Structural Integrity of Fukushima-Daiichi SSCs After The 2011 Great East Japan Earthquake
(PR21)
September 6, 2012IEM 3, IAEA ,Vienna
Kazuyuki NAGASAWA
2012 Tokyo Electric Power Company. All rights reserved. 1
� Unit #1 to #3 of 1F site (Fukushima-Daiichi NPS) shut down automatically by “Seismic SCRAM” and experienced Loss of Off-site Powerright after the GEJE.
� It is expected that safety functions were maintained until the tsunami hit.
� TEPCO confirmed structural and functional integrity of SSCs of 1F Site before the tsunami hit based on the following.
�Visual Inspections�Operation Records�Seismic Response Analysis : Unit 1 - 3�Representative Unit 5 Walkdown and Seismic Response Analysis
Introduction
2012 Tokyo Electric Power Company. All rights reserved. 2
� Original DBE was much conservative than current DBE Ss and observed record at the range of 0.1 - 0.2 sec of natural period.
Observed Records of GEJE
Unit 1 Unit 2 Unit 3
Introduction
Proper Period [s] Proper Period [s]
Sei
smic
Int
ensi
ty
Sei
smic
Int
ensi
ty
Sei
smic
Int
ensi
ty
Observed (North-South direction)Observed (East-West direction)Original Design (North-South direction)Original Design (East-West direction)Ss ( NSEW envelope )
Observed (North-South direction)Observed (East-West direction)Original Design (North-South direction)Original Design (East-West direction)Ss ( NSEW envelope )
Observed (North-South direction)Observed (East-West direction)Original Design (NSEW envelope )Ss ( NSEW envelope )
Proper Period [s]
2012 Tokyo Electric Power Company. All rights reserved. 3
Visual Inspections
�Damage condition of unit 1-3 was visually inspected in the limited area.�No damage on the IC system (isolation condenser) for unit 1.�No damage inside the torus room of unit 2.�No damage even for non seismic classified components in
turbine building for unit 1-3.
�Visual inspection for unit 1-3 was conducted for limited area due to high radiation level, however, within the scope of those inspection, both of safety related and no safety related components were almost unaffected by the earthquake.
2012 Tokyo Electric Power Company. All rights reserved. 4
Visual Inspection for the IC (Unit 1)
No structural damage was found.
Unit 1
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Visual Inspection for the Torus Room (Unit 2)
No structural damage was found.
Direction to PCVSoutheast S/C manholeLower part of Torus Room
Route of northeast Upper part of the route of northeast
North S/C manhole
Upper part of the south route
Upper part of the southeast S/C manhole
Access route of self-propelled remote camera
Unit 2
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No damage by the earthquake was found.Unit 3 Unit 2
1st floor
2nd floor
Unit 1 Unit 3 Unit 2 Unit 1
Turbine driven reactor feed water pumpAir-conditioning duct・Air-conditioning duct is partially swollen and damaged maybe by explosion
Turbine Building auxiliary cooling water system surge tank
6.9kV Metal clad switchgear 1A・Signs of tsunami flooding
Isolated phase bus cooling fan・Signs of tsunami flooding
480VPower center 2A
Turbine Building auxiliary cooling water system pump
Heater
Instrument air compressor
Visual Inspection for the T/B
2012 Tokyo Electric Power Company. All rights reserved. 7
�Unit 1-3 were safely shut down, and plant parameter such as reactor water level and pressure were controlled.� Type of alarm recorder� Records of reactor water level / pressure
�No Evidence showing damage of RPV boundary� Records of PCV pressure / temperature
�All EDGs were actuated under the loss of off-site power condition.� Records for transient recorder
Operation Records after GEJE
2012 Tokyo Electric Power Company. All rights reserved. 8
All control rods were fully inserted by seismic SCRAM
Seismic SCRAM Seismic SCRAM
Full insertion of all control rods Full insertion of
all control rods
Seismic SCRAM
Full insertion of all control
rods
Operation Records : Type of Alarm Recorder
Unit 1 Unit 2
Unit 3
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The water level and the pressure were controlled
Seismic SCRAM
Control of water level by IC Control of
pressure by IC
Seismic SCRAM
Decrease in pressure
following IC operation
Increase in pressure
following IC shutdown
It is assumed that the
tsunami hit
Increase in pressure following closure of the main steam isolation valve
Off-site power loss, Main steam isolation valve closed IC
automatic startup
< Reactor Water Level > < Reactor Pressure >
Red::::Reactor Water LevelGreen:::: Reactor Water Level ( Fuel Range )
Reactor Pressure
Operation Records : RPV Water Level and Pressure
Unit 1
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Red::::Reactor Water Level
Green::::Reactor Pressure
Seismic SCRAM
The water level and the pressure were controlled.
< Unit 2 > < Unit 3>
Tsunami hit
Closure of the main steam isolation valve, Pressure control by SRV.
