Nuclear Damage Compensation and Decommissioning Facilitation Corporation

Technical Strategic Plan 2019for Decommissioning of the Fukushima
Daiichi Nuclear Power Station ofTokyo Electric Power Company Holdings, Inc.
(Explanatory Material)
September 9, 2019
Nuclear Damage Compensation andDecommissioning Facilitation Corporation
NDF
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Table of Contents
1. Introduction
2. Risk sources at Fukushima Daiichi NPS and the future risk reduction
strategy
3. Technological strategies toward decommissioning of the Fukushima
Daiichi NPS[1] Fuel debris retrieval[2] Waste management[3] Contaminated water management[4] Fuel removal from spent fuel pools
4. Handling critical enablers related to the comprehensive approach andsmooth operation of the project
5. Local community engagement

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11. Introduction
 Strategic Plan 2019 provides strategic recommendation on how to retrieve fuel debris fromthe first implementing unit.
 Mid-and-long-term directions that look at the overall efforts of the Fukushima Daiichi NPS,
including waste management, are presented.
Government*) Continually revise based on the progress of programs

Mid-and-Long-Term Roadmap*)

Next R&D Plan

(Project of Decommissioning andContaminated water management)

Proposals for Revision

Strategic Plan (annual)

NDF

The Policy for Preparation ofWithdrawal Plan for Reserve Fundfor Decommissioning (annual)

Withdrawal Plan for Reserve Fundfor Decommissioning (annual)* Jointly created with NDF and approved by METITEPCO

On-site work
Engineering

Planning from
Mid-and-long-term aspect

Feedback

Technological
Development

Promotion of Decommissioning project

Fig. Positioning of the Strategic Plan based on the system of the Reserve Fund
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22. Risk Sources at Fukushima Daiichi NPS and Future Risk Reduction Strategy(1/2)
Basic policy on decommissioning

To continuously and quickly reduce the radioactive risks caused by the accident that do not exist in a normal NPS

Progress in decommissioning
Fuel debris retrieval• Unit 2 (Feb 2019) Deposit contact investigation in the PCV revealed that the deposits are movable at the bottomof the PCV pedestal and on the platform.

Waste management• (Jun 2019) Waste storage management plan was revised.

Contaminated water management【REMOVING】 (continuing) Contaminated water is being purified by multi-nuclide removal equipment, etc.
【REDIRECTING】 (Sep 2018) All areas of the land-side impermeable wall were frozen.
【RETAINING from leakage】(Mar 2019) Transfer of the water purified by the purification equipment to welded tanks
was completed.*【Treatment of stagnant water in buildings】(in 2018) Disconnection of the communication section between Units 1 and
2 was achieved.
* As for the treatment of the water stored in the welded tanks, comprehensive discussion including social standpoints has been madein the government-led subcommittee

Fuel removal from spent fuel pools• Unit 1 (continuing) Removal of rubble on the operating floor is ongoing.
• Unit 2 (Nov 2018 to Feb 2019) Investigations were conducted on the contamination state of the operating floor.
• Unit 3 (Apr 2019) fuel removal from SFP was started.
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32. Risk Sources at Fukushima Daiichi NPS and Future Risk Reduction Strategy
(2/2)

*1

 The interim goal of the risk reduction strategy is to bring the risk levels into the "Region of
sufficiently stable management" (areas in pale blue).

*2

Example of Risk Levels for Fukushima Daiichi NPS*1 : An index of impact of the event, that depends on inventory (radioactive material), form of the risk source and time allowable until the
manifestation of risk in case of loss of safety function.
*2 : An index of likelihood that an event will occur, that depends on integrity of facility and on the packaging and monitoring status of risk source.
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3. Technological strategies toward decommissioning of the Fukushima Daiichi NPS([1] Fuel debris retrieval)
Goals(1) Retrieve fuel debris safely after thorough and careful preparations, including safetymeasures, and bring them to the state of stable storage under full management.
(2) Toward determination of the fuel debris retrieval methods for the first implementing unit in
FY 2019, and start of fuel debris retrieval work for the first implementing unit in 2021,
necessary approaches will be taken according to the Policy on Fuel Debris Retrieval.
Policy on fuel debris retrieval①

Step-by-step approach- Flexibly coordinate the direction while proceeding with the retrieval
work②

Optimization of the overall decommissioning work
- Examine fuel debris retrieval work as a comprehensive project,including coordination with other works③

Combination of multiple methods- Combine the optimum retrieval methods for each unit, depending on
the locations where fuel debris is considered to be present④

