Current Status of Fukushima Dai-ichi NPS- Appendix
September 17, 2012
Tokyo Electric Power Company
Legal Notice:This documentation includes technical knowledge and secret information thatbelong to our company and our licensors.
Therefore, it shall neither be disclosed to any third parties, be copied, nor used
for any purpose other than that accorded by our company.

Side Event by Government of JapanTHE TOKYO ELECTRIC POWER COMPANY, INC.
at 56th IAEA General Conference, Sep 17, 2012
©2012

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【２２】Containment Gas Management• Hydrogen Control : N2 Injection• RI Release Control : PCV Leakage Control with Slightly Positive PressureRadioactive Dust Filtering & Monitoring (Cs)• Monitoring : H2,O2 Monitoring
Rare Gas Monitoring ; Recriticality Check by Xe (Short Half Life)
to RPVFE

Air

N2
Injection
DehumidifierFE

N2 Gas Separation Apparatus
Outdoor ←HeaterHEPA
Filter

Ｒ／Ｂ← →Ｔ／Ｂ

to PCV→Ｒ／Ｂ

Ｔ／Ｂ← →Outdoor
Exhaust Fan
Stack

FE
Monitoring
System©2012

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1

1

3】Accumulated
Accumulated water processing【3
Layout of Circulating Line & Water Storage Tanks
Cesium absorption system
Waste storage facility
Core injection
pump

MEGA Float

Waste sludge storage facility

Lowconcentration
treated watertank

High-concentration
accumulated water tank（Non-used）
Mid-Lowconcentration
accumulated
water tank（Non-used）

Treated water
buffer tankFreshwater
reserve tank

RO concentrated
water tankMulti-nuclide removal
system Waste storage
facility

concentrated
water tank
Evaporative
concentrated water tank

Filteredfreshwatertank

Multi-nuclide removal
system (planned to
be installed)

Desalination
system
RO concentrated water tankFreshwater
reserve tank

Treated water transfer
pomp
Water transfer line

Freshwater injection line

※Total length of the line;
4km (about)Freshwater, RO concentrated water tanks©2012

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2【５５】 Layout of Temporary Waste Storage Facilities
Ａ

RubblesDeforested Trees
VesselＣ

Lofty Target : 1mSv/year at
the boundary of the site

Ｇ
ＢＡ
･Inside a temporary storage facility･Volume of Waste : 11,000 cubic meters

Ｃ
Ｄ

Ｈ
Ｉ

･Open air storage Rubbles･Volume of Waste : 25,000 cubic meters

Ｅ
Ｆ

Ａ・Ｂ

Unit 6
Unit 5Ｅ

Waste storage building･Exterior of a temporary storage facility
and containers･Number of containers : 450

Administrative
bldg
Unit 1
Unit 2
Unit 3
Unit 4Ｉ

Waste storage buildingＪ･Sheet covered Rubbles･Volume of Waste : 3,000 cubic meters

Ｋ
瓦礫（収納容器）･Deforested trees･Volume of Waste : 11,000 cubic meters･Containers in storage building･Number of containers : 410©2012･Temporary storage for Vessel･Number of Waste : 415
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3

2

【６
６】Fuel Removal from Spent Fuel Pools(Water Quality Improvement)
SFP water quality sampling results (July 2012)
Sampli
ng
Date

pH

condu
ctivity

Cl

Cs137

Cs134

－

mS/m

ppm

Bq/cc

Bq/cc

notes
＊Cl、Cs137,134:
sampled on
2012.4.11

Unit 1

2012/7
/11

7.6

15.8

6

1.8E+04

1.1E+04

Unit 2

2012/7
/1

9.1

9

11

2.2E+01

1.4E+01

Unit 3

2012/7
/9

9.1

50

66

2.0E+03

1.3E+03desalinationis ongoing(RO/ED → Ion)

2012/7
/17

9.6

43

100

3.3E+00

1.6E+00

desalinationis ongoing(Mobile RO)

