IEM on Protection against Extreme Earthquakes and Tsunamis in the Light of the Accident at the Fukushima Daiichi NPP Vienna, Austria
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Developing New Regulatory Guidelines on Seismic Isolation of Japan - - PowerPoint PPT Presentation
IEM on Protection against Extreme Earthquakes and Tsunamis in the Light of the Accident at the Fukushima Daiichi NPP Vienna, Austria Developing New Regulatory Guidelines on Seismic Isolation of Japan and the US September 6, 2012 Japan Nuclear
IEM on Protection against Extreme Earthquakes and Tsunamis in the Light of the Accident at the Fukushima Daiichi NPP Vienna, Austria
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IEM on Protection against Extreme Earthquakes and Tsunamis in the Light of the Accident at the Fukushima Daiichi NPP Vienna, Austria
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IEM on Protection against Extreme Earthquakes and Tsunamis in the Light of the Accident at the Fukushima Daiichi NPP Vienna, Austria
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IEM on Protection against Extreme Earthquakes and Tsunamis in the Light of the Accident at the Fukushima Daiichi NPP Vienna, Austria
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IEM on Protection against Extreme Earthquakes and Tsunamis in the Light of the Accident at the Fukushima Daiichi NPP Vienna, Austria
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Location of Bearing
Power Reactor Facilities (September, 2006). ⇒ Possibility of applying seismic isolation into NPP
academia-government over the past two decades in Japan.
Base-isolated Building at K-K Site (Administration Building)
Lead Rubber Bearing Sliding Bearing
IEM on Protection against Extreme Earthquakes and Tsunamis in the Light of the Accident at the Fukushima Daiichi NPP Vienna, Austria
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FEATURES OF THE GUIDELINES
evaluation, construction and operation
address the needs of both newly constructed and existing NPPs
design for structures and equipment regardless of site condition
IEM on Protection against Extreme Earthquakes and Tsunamis in the Light of the Accident at the Fukushima Daiichi NPP Vienna, Austria
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Reactor Type Plant Situation Building Isolation Equipment Isolation Current Type Existing ○ Newly Constructed ○ ○ Next Generation Newly Constructed ○ ○
Used for horizontal motions, vertical motions, or a combination of both.
APPLICATION OF EACH TYPE OF SEISMIC ISOLATION
diesel generator
IEM on Protection against Extreme Earthquakes and Tsunamis in the Light of the Accident at the Fukushima Daiichi NPP Vienna, Austria
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DESIGN OF SEISMIC ISOLATION
Basic Requirements
Reviewing Seismic Design of Nuclear Power Reactor
− The earthquake ground motions to be formulated with and without the site specific epicenter Additional Requirements (consideration of the SI characteristics)
corresponding the natural frequencies of base isolated structures − Horizontal 2 to 5 second, Vertical 0.5 to 1 second, in general
needed (1) Requirements for Design Base Ground Motion
IEM on Protection against Extreme Earthquakes and Tsunamis in the Light of the Accident at the Fukushima Daiichi NPP Vienna, Austria
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(2) Requirements for Isolation Devices
Isolation Device Available Elements Basic Function & Requirement Isolator Rubber bearing Roller bearing Sliding bearing Supporting Function to long term vertical load of superstructure and to maintain the function under the condition of horizontal deformation caused by earthquakes Restoring Function not to lose the function against the design seismic motion and to deform up to the design allowable displacement Damper Steel rod damper Oil damper Damping Function to retain necessary damping capacity under design condition (displacement, velocity, etc 【Design of Rubber Bearing】
be used in linear range.
bearing should be appropriately determined considering the characteristics of axial force – shear force relationship which is based on testing.
