ANS STANDARDS TO SUPPORT DOE NPH DESIGN ANS... · • ANS-2.10 - Criteria for the Handling and...
Transcript of ANS STANDARDS TO SUPPORT DOE NPH DESIGN ANS... · • ANS-2.10 - Criteria for the Handling and...
ANS STANDARDS TO SUPPORT DOE NPH DESIGN
DOE NPH Workshop, Germantown, MD
Carl Mazzola, CFS October 22, 2014
WHY ARE STANDARDS DEVELOPED?
• Provide for safety in design and development of SSCs
• Establish best practices for conduct of operations
• Improve economy and efficiency in the design process
• Ensure quality and reliability of SSCs and processes
• Assist with regulatory compliance, guidance and oversight
STANDARDS DEVELOPMENT DRIVERS
• Legislative • PL 104-113: National Technology Transfer and Advancement
Act (1995)
• Executive • OMB Circular A-119
• NRC Management Directive 6.5
• DOE Technical Standards Project Office
WIDE RANGE OF STANDARDS USERS
• Facility Owners • Government Agencies • National Laboratories • Architect-Engineer-Constructors • Industry • Vendors • Consultants • Universities • Technical Societies • Individuals
NUCLEAR STANDARDS SDOS UNDER 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 and Automation Society (ISA)
• National Fire Protection Association (NFPA)
ANS STANDARDS DEVELOPMENT AND CONSENSUS PROCESS
*
WG established
Written comments
WG drafts standard & evaluates comments
Subcommittee reviews standard & typically votes
ANSI BSR certification
SB certifies process
Consensus Committee reviews & ballots
Public review
American National Standard
Consensus Committee concurs with
ballot resolution
ANS STANDARDS COMMITTEE STRUCTURE
Standards Board
Large Light Water
Reactors Consensus Committee
Research
& Advanced Reactors
Consensus Committee
Safety &
Radiological Analyses
Consensus Committee
Non-
Reactor Nuclear Facilities
Consensus Committee
Joint
Committee on Nuclear
Risk Management
Consensus Committee
Nuclear
Criticality Safety
Consensus Committee
Environmental
& Siting Consensus Committee
Fuel
Waste & Decommissioning
Consensus Committee
Subcommittees
Working Groups
Environmental & Siting
Carl A. Mazzola, CFS.
ANS STANDARDS CONSENSUS COMMITTEE CHAIRMEN
Fuel Waste & Decommissioning
Donald R. Eggett, AMEC AES
Joint Committee on Nuclear Risk Management (ANS/ASME)
Robert J. Budnitz (Co-Chair), LBNL Rick Grantom (Co-Chair), STPNOC
Large Light Water Reactors
William B. Reuland, Individual
Nuclear Criticality Safety
Robert D. Busch, UNM
Non-Reactor Nuclear Facilities
James O’Brien, DOE/AU-30
Safety & Radiological Analyses
Andrew O. Smetana, SRNL
Research & Advanced Reactors
George F. Flanagan, ORNL
ESCC SCOPE AND RESPONSIBILITIES
ESCC is responsible for preparation and maintenance of VCSs for all aspects of nuclear power plant and non-reactor nuclear facility siting, environmental assessment, environmental management, environmental monitoring, and categorization and evaluation of natural phenomena hazards at these public and private sector nuclear facilities
ESCC SUBCOMMITTEE LEADERSHIP
• Environmental & Impact Assessment (Kevin Bryson)
• Siting: Atmospheric (John Stevenson)
• Siting: Hydrogeologic (Yan Gao)
• Siting: Seismic (Quazi Hossain)
• Siting: Ecology (John Downing)
• Siting: General & Monitoring (Leah Parks)
Environmental Impact Assessment and Analysis Siting: Atmospheric Siting: Hydrogeologic Siting: Seismic Siting: Ecology Siting: General & Monitoring
Kevin Bryson (Chair)
John Stevenson (Chair)
Yan Gao (Chair)
Quazi Hossain (Chair)
John Downing (Chair)
Leah Parks (Chair)
0 Current Standard 3 Current Standards 1 Current Standard 4 Current Standards 0 Current Standards 2 Current Standards
1 Project 3 Projects 6 Projects 4 Projects 6 Projects 3 Projects 18.2.1-(NEW) Methods for Inferring Environmental Doses
