Draft Details
- General requirements for seismic design and qu...
- DRAFT STANDARD
- Legal Notice for Draft Standards
- Preface
- + 1 Scope
- 1.1 General
- 1.2 Application
- 1.3 Seismic hazard level for NPPs
- 1.4 Application to other nuclear facilities
- 1.5 Terminology
- 1.6 Terminology – “shall consider”
- 2 Reference publications
- + 3 Definitions and abbreviations
- 3.1 Definitions
- 3.2 Abbreviations
- + 4 Application of the CSA N289 series of Standar...
- 4.1 General
- 4.2 Application
- 4.3 Other standards and specifications
- + 5 General seismic requirements
- 5.1 General
- + 5.2 Seismic classification
- 5.2.1 General
- + 5.2.2 Safety functions
- 5.2.2.1 Seismically qualified SSCs
- 5.2.2.2 Nonseismically qualified SSCs
- 5.2.2.3 Seismic Interaction
- 5.2.3 Basis for seismic categorization
- + 5.2.4 Earthquake level
- 5.2.4.1 Design levels of earthquake
- 5.2.4.2 Beyond design basis earthquake
- + 5.2.5 Selection of seismic category and earthqu...
- 5.2.5.1 Development of a seismic classification...
- 5.2.5.2 Development of seismic categories
- 5.2.5.3 Determining seismic category for SSCs
- + 5.2.6 Application of seismic ground motion to e...
- 5.2.6.1 Seismic demand
- 5.2.6.2 Ground motion representation
- 5.2.6.3 Re-assessment of existing NPP seismic c...
- 5.2.7 Load combinations
- + 5.3 Seismic qualification
- + 5.3.1 General
- 5.3.1.1 Introduction
- 5.3.1.2 Methods of qualification
- 5.3.1.3 Alternative approaches
- 5.3.1.4 Commercially available items
- 5.3.1.5 Inherent seismic ruggedness
- 5.3.1.6 Application of seismic loads on pressur...
- 5.3.2 Seismic qualification by analysis
- 5.3.3 Seismic qualification by testing
- 5.3.4 Seismic qualification by combined analysi...
- 5.3.5 Seismic qualification by similarity
- 5.3.6 Use of Earthquake experience approach
- 5.3.7 Maintaining seismic qualification
- + 5.3.8 Design modifications of seismically quali...
- 5.3.8.1 Screening
- 5.3.8.2 Requalification approaches
- 5.3.8.3 New work and modifications
- 5.3.9 Readiness for beyond design basis seismic...
- + 5.4 Seismic evaluation of plants
- + 5.4.1 General
- 5.4.1.1 Basis for determination of seismic capa...
- + 5.4.1.2 Seismic evaluation of existing NPP SSCs...
- 5.4.1.2.1 General
- 5.4.1.2.2 SSCs not designed to N289.3
- 5.4.1.2.3 Use of earlier editions of standards
- 5.4.1.3 SSCs necessary for safety functions
- 5.4.2 Seismic demand
- 5.4.3 Seismic capacity evaluation
- 5.4.4 Special requirements
- 5.4.5 Seismic margin assessment (SMA) methodolo...
- 5.4.6 Seismic probabilistic safety assessment (...
- + 6 Responsibilities and duties
- 6.1 Nuclear power plant operating organization
- 6.2 Manufacturer of nuclear power plant equipme...
- + 6.3 Architect/engineer of nuclear power plant s...
- 6.3.1 General
- 6.3.2 Qualification of seismic capability engin...
- 6.4 Installer of nuclear power plant systems an...
- + 6.5 Operator response to seismic events
- 6.5.1 Post-seismic plant operations manual
- 6.5.2 Assessment of seismic shaking level
- 6.5.3 Immediate response
- 6.5.4 Earthquake notifications
- 6.5.5 Continued successful operation
- + 6.5.6 Post-seismic recovery
- 6.5.6.1 Engineering report
- + 6.5.6.2 Assessment of earthquake effects
- 6.5.6.2.1 Assessment of damage
- 6.5.6.2.2 Determine seismic design basis exceed...