shear strain
compression tension
axial stress y
tension linear limit stress ty tension-shear linear limit stress tcy compression-shear linear limit stress ccy compression linear limit stress ty
ultimate strength linear limit design area shear strain shear stress fracture linear limit shear strain
compression tension
axial stress y
tension linear limit stress ty tension-shear linear limit stress tcy compression-shear linear limit stress ccy compression linear limit stress ty
ultimate strength linear limit design area shear strain shear stress fracture linear limit
axial force shear force axial force shear force Reference: Japan Electric Association, “Technical Guidelines on Seismic Base Isolation System for Structural Safety and Design of Nuclear Power Plants”, 2001
IEM on Protection against Extreme Earthquakes and Tsunamis in the Light of the Accident at the Fukushima Daiichi NPP Vienna, Austria
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(3) Requirements for Seismic Isolation System
Design Seismic Force
Reviewing Seismic Design of Nuclear Power Reactor Facilities.
structure/component is used. Analysis Model
– demonstrate response motion unique to base-isolated structures such as rocking motion – estimate seismic force, acceleration and displacement on the isolation devices, the superstructure and the substructure
for analysis model should be; – based on tests of the devices – include the change due to environment conditions and aging. Combination of Seismic Loads
appropriate method considering the vibration characteristic of the base-isolated structures. Other Consideration
– requirements for crossover components (ref. next slide)
– wind, lightning, tsunami, flooding, fire, etc.
IEM on Protection against Extreme Earthquakes and Tsunamis in the Light of the Accident at the Fukushima Daiichi NPP Vienna, Austria
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(4) Interfaces between Base-Isolated Structures and Non-Isolated Structures
Available Measures for the Crossover Piping routing arrangement, expansion joint
Shaking table test of piping
simultaneous inputs of both horizontal and vertical vibration Base-isolated structure Fixed support Joint
Design of Crossover Component
designed and maintain required safety function against the design base earthquake with high confidence.
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(5) Combination of Loads and Allowable Limits Combination of Loads
independent or dependent events)
– The combination should comply with Regulatory Guide for Reviewing Seismic Design of Nuclear Power Reactor Facilities. (September, 2006)
Allowable Limits
appropriately determined. Following methodologies are available;
– Displacement limit based on the ultimate displacement of the critical component (isolation device, crossover component) – Displacement limit determined to make CDF and CFF satisfy the performance goal
with Regulatory Guide for Reviewing Seismic Design of Nuclear Power Reactor Facilities. (September, 2006)
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Recognition of Residual Risk
efforts must be made to reduce “residual risk” as much as possible. Evaluation Methodology
safety assessment methods, specifically, seismic PSA methodology is available.
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Pre-Operation Testing
inspection, installation, and testing of isolation devices shall be conducted
checked in advance of operation.
Regular Inspection
inspections. Inspection Before Restarting
inspection shall be conducted in order to confirm the performance of isolation devices/system. – presence of damage to isolation devices, pedestal, interfaces, etc. – current positions of superstructures
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II.3 PROSPECTS FOR APPLYING SEISMIC ISOLATION INTO NPPs
Emergency DG with Air Fin Cooler Emergency Gas Turbine
nuclear accident in order to improve the safety of NPPs. − to improve seismic capacity of equipment related to external power (Measure No.2, 3) − to enhance multiplicity and diversity of emergency AC power (Measure No.7)
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IEM on Protection against Extreme Earthquakes and Tsunamis in the Light of the Accident at the Fukushima Daiichi NPP Vienna, Austria
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IEM on Protection against Extreme Earthquakes and Tsunamis in the Light of the Accident at the Fukushima Daiichi NPP Vienna, Austria