Change in water level due to RCIC operation
Seismic SCRAM
Change in water level due to RCIC operation
Unit 2 Unit 3
Operation Records : RPV Water Level and Pressure
2012 Tokyo Electric Power Company. All rights reserved. 11
Increase in differential
pressure following an increase in
containment vessel pressure
Decrease in suppression chamber pressure
following suppression chamber cooling
Seismic SCRAM
Seismic SCRAM
Increase in pressure following shutdown of the
containment vessel air-conditioning
Primary containment vessel pressureSuppression chamber differential pressure
Primary containment vessel pressure Primary containment vessel temperature
Increase in temperature following
shutdown of the containment vessel
air-conditioning
Operation Records : PCV Pressure and Temperature
Unit 1
Tsunami hit
No sign of leakage from RPV boundaryUnit 1
2012 Tokyo Electric Power Company. All rights reserved. 12
Primary containment vessel pressurePrimary containment vessel temperature
Seismic SCRAM
Seismic SCRAM
Increase in temperature
following shutdown of the
containment vessel air-conditioning
No sign of leakage from RPV boundaryUnit 2
Operation Records : PCV Pressure and Temperature
2012 Tokyo Electric Power Company. All rights reserved. 13
Seismic SCRA
Seismic SCRAM
Primary containment vessel pressure Primary containment vessel temperatureIncrease in temperature
following shutdown of the containment vessel air-
conditioning
No sign of leakage from RPV boundaryUnit 2
Operation Records : PCV Pressure and Temperature
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Securement of EDG voltage
Securement of EDG voltage
Operation Records : EDG Transient Recorder
Unit 2
Unit 1
EDGs started up due to Loss of Off-site Power without malfunction
2012 Tokyo Electric Power Company. All rights reserved. 15
14:40:00 14:45:00 14:50:00 14:55:00 15:30:00 15:35:00 15:40:00 15:45:00 15:50:00 15:55:00 16:00:00 16:05:00
14:40:00 14:45:00 14:50:00 14:55:00 15:30:00 15:35:00 15:40:00 15:45:00 15:50:00 15:55:00 16:00:00 16:05:00
Unit 3
� EDG started up due to loss of off-site power, and the necessary power was secured
Transient Recorder (EDG)
2012 Tokyo Electric Power Company. All rights reserved. 16
� Seismic response analysis for representative safety related components shows that structural and functional integrity were maintained after the earthquake in unit 1 -3.
� Main steam line (unit 1-3)� RPV (unit 1-3)� PCV (unit 1-3)� core support structure (unit 1-3)� residual heat removal system (piping and pump) (unit 1-3)� control rod (unit 1-3)� Isolation Condenser (unit1)� Primary Loop Recirculation piping (unit1)� Suppression Chamber Saddle Support (unit1)� PCV Vent Line (unit1,2)� Core Spray System piping (unit2)� High Pressure Injection Line (unit3)� Emergency Diesel Generator (unit1-3)
Seismic Response Analysis
2012 Tokyo Electric Power Company. All rights reserved. 17
Dynamic analysis (Reactor Building)
Dynamic analysis (Reactor vessel Combined with Building)
Seismic force�Moment�Shear force�Axial force
曲
げ
せ
ん
断
は
り 胴部局部
変形ばね
集中質量
Acceleration�Seismic intensity�Spectrum
Vessels
Pumps Pipe
0.05 0.5Period [s]
Acc
eler
atio
n [G
]
0.1 10
5
10
15
20
Shroud
Reactor Pressure Vessel
Seismic Response Analysis : Unit 1-3
2012 Tokyo Electric Power Company. All rights reserved. 18
FacilityEvaluation
PointItem
Unit 1 Unit 2 Unit 3
Calculation value
Evaluation criteria
Calculation value
Evaluation criteria
Calculation value
Evaluation criteria
RPVFoundation
VoltPrimary Stress
((((MPa))))93 222 29 222 50 222
Core SupportStructure
ShroudSupport
Primary Stress
((((MPa))))103 196 122 300 100 300
PCVDrywell
BodyPrimary Stress
((((MPa))))98 411 87 278 158 278
Main Steam Line System
PipingPrimary Stress
((((MPa))))269 374 208 360 151 378
Residual RemovalSystem
(Shut DownCooling System
for Unit 1)
PipingPrimary Stress
((((MPa))))228 414 87 315 269 363
Volt ofPump
Primary Stress
((((MPa))))8 127 45 185 42 185
Control RodFuel