Approach focused on partial submersion method- Make efforts to focus on a more feasible partial submersion method⑤

Prioritizing fuel debris retrieval by access to the bottom of the
PCV from the side
- It should be considered that the accessibility to fuel debris and theremoval of spent fuel can be accomplished in parallel

RPV

Retrieval device

PCV
Pedestal

Cell

Fuel debris
Basement

Image of the partial submersion - side
access method

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3. Technological strategies toward decommissioning of the Fukushima Daiichi NPS([1] Fuel debris retrieval)
Strategies
Approach to risk reduction in fuel debris retrieval work

 Since retrieving of fuel debris by partial submersion method is unprecedented project in theworld and the information on the condition inside the PCVs is limited, it is important toproceed with operation carefully upon enough and well making preparations.
 By starting with small-scale retrieval basically using existing safety systems such asconfinement (hereafter referred to as “existing safety system” without significant modificationin the state such like processing PCV wall, a series of operations from retrieval to storage will
be performed on a continuous basis, the risk of fuel debris will be reduced and quick
effectiveness of the required systems will be ensured.
 Expected effects by small-scale retrieval in the first implementing unit Equipment, facilities and safety systems, including remote operations, can be verified.
 TEPCO can exploit this occasion as a process of mastering fuel debris retrieval operation.
 Information helpful to understand the situation inside PCV can be obtained.
 After retrieval in the first implementing unit, the amount of fuel debris to be retrieved will be
increased based on the knowledge obtained, or retrieval will be started in units other than thefirst implementing one.
 To expand the scale of retrieval or perform the retrieval operation in units other than the first
implementing unit, it is necessary to examine the actual site applicability based on theconcept of safety systems, and further improve the site environment including further radiationdose reduction, lowering of the water levels and securing of the premises, and conduct
internal investigations and R&D activities.
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63. Technological strategies toward decommissioning of the Fukushima Daiichi NPS([1] Fuel debris retrieval)
Strategies

Outline of the strategic recommendation for determining
fuel debris retrieval methods for the first implementing unit

Progress of R&D and PVC internal investigations••

Deposits in Unit 2 are movable.
Development of the arm-type access equipment
has been taking form.

Progress of work environment improvement• Radiation dose in Unit 2 is relatively
low.

•
•

Utilize existing safety systems and arm-type access equipmentthat actual site applicability is getting in sight .
Start from small-scale retrieval by methods such as gripping andsucking, and also prepare plans for crushing of fuel debris.
Contain retrieved debris in small containers and transfer them,
contain them into canisters, and then store them at the dry
temporary storage facility within site .

•Spent fuel removal from SFP can be
performed in parallel with fuel debris
retrieval operation.

Study results of the actual site applicability for each unit

Study on the retrieval concept•

Progress of site-wide planning•••

Unit 1: Although the air-tightness of existing safety systems is relatively high, theradiation dose in the work environment is high, and the access route has been
unidentified.
Unit 2: The air-tightness of existing safety systems is high, and the radiation dose in
the work environment is relatively low. The access route has been mostly confirmed.
Unit 3: The access route has been mostly confirmed, but the air-tightness of existing
safety systems is lower than other units, and the radiation dose in the work
environment is relatively high.

: Preliminary engineering

Comprehensive assessment

 In Unit 2, fuel debris can be retrieved “safely”, “reliably” and “promptly” using an arm-type accessequipment, and the risk resulting from all fuel debris in Units 1 to 3 can be “promptly” reduced.

Points to be recommended for determining fuel debris retrieval method for the first implementing unit
[1]
[2]
[3]
[4]
[5]

Fuel debris retrieval should be started on a small-scale basis by methods such as gripping and sucking.
Next step of fuel debris operation are to be studied using information and experience accumulated through previous operation .
Retrieved fuel debris should be transferred to the on-site temporary dry storage facilities at the Fukushima Daiichi NPS.
Unit 2 is most appropriate as the first implementing unit from the viewpoint of optimization of the overall decommissioning work,and so on .
The method for expanded scale of fuel debris retrieval should be determined by proceeding with engineering including theassessment of safety based on progress of R&D, PCV internal investigation, Improvement of site condition as well as
information & experience accumulated through previous operation.
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3. Technological strategies toward decommissioning of the Fukushima Daiichi NPS([1] Fuel debris retrieval)
Challenges
Comprehensive understanding of PCV conditions
by continued internal investigations, etc.