2.3-2011 Estimating Tornado, Hurricane, and Extreme Straight Line Wind Characteristics at Nuclear Facility Sites App'd 4/22/2011
2.8-(W2002) Determine External Flood Hazards for Nuclear Facilities
2.2-(W2012) Earthquake Instrumentation Criteria for Nuclear Power Plants
2.25-(W1999) Surveys of Terrestrial Ecology Needed to License Thermal Power Plants
2.6-(NEW) Guidelines for Estimating Present & Forecasting Future Population Distributions Surrounding Power Reactor Sites
2.15-2013 Criteria for Modeling and Calculating Atmospheric Dispersion of Routine Radiological Releases from Nuclear Facilities App'd 2/27/2013
2.9-(W2000) Evaluation of Ground Water Supply for Nuclear Facilities
2.10-(W2013) Criteria for the Handling and Initial Evaluation of Records from Nuclear Power Plant Seismic Instrumentation
18.3.1-(NEW) Entrainment: Guide to Steam Electric Power Plant Cooling System Siting, Design and Operation for Controlling Damage to Aquatic Organisms
2.22-(NEW) Environmental Radiological Monitoring at Nuclear Facilities
2.16-(NEW) Criteria for Modeling Design-Basis Accidental Releases From Nuclear Facilities
2.19-(W1999) Guidelines for Establishing Site-Related Parameters for Site Selection and Design of ISFSIs (Water Pool Type)
2.11-(W1999) Guidelines for Evaluating Site-Related Geotechnical Parameters at Nuclear Power Sites
18.3.2-(NEW) Cold Shock: Guide to Steam Electric Power Plant Cooling System Siting, Design and Operation for Controlling Damage to Aquatic Organisms
3.11-2005;R2010 Determining Meteorological Information at Nuclear Facility Sites RF 12/23/2010
2.21-2012 Criteria for Assessing Atmospheric Effects on the Ultimate Heat Sink App'd 6/5/2012
2.13-(W1998) Evaluation of Surface-Water Supplies for Nuclear Power Sites
2.23-2002 (R2009) Nuclear Plant Response to an Earthquake RF 6/15/2009
18.3.3-(NEW) Entrapment/Impingement: Guide to Steam Electric Power Plant Cooling System Siting, Design and Operation for Controlling Damage to Aquatic Organisms at Water Intake Structures
16.1-2003;R2008 Measurement of the Leachability of Solidified Low-Level Radioactive Wastes by a Short-Term Test Procedure RF 8/4/2008
2.31-(NEW) Estimating Extreme Precipitation at Nuclear Facility Sites
2.17-2010 Evaluation of Subsurface Radionuclide Transport at Commercial Nuclear Power Plants App'd 12/23/2010
2.26-2004 (R2010) Categorization of Nuclear Facility Structures, Systems, and Components for Seismic Design RF 5/27/2010
18.4-(NEW) Aquatic Ecological Surveys Required for Siting, Design, and Operation of Thermal Power Plants
18.7-(NEW) Control and Monitoring of the Discharge of Chemicals
3.8.10-(NEW) Criteria for Modeling Real-Time Accidental Release Consequences at Nuclear Facilities
2.18-(NEW) Standards for Evaluating Radionuclide Transport in Surface Water for Nuclear Power Sites
2.27-2008 Criteria for Investigations of Nuclear Facility Sites for Seismic Hazard Assessments App'd 7/31/2008
18.6-(NEW) Discharge of Thermal Effluents into Surface Waters
2.32 (NEW) Guidance on the Selection and Evaluation of Remediation Methods for Subsurface Contamination
2.29-2008 Probabilistic Seismic Hazard Analysis App'd 7/31/2008
2.30-(NEW) Criteria for Assessing Tectonic Surface Fault Rupture and Deformation at Nuclear Facilities
ESCC STANDARDS SUPPORT NRC AND DOE OVERSIGHT
• 10 CFR 50 and 10 CFR 52 early site selection • 10 CFR 50 and 10 CFR 52 environmental compliance and monitoring
requirements • 10 CFR 51 and 10 CFR 1021 NEPA requirements (e.g., EIS, EA) • Operational environmental concerns
• Groundwater transport of tritium
• Atmospheric transport and diffusion
