Overview of Seismic Isolation of Nuclear Power Plants
Jenna Wong PhD Candidate UC Berkeley
PEER Annual Meeting October 26, 2012 Outline n Motivation n Nuclear Power Plant (NPP) Background n Seismic Isolation Background n Analysis n Conclusions and Future Research Motivation n US Energy Sector
n Increased Energy Demand and Environmental Concerns n Potential for Nuclear Power Renaissance n Policy Perspective: Goal is to ensure the safety and security of nuclear power plants (NPPs) n Engineers: Improve design to address concerns likely to be raised in the licensing process n Seismic Isolation can be reliable means of improving seismic safety Motivation – PEER Project n Long-term project sponsored by: n Electric Power Research Institute (EPRI)
n Korean Electric Power Corporation (KEPCO) n Goal
n To understand the viability of seismic isolation in NPPs using Performance Based Design methodologies n Pilot Studies
n Background Information
n Preliminary Analysis Nuclear Power Plant Background
n February 2012: 1st Nuclear Reactor Construction Permit in 35 Years
n Changes in licensing and development of NPPs since the 1970s
n 114 reactors in use
today (NRC, 2011) Behavior of Building Structure Base Isolationwith BaseBackground Isolation System
Conventional Structure Base-Isolated Structure (Symans)
n Introduction ofInstructional laterally Material Complementing FEMA 451, Design flexible Examples Seismic Isolation layer15 - 7- 7 between structure and foundation
n Structure moves as a rigid body supported by bearings Base Isolation Background n Period Shift: T = 2π(M/K)1/2 n Balance between SA and SD (design of isolation gap) n Higher mode contributions are nearly zero for ideal case
(DIS, 2010) Elastomeric Bearings n Laminated rubber layers and steel shims
n Damping: 2-20%
n Can achieve shear strains above 200%
n Types n Low Damping Rubber Bearings (LDRB)
n Lead Plug Rubber Bearings (LPRB)
n High Damping Rubber
(DIS, 2010) Bearings (HDRB)
3 Multi-Stage Friction Pendulum Bearings
In this chapter, common types of friction pendulum (FP) bearings currently available in the United States are summarized, including mechanical characteristics, analytical models, and important considerations for design. Multi-stage FP bearings are defined as those 3 Multi-Stage Frictioncharacterized Pendulum by more than Bearings one pendulum mechanism. Emphasis is placed herein on multi- stage FP bearings since there is scant documentation on these devices in the available literature, and investigations into their modeling and behavior serve as the basis for several In this chapter, common types of friction pendulum (FP) bearings currently available of the studies contained in this report. in the United States are summarized, including mechanical characteristics, analytical models, and important considerations for design.3.1 Multi-stage Single-Pendulum FP bearings Bearings are defined as those
characterized by more than one pendulum mechanTheism. single-concave Emphasis is placed friction herein pendulum on multi- bearing is the original Friction Pendulum stage FP bearings since there is scant System documentation described on by thes Zayase devices et al. [1987] in the and available represents the first manufactured sliding-bearing literature, and investigations into their modelito makeng anduse ofbehavior the pendulum serve as conc theept. basis This for bearing several consists of an articulated slider resting on of the studies contained in this report. a concave spherical surface. The slider is coated with a woven PTFE (polytetrafluoroethylene) composite liner, and the spherical surface is overlain by polished 3.1 Single-Pendulum Bearings Friction Bearings stainless steel. A picture showing an FP bearing and a cross-section is shown in Figure 3-1, The single-concave friction pendulum bearing is the original Friction Pendulum indicating the above-described components. n Pendulum-likeSystem described by Zayas restoring et al. [1987] and represents the first manufactured sliding-bearing forceto make use of the pendulum concept. This bearing consists of an articulated slider resting on a concave spherical surface. The slider is coated with a woven PTFE Spherical concave surface n Lining materials with friction(polytetrafluoroethylene) coefficients composite from liner, and the spherical surface is overlain by polished stainless steel. A picture showing an FP bearing and a cross-section is shown in Figure 3-1, 1% indicatingto more the above-described than 20% components. Articulated slider n Period independent of structure’s weight: Figure 3-1: Photo (left) and section (right) of a typical FP bearing Spherical concave surface T = 2π(R/g)1/2 n Types 19 Articulated slider • Single, Double and Triple
Pendulum Friction Bearings (Morgan, 2011) Figure 3-1: Photo (left) and section (right) of a typical FP bearing
19 Isolation Applications
n Structures n Bridges
n Off-shore Oil Platforms n LNG Tanks
n Port Cranes
n NPPs (Earthquake Protection) NPP Isolation - Koeberg
n Design by Framatome
n Built in 1976 in Koeberg, South Africa
n First Seismically Isolated Nuclear Power Plant
