0Physics of Reactors Topical Meeting 2014 - PHYSOR2014

Current Status
on Fukushima Daiichi NPS
September 29, 2014
Jun Matsumoto
Corporate Officer, Vice President,
Fukushima Daiichi Decontamination andDecommissioning Engineering Company
Tokyo Electric Power Company
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Today’s topics

1. Earthquake/tsunami and emergency response immediately
after the accident
2. Measures against contaminated water
3. Steps for decommissioning
3-1. Current status of Unit 1
3-2. Current status of Unit 2
3-3. Current status of Unit 3
3-4. Current status of Unit 4
4. Work environment etc.

All Rights Reserved ©2014 The Tokyo Electric Power Company, Inc.

1

2

1.Earthquake/tsunami and emergency
response immediately after the accident

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3

Earthquake and tsunami
Time/date of earthquake: Friday, March 11, 2011 at 14:46pm
Epicenter: Off the Sanriku coast （38°N, 142.9°E) Focal Depth of 24km Magnitude 9.0
The Japan Meteorological Agency Seismic Intensity Scale: (Range: 0-7, 10 grades with 5-U/L, 6-U/L)
7: Kurihara City, Miyagi Prefecture
6-Upper: Naraha, Tomioka, Okuma, and Futaba Towns in Fukushima Prefecture
6-Lower: Ishinomaki City & Onagawa Town, Miyagi Prefecture; Tokai Village, Ibaraki Prefecture
JSCE Wave Source
土木学会の波源
Modelsモデル（黒の部分）(black sections)

Jogan Tsunami’s
貞観津波波源Claimed Wave
SourceModelsモデル（緑）(unfixed: green)

Epicenter
震源
Fukushima Daiichi/Daini
原子力発電所

Distribution of Seismic Intensity on 3-11

海溝沿いの波源Areasalong trenchwithモデルのない
no wave source
modelsin JSCE (red)領域（赤）JSCE Method and Jogan Tsunami Claimed Sources(Jogan source is based on Satake et.al 2008)

すべり量

Tsunami Wave Source on 3-11
(Evaluated by TEPCO) Massive earthquake (magnitude 9.0 and the fourth largest ever recorded worldwide) Caused by simultaneous move of several regions: Area of 500 km x 200 km slipped off the coast along thetrench Even though the Head of Earthquake Research Promotion evaluated earthquake and tsunami for individualarea with historical records, simultaneous movements was not considered.
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Damages by tsunami

Unit5 Sea water pump area

4

The main inundation routes are:1) Building entrance2) Equipment hatches3) Emergency D/G air in-take louvers
4) Trenches, ducts (cable penetrations, etc.) etc.
The D/G and electric panel room etc. were flooded.
Unit1 D/G（１Ｂ）

Inundation height
Unit1 PCV cooling sea water pump Units 1-4: O.P.+11.5~15.5m

Height of the
Tsunami as
Predicted by
JSCE O.P.+5.4～6.1m

Units 5&6: O.P.+13~14.5
Site height
O.P.+10m(Units 1-4 *1)

Site height
O.P.4mBreakwater
Sea
water
pump
O.P.0mEmergency D/Gair supply louver

Unit1 Turbine Building Power panel

吸気ルーバーからの進入

Building entrance

・・

Equipment hatch
Basement floor

Emergency D/GPower panel

Makeup pump

Ｄ／Ｇ * 2
* 2 The Unit 6 D/G is placed in a separatebuilding such as the Reactor Building*1 The site height of Units 5 & 6 is O.P.+13m

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Core cooling after the accident

5

Immediately after the accident
A month after the accident

Fire engine

RPV

RPV

Contaminated
water

Sea
water

Sea

Continuously
accumulated

Contaminatedwater
Continuously
accumulated

Motor-driven
pump
Fresh
water
Fresh
water tank

Four month after the accident
RPVContaminatedwater

Motor-driven
pump

Fresh
water

Water treatment
Circulated and reusedFreshwater tankAfter that,
Multiplexing pumps and pipes
Replacing pipes with more durable ones
Newly installing advanced water clean-up facilities
Newly installing water storage tanks
etc. are conducted.

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Assumption of current situation

6

Current assumption of reactor condition(Water level and position of fuel debris)・ Unit 1– Almost all amount of debris is at the bottom of PCV・ Units 2 & 3 – A certain amount of debris remains RPV, and the other amount is
at the bottom of PCV.
・ Fuel debris is cooled by water of CS system and feed water system.

CS system

Feed water system

Unit 1CS
CS系
systemFeed water
給水系
systemUnit 2All Rights Reserved ©2014 The Tokyo Electric Power Company, Inc.

CS
CS系
systemFeed water
給水系
systemUnit 3Current status

7

 All plants maintain cold shutdown state.
Spent fuel pool(SFP)

Building cover* The fuel removal work was resumed on September 4, 2014, which
had been suspended since July 1, 2014 due to the annual
inspection of ceiling crane.

Blowout panel(Closed)Completionof rubble構台
removal on
top floor

Reactor building (R/B)

Fuel removal cover

Removed fuel assemblies
福島第一
安全第一
福島第一
福島第一
安全第一
安全
第一

ｸﾛｰﾗｸﾚｰﾝ1254/1533

82%；As of September 24，2014
Reactor pressure
vessel(RPV)

Cooling water
injection

Cooling water
injection

Cooling water
injection

FueldebrisVent pipe

福島第一
安全第一

Torus
Suppression chamber(S/C)

Unit 2

Unit 1

RPV bottom temp.