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IEM on Protection against Extreme Earthquakes and Tsunamis in the Light of the Accident at the Fukushima Daiichi NPP Vienna, Austria
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Kammerer1, Whittaker2, and Constantinou2
1US NRC 2University of Buffalo
IEM on Protection against Extreme Earthquakes and Tsunamis in the Light of the Accident at the Fukushima Daiichi NPP Vienna, Austria
IEM on Protection against Extreme Earthquakes and Tsunamis in the Light of the Accident at the Fukushima Daiichi NPP Vienna, Austria
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IEM on Protection against Extreme Earthquakes and Tsunamis in the Light of the Accident at the Fukushima Daiichi NPP Vienna, Austria
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IEM on Protection against Extreme Earthquakes and Tsunamis in the Light of the Accident at the Fukushima Daiichi NPP Vienna, Austria
Isolators and/or Isolation system Super- structure Connections/ umbilicals Moat/Hard Stop
Hazard and Associated Risk Parameter Isolation unit and system design and performance criteria Approach to demonstrating unit performance Performance expectations
GMRS+2 Envelope
RG1.208 GMRS and the minimum foundation input motion3 for each spectral frequency No long-term change in mechanical properties. 100% confidence of the isolation system surviving without damage when subjected to the mean displacement
system under the GMRS+ loading. Production testing must be performed on each isolator for the mean system displacement under the GMRS+ loading level and corresponding axial force. Super- structure design and performance must conform to NUREG- 0800 under GMRS+ loading. Umbilical line design and performance must conform to NUREG- 0800 under GMRS+ loading. The moat is sized such that there is less than 1% probability of the superstructure contacting the moat or hard stop under GMRS+ loading. 2) 10CFR50 Appendix S requires the use of an appropriate free-field spectrum with a peak ground acceleration of no less than 0.10g at the foundation level. RG1.60 spectral shape anchored at 0.10g is often used for this purpose. 3) The analysis can be performed using a single composite spectrum or separately for the GMRS and the minimum spectrum.
IEM on Protection against Extreme Earthquakes and Tsunamis in the Light of the Accident at the Fukushima Daiichi NPP Vienna, Austria
Isolators and/or Isolation system Super- structure Connections/ umbilicals Moat/Hard Stop
Hazard and Associated Risk Parameter Isolation unit and system design and performance criteria Approach to demonstrating unit performance Performance expectations
EDB4 GMRS The envelope
motion amplitude with a mean annual frequency of exceedance of 1x10-5 and 167% of the GMRS+ spectral amplitude 90% confidence of each isolator and the isolation system surviving without loss of gravity-load capacity at the mean displacement under EDB loading. Prototype testing must be performed
number of isolators at the CHS5 displacement and the corresponding axial force to demonstrate acceptable performance with 90% confidence. Limited isolator unit damage is acceptable but load-carrying capacity must be maintained. There should be less than a 10% probability
structure contacting the moat or hard stop under EDB loading. Greater than 90% confidence that each type
umbilical line, together with its connections, remains functional for the CHS displacement. Performance can be demonstrated by testing, analysis or a combination of both.6 CHS displacement must be equal to or greater than the 90th percentile isolation system displacement under EDB loading. Moat or hard stop designed to survive impact forces associated with 95th percentile EDB isolation system displacement.7 Limited damage to the moat or hard stop is acceptable but the moat
perform its intended function.
4) The analysis can be performed using a single composite spectrum or separately for the 10-5 MAFE response spectrum and 167% GMRS. 6) SC 2 SSCs whose failure could impact the functionality of umbilical lines should also remain functional for the CHS displacement. 7) Impact velocity calculated at the displacement equal to the CHS assuming cyclic response of the isolation system for motions associated with the 95th percentile (or greater) EDB displacement.