Assembly
FlexibleVolume
((((mm))))
26.4 40 33.2 40 24.1 40
Seismic Response Analysis : Unit 1-3
2012 Tokyo Electric Power Company. All rights reserved. 19
Piping Model
PCV
PLR
RPV
Max. StressEvaluation Point Max. Stress
Evaluation Point
Max. StressEvaluation Point
Max. StressEvaluation Point
Max. StressEvaluation Point
Max. StressEvaluation Point
Max. StressEvaluation Point
Max. StressEvaluation Point
Structure Evaluation Result
AnalyticalModel
CalculatedValue [MPa]
CriteriaValue [MPa] Margin
Isolation Condenser System
ValveHorizontal Vertical
CalculatedValue
CriteriaValue
CalculatedValue
CriteriaValue
Active Function Maintenance Evaluation
Seismic Response Analysis – Unit 1 : IC
2012 Tokyo Electric Power Company. All rights reserved. 20
Max. StressEvaluation
Point
PLR Piping Model (PLR-PD-1)
PCV
PLR
RPV
Primary Loop Recirculation System Diagram
Structural Integrity Evaluation Result
AnalyticalModel
CriteriaValue [MPa]
CalculatedValue[MPa]
CriteriaValue [MPa] Margin
Seismic Response Analysis – Unit 1 : PLR
2012 Tokyo Electric Power Company. All rights reserved. 21
S/C Seismic Intensity
Analytical ModelBracing Saddle Support
ReinforcedRing
Torus Body
Altitude Horizontal Vertical
R/B seismicResponse Analysis
Floor ResponseSpectrum, Intensity Set
S/C Support LoadingEvaluation by
Calculation Code
Evaluation for S/CSupport Class
Evaluation Flow
Zoom
Structural Drawing
●●●●::::Evaluation Point
Moment
EvaluationPoints
Support
StressCategory
Combination
CalculatedValue [Ratio]
CriteriaValue [Ratio] Note
Compression+Bend
Tension+Bend
Input Floor Response Spectrum(Horizontal)
Input Floor Response Spectrum(Vertical)
Ear
thqu
ake
Inte
nsity
Ear
thqu
ake
Inte
nsity
Proper Period
Proper Period
Seismic Response Analysis – Unit 1 : S/C Support
0.64
0.46
1.0
1.0
2012 Tokyo Electric Power Company. All rights reserved. 22
Vent pipes or tubes from the drywell directthe steam below the water level maintainedin the Suppression Chamber ( also knownas a torus or suppression pool), condensingthe steam, limiting the pressure ultimately
Vent Piping
Downcomer
Reactor Building
SuppressionChamber
Primary Containment Vessel
Structural Drawing
Evaluation Scope
Downcomer
Vent Piping
Suppression Chamber
Floor View
Zoom
: Evaluation Point
Vent Header
Primary Containment Vessel
Ring Header
Section View
Vend Pipe => Vent Header => Steam fromDowncomer lead into S/C Water
Vent Header
Seismic Response Analysis – Unit 1 : PCV Vent
2012 Tokyo Electric Power Company. All rights reserved. 23
Unit 1 Seismic Response Analysis Result for Vent Line, etc (MPa))))
Seismic Response Analysis – Unit 1 : PCV Vent
Joint of Vent Header andDowncomer
Evaluation Point
Vent Line
Downcomer body
Ring Header
CalculationValue
EvaluationCriteria Value Margin
16 230 14.73
122 432 3.54
120 346 2.88
75 411 5.48
Analytical Model for Vent Line
2012 Tokyo Electric Power Company. All rights reserved. 24
Evaluation Point
Calculation
Value
[[[[MPa]]]]
Criteria Value
[[[[MPa]]]]Margin
Vent Line 91 418 4.59
Joint of Vent Header and
Downcomer145 354 2.44
Downcomer body 12 236 19.66
Structural Drawing
<Analytical Model>
Vent Piping
Downcomer
SuppressionChamber
Vent Header
Primary Containment Vessel
Downcomer
Vent Header
Vent Piping
: Evaluation Point
Seismic Response Analysis – Unit 2 : PCV Vent
2012 Tokyo Electric Power Company. All rights reserved. 25
炉心スプレイ系概略系統図
Max. StressEvaluation Point
Max. StressEvaluation PointPiping Model
RPVPCV
PCV
Core Spray System Diagram
Seismic Response Analysis Result
AnalyticalModel
CalculatedValue[MPa]
CriteriaValue [MPa] Margin
Seismic Response Analysis – Unit 2 : CS System
2012 Tokyo Electric Power Company. All rights reserved. 26
: Evaluation Scope
High Pressure Core Injection System Diagram
Seismic Response Analysis Result
AnalyticalModel
CalculatedValue [MPa]
CriteriaValue [MPa] Stress Ratio
No abnormalities such as pipe rupture were found in the HPCI room and the Torus Room which contains steam piping.