PCV internal
temp.

Fuel pool temp.

Unit 1

Approx.
29℃

Unit 1

Approx.
29℃

Unit 1

Approx.
26℃

Unit 2

Approx.
36℃

Unit 2

Approx.
37℃

Unit 2

Approx.
22℃

Approx.
34℃

Unit 3

Approx.
34℃

Unit 3－

Unit 4－

Unit 4

Unit 3
Unit 4

Unit 4

Unit 3

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Approx.
21℃
Approx.
22℃

Reactor cooling water injection volume

Unit 1

Feed water system： 2.6㎥/h
Core spray system： 2.0㎥/h

Unit 2Feed water system： 2.0㎥/h
Core spray system： 2.5㎥/h

Unit 3

Feed water system：1.9㎥/h
Core spray system： 2.4㎥/h

Unit 4－As of September 24, 2014

Status of airborne radioactive materials

8 Concentration of radioactive materials in the air on the site boundary additionally released
from R/B in Units 1 to 4 is 1.4×10-9 Bq/cm3 both for Cs-134 and for Cs-137.
 Radiation dose from released radioactive materials is 0.03 mSv/year on the site boundary
which is equivalent to one-seventieth of annual dose from background radiation(2.1mSv/year, mean value in Japan).
Annual dose on the site boundary by radioactive materials (cesium) released from R/B in Units 1 to 4
被ばく線量（mSv/年）
Radiationdose (mSv/year)

0.6

1.7

0.5
0.4
0.3
0.2
0.1
0.03

月

月

５

７

９月

月
３

１月

月

月
７

１１

月
５

９月

月
３

月
９

１月

月
７

月

月
５

１１

月
３

１月

月

月
９

１１

月

Month

７

0
H24年
H25年
H26年
YearH23年
2011
2012
2013
2014
（Reference）* Dust concentration in the area surrounding 1F site
* Concentration limit in the air of environment surveillanceboundary：area：[Cs-134]：ND（Detection limit: approx. 1×10-7Bq/cm3）,
-5
3
-5
3
[Cs-134]：2×10 Bq/cm ,[Cs-137]：3×10 Bq/cm[Cs-137]：ND（ Detection limit: approx. 2×10-7Bq/cm3）
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Concentration of radioactive materials in seawater
Concentration of radioactive materials has been reduced up to one-100,000th to one1,000,000th as compared to the time right after the accident.
①

North side of water outlets at Units 5 and 6②

Front of cargo unloading wharf③ Vicinity of south side of water outlet<Reference> Notified concentrations(Concentration limits for water outsideenvironmental monitoring area)
・Cesium 137: 90 Bq/L
・Cesium 134: 60 Bq/L①②

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③

9

10

2. Measures against contaminated water

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Reactor cooling and contaminated water treatment

11

 Plants have been stabilized with sufficiently low temperature by continuous circulation water cooling.
 Plant conditions have been monitored at seismic isolated building on a 24-hour basis.
Reactor building

Primary
containment vessel

Spent fuel pool
Reactor pressure
vesselInflow ofground water~400m3/day

Turbinebuilding

CesiumremovalContaminated water

Groundwater
Reactor cooling water
Approx. 320m3/day

Reactor water injection pump

Cooling by recirculating cooling water

Coolingwatertank

Approx. 720
m3/dayDesalination
・ Reserve
osmosismembrane・ Evaporative
concentration

Treated water(contaminated water)

Approx. 400 m3/day

Cooling
water
tank

Fresh
water

Back-up equipment

Temporary storage
facility
Waste sludge
Waste absorbent, etc.

Storage tanks

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Advanced Liquid
Processing System (ALPS)

Storage tanks

Current site layout

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12

Contaminated water storage tanks

13 Current available storage capacity is approx. 580,000m3 . Total amount of approx. 540,000m3 is stored in tanks.
 Available storage capacity will increase up to 800,000m3. (Under consideration on further increase in capacity )Steel square type tank

Steel horizontal tankFlange type steel
cylindrical tank

Welded type steel
cylindrical tank

Tank type
Cylindrical tank

Numbers(Units 1 to 4)
Flange type
（Bolted）

332

Welded type232

Square type tank

Welded type78

Horizontal tank

Welded type

262

(Note) Including a filtrate tank and tanks whose operation has not started.
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Contaminatedwater storage in Units 1 to 4 [単位：万ｍ3］
１～４号処理水タンク貯蔵量[Unit: 104 m3]
タンク区分
Tanks

貯蔵量
Storedamount

貯蔵容量
Capacity＊

Receiving tank of concentrated
salt water at RO device

濃縮塩水受ﾀﾝｸ

36.7
36.5

39.2
39.5

Receiving tank of fresh water

淡水受ﾀﾝｸ

2.1
2.2

2.8
2.8

Storage tank of waste water
generated by evaporative
concentration

濃縮廃液貯槽

0.9
0.9

1.0
1.0

処理水貯槽

12.8
14.2

14.1
15.2

Storage tank of water treated by
ALPS（Note） Including a filtrate tank and excluding tanks whose operation has not started.