Unit 4

For Unit 2,3,4 hydrazine is injected into SFP intermittently. Hydrazine concentration is less thanapprox.200ppm.
I-131 is not detectable for every Unit.
For Unit 3 and 4 desalination is ongoing.
©2012

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5【６】 Fuel Removal from Spent Fuel Pools
Amount of Fuels in SFP

Unit1
Unit2
Unit3
Unit4

Amount of Amount of
Spent Fuels New Fuels
292
100
587
28
514
52
1331
204

©2012

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【8】The integrity of the Spent Fuel Poolin Unit 4©2012

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68】 Unit 4 Spent Fuel Storage Conditions【8
Despite the Reactor Building explosion of Units 1, 2, and4, the spent fuel pools were filled with water and cooledusing the concrete pump car and Fuel Pool CoolingsystemCurrently, the water level and water temperature of thevarious pools are stable at around 30-50 degrees
The explosion at Unit 4 happened when all fuel was being
stored in the spent fuel pool, but based on helicopter
verification (March 16, 2011), nuclide analysis of poolwater, and the fact that pool water filling and cooling had
been accomplished, there is thought to be no damage tothe pool itself

Unit 4 Spent fuel pool conditions

Concentration (Bq/cm3)
Detected
nuclideHalf-life
Apr
12

Apr
28

May 7

Aug
20

(Reference)

March 4

(Reference)
Accumulated water in
the Unit 4 T/B basement(March 24)

Unit 4 pool waterCs-134

Approx. 2 years

88

49

56

44

ND

31

Cs-137

Approx. 30 years

93

55

67

61

0.13

32

I-131

Approx. 8 days

220

27

16

ND

ND

360

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74

8】 The situation of the Reactor Building at unit 4【8
The top of the Unit 4 R/B was damaged by the hydrogen explosion
BUT we confirmed that・the building has not tilted・the building, including the Spent Fuel Pool, will not collapse
even if an earthquake equivalent (JMA Seismic Intensity Scale 6+)
to the Tohoku-Pacific Ocean Earthquake occurs in the area.

Spent
Fuel Pool

燃料
Fuel【The fuel situation at unit 4】

ReactorPressure
Vessel・No fuel in the Reactor Pressure Vessel*Planned outage at the TohokuPacific Ocean Earthquake
・1535 fuels in the Spent Fuel Pool*include 204 fresh-fuels
Image of the Unit 4 R/B©2012

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88】 Confirmed that the building has not tilted①【8
We measured the distance between the water surface of theSpent Fuel Pool and the floor surface of the Reactor Building, andconfirmed that the building has not tilted1）not tilted
height height

Measurement Point
Equipment storage pool

Spent fuel pool

③

④ ⑦
11m

⑧

②

Almost same

Reactor well①⑥

5th floor

⑤

12m

10m

2）tiltedheight heightNorth

Measurement Point（on the 5th floor）

Not same©2012

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95

8】 Confirmed that the building has not tilted②【8
We conducted the measurements four times on Feb.7, Apr.12, May 18
and Aug.21, 2012 and the measured data at the 4 corners were almost
the same.
Thus, we confirmed that the floor surface of the 5th floor and water
surfaces of the spent fuel pool and the reactor well were leveled.
Measurement results Unit[mm]Water surface of the
spent fuel pool andthe reactor well

Steel ruler
Floor surface of the 5th floor

Measureddata

Reactorwell

Measurement Date
Feb 7
2012

Apr 12
2012

May 182012

Aug 21
2012

①

462

476

492

462

②

463

475

492

462

③

462

475

492

461

④

464

475

492

461

Feb 7
2012

Apr 12
2012

May 182012

Aug 21
2012

⑤

468

461

453

⑥

468

461

453

468

461

452

468

461

452

Spent fuelpool

Measurement Date－⑦

Measurement Method⑧※The measured data includes measurement errors©2012※Only reactor well was measured on Feb. 7※Water level changes depending on the operationof cooling system

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108】 Confirmed that the building has not tilted③【8Perpendicularity of the exterior wall was measured by using an optical equipment.