Max. StressEvaluation Point
Max. StressEvaluation
Point
Max. StressEvaluation Point
Analytical Model
Seismic Response Analysis – Unit 3 : HPCI
2012 Tokyo Electric Power Company. All rights reserved. 27
�Structural Integrity Evaluation Result
�Functional Operable Integrity Evaluation Result
Unit Components Evaluation PointCalculation
Value MPa))))
Criteria
Value MPa))))
Unit 1
Diesel Engine and Generator Holding Down Bolt 26 207
Fuel Service Tank Holding Down Bolt 18 207
Startup Air Tank Holding Down Bolt 19 207
Unit 2
Diesel Engine and Generator Foundation Bolt 38 146
Fuel Oil Tank Foundation Bolt 137 183
Startup Air Tank Shell Plate 91 268
Unit 3
Diesel Engine and Generator Foundation Bolt 56 146
Fuel Oil Tank Foundation Bolt 137 183
Startup Air Tank Shell Plate 91 288
Unit Components Evaluation Point
Horlizontal Vertical
Calculation
Value
Criteria
Value
Calculation
Value
Criteria
Value
Unit 1 Diesel Engine the center of gravity 0.60 1.1 0.35 1.0
Unit 2 Diesel Engine the center of gravity 0.69 1.1 0.44 1.0
Unit 3 Diesel Engine the center of gravity 0.79 1.1 0.54 1.0
The Japanese Diet report indicated the dame to the components. However, seismic impact to the components were not confirmed from this evaluation result.
Seismic Response Analysis – EDG
2012 Tokyo Electric Power Company. All rights reserved. 28
� Unit 5 Plant Walkdown was conducted as representative of unit 1-3 to estimate the seismic impact to unit 1-3.
� Seismic response analysis for Class S (Safety related) components was carried out based on observed record.
� As result of walkdown and seismic response analysis, no damage caused by the earthquake was identified on safety related components.
Unit 5 Walkdown / Seismic Response Analysis
�Unit 1-3 are inaccessible due to explosion and high radiation level.�Seismic acceleration observed at unit 5 was almost same as those of unit
1-3. (Unit 2-5 have same reactor type, BWR-4)
2012 Tokyo Electric Power Company. All rights reserved. 29
�Unit 5 is appropriate plant to estimate the seismic impact of unit 1-3 since seismic acceleration for unit 5 was almost same as unit 1-3 .
Unit 5 Walkdown / Seismic Response Analysis
Observed Point(R/B Foundation)
Observed Point Max. Response Accelerationto Ss (GAL)Max. Acceleration (GAL)
NS EW UD NS EW UD
FukushimaDaiichi NPS
Unit 1 460 447 258 487 489 412
Unit 2 348 550 302 441 438 420
Unit 3 322 507 231 449 441 429
Unit 4 281 319 200 447 445 422
Unit 5 311 548 256 452 452 427
Unit 6 298 444 244 445 448 415
Comparison between Observed Record and Response toDesign Basis Earthquake Ground Motion (Ss)
Note)))) NS : North-South, EW : East-West, UD : Up-Down
2012 Tokyo Electric Power Company. All rights reserved. 30
�Seismic integrity for unit 5 is almost same as unit 1-3, since seismic design condition for unit 5 is almost same as unit 1-3. Unit 5 is appropriate plant to estimate the seismic impact of unit 1-3.
Unit 5 Walkdown / Seismic Response Analysis
2012 Tokyo Electric Power Company. All rights reserved. 31
Unit 5 Walkdown
No equipment abnormality in terms of external appearance
Reactor Building Turbine Building
4th/3rd
Floor
2nd/1st
Floor
BasementFloor
PCV
RCIC Pump Flammablity Control System SLC Pump
MSIV HCU CUW Pump RCW Heat Exchanger
RPV SkirtPedestalSRVMSIV
Stabilizer (PCV) Stabilizer (RPV) PLR Riser PipingM/D-RFP
D/G
Moisture SeparatorPiping around
Moisture Separator
Instrument Compressor TCW Pump
2ndFloor
1stFloor
BasementFloor
HP TurbineThere are some cracks on the front standard foundation grout
T/D-RFP
No equipment abnormality in terms of external appearance
No equipment abnormality in terms of external appearance
No equipment abnormality in terms of external appearance
Missing of insulation Gap of support
Damage to the small diameter drain pipe of the moisture separator
480V P/C
6.9kV M/CNo equipment abnormality in terms of external appearance
P/C6B-1 was inoperable because of inundation
Receiving electricity after installment of drain
No equipment abnormality in terms of external appearance
No equipment abnormality in terms of external appearance
4th
No equipment abnormality interms of external appearance
3rd
FPC Pump Although some signs of corrosion is found in both units, there are no equipment abnormalities in terms of external appearance
No equipment abnormality in terms of external appearance
2nd1st
No equipment abnormality in terms of external appearance
CRD PumpHPCIRHR PumpCore Spray Pump
No equipment abnormality in terms of external appearance
No equipment abnormality in terms of external appearance
No equipment abnormality in terms of external appearanceRetained water on the floorSigns of leakage on the wall penetration in the same area Retained water on the floor
2012 Tokyo Electric Power Company. All rights reserved. 32
Unit 5 Seismic Response Analysis�Evaluation Flow
Component SeismicResponse Analysis
Structure SeismicResponse Analysis
Calculating Seismic Force (Acc, Shear force, Moment,
etc)
PrimaryScreening
DetailAnalysis
AnalysisCompletion
Checkup withOn-Site Information
Calculating Max.Response Acc.