*As of September 23, 2014

Measures against contaminated water (1/5)
Three basic principles
1. Removal of contamination source ●2. Isolation of water from contamination source ○3. Leakage prevention of contaminated water ◆Provided by Japan Space Imaging
Corporation, (C)Digital Globe

Ground improvement⑩⑪

Ocean-side
Impermeable
walls

Removal of highly
contaminated waterfrom trenches⑧

Land-side frozen-soil １
impermeable walls
Groundwater
bypassPurification system
for subdrain water

①

３

２

４

⑦

⑨

Pumping wellnear the building(Subdrain)

Emergency measures

Fundamental measures

1. Removal of highly
contaminated water fromtrenches ●2. Ground improvement at
contaminated area with waterglass, pavement of groundsurface with asphalt, etc. andpumping up groundwater ○◆3. Groundwater bypass ○4. Sub-drain ○5. Ocean-side impermeable
walls ◆
6. Land-side frozen-soil
impermeable walls ○7. Contaminated water
processing facilities withhigher performance ●
etc.

＋

＋
Main preventive measures and measures in depth

Groundwater Flow

Pavement ofground surface
for prevention
from soil
infiltration

Tank
Installation
⑥
Area

③

②

⑤
④

ALPS

14

Tank
Installation
Area(Planned)

提供：日本スペースイメージング（株）、(C)DigitalGlobe① Additional measures for mitigating inflow of groundwater (Facing) ○② Elevating dikes surrounding tanks and making dikes redundant◆③ Acceleration and reliability improvement of installation of welded type tank◆④ Covering drainage, and change on route of drainage channel into port area◆⑤ Detection of microleakage from tank◆⑥ Capture of strontium in the soil●⑦ Shortening transferring route of contaminated water◆⑧ Sealing buildings (penetration and gap between the buildings, perimeter of thebuilding)◆⑨ Countermeasure against large-scale tsunami (improvement on water-proof
performance, consideration on countermeasures such as seawall)◆⑩ Cleaning up the seawater within the port area, covering soil at the bottom of the sea
in the port area●⑪ Using contamination preventing filter which can remove radioactive materials● etc.

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Measures against contaminated water (2/5)
Emergency

Groundwater bypass [Isolation]

Fundamental

Pump up groundwater by subdrains [Isolation]15

 Groundwater bypass – Pump up groundwater flowing from the mountain side upstreamof the building to reduce groundwater inflow.
 Subdrains – Restoring subdrains and pump up groundwater around the buildings withthe subdrains to reduce groundwater inflow.
Pump-up
Reactor Building

Water Level
Pump-upTurbine Building

Pump-upPump-upPump-up Well
(Ground
Water Bypass)（地下水バイパス）

Subdrain

Subdrain
Isolating water from thecontamination source

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Pump-up

Groundwater drain
pump-upSea level

Measures against contaminated water (3/5)
Fundamental Ocean-side impermeable walls [Prevent leakage] Impermeable walls are installed on the ocean side to suppress the outflow ofgroundwater to the sea. It is scheduled to complete in September 2014.
Ocean- side Impermeable
Wall
Existing bankprotection
Permeable Layer
Low-Permeable Layer
Permeable Layer
Low-Permeable Layer

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遮水壁
Ocean-side Impermeable Wall

16

Measures against contaminated water (4/5)

17Land-side frozen-soil impermeable walls by Government support [Isolation]

Freezing plant

Unit 1
Unit 2s

Unit 3

Unit 4Ice wall

ide
im
pe
rm
ea
ble
wa
ll




Installation of underground ice walls in the mountain side area near the buildings mitigates
groundwater inflow into the buildings.
Operation is scheduled to start in March, 2015.
Construction has started since June 2, 2014.

Oc
ea
n-s



-Total length; 1,500m-Amount of soil to be froze; 70,000m3(In case Units 1 to 4 is surrounded by
ice wall)

Layout (Planned)*
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# Freezing plant(Minus 30-40℃ coolant(brine) production facility)- Cooling tower: 30 units- Brine tank
- Brine pump

* Installation range issubject to change
depending on the future
consideration.

Measures against contaminated water (5/5)
Fundamental

18

For more efficient contaminated water processing(ALPS with high-performance by Government support)

 Current ALPS has three trains. It has started processing contaminated water since March, 2013.
 Additional ALPS will also have three trains. In the middle of September, 2014, 1 train out of 3 trains started processing
contaminated water.
 High-performance ALPS will have one train. In the middle of October, 2014, it will start processing contaminated water.
Current ALPS

Outline of each system
Current
ALPS

Additional
ALPS

Highperformance
ALPS

Capacity

750
m3/day750
m3/dayOver 500
m3/dayNumber oftrains3(250 m3each)

3(250 m3
each)

1

PerformancetargetConcentration of 62 nuclides in all of 63
nuclides should be under regulatory limit(excluding tritium)High
performance
adsorbent
Simplified
preconditioning

High performance
ALPS

Filtering

2. To reduce the number of towers
and waste towers by using highperformance adsorbent
Adsorption

ROconcentrated
water

Treatedwater

Transferring water

1. Colloid remove filter etc. having
equivalent capacity to coprecipitation

Note: this diagram only shows the concept and is not necessarily corresponds to actual equipment configuration

Concept of high-performance ALPSAll Rights Reserved ©2014 The Tokyo Electric Power Company, Inc.

Waste to begenerated－－

One-twentiethof current
ALPS

Starting date

March
2013

Middle ofSept., 2014

Middle ofOct., 2014

19

3. Steps for decommissioning

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Major work for decommissioning

20

 The major work for decommissioning includes fuel removal from SFP, fueldebris removal (molten fuel), dismantling plant etc.
 Currently removing fuels from Unit 4 SFP and simultaneously preparing forstarting fuel debris removal in Units 1 to 3.