n Twin 900 MWe PWR Units Koeberg n Site Conditions$23G39I+6JJ n PGA = 0.6g n Bearing Details
n 900 Isolators per Reactor <>?+/A'3DK%#'I-2883"+A%#3-# n Neoprene Pads and Sliders
n 5% critical damping
n 2 in. displacement at point of sliding
n µ = 0.18 (Labbe)
!"# $%"&'(%)%*'+,-#.+/01.+2-+/3'"1'4+/%53#0+25+67483%9+,-"#%88%#'2-"+:+;6?+@29*"&2A+2-+/3'"1'4+,"28%#'2-+25+67483%9+?%4'8'#'3"+:+BCDBE+62F31G39+BH!H Koeberg - Construction
(Spie Batignolles) n Pre-fabricated units n Each unit weighed approximately 4 tons n 20-60 units installed per day n Horizontality of unit carefully checked throughout production and installation process NPP Isolation - Cruas
n Design by Framatome n Built in 1978 in Cruas, France
n (4) 900 MWe PWR Units NPP Isolation - Cruas
n Site Conditions n Bearing Details n PGA = 0.3g n 900 Isolators per Reactor n Neoprene Pads
n 5% Critical Damping Cruas
(Labbe) Other Isolated Nuclear Facilities 408 M. Hashimoto et al. / Fusion Engineering and Design 41 (1998) 407–414
Fig. 1. Partial isolated building (East–West section).(Hashimoto) (CEA) partial seismic isolation was selected (Fig. 1). In study considering the Ministry of International this case the tokamakn building pit, in which the Trade and Industries (MITI) Notification No. 501 tokamak machine and itsITER ancillary systems and are and Jules the seismic design Horowitz criteria of the Japan Elec- Reactor installed, will be supported on horizontally com- tric Association (JEAG 4601). Stresses at various pliant seismic isolators whichn reduce Low the earth- Dampingpoints are analyzed Elastomer by using the computer pro- Bearings quake acceleration (from 0.4 to 0.2 g). However, gram SAP-V. The displacement and the accelera- the relative motion between the unisolated and tion are combined to the operational loading of isolated parts of the buildingn will Under be relatively Constructioneach representative service. in France large, from 5 to 15 cm in any horizontal direction For the normal busbars and the HVAC ducts, and from 1 to 2 cm vertically, depending on the special expansion joints are investigated from the characteristics of the isolators. Pipes, busbars, first. For the mechanical rail for remote handling cables, HVAC ducts, mechanical rails and other transporter, a special adjusting mechanism is services must cross the boundary from the non- investigated. isolated part of the building to the isolated struc- ture (subsequently referred to as the seismic gap) absorbing the relative motion and withstanding 2. Design solutions for tokamak services crossing the inertia force. Therefore, in order to realize this the seismic gap partial seismic isolation method, a feasibility of layout of these services across the seismic gap The ITER tokamak building is actually a clus- must be shown ensuring their integrity during ter of buildings around a central tokamak crane earthquake. hall and deeply embedded cylindrical pit. The In order to reduce the effect caused by the large seismic gap has been set at 1 m clearance based on displacement, some piping elements, such as U construction access requirements to allow for dis- type routings, longer straight pipes, coil springs placements during design basis ground motion and velocity proportional type oil dampers, are and for construction access (Fig. 1). There are installed considering minimum space and cost ac- many individual service lines, cables, bus bars and cording to the results of analyses. With the analy- components which must cross the seismic gap. sis method, a conventional one is used in this Table 1 summarizes the generic items crossing the NRC Regulations
n Types of Isolators
n Low Damping Rubber Bearing n Lead Rubber Bearing
n Friction Pendulum Bearing
n High Damping Rubber Bearings? n Problems with scragging and unpredictable changes in properties
n 90%< confidence in the survival of the isolation system
n Limited moat damage or potential for hard stop
DRAFT FOR COMMENT
Table 8-1. Performance and design expectations for seismically isolated nuclear power plants1 Isolation system Superstructure Umbilical line Isolation unit and Approach to demonstrating Moat or hard stop design Ground motion design and design and system design and acceptable performance of and performance levels performance performance performance criteria isolator unit
2 No long-term change in GMRS+ mechanical properties. Umbilical line The envelope of Production testing must be The superstructure The moat is sized such that 100% confidence of the design and the RG1.208 performed on each isolator design and there is less than 1% isolation system surviving performance must GMRS and the for the mean system performance must probability of the without damage when conform to minimum displacement under the conform to NUREG- superstructure contacting the subjected to the mean NUREG-0800 foundation input GMRS+ loading level and 0800 under GMRS+ moat or hard stop under 3 displacement of the under GMRS+ motion for each corresponding axial force. loading. GMRS+ loading. isolator system under the loading. spectral frequency GMRS+ loading.