Approach to the commencement of fuel debris
retrieval from the first implementing unit (Unit 2)

 Internal investigations and sampling must be
carefully prepared over a certain period of time.
Unit 1:

Unit 2:

Unit 3:

Investigations on the distribution of deposits (including asmall-amount sampling) are scheduled to begin in thesecond half of FY 2019.
Deposit contact investigations were conducted in thesecond half of FY 2018 (conducted on 2/13).
Investigations on the distribution of deposits (including asmall-amount sampling) are scheduled to begin in thesecond half of FY 2019.
The necessity of further investigations by means ofmeasures for lowering the water levels in PCVs and using
an submersible-type access robot are being examined.

 The method of retrieving fuel debris from Unit 2
should be determined in line with therecommendations.
 In determining the method of fuel debris
retrieval in Unit 2, the following issues need tobe considered.


Removal of obstacles in consideration ofenhancing the prevention of the scattering ofradioactive materials

Reduction of the on-site radiation dose on the 1st
floor of the reactor building

Adjustment of work interference in cases where
the operations of fuel removal from SFP and fueldebris retrieval are carried out in parallelFig. Deposit contact investigations in Unit 2** Source: TEPCOUnauthorized reproduction prohibited - Nuclear Damage Compensation andDecommissioning Facilitation Corporation©Nuclear Damage Compensation and Decommissioning Facilitation Corporation

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3. Technological strategies toward decommissioning of the Fukushima Daiichi NPS([2] Waste management)
Goals
(1)

(2)

As the approaches to solid waste storage, the Solid Waste Storage Management Plan (“Storage Management Plan”) is appropriately
developed, revised and implemented, including waste prevention, volume reduction and monitoring, while updating the estimated amount of solid
waste to be generated in the next 10 years periodically.
As an approach to processing/disposal, countermeasures integrated from characterization to processing/disposal of solid waste are studied fromexpert point of view, and. the prospects of a processing/disposal method and technology related to its safety should be made clear byaround FY 2021

Strategies andChallenges


Fiscal Year

Promotion of characterization andenhancement of analysis systems andtechnical capabilities

Through the development of radioactive
material analysis and research facilities andthe fostering of analytical human resources,
technologies, facilities, and the systemshould be established to continuously, timely
and appropriately carry out the analyticalwork necessary for decommissioning.
Development of the processing/disposal
concept and safety assessment method

Milestones

2015

2016

2017

2019

2020

2021

2022 and later*

Based onClarification of technical prospects onprocessing/disposal method and its safety

Compilation of basic conceptof processing/disposal

1. Waste Characterization(1) Analysis data acquisition, management, etc.

Planning/updating analysis plan, conducting analysis, characterization, accumulation/evaluation/management of analysis data*
Development of radioactive material analysis and research facilities(2) Improvement of analysis capacity
Human resource development for analysis personnel*(3) Improvement in efficiency of waste
characterization

Optimization of the number of analytical samples, review of nuclides to be analyzed,
simplified and speed-up analysis methods, etc.

2.Storage(1) Storage management plan

For candidate technologies for preceding
processing, reasonable and feasible(2) Study and evaluation of Storage method
technologies should be selected, and a safety(3) Study and evaluation of Storage methods
assessment method should be developed.
of solid waste generated during fuel debris
retrievalOn-site work
Technical studies for on-site
construction, etc., for each item
Research and development

2018

Development and review of the Storage Management Plan*
Study on Storage measures of secondary waste from water treatment

Study on Storage method, storage containers, and the way of putting waste into container

Establishment of a
selection system of preceding
procesing methods

3. Development of processing/disposal
concept and safety assessment method

Study on safety
improvement
measures*
Use of a selected
system*Survey and development of a safety assessment method for each disposal method

Survey on conditioning
technology

Technical development of processinhg methods related tostabilization and immobilization*

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93. Technological strategies toward decommissioning of the Fukushima Daiichi NPS([3] Contaminated water management)
Goals
(1)

(2)

Under the three basic principles concerning contaminated water issues (“Removing” contamination sources, “Redirecting” fresh water fromcontamination sources, and “Retaining” contaminated water from leakage), while continuing reinforced and optimum operations of thewater level control system, multilayered measures should be taken to complete the processing of the stagnant water in buildings
by 2020.
Considering the total decommissioning process, including the full-scale fuel debris retrieval beginning in near future, a long-term
strategy should be examined for the measures of the contaminated water.

