTRUMENTATION CRITERIA FOR NUCLEAR POWER PLANTS

Purpose:

To specify the minimum requirements for earthquake instrumentation. Should an earthquake occur, the instrumentation provides information on the vibratory ground motion and resultant vibratory responses of representative structures

  • Status: Reaffirmed in 2020. Reaffirm/revise decision in 2025

ANS-2.3-2021: STANDARD FOR ESTIMATING TORNADO, HURRICANE & EXTREME STRAIGHT-LINE WIND CHARACTERISTICS AT NUCLEAR FACILITY SITES

Purpose:

Establishes guidelines to estimate frequency of occurrence and magnitude of parameters associated with rare meteorological events such as tornadoes, hurricanes, and extreme straight-line winds at nuclear facility sites. Parameters addressed include: maximum translational and rotational wind speed, atmospheric pressure change, and design basis missile characteristics. Does not address forces on structures resulting from these phenomena

  • Status: Reaffirmed in 2021. WG reconstituted to revise. Evaluating relevant information from 6-yr NIST/ASCE Joplin, MO tornado study that also supported ASCE 7-22 and EPRI High Wind Manual. NRC (RG 1.76) and DOE (DOE-STD-1020-2016) will also be looking at these new technical sources

ANS-2.8-2019: PROBABILISTIC EVALUATION OF EXTERNAL FLOOD HAZARDS FOR NUCLEAR FACILITIES

Purpose:

To present criteria to establish design basis flooding for nuclear safety-related features at nuclear facilities. Describes evaluation of 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

  • Status: Addresses many flood initiators inclusive of seiches, surges, and tsunamis. Contains methodologies to perform PFHAs

ANS-2.10-2022: CRITERIA FOR THE HANDLING & INITIAL EVALUATION OF RECORDS FROM NUCLEAR POWER PLANT SEISMIC INSTRUMENTATION

Purpose:

To provide criteria for proper handling, and evaluation of seismic instrumentation records

  • Status: Reaffirmed in 2022. Endorsed by NRC in DG-1337

ANS-2.23-2020: NUCLEAR POWER PLANT RESPONSE TO AN EARTHQUAKE

Purpose:

Describes actions to take preceding and immediately following an earthquake felt at a nuclear facility to determine the need to shut the facility down and, if shutdown is required, actions to determine the facilitys readiness to restart

  • Status: Reaffirmed in 2020. Reaffirm/revise decision in 2025. Endorsed by NRC in DG-1337 with some exceptions

ANS-2.26-2021: CATEGORIZATION OF NUCLEAR FACILITY STRUCTURES, SYSTEMS, AND COMPONENTS FOR SEISMIC DESIGN

Purpose:

Provides criteria for selecting Seismic Design Category (SDC) for nuclear facility structures, systems, and components (SSCs) to achieve earthquake safety and criteria and guidelines for selecting Limit States for these SSCs to govern their seismic design. Limit States are selected to ensure desired safety performance in an earthquake

  • Status: Reaffirmed in 2021. WG re-established to develop revision. Will be addressing design categorization of all NPHs.

Harmonizing SDCs since these used in this standard are not the same as SDCs referred to in the International Building Code

ANS-2.27-2020: CRITERIA FOR INVESTIGATIONS OF NUCLEAR FACILITY SITES FOR SEISMIC HAZARD ASSESSMENTS

Purpose:

Provides criteria and guidelines for conducting geological, seismological, and geotechnical investigations needed to provide information to support seismic source characterization input to a probabilistic seismic hazard analysis (PSHA), evaluation of surface fault rupture hazard, site response analysis, and seismic-induced ground failure hazard

  • Status: Reaffirmed in 2020. Reaffirm/revise decision in 2025
  • Note: These criteria are applicable for SDC-3 thru SDC-5 SSCs.

Does not address use of PSHA results or selection of design basis events for nuclear facilities. These topics are covered in ANSI/ANS-2.26-2021 and ASCE/SEI 43-05

ANS-2.29-2020: PROBABILISTIC SEISMIC HAZARD ANALYSIS

Purpose:

Provides criteria and guidance for performing a Probabilistic Seismic Hazard Analysis (PSHA) for design and construction of nuclear facilities

  • Status: Reaffirmed in 2020. Reaffirm/revise decision in 2025

ANS-2.30-2020: CRITERIA FOR ASSESSING TECTONIC SURFACE FAULT RUPTURE AND DEFORMATION AT NUCLEAR FACILITIES

Purpose:

Provides criteria and guidelines for assessing permanent ground deformation hazard due to tectonic surface fault rupture and deformation at nuclear facilities. Provides an outline of procedures and methods for performing probabilistic fault displacement hazard analysis and probabilistic tectonic deformation hazard analysis

  • Status: Reaffirmed in 2020. Reaffirm/revise decision in 2025

ANS-2.34: CHARACTERIZATION AND PROBABILISTIC ANALYSIS OF VOLCANIC HAZARDS

Purpose:

Provides criteria and guidance for performing a Probabilistic Volcanic Hazard Analysis (PVHA) for design and construction of nuclear facilities

  • Status: In advanced stage of development. Incorporated recent INL VPHA. Likely to be issued in 2025

ANS-3.11-2020: DETERMINING METEOROLOGICAL INFORMATION AT NUCLEAR FACILITIES

Purpose:

To provide criteria for meteorological programs at nuclear installations that ensure the collection and processing of quality-assured meteorological data

  • Status: Reaffirmed in 2020. WG reconstituted to address new remote sensing instrumentation and more comprehensive turbulence criteria. Consensus achieved on ESCC ballot

DOE-STD-1020-2016 AND NPH HANDBOOK CROSSWALK DOE-STD-1020-2016 & DOE-HDBK-1220-2017 SECTIONS SUPPORTING ANS ESCC STANDARDS Section 3, Earthquakes ANS-2.2, ANS-2.10, ANS-2.23, ANS-2.26, ANS-2.27, ANS-2.29, ANS-2.30 Section 4, Extreme Winds ANS-2.3, ANS-3.11 Section 5, Floods ANS-2.8 Section 7, Extreme Precipitation ANS-2.8, ANS-3.11 Section 8, Volcanic ANS-2.34

SUMMARY

  • ANS has been developing standards for 67 years
  • ANS standards have met NTTAA objectives since 1995 saving Federal Government $M of standards development costs
  • DOE (DOE-STD-1020-2016, DOE-STD-1189-2016, DOE-STD-3009-2014, DOE-HDBK-1220-2017, DOE-HDBK-1216-2015, DOE-HDBK-1224-2024)

SUMMARY

  • ESCC develops and maintains numerous multi-media environmental and siting standards to assist private and public sectors in nuclear facility licensing, design and construction
  • Atmospheric
  • Hydrogeologic
  • Seismic
  • Volcanic
  • Environmental Monitoring
  • Environmental Impact Assessment

SUMMARY

  • ESCC develops and maintains several risk-informed performance-based (RIPB) NPH standards that support DOE standards needs
  • All required NPH design standards that complement ASCE design standards will be completed and up-to-date in 2025
  • All NPH design standards continually undergo reaffirmation or revision to maintain state-of-the-science by 21-member ESCC

QUESTIONS??

ESCC WELCOMES NEW VOLUNTEERS

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