Greater than 90% CHS displacement must be confidence that equal to or greater than the 4 Prototype testing must be EDB GMRS each type of safety- 90th percentile isolation performed on a sufficient related umbilical system displacement under The envelope of 90% confidence of each number of isolators at the There should be less 5 line, together with EDB loading. the ground motion isolator and the isolation CHS displacement and the than a 10% its connections, amplitude with a system surviving without corresponding axial force to probability of the Moat or hard stop designed to remains functional mean annual loss of gravity-load demonstrate acceptable superstructure survive impact forces for the CHS frequency of capacity at the mean performance with 90% contacting the moat associated with 95th percentile displacement. exceedance of displacement under EDB confidence. Limited isolator or hard stop under EDB isolation system -5 Performance can 7 1x10 and 167% loading. unit damage is acceptable EDB loading. displacement. Limited be demonstrated of the GMRS+ but load-carrying capacity damage to the moat or hard by testing, analysis spectral amplitude must be maintained. stop is acceptable but the or a combination of 6 moat or hard stop must both. perform its intended function.
1. Analysis and design of safety-related components and systems should conform to NUREG-0800, as in a conventional nuclear structure. 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. 4. The analysis can be performed using a single composite spectrum or separately for the 10-5 MAFE response spectrum and 167% GMRS. 5. CHS=Clearance to the Hard Stop 6. Seismic Category 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.
69 Non-seismic Buildings
The following buildings are non-seismic Category 1 structures, and contain no safety-related equipment. They are designed for wind and seismic loads in accordance with the Uniform Building Code. The foun- dation of each building is a reinforced concrete mat on grade.
The annex building serves as the main personnel entrance to the power generation complex. The building includes the health physics area, the non-Class 1E ac and dc electric power systems, the ancillary diesel generators and their fuel supply, other electrical equipment, the technical support center, and various HVAC systems. The annex building provides large staging and laydown areas immediately outside the equipment hatches.
The turbine building houses the main turbine, generator, and associated fluid and electrical systems. It also houses the makeup water purification system.
The diesel generator building houses two diesel generators and their associated HVAC equip- ment.
The radwaste building contains facilities for segregated storage of various categories of solid waste prior to processing, for processing by mobile systems, and for storing processed solid waste in shipping and disposal containers.
How might Isolation Benefit Current NPP designs
n A simple numerical “stick” model was found in the open literature to represent an AP 1000 standard plant design (Westinghouse)
20 14 Simplified Numerical Stick Model
Study Input Parameters
! '%( 5)+ 5)+123 n From EPRI/Bechtel 0*, %#&
.)0 .)0123 study of SSI modeling /*,
9)+, )6+ n Structures Considered )6+123 0*, 96+, #$%
9)+, *54 *54123 )6+78 • Auxiliary/Containment 9)+, 0*,
.+/ 9)+, *5478 4+ Building (ASB) 9)+, *5* 96+, 9)+, (T1 = 0.31 sec) .+) 4+78 *5*78