- 6.5.6.3 Use of earthquake records
- 6.5.6.4 Exceedance of design basis
- + 6.5.7 Required operator actions
- + 6.5.7.1 While online
- 6.5.7.1.1 Stabilization of the plant
- 6.5.7.1.2 Continued operation
- 6.5.7.2 Prior to shutdown
- 6.5.7.3 While shut down
- 6.5.7.4 Start-up
- 6.5.7.5 Walkdowns
- 6.5.7.6 Procedures
- 6.5.7.7 Reporting
- 6.6 Documentation
- 7 Quality assurance
- Annex A (Informative)
- + Annex B (Informative)
- B.1 General
- + B.2 Uniform hazard spectrum (UHS)
- B.2.1 General
- B.2.2 Characteristics of UHS
- B.2.3 Modifying UHS
- + B.3 Use of CAV in determining effects of earthq...
- B.3.1 Ground acceleration vs potential damage
- B.3.2 Ground velocity vs potential damage
- B.3.3 CAV vs lower bound magnitude cut-off leve...
- B.4 Peak ground velocity
- B.5 Ground motion uncertainty factors
- + B.6 UHS high-frequency effects
- B.6.1 De-aggregation into separate ground motio...
- B.6.2 Low vs high fundamental frequencies
- B.7 Site response analysis
- + B.8 Seismic wave incoherence effects on foundat...
- B.8.1 Factors affecting incoherence
- B.8.2 Coherency functions
- B.8.3 Soil-structure interaction and ground mot...
- B.9 Effect of limited inelastic behaviour on hi...
- B. 10 High Frequency Seismic Inelastic Effects...
- + Annex C (Informative)
- C.1 General
- + C.2 Seismic probabilistic safety assessment (SP...
- C.2.1 Conducting a SPSA
- C.2.2 Principal products of a SPSA
- C.2.3 Flowchart of a sample SPSA
- + C.3 Seismic margin assessment (SMA)
- C.3.1 General
- + C.3.2 SMA methods
- C.3.2.1 General
- C.3.2.2 EPRI SMA method
- C.3.2.3 NRC SMA method
- C.3.2.4 PSA-based SMA method
- C.3.3 Checking/review level earthquake selectio...
- C.3.4 SMA products
- C.3.5 Additional information on SMA methodologi...
- + C.4 Major SMA and SPSA elements
- + C.4.1 Seismic walkdowns
- C.4.1.1 Objectives of seismic walkdown
- C.4.1.2 Skills of seismic walkdown team
- C.4.1.3 Formation of a seismic walkdown team
- C.4.1.4 Focus of seismic walkdown
- C.4.1.5 Walkdown procedures
- C.4.1.6 SSCs that are not accessible
- C.4.1.7 Use of a single representative componen...
- C.4.1.8 Additional seismic capacity evaluation ...
- C.4.2 Seismic response analysis
- + C.4.3 Seismic capacity analysis
- C.4.3.1 General
- + C.4.3.2 Fragility analysis method
- C.4.3.2.1 General
- C.4.3.2.2 Objective of fragility evaluation
- C.4.3.2.3 Component failure modes
- C.4.3.2.4 Structure failure modes
- C.4.3.2.5 Sources for estimating response and c...
- C.4.3.2.6 Key variables for fragility analysis
- C.4.3.3 CDFM method
- + C.4.3.4 Generic seismic capacities
- C.4.3.4.1 Sources of generic seismic capacity d...
- C.4.3.4.2 U.S. Testing facilities
- C.4.3.4.3 Applicability to CANDU-specific equip...
- C.5 Peer review
- + C.6 Multiple hazard interaction
- Figure C.2
- Figure C.3
- Table C.1
- + Annex D (Informative)
- D.1 General
- + D.2 Seismic capacity evaluation
- D.2.1 General
- D.2.2 Application of experience-based screening...
- + D.2.3 Qualification by experience database meth...
- D.2.3.1 [need title]
- D.2.3.2 [need title]
- + D.2.4 Seismic technical evaluation of replaceme...
- D.2.4.1 Application
- D.2.4.2 Screening process
- + D.2.5 Generic implementation procedure (GIP)
- D.2.5.1 Evaluation using GIP
- D.2.5.2 GIP evaluation team
- D.2.5.3 Identification of safe shutdown equipme...
- D.2.5.4 Verification of the screening of the ev...
- D.2.5.5 Outliers
- D.2.6 Conservative deterministic failure margin...
- D.2.7 Fragility analysis method
- D.3 Limitations of experience-based methods
- D.4 Qualification by similarity
- D.5 Qualification based on industry test databa...
- D.6 EPRI′s high-frequency test program
- D.7 Qualification of inherently rugged equipmen...
- D.8 Documentation of qualification based on exp...