Units 1 to 2
Fuel removal from
SFP

Unit 3

Rubbleremoval,clean-up

Unit 4
Installation offuel removal
facility

Fuel removal

Storage/Trans
port

Units 1 to 3
Fuel debris removal(molten fuel)Clean-up,
Investigationof leaklocation

Water sealing,filling water

Dismantling plant etc.

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Fuel debris
removalDeveloping
scenario andtechnology

Storage/Trans
port

Designing andmanufacturing
equipment

Dismantlingetc.

Toward removal of spent fuels and fuel debris

21

 Based on constraints of construction of seismic safety/covers etc., plan and commencing
time is set for each task.
FY 2013

FY 2014

FY 2015

FY 2016

Status survey on refueling floor

Unit 1

Dismantling building cover

FY 2013

Unit 2

Fuel removal(under consideration)

Preparation for dismantling building coverRisk/Issue
Prevention of radioactive
materials from dispersion

FY 2017

Rubble removal (under consideration)

FY 2014

Installation of fuel removal building/facility (under consideration)
FY 2015

FY 2016

FY 2017

Survey on refueling floor
Decontamination/shielding on refueling floor and restoration of fuel handling facility (under consideration)
Fuel removal
Risk/Issue
Measures against dose reduction of refueling floor(Under consideration)

FY 2013

FY 2014

FY 2015

FY 2016

FY 2017

Rubble removal

Unit 3

Decontamination on refueling floor
Furl removal

Removal of rubbles inside of pool
Risk/Issue
Damage of SFPs by drop ofheavy materials

Installation of fuel removal building/facility

FY 2013

FY 2014

Installation of fuel removal building/facility

Unit 4

Fuel removal
Risk/Issue
Measures against dose reduction of workers

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FY 2015

FY 2016

FY 2017

22

3. Steps for decommissioning
3-1. Current status of Unit 1

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Current Status of Unit 1
Current Status•Building cover installed (November, 2011)•Sustained stable reactor cooling, which has reduced the generated amount of radioactive
materials

Tasks•Removal of the building cover•Identification of the status of debris on the refueling floor and inside the pools•Countermeasures for the dispersion of radioactive materials during the removal of thebuilding cover

As of Mar. 12, 2011
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Completion of building cover structure
Present

23

Building cover removal process (1/2)

24

 Ceiling panels ⇒ Wall panels ⇒ Columns and beams are to be dismantled①Ceiling panel④De-installation of beam*② Wall panel⑤Re-installation of beam *③ Frame dismantle⑥ Complete After dismantlement of the second ceiling panel, monitoring and trending will be performed to ensure
everything is fine then proceed to next panel.
* Windbreak sheet will be attached to removed beam and returned to the structure.
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Building cover removal process (2/2)

25

1. Spraying anti-scattering agent
2. Reduction of air volume into the refueling floor: By installing balloons to decrease
area of openings in the reactor building (equipment hatch, air-lock and emergency
doors), air volume flow into the refueling floor is reduced. (Installation completed onJune 4, 2014)
3. Vacuuming up roof blocks, sand and dust scattered on the fallen roof before cover
removal.
4. Installation of water spray equipment
1. Spraying anti-scattering agent

3. Debris, dust vacuum machine

Balloon

2. Installation of balloon
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4. Water spray (image)Investigation inside of torus room in Unit 1 (1/2)
 To repair (seal the water leak locations of) the PCV in preparation for the fuel debris removal, investigation undervent pipes was conducted to identify the leak locations in the PCV.
 With the images taken by the camera equipped with the water boat, it was checked whether there is any water flowfrom the sleeve ends of vent pipes or not, and the status of the sand cushion drain pipes was also checked (byviewing appearance).

PCV

Vacuum break line

SR
valv
e ex
Ven
ha u
t pi pst p
s l ee
e
ipe
ve

A
Sand
cushion

Sand cushiondrain pipe

S/C
Vent pipe

B
C
D

Location Ａ: Vent pipe sleeve
Location B: Vent pipe
Location C: Sand cushion drain
pipe
Location D: Sand cushion ringheader

サンドクッション
ドレンライン
Drain funnel

Water boat
Water boat: trial operation at the plant
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Suppression chamber (S/C)

26

Investigation inside of torus room in Unit 1 (2/2)
 By deploying a remote controlled robot on the cat walks in the torus room in the unit 1
from May 27, a leak from the cover of a expansion joint on vacuum break line was
identified.
 The investigation results will be reflected into the planning for further investigation andsealing the PCV for filling the PCV with water in the future.
SHC

CameraAC

Torus hatch V

um
acu

b

n
k li
a
e
r

e

r
wa
o
T

CV
P
d

Protective cover for
expansion joint
Leakexpansion
joint
Vacuumbreak valve

Vacuum break valve

Cat walks

Robot “Hitachi Tele Runner

Image of investigation on upper part of suppression chamber
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27

28

3. Steps for decommissioning
3-2. Current status of Unit 2

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Current Status of Unit 2
Current Status•Very high radiation level in the building
Inspection of contamination status on the refueling floor will be conducted in the future.