Strategies andChallenges

Fiscal Year

2019



Steady execution of contaminatedwater management indicated in the
Mid-and-Long-term Roadmap
 Study on contaminated water
management based on therelationship with fuel debris retrieval
 It is necessary to proceed with theexamination of the entire system,
including enhancement of themonitoring to confirm theconcentration of radioactive materials
at the inlet of the water treatment
system.
 Further enhancement is needed onmonitoring system for water level ofgroundwater and radioactive materials
for the purpose of steadily managing
the groundwater surrounding thebuildings as well as implementing
regular inspections and updates offacilities for sure.
:
:

2020

2021

2022

2023

Reducing the total amount of contaminated water toabout 150 m per day

Milestones

Complete the treatment of stagnant water in buildings(1) Contaminated water management
as shown in the mid-and-Long-term
Roadmap
Treatment with purification Systems･ REMOVING contamination sources

Control by groundwater by-pass, subdrainage and land-side impermeable walls･ REDIRECTING fresh water fromcontamination sources

Paving the site, Removal of
rubble from the roof, Waterproofing
To be responded properly according to generation of contaminated water, etc.

Securing Tank capacity･ RETAINING contaminated water fromleakage･ Treatment for the stagnant water inthe buildings

Ground stabilization, Maintenance of land-side impermeable wall,
Monitoring of groundwater/inside harbor
Lowering the level of groundwater/
stagnant water in the buildings(2) Contaminated water management
in consideration of fuel debris
retrieval

Determination of fuel debris
retrieval methods for the first
implementing unit

Maintaining exposed condition of thefloor line for turbine buildings
Start of fuel debris retrieval
from the first implementing unit

Studies on PCV circulation coolingsystem and its monitoring method

Taking required actions in accordance withthe phase of fuel debris retrival

On-site operation
Technical reviews for the on-site construction, etc., for each item
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the fuel stored in the Ccommon Sspent Ffuel Sstorage Ppool

3. Technological strategies toward decommissioning of the Fukushima Daiichi NPS([4] Fuel removal from spent fuel pools)
Goals
(1)

Risk assessment and management for the progress of the work will be carried out properly, and measures for safety and security
including the prevention of the scattering of radioactive materials will be undertaken thoroughly. For Units 1 and 2, the removal offuel in SFP will start by 2023. For Unit 3, the removal is scheduled to be completed in FY 2020.

(2)

By transferring the fuel stored in the common spent fuel storage pool to dry cask temporary custody facility in order to secure thecapacity in the common spent fuel storage pool, the fuel removed from the spent fuel pools of Units 1 to 4 is to be appropriately
stored in the common spent fuel storage pool.

(3)

Based on the assessment of the long-term integrity and investigations for future treatment of the removed fuel, the future
treatment and storage methods of them will be fixed around 2020.
Fiscal Year

Strategies and Challenges

2019

2020

2021

2022

2023

2024

2025

Start of fuel removal from unit 1 (by FY 2023)

•

Milestones

The evacuation order was lifted in the municipalities where
the nuclear power plants is located, and efforts for the
return of residents and reconstruction have been started.
Careful efforts with more emphasis on safety are required.

dust dispersion during removal•(1) Removal of fuel from the pool
- Unit 1

Unit 1: Careful removal of rubble and continued
implementation of measures to prevent radioactive- Unit 2 (plan selection)

Dismantlement andmodification of upper
part of building, etc.

Construction, etc.

FuelremovalFuel removal(2) Proper storage of removed fuelProcurement of dry casks, transfer of dry casks
from common spent fuel storage pool to the dry cask temporary custody facility

Unit 3: The removal began this April and is expected to be

Implemented to theextent not affect theoperations on Units 1 to
3completed by the end of FY 2020
: On-site operation: Technical reviews for the on-site construction, etc.,
for each item

Fuel removal- Unit 3

reactor building without dismantling, to the extent•

Cover installation, etc.

Submit/Approval request to
implementation plan/Preparation work

Investigationof operating
floor, etc.

dismantling the upper part of the operating floor, apossible, is being considered

Rubble removal, etc.