- + Annex E (Informative)
- + E.1 General
- E.1.1 Scope
- E.1.2 Impairment of nearby SSCs
- + E.2 Civil structures
- E.2.1 Unreinforced masonry walls (URMs)
- E.2.2 Control room ceilings
- E.2.3 Reactor building
- E.2.4 Powerhouse and service buildings
- E.2.5 Ancillary buildings
- E.2.6 Foundations
- E.2.7 Anchorage
- + E.3 Mechanical equipment
- E.3.1 Tanks and heat exchangers
- E.3.2 Anchorage and support
- E.3.3 Fire suppression systems
- E.3.4 Brittle, non-ductile materials
- E.3.5 Valves
- E.3.6 Threaded connections and Victaulic-type c...
- E.3.7 Seismic anchor motions
- E.3.8 Welded steel piping supported vertically ...
- E.3.9 Vibration isolator displacements
- E.3.10 Earthquake damage to HVAC ducts
- + E.4 Electrical equipment
- E.4.1 Base anchorage and top bracing
- E.4.2 Separation of adjacent panels, cabinets, ...
- E.4.3 Slack in cables
- E.4.4 Suspended electrical raceways
- E.4.5 Batteries
- E.4.6 Anchoring heavy batteries and transformer...
- E.4.7 Protection of seismically qualified power...
- E.4.8 Combined analysis and testing method
- + E.5 Instrumentation and control equipment
- E.5.1 Relays
- E.5.2 Supports for equipment
- E.5.3 Avoiding instrument air loss
- E.6 Response of unanchored components to seismi...
- + Annex F (Informative)
- F.1 General
- + F.2 Readiness for beyond design basis seismic e...
- + F.2.1 Strengthening reactor defence in depth
- F.2.1.1 Effectiveness of existing design
- + F.2.1.2 Practices for strengthening defense in ...
- F.2.1.2.1 Assessment of site-specific seismic h...
- F.2.1.2.2 Periodic evaluation of seismic hazard...
- F.2.1.3 Continuous improvement of modelling cap...
- + F.2.2 Equipment response and margin factor
- F.2.2.1 Equipment for management of severe acci...
- + F.2.2.2 Minimum margin factor
- F.2.2.2.1 Minimum margin factor for new plants
- F.2.2.2.2 Minimum margin factor for existing pl...
- F.2.2.3 Minimum margin factor for new SSCs qual...
- + F.3 Design extension condition (DEC) for seismi...
- F.3.1 General
- F.3.2 SSCs credited for BDBE
- + F.4 Application for seismic input other than DB...
- F.4.1 General
- + F.4.2 Acceptance criteria
- F.4.2.1 Primary principle
- F.4.2.2 Basic safety functions of safety-relate...
- F.4.2.3 Basic safety functions of safety-relate...
1.1 General
This Standard sets forth the general requirements for seismic design and qualification of nuclear power plants (NPPs).
Note: This Standard also provides guidance for preparing a seismic qualification governance document (see Clause 5.3.7).
1.2 Application
This Standard applies to all structures, systems, and components (SSCs) of NPPs requiring seismic qualification based on nuclear safety considerations (see Annex A). This Standard may also be applied to other SSCs, as deemed appropriate by the operating organization or by the authority having jurisdiction (AHJ) such as the Canadian Nuclear Safety Commission (CNSC).
1.3 Seismic hazard level for NPPs
This Standard was developed for NPPs in regions of low to moderate seismic hazard, comparable to the levels near Canada’s existing NPPs. In regions of higher seismic hazard, the engineering required for reliable design under strong earthquake shaking is more complex, and is beyond the scope of this Standard. Therefore, while the provisions of this Standard can be applied to any NPP site, additional provisions can be required for high seismic hazard sites.
1.4 Application to other nuclear facilities
This Standard may be applied, as appropriate, to nuclear facilities under the jurisdiction of the Nuclear Safety and Control Act.
1.5 Terminology
In this Standard, “shall” is used to express a requirement, i.e., a provision that the user is obliged to satisfy in order to comply with the standard; “should” is used to express a recommendation or that which is advised but not required; and “may” is used to express an option or that which is permissible within the limits of the standard.
Notes accompanying clauses do not include requirements or alternative requirements; the purpose of a note accompanying a clause is to separate from the text explanatory or informative material.
Notes to tables and figures are considered part of the table or figure and may be written as requirements.
Annexes are designated normative (mandatory) or informative (nonmandatory) to define their application.
1.6 Terminology – “shall consider”
In this Standard, “shall be considered” or “shall consider” means that the user evaluates the impact and documents any decisions.
You may comment on any section of this document by clicking the “Submit Comment” link at the bottom of the relevant section.