1) Building not tilted
Fixed point

South 1
(5th floor)

Fixed point

West 1(3rd floor)West 2(3rd floor)

No tilt

West 1(1st floor)Z2) Building tilted
Horizontal difference*West 2(1st floor)

South 1
(3rd floor)

South 1
(1st floor)

South 2
(5th floor)

South 2
(3rd floor)

South 2
(1st floor)

Y
x

Tilt

*Horizontal difference: The horizontal difference
between the fixed point on the first floor and thefixed point on the upper floor

Optical equipment

Tilted©2012

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116

8】 Visual Inspection【8
We inspected the defects such as cracks on the concrete floor and walls of the spent fuelpool (building frame) .
Spent Fuel
Pool

N

1

3

The
supportofThe
wallthat wall
supports
the spent fuel pool

The spent fuel pool wall

2

4

3

1

3rd Floor Plan
1st Floor Plan

4

2

Spent FuelPool

4th Floor Plan
LegendThe
wallthat wall
supports
The
supportof
The spent fuel pool wall
the spent fuel pool

Visual inspection

2nd Floor Plan

As a result of visual inspection, cracks of which the width exceed 1mm or which have thepossibility of rebar corrosion were not confirmed.
©2012

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12

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8】 Concrete Strength Verification【8
The concrete strength of the spent fuel pool was measured by non-destructive
inspection techniques (Schmidt Hammer*) to confirm that the strength fulfills the design
standard（22.1N/mm2）.
Results of Concrete Strength Verification
4
Unit（N/mm2)

Spent Fuel
Pool

No.

Verification Points

Concrete
Strength※①

Reactor Shell Wall, 1st Floor(Support Walls of SFP)

38.4

②

Support Walls of SFP, 2nd
Floor

36.3

③

Bottom of SFP, 2nd Floor

33.1

④

SFP Wall, 3rd Floor

39.1

⑤

SFP Wall, 4th Floor

35.6

1
3rd Floor
Spent FuelPool

1st Floor
Bottom of Spent Fuel Pool

5⑤2

4th Floor③
3N

LegendThe concrete strengthverification points

2nd Floor©2012

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137

8】 Preliminary analysis on SFP accident in Unit 4【8However fuel in SFP was stably cooled in nowadays. we conducted preliminary accident analysis onunit 4 SFP with assumption that water was lost due to some reason.
Decay heat around late July with considering fuel loading history was employed.
As a LOCA scenario, accident analysis was conducted by employing initial condition with zero SFP
water level. We also conducted accident analysis in case of gradual water level decrease due toevaporation.
LOCA : PCT rising was saturated around 850 degree-C by air natural convection cooling.
Non-LOCA : It took about 50 days until fuel uncovery. After the fuel uncovery, PCT was suddenly
increased and resulting in fuel melt due to water blockage of air natural convection cooling.
z

12.2 my

3000

Max. Cladding Temperature [K]xSpent Fuel Channel

9.9 m（20 channels）
CH1
CH6
CH11
CH16

CH2
CH7

CH12

CH17

CH3
CH8

CH13

CH18

CH4
CH9

CH14

CH19

CH5
CH10

CH15

CH20

11.8 m(water level: 11.5 m)～ 4.3 mNon-LOCA
2500

LOCA (No water)

2000
1500
1000
500
0
0

～ 17 cm

Fig.1 MAAP model

20

40
60
Time (days)

80

100

Fig.2 MAAP results©2012

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14【９９】 Approach for monitoring of the reactors and removal of fuel debris

Unit 2 PCV Investigation

First Investigation on Jan. 19th
Second Investigation on Mar. 26th

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8

【９】 Photos inside of PCV, Unit 2① on Jan.19th
X-53

Borescope

CRD rail

Guide pipe
(inside diameter 13mm13mm))

Borescope
X-53

Weights to pull thethermocouple into
the PCV

OP:12490m
1FL, R/B(OP.10200)

Thermocouple

Inside of the guide pipe located in X-53 penetration(Before the borescope enters the PCV)