• Protection from flooding hazards
• Risk-informed NPH determinations to ensure design adequacy • Earthquakes
• Extreme straight-line winds, hurricanes, tornadoes
• Floods, tsunamis, seiches, storm surges, dam failures
• Extreme precipitation
ESCC STANDARDS AND ACTIVE 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 – Determination of External Flood Hazards for Nuclear Facilities
• ANS-2.9 - Evaluation of Ground Water Supply for Nuclear Facilities
• ANS-2.10 - Criteria for the Handling and Initial Evaluation of Records from Nuclear Power Plant Seismic Instrumentation
• ANS-2.15 - Criteria for Modeling and Calculating Atmospheric Dispersion of Routine Radiological Releases from Nuclear Facilities
• ANS-2.16 - Criteria for Modeling Design-Basis Accidental Releases From Nuclear Facilities
• ANS-2.17 - Evaluation of Subsurface Radionuclide Transport at Commercial Nuclear Power Plants
• ANS-2.21 - Criteria for Assessing Atmospheric Effects on the Ultimate Heat Sink
ESCC STANDARDS AND ACTIVE PROJECTS (CONTINUED)
• ANS-2.22 – Environmental Monitoring at Nuclear Facilities
• ANS-2.23 - Nuclear 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 - Assessing Capability for Surface Faulting at Nuclear Facilities
• ANS-2.31 - Estimating Extreme Precipitation at Nuclear Facility Sites
• ANS-3.8.10 - Criteria for Modeling Real-Time Accidental Release Consequences at Nuclear Facilities
• ANS-3.11 - Determining Meteorological Information at Nuclear Facility Sites
• ANS-16.1 - Measurement of the Leachability of Solidified Low-Level Radioactive Wastes by a Short-Term Test Procedure
RISK-INFORMED NPH STANDARDS • EARTHQUAKE HAZARDS/SEISMIC DESIGN
• 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 - Assessing Capability for Surface Faulting at Nuclear Facilities
• EXTREME WIND HAZARDS • ANS-2.3 - Standard for Estimating Tornado, Hurricane and Extreme
Straight-Line Wind Characteristics at Nuclear Facility Sites
• FLOODING HAZARDS • ANS-2.8 – Determination of External Flood Hazards for Nuclear Facilities
• ANS-2.31 - Standard for Estimating Extreme Precipitation at Nuclear Facility Sites
ANS-2.3-2011: 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 within CONUS. 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.
• WG Members: John Stevenson (Chairman), Mo Amin, Antonio Godoy, Tom Grazulis, Brad Harvey, Quazi Hossain, Carl Mazzola, Jim McDonald, Emil Simiu.
• Regulatory Applications: NRC RG 1.76, NRC RG 1.221, DOE-STD-1020-2012, DOE G 420.1-2.
• Status: Issued in April 2011. WG being reconstituted to determine reaffirmation or revision prior to April 2016 sunset.
ANS-2.8-201X: DETERMINATION OF EXTERNAL FLOOD HAZARDS FOR NUCLEAR FACILITIES
• Purpose: Presents criteria to establish design basis flooding for nuclear safety-
related features at nuclear facilities. 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.
• WG Members: Yan Gao (Chair), Marty McCann; Ray Schneider, Ray Rishel, Robert; Quazi Hossain, Joe Hunt, Joe Kanney, Victoria Lawrence, Gerry Meyers, Vasily Titov; Greg Lowe, David Finnicum, Jery Stedinger, Philip Watts.
• Regulatory Applications: NRC RG 1.59, DOE-STD-1020-2012, DOE G 420.1-2.
• Status: Draft revision of 1992 standard, inclusive of tsunamis, to ESCC by November 2014. Targeting mid-2015 for issuance.
ANS-2.26-2004(R2010): 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.
Note: SDCs used in this standard are not the same as SDCs referred to in the International Building Code (IBC).
• WG Members: Neil Brown (Chairman), S. Additon, Haresh Chander, D. Guzy, A. Hadjian, Quazi Hossain, C. Morrell, Andrew Persinko, Howard Shaffer, John Stevenson, C. Vaughan.