Selection and examination

Unit 2: In addition to the conventional method of completely
method of accessing from the south side of theStart of fuel removal from unit 2 (by FY 2023)(3) Study on future treatment andstoring methods of removed spent
fuel

Fuel removal from Unit 5 and 6
Adding dry cask temporary custody facilities

Determination of a treatment/storage method

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4. Handling critical enablers related to the comprehensive approach and smoothpromotion of the project
R&D initiatives

Comprehensive approach to the project Formulate a consistent long-term plan for the entire
decommissioning process covering from the current
status to the short, medium, and long term plans,and comprehensively manage of various efforts inline with this plan⁻ Securing the lead time⁻ Optimized allocation of limited resources (people,
things, money, time, and space) In making specific use of the long term plan, set
decision points at appropriate times while revising
flexibly for effective operation of the plan

Handling critical enablers forsmooth operation of the project The government, industry and universities
associated with the nuclear industry as a whole to
make steady efforts to foster and secure future
researchers and engineers

 TEPCO places much more importance on its own
technological development that is directly linked toactual site applicability.
 Management of R&D activities associated withengineering schedule, that the R&D results will beapplied to the site in a timely and appropriate manner
 It is also important for universities and public research
institutes to share awareness of issues identified at thedecommissioning site.

Enhancement of international cooperation
 Learning lessons from the legacy sites and treatment
for preceding accident reactors to apply them todecommissioning through utilization of technologies
and human resources cultivated in various nations, asa risk reduction strategy
 Establishment and strengthening of a long-term
partnership with overseas decommissioning
organizations
 NDF proactively participates in international joint
activities, such as applying knowledge acquired from
accident of Fukushima Daiichi and decommissioning
process to other issues in order to respond to newconcerns from overseas.
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5. Local community engagement
Concept on local community
engagement

Actual efforts for better communication

 Providing more in-depth information anddeveloping an interactive communication inprogressing decommissioning Addressing development of local human resources in cooperation withthe "Fukushima Innovation Coast Framework".
 Compatibility between the safe and steady decommissioning andgiving priority to local communities
 Development of an environment in which more local companies canparticipate in the decommissioning work through the resources
possessed by relevant organizations
Robot

Decommissioning

Major bases ・Projects

 “Decommissioning and the reconstruction of
Fukushima as an indispensable pair”
 To provide accurate information on
decommissioning in a timely and appropriatemanner, and to respond to requests from
communities through attentive communication.

Decommissioning in line with thereconstruction of affected regions

 Improvement of international
decommissioning R&D bases foraccelerating decommissioning ofFukushima Daiichi NPS
 Development of equipment anddevice and demonstration Using
mockup test facilities

Mockup test
facility Hosting World Robot Summit
Fukushima Robot Test Field

Energy Creating new energy industries
including renewable energy, etc.

hydrogen plant anddemonstration basefor reusable energy
and energy

 Establishing Smart community
utilizing renewable energy andhydrogen energy efficiently in regions

Future Directions

Smartcommunity

The 4th International Forum on the Decommissioning of
the Fukushima Daiichi NPS (Aug, 2019)(Day 1 "Considering the decommissioning of 1F withlocal residents" in the town of Tomioka) Improvement of Comprehensive bases
for robotics and demonstration(Fukushima Robot Test Field)

Test flight of drones

Agricultural
Sciences Promoting advanced agriculture, forestry and fisheries industry
ahead of any other region in the country
 Development of high technology and practical application inagriculture, forestry and fisheries fields
Approach to
improveproductivity(driverless tractor)

Tomatocultivation in
Wonder Farm

Industrial cluster

Education and
Human Resource
Development

Maintenance of
LivingEnvironment

Enhancement ofReceiving Visitors

Attracting companies related
to decommissioning, Robotics
and energy fields andintegrating new industries incollaboration with bases

Developing human resources
to support wider vision fromprimary and secondary
education through higher
education

Promoting maintenance ofliving environment, e.g.
improving public transportationand purchase environment,enriching educational andmedical/care system

Promoting the approaches toenhance visitor-receiving
centered on the bases forboosting visitors* by METI
Material provided
Fig. Overview of Fukushima Innovation Coast Framework* Source : Material from Ministry of Economy, Trade and Industry

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References

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Status of the Estimated Distribution of Fuel Debris

Comprehensive analyses andevaluations will be conductedbased on the following information:• Distribution of fuel debris• Access routes and the status ofsurrounding structures(The figures on the right show
the distribution of fuel debris.)

Spent
fuel

Spent
fuel

Unconfirmed, to reflect
results of planned surv ey

Fuel debris

W ater level
inside the PCV
W ater depth ofApprox. 2 m

Core Region

PCV internal investigation,
muon-based fuel debris
detection technology

Scientific knowledge(Tests, etc.)

RPV Lower
Head

REACTOR
CORE

Water Leakage (v isual observation)

 Little fuel debris remains

W ater level inside
the PCVW ater depth ofApprox. 6 m

W ater level
inside the PCV
W ater depth ofapprox. 30 cm

Personal
entrance(Plant parameters, etc.)