Grating, 1FL(OP.9500)：Shooting to this direction©2012

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16【９】 Photos inside of PCV, Unit 2② on Jan.19th
X-53

Borescope

Up

Up
PipingSupport

Down
CRD rail

Down

Small size piping or cable conduit
Borescope
X-53

OP:12490m

Deposits

Internal wall of PCV： Shooting to this direction©2012

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179【９】 Photos inside of PCV, Unit 2③ on Jan.19th
X-53

Borescope

CRD rail

GratingOP．9500
9500）（OP

Inside wall of PCVBorescope
X-53

GratingOP．9500
9500）（OP

OP:12490m

Inside wall of PCV： Shooting to this direction

Thermo couple

Around the grating, 1FL, Dry well
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18【９】 Photos inside of PCV, Unit 2④ on Jan.19th
X-53

Borescope

CRD rail

Borescope
X-53

OP:12490m
Structures assumed to be piping

Looking up from X-53 penetration： Shooting to this direction©2012

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19

10【９】 Water level and Surrounding temperature in the PCV, Unit2
on March 26th

①－a

X-53
Penetration（OP12490）

42.8℃

①－b

43.0℃

：Temperature measurement point：Water level measurement point
Approx..1m

Guide pipe

①－a

①－c

43.5℃

①－d

Approx. 60 cm
from bottom of PCV①－e

48.5～50.0 ℃

Approx. 1m①－b

Approx. 1m

①－c

ＰＣＶ

Internal wallof PCV

Grating （OP9510）①－dBottom of ＰＣＶ（OP5480）Upper of water surface
Thermo couple

Water surface

Approx. 60cm

1～1.6mm①－e

Under water©2012

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20【９】 PCV Atmosphere temperature, Unit 2(Approx. 1m from X-53 penetration) on Mar. 26th
X-53
Penetration（OP12490）：Temperature
measurement point
Approx. １m

②－a

②－a

44.9℃

②－b

44.6℃

②－c

44.5℃

ConduitApprox. 1mGuide pipe②－ｂApprox. 1.5m

②－c
ＰＣＶ

Grating （OP9510）

Bottom of ＰＣＶ（OP5480）

Thermo couple

Approx. 60cm

©2012

Looked down from ②-cof left figure

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Grating21

11

【９】 Radiation Level in the PCV, Unit 2 (approx. 1000mm inside of the internal wall)on Mar. 26th
：Location of the measurement

ＲＰＶ

①－a

39.0 Sv/h①－b54.1 Sv/h①－c57.4 Sv/h①－d72.9 Sv/h②－a31.1 Sv/h②－b48.0 Sv/h②－c41.4 Sv/h②－d37.3 Sv/h

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ＰＣＶ
雰囲気線量測定①
X-53

Penetration Approx. 500mm
Approx1000mm（OP12490） ②－a①－a

Guide Pipe

②－b
②－c
②－d

Terminal box①－ｂ
Approx1000mm①－ｃ
Approx 1000mm
Approx830mm
Approx150mm①－ｄ

Grating（OP9510）
Bottom of ＰＣＶ（OP5480）

Approx 60cm

©2012

22

【９
９】 Approach for monitoring of the reactors and removal of fuel debris

Unit 2 Torus Room Investigation
Robot survey : Apr. 28th ,2012
Water level measurement : June. 6th ,2012

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All Rights12【９】 Access route of the robot (Result) ,Apr 28th

S/C manhole

First Floor of the Reactor Building

Basement Floor of the Reactor Building

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©2012
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Electric
Company, INC.
All Rights【９】 Air dose rate in the Torus Room ,Apr 28th
(mSv/h)

２

13

73

47

82

42
53

88

42
118
Maximumvaluemeasured

88

110
40

38

48
50

38
55

51
30

42

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Direction to PCVUpper part of the southeast S/C manhole

Southeast S/C manhole

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All Rights【９】 Photos 2/3 ,Apr 28th

Manhole of North S/CRoute of northeast

Upper part of the route ofnortheast27©2012 The Tokyo Electric Power
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Lower part of the Torus Room