Tasks•Radiation dose reduction measures•Countermeasures for the dispersion of radioactive materials during engineering work
Opened blowout panel

As of Apr. 10, 2011
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Present29

Preparation for fuel debris removal in Unit 2 (1/2)

30

 A water level gauge was introduced into PCV, and water level was confirmed (bottom + approx. 60cm) in Unit 2.
 Investigation for identifying leakage: Since the water level inside S/C seems to be relatively low, remote-operated
device investigated the inside of S/C with ultrasonic wave. As a result, it was confirmed that water level inside S/C
is almost the same as that outside S/C (Groundwater level in R/B).
 Fuel debris status investigation: A investigation device will be inserted into PCV so that location of fuel debris at
the bottom of PCV can be identified (the following ①-⑤). As a preliminary investigation, a camera was inserted
into the vicinity of the bottom of RPV (Opening of pedestal)(①, ②). Status of interference objects will be confirmed,
and the result will be reflected on the actual investigation plan.
Preliminary investigation （①, ②）

ＰＣＶ

For the purpose of identifying access route inpedestal, status inside PCV and circumstantialcondition①Status investigation
on CRD rail and openingof pedestal②Status/circumstanceinvestigation on the inside ofpedestal

Implemented from X-53 penetration
on August, 2013

Planned to be implemented from X-6 penetration.

RPV

For the purpose of identifying location(distribution) of fuel debris③CRD/Platform investigation
CRD④Pedestal bottom
investigation
Platform

X-6
penetration

CRD exchanging
rail

Full-scale investigation（③, ④, ⑤）⑤*Investigation of
personnel access openingat pedestal bottom

Opening of pedestal
Personnel airlock* As for ⑤, access from the outside of pedestal is also under consideration.

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Preparation for fuel debris removal in Unit 2 (2/2)

31

 A survey will be conducted on the pedestal's internal side in order to check the condition inside the PCV (fueldebris position, etc.).
 In preparation for the survey, equipment was introduced from the penetration (cameras, dosimeters andthermometers) to investigate the status of the CRD exchanging rail, etc. (August 12, 2013)
 The survey was conducted up to the vicinity of the opening of pedestal. However, the interior could not bechecked due to interference by deposits, etc.
 Based on the issues identified by the preliminary survey, survey equipment has been developed and will be tested
in the field in the second half of FY 2014.
Penetration

RPVVideo position/direction(3)
Opening Of pedestal

X-53
PCV

Opening of pedestal

Penetration

X-6

(1)
(2)
(3)

Found what seems to be a cable

Pedestal

1st floor grating
CRD exchanging rail
Atmospheric radiationlevelsTemperature(1)

About 24 Sv/h

About 41 ℃

(2)About 30 Sv/h

About 45 ℃

(3)About 36 Sv/h

About 45 ℃

the pedestal entrance at Unit 2
Pedestal: foundation of the bottom of RPV

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Reference: opening of pedestal at Unit 5

Measurement of water level inside of torus room in Unit 2 (1/2)

32

 To repair (seal the water leak locations of) the PCV in preparation for the fuel debris removal, the waterlevel in S/C was measured to assume the state of the opening area at leak locations in the PCV.
(By checking the water level difference between the inside and outside of the S/C, the opening area
was assumed, and it will be considered that it is possible whether the water sealing material might flowout of the S/C or not.)Water levelmeasurement device

Ascending/descending unit

Winch unit

Transfer unit

Status of installation of device on
S/C outer surface

Appearance of measurement
device-hanging/retrieving device

Outer surface on S/CTorus room

トーラス室

S/C
Ｓ／Ｃ

Device-hanging/retrieving device
装置吊り
下ろし・回
収装置

Water levelmeasurement device

Water level
Ｓ／Ｃ内
difference
水位測定
between theinsideand outside
装置of S/C:

Water levelmeasurement
deviceMovingApprox. 30 cm

Accumulated water surface
in torus room

Overview on water level measurement in S/C at Unit 2
All Rights Reserved ©2014 The Tokyo Electric Power Company, Inc.

Measurement by device

Measurement of water level inside of torus room in Unit 2 (2/2)

33 The measuring was conducted from January 14 to 16 at multiple lines (multiple longitudes) in orderto enhance the reliability of specifying the exact water level. The numerical values of January 14 and
15 in the following chart were obtained in the middle of the series of the data collecting work.
Measuring date

January 14

January 15

January 16

Water level inside S/CApprox. OP. 3,210 mm

Approx. OP. 3,160 mm

Approx. OP. 3,150 mm

Water level inside Torus
Room (Reference)

Approx. OP. 3,230 mm

Approx. OP. 3,190 mm

Approx. OP. 3,160 mm

Water level difference

Approx. 20 mm

Approx. 30 mm

Approx. 10 mm

Measuring method

Direct distance measuring for structures the in the water[Note] It is estimated that the water level inside the S/C is influenced by the change of the water level of accumulating water inside the torus room.
S/C diameter: 8900mm
Ven
t pip
e

First floor level of the Unit 2
Reactor Building: OP 10,200 mm

Ｓ／Ｃ

S/C equator : OP 1,900 mm

During the water level measuring
All Rights Reserved ©2014 The Tokyo Electric Power Company, Inc.

First basement floor of the Unit 2
Reactor Building (Lowest level): OP-3,360 mm

34

Measurement of water levels inside of PCV in Unit 2
 After failing to insert a measurement instrument in March 2012, re-inserting of an
instrument was successful in early June 2014.
 Water levels and temperatures inside PCV have since been monitored.