• Regulatory Applications: DOE-STD-1020-2012, DOE G 420.1-2, DOE-STD-1189-2008.
• Status: In reaffirmation/revision review process.
ANS-2.27-2008: 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.
Note: These criteria are applicable for SDC-3, SDC-4, and SDC-5 SSCs.
Note: This standard does not address use of PSHA results or selection of design basis events for nuclear facilities. These topics are covered in ANSI/ANS-2.26-2004(R2010) and ASCE/SEI 43-05.
• WG Members: Kathryn Hanson (Chair), William Lettis , J. Ake, J-C. Chen, C. Costantino, C. Crouse, J. Egan, Jeff Kimball, J. King, R. Lee, Y. Li, Joe Litehiser, W. Savage, D. Schwartz, M. Shah, P. Thenhaus.
• Regulatory Applications: DOE-STD-1020-2012, DOE G 420.1-2, DOE-STD-1189-2008.
• Status: In reaffirmation/revision review process.
ANS-2.29-2008: PROBABILISTIC SEISMIC HAZARD ANALYSIS
• Purpose: Provides criteria and guidance for performing a Probabilistic Seismic Hazard Analysis (PSHA) for design and construction of nuclear facilities.
• WG Members: Jean Savy (Chairman), J. Ake, K. Campbell, N. Chokshi, K. Coppersmith, C. Costantino, C. Crouse, A. Hadjian, Quasi Hossain, Jeff Kimball, J. King, R. Lee, Marty McCann, M. Power, G. Toro, Ivan Wong, R. Young.
• Regulatory Applications: DOE-STD-1020-2012, DOE G 420.1-2, DOE-STD-1189-2008.
• Status: In reaffirmation/revision review process.
ANS-2.30-201X: ASSESSING CAPABILITY FOR SURFACE FAULTING 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.
• WG Members: Ivan Wong, W. Bryant, Richard Chen, K. Kelson, Jeff Kimball, Joe Litehiser, S. Olig, D. Schwartz, A. Stieve, D. Wells.
• Regulatory Applications: RG 1.29, DOE-STD-1020-2012, DOE G 420.1-2.
• Status: Draft in ESCC and JCNRM (risk-informed review only) consensus review. Targeting early-2015 for issuance.
ANS-2.31-201X: STANDARD FOR ESTIMATING EXTREME PRECIPITATION AT NUCLEAR FACILITY SITES
• Purpose: To establish guidelines to estimate occurrence frequency and
magnitude of parameters associated with extreme precipitation events at nuclear facility sites within contiguous United States.
• WG Members: John Stevenson (Chairman), Brad Harvey, Walt Schalk, Quazi Hossain, Carl Mazzola, Joe Kanney, Wesley Wu, Yonas Kinfu, Matt Carney, Steve Weinbeck.
• Regulatory Applications: NUREG-0800 Section 2.3, DOE-STD-1020, DOE G 420.1-2.
• Status: WG Revision 5 under review, to ESCC by November 2014. Targeting mid-2015 for issuance.
DOE-STD-1020-2012 AND NPH HANDBOOK CROSSWALK
DOE-STD-1020-2012 & NPH HANDBOOK
SUPPORTING ESCC STANDARDS
Chapter 3, Earthquakes ANS-2.26, ANS-2.27, ANS-2.29
Chapter 4, Extreme Winds ANS-2.3
Chapter 5, Floods ANS-2.8
Chapter 7, Extreme Precipitation ANS-2.31
SUMMARY
• ANS has been developing consensus standards for more than 50 years and consistently meets NTTAA objectives saving Federal Government millions of dollars of standards development costs
• Nuclear Regulatory Commission
• Department of Energy
SUMMARY (CONTINUED)
• 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
• Ecological
• Environmental Monitoring
SUMMARY (CONTINUED)
• ESCC develops and maintains several risk-informed NPH standards that support DOE-STD-1020-2012 and DOE-STD-1189-2008 needs • All required NPH design standards will be available
by mid-2015
• Seismic design standards will soon undergo reaffirmation or revision
• Extreme wind design standard will soon be evaluated for reaffirmation or revision prior to its April 2016 sunset