On Floor
Calculating FloorResponseSpectrum
PipingDetail Analysis
Without Screening
ResponseRatio is LessThan Margin
of Design
CalculationValue is LessThan Criteria
Value
NO
YES
NO
YES
2012 Tokyo Electric Power Company. All rights reserved. 33
Unit 5 Seismic Response Analysis�Structural Integrity Evaluation (Primary Screening)
�Confirm that ratio between seismic load on March 11th and design (response ratio) is less than design margin
�Conduct detail evaluation when response ratio is more than design margin
Seismic Load on March 11th
Design Seismic Loadα=
α (Response Ratio) < β (Design Margin)
[Response Ratio]
Evaluation Criteria Value
Calculation Valueβ=
[Design Margin]
2012 Tokyo Electric Power Company. All rights reserved. 34
FacilityEvaluation
PointR
PV
Rea
ctor
RP
VA
ttach
men
tS
yste
mStress
CategoryCalculation Criteria
Judgment
Support Skirt
Sleeves for control Rod
PLR Inlet Nozzle (N2)
Feed Water Nozzle (N4)
Stabilizer Bracket
Bearing Plate and &Attachment Bolt
Skirt
Sleeve
Nozzle Safe End
Nozzle Safe End
StabilizerAttachment
Bearing Plate
Gusseted Plate
Bearin Plate and &Attachment Bolt
Stabilizer (RPV-Shield Wall)
Stabilizer (Shield Wall-PCV) Connection Pipe
Envelope
AxialCompression
Envelope + Bend
Envelope
Envelope
Bend
Compression
Envelope + Bend
�Primary Screening Evaluation Result (1)
Unit 5 Seismic Response Analysis
2012 Tokyo Electric Power Company. All rights reserved. 35
FacilityEvaluation
Point
Rea
ctor
Rea
ctor
Cor
e S
truc
ture
Stress Category
Calculation CriteriaJudgment
Envelope + Bend
Envelope + Bend
Envelope + Bend
Envelope + Bend
Envelope + Bend
Envelope + Bend
Envelope
Envelope
Feed-water Sparger
Core Spray Sparger
Header
Header
Jet Pump
Core Shroud
Core Support Plate
�Primary Screening Evaluation Result (2)
In-Core Monitor Tube
Control Rod Guide Tube
Upper Grid Plate
Riser
SupportPlate
GridPlate
LowerTorso
Central OutsideSurface
(Longer Direction)
In-Core Monitor Tube
Unit 5 Seismic Response Analysis
2012 Tokyo Electric Power Company. All rights reserved. 36
FacilityEvaluation
Point
Rea
ctor
Rea
ctor
Cor
e
Str
uctu
re
RP
V
Fou
ndat
ion
Stress Category
Calculation CriteriaJudgment
Envelope + Bend
Envelope + Bend
TensileForce
ShearForce
�Primary Screening Evaluation Result (3)
Core Spray Pipe
SLC Pipe
Support Structure(Foundation)
Support Structure (Top)
Pipe
Pipe
ReinforcingSteel
Joist Part
Unit 5 Seismic Response Analysis
2012 Tokyo Electric Power Company. All rights reserved. 37
FacilityEvaluation
Point
SLC
CR
D
Inst
rum
ent a
nd C
ontr
ol
Equ
ipm
ent
Mea
sure
men
t In
stru
men
t
Stress Category
Calculation CriteriaJudgment
TensileForce
TensileForce
TensileForce
Hydraulic Control Unit
SLC Pump
SLC Storage Tank
�Primary Screening Evaluation Result (4)
Field Measurement Instrument
Bolt
AnchorBolt
Pump HoldingDown Bolt
Frame
MaximumPrinciple
Stress
Unit 5 Seismic Response Analysis
2012 Tokyo Electric Power Company. All rights reserved. 38
FacilityEvaluation
PointR
HR
RC
IC
Rea
ctor
Coo
ling
Equ
ipm
ent
HP
CI
Cor
e S
pray
sy
stem
Stress Category
Calculation CriteriaJudgment
Combination
TensileForce
TensileForce
ShearForce
ShearForce
ShearForce
Primary Stress
�Primary Screening Evaluation Result (5)
RCIC Pump
RCIC-Turbine
HPCI Pump
Core Spray Pump
HPCI-Turbine
RHR Heat Exchanger
RHR Heat Strainer
Core Spray Strainer Primary Stress Pocket Sheet(Porous Plate)
Holding DownBolt
Turbine FixingGuide Block
Pump HoldingDown Bolt
FixingKnock Pin
FoundationBolt
Pocket Sheet(Porous Plate)
FoundationBolt
Unit 5 Seismic Response Analysis
2012 Tokyo Electric Power Company. All rights reserved. 39
FacilityEvaluation
Point
PC
V
Prim
ary
Con
tain
men
t
Stress Category
Calculation CriteriaJudgment
Combination