［As of 8:00, June 11, 2014］：Thermometer：Water gauge

Monitoring results
Height

TE08

X-53

X-53
OP12,460

Temp.[℃]

The water level seems to bearound over flow height into
the vent pipe

TE07

V
PC

Grating OP 9,510

ell
sh

pe
t pi
ven

TE06

Water depth :300 mm

TE05
TE04
TE03
TE02
TE01

LE05
LE04
LE03
LE02
LE01

344 mm(design value)

Water level

TE08

33.7

－

－

OP.11,920

TE07

33.7

－

－

OP.10,690

TE06

33.5

－

－

OP.8,100

TE05

33.5

LE05

OFF

OP.6,430

TE04

33.5

LE04

OFF

OP.6,230

TE03

33.6

LE03

OFF

OP.6,030

TE02

35.0

LE02

OFF

*350 mm from the bottom of
PCV

TE01

35.8

LE01

ON

* 350 mm from the bottomof PCV

OP.5,830
Bottom of PCV

Ref: around a vent pipe

Bottom of PCV OP 5,480

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OP.5,630

35

3. Steps for decommissioning
3-3. Current status of Unit 3

All Rights Reserved ©2014 The Tokyo Electric Power Company, Inc.

Current Status of Unit 3

36

Current Status•Debris removal from the top of the reactor building completed (October 11, 2013)•Installation of fuel removal cover and fuel handling facility planned•Steel frame debris dropped into SFP (September, 2012)•Beginning target of fuel removal activities rescheduled from the perspective of getting safety most prioritized(Changed from the end of December, 2014 to the end of September, 2015)
Tasks•Due to high radiation levels, radiation dose reduction measures must be conducted safely and steadily withremote-controlled heavy machinery.

Completion ofdebris removal
As of Oct. 11, 2013

Damaged byhydrogen explosion
As of Feb. 12, 2012
Measuresagainstrainwater(protection
againstrainwater)

North

Present
Fuel handling machine
Crane

Fuel removal
Image of Fuel removal
cover
cover structure

All Rights Reserved ©2014 The Tokyo Electric Power Company, Inc.

Spent fuel removal

37

 With remotely operated heavy machinery, the removing activity of debris from the top floor
completed (October 11, 2013)
 Fuel removal from spent fuel pool continuously conducted Currently developing/implementing the plan for decontamination and shielding against radiationN

Photo taken on March 24, 2011
Before large debris removal
N

Photo taken on April 19, 2014
All Rights Reserved ©2014 The Tokyo Electric Power Company, Inc.

After removal of large debris

Water flow from area near MSIV room (1/2)

38

Water flow from area near MSIV room to floor drain funnel on 1st floor in R/B at Unit 3
 On January 18, 2014, checking the camera images from the debris removal robot (ASTACO-SoRa) inunit 3, our personnel found that water flowing from the area near the door of the main steam isolation
valve (MSIV) room toward the floor drain funnel in the vicinity in the north-eastern area on the 1st floor
at Unit 3 R/B.
 On January 21, 2014, it was identified that water injection amount was greatly reduced while the robot
was operated for debris removal work.
 No change on plant parameter, etc has been found.

North

Floor drain
funnel(RF-123B)

Water flow

Floor drain funnel
Water flow confirmed (on Jan. 18)

MSIV
room

Remote-controlled
heavy machinery(ASTACO-SoRa)
Floor map of 1st floor in R/B at Unit 3

Water flow reduction confirmed(on Jan. 21)

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39

Identification of water leakage in Unit 3
 On May 15, by inserting a camera into the Main Steam Isolation Valve (MSIV) room, a leak fromaround a Main Steam (MS) line was identified. It was the first confirmation of a leak from the Unit 3
PCV.

Expansion joint Ｃ
構台
福島第一
安全第一
福島第一
福島第一
安全第一
安
全
第
一

Expansion joint Ｄ

Pan-tilt camera

Water flow

Pan-tilt camera

injection

Dose monitor

Endoscope camera
Endoscope camera
R/B 2nd floor
HVAC room

安全第一
福島第一

Penetration on
PCV by MS pipes
R/B 1st floor
MSIV room

Backup penetration（X-46,47）

MS process
radiation
monitorFeed water penetration（X-9A,B）

O.P.13270
Level of water inside
PCV(estimated by water head)

O.P.12020～12090
O.P.11670

Ｂ

Ａ

PCV side

O.P.15280
Feed water pipes

grating

Ａ

Ｂ

Ｃ

Ｄ

MS pipes

MS penetration（X-A to D）

O.P.10610
MS drain penetration（X-8）

Penetration on PCV in MSIV room
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Cross section of MSIV room

Water flow from area near MSIV room (2/2)

40

Water flow from area near MSIV room to floor drain funnel on 1st floor in R/B
at Unit 3 (Estimation of the flow pathway )Containment vessel pipe penetration seal
 There are a total of 9 pipe penetration seals in the MSIV
room: main steam system (X-7A~D), main steam systemdrain (X-8), feed water system (X-9A,B), and the backup
penetrations (X-46,47)
 The height of the main steam system and the main steam
system drain penetrations (total of 5 places) are estimated to
be at a lower level than PCV water level (estimated waterlevel from pressure conversion)
Containment vessel water level(Estimated water level from pressure conversion)
O.P.12020~12090
Backup(X-46,47)
Height: O.P. approx. 14800~15300
Feed water system pipe penetration seal (X-9A,B)
Height: O.P. approx. 12800~13700
Main steam system pipe penetration seal (X-7A~D)
Height: O.P. approx. 11100~12200
Main steam system drain pipe penetration seal (X-8)
Height: O.P. approx. 10400~10800

Unit 3 Reactor Building cross-section

All Rights Reserved ©2014 The Tokyo Electric Power Company, Inc.

41

3. Steps for decommissioning
3-4. Current status of Unit 4

All Rights Reserved ©2014 The Tokyo Electric Power Company, Inc.