Upper part of the south route28©2012 The Tokyo Electric Power
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©2012
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All Rights【９】 Water Level Measurement at Unit 2-3 Torus Room, June 6thN
北Measurement Result on June 6th

Ａ

Ｂ

段室
Stair階case
Ｃ

Unit 2

Unit 3

Stair casewater level

OP 3260

OP 3150

Torus room
water level

OP 3270

OP 3370

Ｄ

トーラ
ス室
Torus
room

Mid basement of the Reactor Building

Ａ

Catwalk level

Ｂ/ＣＤ

1st floor
１階

Floor surface(OP4000)

OP1900中地下階
Mid
basement
0P+4000

Measuring tape
Weight

Φ8.9
Stair
case
階段室

Water level measurement

トーラス室
Torus
room

29
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All Rights15【９】 Photos at Unit 2&3 Torus Room , June 6th

Unit 2 stair case (Northwest)

Unit 3 stair case (Northwest)

Unit 2 torus room (Northwest entrance)

Unit 3 torus room catwalk30©2012 The Tokyo Electric Power
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©2012
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All Rights【９】 Water Level at the Bottom of Unit 2 PCV

Catwalk (OP5880)

Torus Room
Floor surface (OP4000)
Water accumulated in theTorus Room, June 6th
OP3270Suppression Chamber (S/C)

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【９】 Large Explosive Sound on Mar.15 , 2011
An explosion was believed to occur at unit 2, because large
explosive sound seemed to accompany drop on S/C pressure
at unit 2 on Mar.15, 2011
Explosive sound is confirmed to come from unit 4
Distance from unit 2 参考Distance from unit 4（m） 1200（m） 1200

P-wave1000

S-wave

1000

A

Ｐ波

Ｓ波

800

800

A

B
600

E

600

B
400
C

D

E

400

200

200

0

0

D

C
14.5

15.0

15.5

16.0

16.5

17.0 （sec）

14.5

Vibration Arrival Time on Mar.15 06:12

15.0

15.5

16.0

16.5

17.0 （sec）

Vibration Arrival Time on Mar.15 06:12

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©2012
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All Rights【９９】 Approach for monitoring of the reactors and removal of fuel debris
Unit 1 Reactor Building Dose map (mSv/h)(1st floor)

Measurement period: May 14~18 ※ wall surface

Measurementpoint

shield50mm
above floor

1500mmabove floor

Measurement
point

50mm
above floor

1500mmabove floor

Dose around
PCV penetrations

large equipment
entrance

shielddose rate
Measurement point

wall dose rate
Measurement
point

Visual confirmation
range

20．Equipment
funnel

21．Floor
penetration

July
4,2012

Measurement
point
1500mmabove floor
150mm
above floor
Measurement
point

Temporary shield wall

1500mmabove floor
150mm
above floor※1 approx. 60cm above floor ※2 106cm above floor ※3 the top of funnel ※4 the top of floor penetration

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All Rights17【９９】 Approach for monitoring of the reactors and removal of fuel debris
Unit 2 Reactor Building Dose map (mSv/h) (1st,3rd~5th floor)【notes】 dose rate measured
by Feb. 27 on Jun.13

Equipment etc.
Landing

Landing

3rd floor
4th floor

FHM
Fence(1m)

3rd floor
5th floor

4th floor
Measurement
point

50mm
above
floor

1500mmabove
floor

Measurement
point

50mm
above
floor

1500mmabove
floor

Measurement period: May 28~31 ※ wall surface
Measurement
point

50mm
above
floor

1500mmabove
floor

Measurement
point

50mm
above
floor

1500mmabove
floor

1st floor

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©2012
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Company, INC.
All Rights【９９】 Approach for monitoring of the reactors and removal of fuel debris
Unit 3 Reactor Building Dose map (mSv/h)(1st floor)※ red: beyond 50mSv/h ※ ※ wall surface
Measurement
point

50mm

1500mmAbove floor

Above floor

Measurement
point

50mm

1500mmAbove floor

Above floor

※※
※※

※※

※※

35
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18