ShearForce
Envelope + Bend
Envelope + Bend
Envelope + Bend
Envelope + Bend
Envelope
Compression
�Primary Screening Evaluation Result (6)
Dry Well
D/W Vent Nozzle
D/W Stabilizer
D/W Bottom Sheet
D/W Skirt
Vent Header
Hatch
Airlock
SandCushion
Insert PlateAttaching
WeldedPart
Beam SheetAttaching
Concrete
End Plate
Insert PlateAttaching
PersonnelAirlock Attaching
Unit 5 Seismic Response Analysis
2012 Tokyo Electric Power Company. All rights reserved. 40
FacilityEvaluation
Point
Prim
ary
Con
tain
men
t
SG
TS
Rad
iatio
n C
ontr
ol
Equ
ipm
ent
Mea
sure
men
t In
stru
men
t P
CV
P
enet
ratio
nStress
CategoryCalculation Criteria
Judgment
TensileForce
Combination
ShearForce
ShearForce
Bend
Primary Stress
�Primary Screening Evaluation Result (7)
SGTS VentilatingExhaust Equipment
Suppression ChamberSpray Header
Penetration (Sleeve)
Dec
ompr
essi
onE
quip
men
t
SGTS Train
PCV Radiation Monitor
Rector Building Radiation Monitor
HoldingDown Bolt
HoldingDown Bolt
Leg Rod
Bolt
Penetration
Bolt
Unit 5 Seismic Response Analysis
2012 Tokyo Electric Power Company. All rights reserved. 41
FacilityEvaluation
PointStress
CategoryCalculation Criteria
JudgmentF
HM
Fue
l Han
dlin
g E
quip
men
t
Fue
l Sto
rage
E
quip
men
t TensileForce
TensileForce
�Primary Screening Evaluation Result (8)
FHM Platform
Reactor Building Crane
Spent Fuel Storage Rack
Control Rod Storage Rack
Rack Foundation
Bolt
Rack HoldingDownBolt
( Seismic Class B Equipment )No falling accidents were found.
( Seismic Class B Equipment )No falling accidents were found.
Unit 5 Seismic Response Analysis
2012 Tokyo Electric Power Company. All rights reserved. 42
FacilityEvaluation
Point
Rea
ctor
Rea
ctor
Cor
e
Str
uctu
reR
PV
Stress Category
Calculation CriteriaJudgment
TensileForce
ShearForce
Envelope
Envelope
�Detailed Evaluation (1)
Foundation Bolt
Core Shroud Support
Drier Housing
Shell Plate
ShroudSupport Leg
EarthquakeBlock
FoundationBolt
Cylindertorso
Unit 5 Seismic Response Analysis
2012 Tokyo Electric Power Company. All rights reserved. 43
FacilityEvaluation
PointR
HR
PC
V
Prim
ary
Con
tain
men
tR
eact
or C
oolin
g
Equ
ipm
ent
Inst
rum
ent
and
Con
trol
E
quip
men
t
Mea
sure
men
t In
stru
men
t
Stress Category
Calculation CriteriaJudgment
TensileForce
Combination
ShearForce
ShearForce
Envelope + Bend
Envelope + Bend
Envelope
�Detailed Evaluation (2)
RHR Pump
D/W Bottom Sheet
Suppression Chamber
S/CAnti-seismic Support
S/CColumn Support
SRNMDry tube
LPRM
SupportRod
AnchorBolt
Anti-seismicSupport
Connection
Sheet PlateWelding Area
Motor HoldingDown Bolt
CoverTube
DryTube
Ratio to the criteria
Unit 5 Seismic Response Analysis
2012 Tokyo Electric Power Company. All rights reserved. 44
評価対象設備評価対象設備評価対象設備評価対象設備 評価部位評価部位評価部位評価部位 応力分類応力分類応力分類応力分類
計算値計算値計算値計算値
((((MPa))))評価基準値評価基準値評価基準値評価基準値
((((MPa))))判定判定判定判定
配
管
配
管
配
管
配
管
主蒸気系主蒸気系主蒸気系主蒸気系
配管本体配管本体配管本体配管本体 一次応力一次応力一次応力一次応力 244 417 ○○○○
サポートサポートサポートサポート スナッバスナッバスナッバスナッバ反力反力反力反力 40 kN 67 kN ○○○○
残留熱除去系残留熱除去系残留熱除去系残留熱除去系
配管本体配管本体配管本体配管本体 一次応力一次応力一次応力一次応力 189 364 ○○○○
サポートサポートサポートサポート 一次応力一次応力一次応力一次応力 159* 245 ○○○○
原子炉冷却材再循環系原子炉冷却材再循環系原子炉冷却材再循環系原子炉冷却材再循環系
配管本体配管本体配管本体配管本体 一次応力一次応力一次応力一次応力 245 354 ○○○○
サポートサポートサポートサポート 一次応力一次応力一次応力一次応力 149* 234 ○○○○
給水系給水系給水系給水系
配管本体配管本体配管本体配管本体 一次応力一次応力一次応力一次応力 167* 363 ○○○○
サポートサポートサポートサポート 一次応力一次応力一次応力一次応力 105* 245 ○○○○
FacilityEvaluation
Point
Main Steam system
RHR
PLR
FDW
Pip
ing
Stress Category
Calculation Criteria Judgment
Support
Support
Support
Support
Piping
Piping
Piping
Piping
Primary Stress
Primary Stress
Primary Stress
Primary Stress
Primary Stress
Primary Stress
Primary Stress
�Detailed Evaluation (3) Note ::::Underlined values are evaluation results for the design basis ground motion (Ss).