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IEM on Protection against Extreme Earthquakes and Tsunamis in the Light of the Accident at the Fukushima Daiichi NPP Vienna, Austria
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IEM on Protection against Extreme Earthquakes and Tsunamis in the Light of the Accident at the Fukushima Daiichi NPP Vienna, Austria
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IEM on Protection against Extreme Earthquakes and Tsunamis in the Light of the Accident at the Fukushima Daiichi NPP Vienna, Austria
39 Resourced proposed from member states IAEA Technical Report
Chapter 1 Chapter 2 ・ ・ ・ Appendix A Appendix B Appendix C ・ Basic Requirements
Member state A Member state B
・ ・
Member state C
Practice specific to Member States Guidance common among Member States
December 16, 2011 39
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1.1 Purpose of Technical Report 1.2 Overview of Seismic Isolation 1.3 History of Seismic Isolation and Current Use
Seismic Isolation Systems 2.1 Applicable Facilities 2.2 Site and Seismic Conditions 2.3 Directions of Isolation 2.4 Peer Review 2.5 Definition of Technical Terms
4.1 Design Base Earthquake 4.2 Design of Isolation Device 4.2.1 Basic Elements of the Isolation Devices 4.2.2 Basic Performance Requirements for the Isolation Devices. 4.3 Design of Base-Isolated System 4.3.1 Design Concept of Base-Isolated Systems 4.3.2 Input Seismic Motion 4.3.3 Analysis Models 4.3.4 Analysis Methods 4.3.5 Allowable Limits 4.3.6 Combinations of Loads 4.3.7 Other Considerations for Design
4.4 Interfaces between Seismic Isolated Structures and Non-Seismic Isolated Structures 4.5 Considerations for Other External and Internal Events
Basis
Isolation Device 7.1 Requirements for Manufacturing Stage 7.2 Requirements for Construction Stage 7.3 Requirements for Operation Stage
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(G) ; group meeting (i.e. all member states)
(G-1) (G-2) (G-3) Final report completion (G-4) (G-3) (G-2)
ACTIVITIES 2011 2012 2013 REMARKS (Activities of the member states) 1Q 2Q 3Q 4Q 1Q 2Q 3Q 4Q 1Q 2Q 3Q 4Q Kick off meeting Activity 1: Arrangement of technical report Activity 2: Gathering resources from member states The member states provide their guidelines by the end of the 2Q, 2012 Activity 3: Integration of documents (by IAEA Experts) Activity 4: Compiling final technical report
IEM on Protection against Extreme Earthquakes and Tsunamis in the Light of the Accident at the Fukushima Daiichi NPP Vienna, Austria
Thank you for your kind attention
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IEM on Protection against Extreme Earthquakes and Tsunamis in the Light of the Accident at the Fukushima Daiichi NPP Vienna, Austria
US NRC Extra Slides
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IEM on Protection against Extreme Earthquakes and Tsunamis in the Light of the Accident at the Fukushima Daiichi NPP Vienna, Austria
Does not specify types of isolators. Provides design and review criteria to address a broad range of possible SI approaches. Specifies three types of isolators (LDR, LR, and FP) as generally appropriate and two types (synthetic rubber and high-damping rubber) as inappropriate. Does not preclude
activities to demonstrate the appropriateness
Deterministic design with design criteria provided up to DBE Performance-based with GMRS+ and EDB incorporated as part of design basis Consideration of residual risk using seismic probabilistic safety risk analysis Explicit criteria for extended-design-basis ground motions Focused on foundation isolation for new NPPs and equipment and floor isolation for existing NPPs Focuses only on foundation isolation for new NPPs, but does not preclude other uses Includes horizontal &vertical isolation Focuses on horizontal isolation Prefers time-history method and allows for modified SRSS (all maximums combined) Only allows time-domain non-linear 3D modeling most cases
IEM on Protection against Extreme Earthquakes and Tsunamis in the Light of the Accident at the Fukushima Daiichi NPP Vienna, Austria
IEM on Protection against Extreme Earthquakes and Tsunamis in the Light of the Accident at the Fukushima Daiichi NPP Vienna, Austria
IEM on Protection against Extreme Earthquakes and Tsunamis in the Light of the Accident at the Fukushima Daiichi NPP Vienna, Austria
at all times, including under extreme loading conditions
related structure
address the potential for loss of offsite power after an earthquake
isolators should be replaceable if needed
isolators; and adequate performance after the loss of one isolator unit must be demonstrated
related equipment must be developed
IEM on Protection against Extreme Earthquakes and Tsunamis in the Light of the Accident at the Fukushima Daiichi NPP Vienna, Austria
all associated structures, systems, and components
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