Current Status of Unit 4
Current Status•Fuel removal from SFP commenced (November 18, 2013, target by the end of year 2014)

Tasks•Continuing work while ensuring safety•Exploring the methodology for the removal of the fuels with their leaks confirmed

As of Sep. 22, 2011

All Rights Reserved ©2014 The Tokyo Electric Power Company, Inc.

Fuel Removal Cover Structure
Present42

Spent fuel removal (1/2)

43 1254/1533 fuels have been already removed and transported to common fuel poolon site as of September 24, 2014.
• Fuels have been removed from Spent Fuel Pool (SFP) in Unit 4 since November
18, 2013.
• 1533 fuels was stored inside SFP at the time of starting fuel removal.
They are scheduled to be completely removed by the end of year 2014.
Defueling cover
Fuel
handling
facility

Crane
Fuel handlingmachine (FHM)

Work environment
arrangement area(within dot line)
Spent fuel pool (SFP)
Fuel assembly
Spent fuel storage rackOn-sitetransporting cask

Fuel removal

Cask
pit

キャスク
ピット

Storage area
貯蔵エリア

キャスク
ピット

Ensuring
空きスペース
emptyの確保
space.

On-site transport
Common pool on site
All Rights Reserved ©2014 The Tokyo Electric Power Company, Inc.

Cask
pit

Spent fuel removal (2/2)
Fuel removal activity

44

Loading the cask on transporting vehicle

All Rights Reserved ©2014 The Tokyo Electric Power Company, Inc.

45

4. Work environment etc.

All Rights Reserved ©2014 The Tokyo Electric Power Company, Inc.

Number of workers

46

 Since registered workers are approx. 12,500* and workers who actually conducted theactivities in the field are approx. 9,600*, registered workers are ensured with a certain
margin.
 The average number of workers per weekday in each month of FY 2014 wasapproximately between 3,000 and 5,800.
 Employment rate of contractors and TEPCO personnel who had lived near the plant siting
area is approximately 45% as of August, 2014.
Numberof workers per weekday
平日１日あたりの作業員数* The average number of workers in each month from May to July, 2014
7000
6000

5490

5000

4450

4000

3130

3000
2950 3060 3130

3290

2990

3220

3410 3540

3730

4020

5730 5800

4840

4270

2000
1000
0
Apr
４月

May
５月

Jun
６月

Jul
７月

Aug
８月 Sep
９月

Oct １１月
Nov １２月
Dec １月
Jan
１０月

Feb
２月

Mar
３月 Apr
４月 May
５月

Jun
６月

Jul
７月

Aug
８月

FY 2013
FY 2014
Trend in the average number of workers per weekday in each month of FY 2013 and 2014
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Radiation exposure of workers

47

For most workers, the exposure dose is sufficiently within the limit and at a level
which allows them to continue engaging in radiation work.
•Cumulative radiation exposure in FY 2012 was 20 mSv/year or less for approx. 95% of the total.
•Cumulative radiation exposure in FY 2013 was 20 mSv/year or less for approx. 96% of the total.
Cumulative radiation exposure in FY 2012
TEPCO Contractors

Cumulative radiation exposure in FY 2013
TEPCO Contractors

Total

Category (mSv)

employees

Total

Category (mSv)

employees

Over 250000Over 250000Over 200 and no more than 250

0

0

0

Over 200 and no more than 250

0

0

0

Over 150 and no more than 200

0

0

0

Over 150 and no more than 200

0

0

0

Over 100 and no more than 150

0

0

0

Over 100 and no more than 150

0

0

0

Over 50 and no more than 100

1

0

1

Over 50 and no more than 100

0

0

0

Over 20 and no more than 50

62

567

629

Over 20 and no more than 50

30

625

655

Over 10 and no more than 20

129

1778

1907

Over 10 and no more than 20

93

2049

2142

Over 5 and no more than 10

261

1837

2098

Over 5 and no more than 10

195

1882

2077

5 or less

1159

7427

8586

5 or less

1375

8492

9867

Total

1612

11609 13221

Total

1693

13048 14741

Maximum

53.97

41.45

53.97

Maximum

41.59

41.36

41.59

Average

4.46

5.44

6.32

Average

3.18

5.46

5.20

The radiation exposure of 95% workers are 20 mSv or less in FY 2012
The radiation exposure of 96% workers are 20 mSv or less in FY 2013
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Improvement on work environment - Dose reduction (1/2)

48

To reduce dose of site workers, dose reduction is proceeded through deforestation, top soil removal, soil flippingand shielding, etc, considering characteristics of fall-out contamination and radiation source per area (direct rays,
leakage points of contaminated water etc.) on the Fukushima Daiichi Nuclear Power Station's entire site.
Target radiation dose rates will be gradually marked down, ultimately coming close to pre-accident levels.
Area

Ⅰ

Current dose
[μSv/h] *1

Target dose
[μSv/h] *2

Measures against dose
reduction＞100+radiation

Investigating
detailed
situation ofradiation
source andsetting targetof dose rate

- Removing rubble impeding works- Shielding main road, pipe with highdose etc.
- Considering direct ray from building
and facility etc. based on
decommissioning process

Ⅰ
Ⅱ- Deforestation, top soil removal, soil
flipping and shielding etc.