SnubberReaction Force
* Temporary calculated values for the design basis ground motion Ss exceeded criteria value. However, Detailed calculated values, which were based on the observed records, were below the criteria values.
Unit 5 Seismic Response Analysis
2012 Tokyo Electric Power Company. All rights reserved. 45
評価対象設備評価対象設備評価対象設備評価対象設備 評価部位評価部位評価部位評価部位 応力分類応力分類応力分類応力分類
計算値計算値計算値計算値
((((MPa))))評価基準値評価基準値評価基準値評価基準値
((((MPa))))判定判定判定判定
配
管
配
管
配
管
配
管
原子炉冷却材浄化系原子炉冷却材浄化系原子炉冷却材浄化系原子炉冷却材浄化系
配管本体配管本体配管本体配管本体 一次応力一次応力一次応力一次応力 79 337 ○○○○
サポートサポートサポートサポート 一次応力一次応力一次応力一次応力 160 245 ○○○○
放射性放射性放射性放射性ドレンドレンドレンドレン移送系移送系移送系移送系
配管本体配管本体配管本体配管本体 一次応力一次応力一次応力一次応力 102 366 ○○○○
サポートサポートサポートサポート 一次応力一次応力一次応力一次応力 13 245 ○○○○
ほうほうほうほう酸水注入系酸水注入系酸水注入系酸水注入系
配管本体配管本体配管本体配管本体 一次応力一次応力一次応力一次応力 174 351 ○○○○
サポートサポートサポートサポート 一次応力一次応力一次応力一次応力 73 245 ○○○○
原子炉隔離時冷却系原子炉隔離時冷却系原子炉隔離時冷却系原子炉隔離時冷却系
配管本体配管本体配管本体配管本体 一次応力一次応力一次応力一次応力 331 364 ○○○○
サポートサポートサポートサポート 一次応力一次応力一次応力一次応力 234* 245 ○○○○
FacilityEvaluation
Point
RCIC
SLC
Radiation Drain
CUW (RWCU)
Pip
ing
Stress Category
Calculation Criteria Judgment
Piping
Support
Support
Support
Support
Piping
Piping
Piping
Primary Stress
Primary Stress
Primary Stress
Primary Stress
Primary Stress
Primary Stress
Primary Stress
Primary Stress
�Detailed Evaluation (4)Note ::::Underlined values are evaluation results
for the design basis ground motion (Ss).
* Temporary calculated values for the design basis ground motion Ss exceeded criteria value. However, Detailed calculated values, which were based on the observed records, were below the criteria values.
Unit 5 Seismic Response Analysis
2012 Tokyo Electric Power Company. All rights reserved. 46
評価対象設備評価対象設備評価対象設備評価対象設備 評価部位評価部位評価部位評価部位 応力分類応力分類応力分類応力分類
計算値計算値計算値計算値
((((MPa))))評価基準値評価基準値評価基準値評価基準値
((((MPa))))判定判定判定判定
配
管
配
管
配
管
配
管
高圧注水系高圧注水系高圧注水系高圧注水系
配管本体配管本体配管本体配管本体 一次応力一次応力一次応力一次応力 353 402 ○○○○
サポートサポートサポートサポート 一次応力一次応力一次応力一次応力 221* 245 ○○○○
炉心炉心炉心炉心スプレイスプレイスプレイスプレイ系系系系
配管本体配管本体配管本体配管本体 一次応力一次応力一次応力一次応力 197 336 ○○○○
サポートサポートサポートサポート 一次応力一次応力一次応力一次応力 63 245 ○○○○
燃料燃料燃料燃料プールプールプールプール冷却浄化系冷却浄化系冷却浄化系冷却浄化系
配管本体配管本体配管本体配管本体 一次応力一次応力一次応力一次応力 140 431 ○○○○
サポートサポートサポートサポート 一次応力一次応力一次応力一次応力 18 245 ○○○○
FacilityEvaluation
Point
Flammability Control System
Pip
ing
Stress Category
Calculation CriteriaJudgment
Core Spray system
HPCI
Piping
Piping
Piping
Support
Support
Support
Primary Stress
Primary Stress
Primary Stress
Primary Stress
Primary Stress
Primary Stress
�Detailed Evaluation (5)Note ::::Underlined values are evaluation results
for the design basis ground motion (Ss).