Ⅲ

- Deforestation, top soil removal, soil
flipping and shielding etc. at the timeof installation- Implementing them in order fromthe area contaminated by theleakage of contaminated water- Treating water with highcontamination level

Ⅱ
Ⅲ

10100

Ⅳ

Provided by: Japan Space Imaging Corporation, (C) Digital GlobeArea Ⅰ Areas in the vicinity of Units 1-4 where radiation dose rates are
particularly highArea Ⅱ Planting areas and areas with remaining woods
Area Ⅲ Areas where facilities are installed or are to be installed in the future
Area Ⅳ Already paved areas, such as streets and parking lots
Scope of the mid- and long-term implementation policy for reducing on-site dose

All Rights Reserved ©2014 The Tokyo Electric Power Company, Inc.

＜5

Ⅳ

-Cleaning road surface, replacementof pavement, shielding etc.
- Implementing them in order fromthe area where many workers exist,
work interference is small

Other
Area

- Conducting clean-up based on siteutilization plan
- The area surrounding Units 5 and 6
has low dose level, and there is nosite utilization plan in the north ofsolid waste storage area.

5-50

―

*1

Survey results with on-site vehicles (Nov. 21, 2013)*2

Mean value without impact form direct rays per block where clean-up was conductedImprovement on work environment - Dose reduction (2/2)◇ Efforts to expand the low radiation dose area toreduce radiation dose for site workers
Measures for dose reduction (e.g. removal and area
shielding etc. of rubbles disturbing decommissioningwork) are being conducted.
Since the area surrounding Units 1 to 4 (AreaⅠ) is
high-radiation area where plants and facilities exists,
dose reduction will be conducted according to theschedule regarding dismantlement of high-radiation
facilities and rubble removal of R/B.

49

平成25年度末
Expected areas at the end of FY 2013

Ⅰ

Ⅱ
Ⅲ

Ⅳ

Provided by Japan Space Imaging Corporation, (C)DigitalGlobe

Expected areas 予想
at the end of FY 2014
平成2６年度末

Provided by Japan Space Imaging Corporation, (C)DigitalGlobe

Expected areas予想
at the end of FY 2015
平成2７年度末

Provided by Japan Space Imaging Corporation, (C)DigitalGlobe* Areas with approx. 5 μSv/h are marked withAll Rights Reserved ©2014 The Tokyo Electric Power Company, Inc.

.

Improvement on work environment - Temporary office administrative building 50

Administrative room inside the building
Progress outline

Illustration of building exterior*

As for temporary office administrative building, 1st phase of construction
was completed. (June 30, 2014) The operation partly started. (July 22, 2014)
The vicinity of access control building is considered as a candidate site forconstruction of main office administrative building.

All Rights Reserved ©2014 The Tokyo Electric Power Company, Inc.

Improvement on work environment - Fukushima meal service center
Fukushima meal
service center

Leftovers,
eating utensils

Kitchen（Cooking,
cleaning-up）

Cooked meal,eating utensils

Fukushima
DaiichiTemporary officeadministrative building,
Large size break area

The way to provide on Fukushimameal service center
Conceptual drawing on completion of construction

Progress outline
2013

TEPCO

Tousouhudousan
kanri Co., Ltd.

Business consignment(Operation of Fukushima meal

second halfmeal service

first halfsecond half

center Co.,Ltd.

Partial business consignment(Cooking, distributing, procuringservice center)(Investment）

meals）

70%

2014

Item

Fukushima Fukko

20%

Planning

Selection of premise anddevelopment of basic plan

10%

Nippon General FoodTokyoLivingService

Torifuji Shoten

Co., Ltd.

Co.,Ltd.

Co.,Ltd. HQ

Design andconstruction

Operation scheme
All Rights Reserved ©2014 The Tokyo Electric Power Company, Inc.

51

Design and construction

Promotion of decommissioning work

52

 Fukushima Daiichi Decontamination and Decommissioning Engineering Company(FDEC) was established to control the entire decommissioning-related divisions.
Decommissioning and measures against contaminated water issue will be expedited as aJapanese government project by collecting the wisdom from experts inside and outside ofJapan.
[Currently][UntilMarch, 2014][April 2014
onwards][Present]

National Government
Inter‐Ministerial Council for Contaminated
Water and Decommissioning Issues

Main guidelines
Nuclear Damage
Compensation andDecommissioning
supportDecommissioning Facilitation
Corporation（NDF）
organizations

International Research Institutefor Nuclear Decommissioning

Directives, etc.
Corporation

Decommissioning
Company
Funding, staff,
technology

Nuclear Power &Plant Siting
Division

Person with ultimate responsibility fordecommissioning and water decontamination(CDO, Company President)
Vice President

Active use of internaland external
personnel withspecialist knowledge

Company Management
Committee

Internal company
subdivision

Enhanced project
management&
6

Contaminated water5

Decommissioning

Units

Fukushima Daini
Daini
Fukushima

Kashiwazaki-Kariwa
Kashiwazaki-Kariwa

Higashidori
Higashidori* Decommission
Units 5 & 6;
use for R&D

Fukushima
Fukushima Daiichi
Daiichi
Improved on-site capability
International platform for decommissioning
and nuclear power safety

All Rights Reserved ©2014 The Tokyo Electric Power Company, Inc.

Building an international
promotional structure
as a Japanese nationwide system

For more information53

 Updated information regarding decommissioning is shared on TEPCO website.
http://www.tepco.co.jp/en/decommision/index-e.html

Click<Result of radioactive analysis around
Fukushima Daiichi NPS map imaging>
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<Photo and video library>

54

We will push forward with
our reforms in earnest.

All Rights Reserved ©2014 The Tokyo Electric Power Company, Inc.