* Temporary calculated values for the design basis ground motion Ss exceeded criteria value. However, Detailed calculated values, which were based on the observed records, were below the criteria values.
Unit 5 Seismic Response Analysis
2012 Tokyo Electric Power Company. All rights reserved. 47
評価対象設備評価対象設備評価対象設備評価対象設備 評価部位評価部位評価部位評価部位 応力分類応力分類応力分類応力分類
計算値計算値計算値計算値
((((MPa))))評価基準値評価基準値評価基準値評価基準値
((((MPa))))判定判定判定判定
配
管
配
管
配
管
配
管
可燃性可燃性可燃性可燃性ガスガスガスガス濃度制御系濃度制御系濃度制御系濃度制御系
配管本体配管本体配管本体配管本体 一次応力一次応力一次応力一次応力 210 363 ○○○○
サポートサポートサポートサポート 一次応力一次応力一次応力一次応力 126 245 ○○○○
不活性不活性不活性不活性ガスガスガスガス系系系系
配管本体配管本体配管本体配管本体 一次応力一次応力一次応力一次応力 263 335 ○○○○
サポートサポートサポートサポート 一次応力一次応力一次応力一次応力 244* 245 ○○○○
残留熱除去海水系残留熱除去海水系残留熱除去海水系残留熱除去海水系
配管本体配管本体配管本体配管本体 一次応力一次応力一次応力一次応力 338 428 ○○○○
サポートサポートサポートサポート 一次応力一次応力一次応力一次応力 100* 245 ○○○○
FacilityEvaluation
Point
Pip
ing
Atmospheric Control system
RHR Sea water system
Stress Category
Calculation Criteria Judgment
Piping
Support
Piping
Support
Piping
Support
Primary Stress
Primary Stress
Primary Stress
Primary Stress
Primary Stress
Primary Stress
�Detailed Evaluation (6)Note ::::Underlined values are evaluation results
for the design basis ground motion (Ss).
* Temporary calculated values for the design basis ground motion Ss exceeded criteria value. However, Detailed calculated values, which were based on the observed records, were below the criteria values.
Flammability Control System
Unit 5 Seismic Response Analysis
2012 Tokyo Electric Power Company. All rights reserved. 48
�Functional maintenance evaluation for active (1)
Calculated Value [G] Criteria Value [G] JudgementHorizontal Vertical Horizontal Vertical
Evaluation components
HCU (Scram Valve)
SLC Pump
RHR Pump
RCIC Pump
RCIC-Turbine
HPCI Pump
Core Spray Pump
HPCI-Turbine
SGTS Exhauster
Unit 5 Seismic Response Analysis
2012 Tokyo Electric Power Company. All rights reserved. 49
�Functional maintenance evaluation for active (2)
Note ::::Underlined values are evaluation results for design basis ground motion (Ss).
Judgement
Calculated Value [G] Criteria Value [G]
Horizontal Vertical Horizontal Vertical
Evaluation components
Valve
Main Steam system (SRV)
Main Steam system (MSIV)
PLR
FDW
RHR
RHR Sea water system
CUW (RWCU)
RCIC
Core Spray system
Atmospheric Control system
FPC
Flammability Control System
Unit 5 Seismic Response Analysis
2012 Tokyo Electric Power Company. All rights reserved. 50
�Seismic integrity for unit 1-3 was enough against the earthquake since the original DBE was conservatively decided.
�As the result of the visual inspection to the greatest extent possible, safety related components and even low seismic class components were almost completely unaffected by the damage caused by the earthquake.
�No evidence of damage for safety related componentsbased on the records of operation for unit 1-3 after the earthquake.
�Seismic response analysis result for unit 1-3 shows the functional integrity of safety related components.
�No damage was identified for safety related components of unit 5 which has the same type of reactors, based on the result of plant walkdown and seismic response analysis.
Summary
2012 Tokyo Electric Power Company. All rights reserved. 51
<<<<Conclusion>>>>� It is reasonable that the accident for unit 1-3 did not
depend on seismic cause but the tsunami-induced event.
<<<<Future>>>>� Further seismic response analysis based on the
seismic observed record for unit 1-3 will be continued.
Summary