Severe accident
progression analysis

Spent
fuel

REACTOR
CORE

REACTOR
CORE

Personal
entrance

Actual measurements taken
during the accident

Unit 3

Unit 2

Unit 1

Fuel debris

Personal
entrance

Water Leakage (v isual observation)

 Little fuel debris remains(Stub-shaped fuels might exist in peripheral region)

 A small amount of fuel debris is present
 Large amount of fuel debris is present A small amount of fuel debris is present in the  A small amount of fuel debris is present in
inside and on the outer surface of the CRD
the inside and on the outer surface of the
housing
CRD housing

Fuel debris

Water Leakage (v isual observation)

 Little fuel debris remains
 Fuel debris remains on the RPV lower headparty
 A small amount of fuel debris is present in
the inside and on the outer surface of the
CRD housing

Bottom of PCV
 Most of the fuel debris is present
Pedestal inside A certain amount of fuel debris is present on
the floor of the pedestal inside Amount of fuel debris in Unit 3 is more thanthat in Unit 2.

Bottom of PCV  Fuel debris may have spread on the pedestal
outside through the personal entrance The possibility of fuel debris spreading on
the pedestal outside through the personalentrance is low.

 Fuel debris may have spread on the pedestal
outside through the personal entrance

Radiation dose  Radiation dose rate around penetration X-6
in operation site * on the first floor of R/B is high (630mSv/h).

 Radiation dose rate on the first floor of  Radiation dose rate on the first floor of R/B
R/B had reduced by about 5mSv/h.
is higher than tens of mSv/h.

Pedestal Outside* Data provided by TEPCO
Prepared based on the Achievement Report 2017, Subsidy for “The Government-led R&D program on Decommissioning and Contaminated Water
Management (Advancement of the comprehensive internal PCV condition analysis)” provided by IRID, The Institute of Applied Energy, June 2018

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Key Issues and Future Processes Concerning Fuel Debris Retrieval
Fiscal Year

Milestones

2019

2020

Determination of the fuel debris
retrieval methods for the first
implementing unit

2021

2022

2023

Start of fuel debris retrieval
from the first implementing unit

(1) Internal investigation etc.
･The Government-led program on
Decommissioning andContaminated Water Management

Continue as necessary･ Engineering･ Internal investigation etc.

Preparation for investigation/ Internal investigation / Characterization of fuel debris (from retrieved sampling, etc.)(2) Fuel debris retrieval･The Government-led program on
Decommissioning andContaminated Water Management

Continue as necessary･ Engineering･ Fuel debris retrieval

Preparation for small-scale retrieval→- Small-scale retrieval- Preparation for expanded-scale retrieval: On-site operation: Technical reviews for the on-site construction, etc., for each item
: Research and development

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Steady execution of contaminated water management indicatedin the Mid-and-Long-term Roadmap
It is expected that preventive and multi-layered fundamental measures will be continuously
implemented based on the three basic policies, to achieve the milestones indicated in the
Mid-and-Long-term Roadmap
Milestones (key target processes) and the status of implementation as of August 2019[1] Reduction of the amount of contaminated water generated to approximately 150
m3/day (in 2020)  Currently underway[2] All of the water treated with purification equipment is stored in welding-type tanks (FY2018)  Completed[3] Disconnection of the communication sections between Units 1 and 2 and between
Units 3 and 4 was achieved for the stagnant water in buildings (in 2018)  Completed[4] Reduction of the amount of radioactive materials contained in the stagnant water inbuildings to approximately 1/10 of the level at the end of FY 2014 (FY 2018) 
Approx. 2/10 of the level at the end of FY 2014 *1[5] Completion of treatment of the stagnant water in buildings (In 2020) *2 Currently underway*1 Calculated amount of radioactive materials as of the end of 2014(assuming that concentrations of stagnant water in each building are uniform.)*2 Excluding reactor buildings

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Storage Status of Spent Fuels, etc.

Number of spent fuel, etc.

10000
Number in the capacity
available as of now in entire
common spent fuel storage pooland dry cask temporary
custody facility : 1563

8000

Unit 3 (under transportation):
538 remained

6000

For fuel removal from
Units 1, 2, 5 and 6 (4433),
it is necessary to ensure
storage capacity of dry
cask temporary custodyfacility and to consider
exporting fuel to off-site.

Vacancy: 666

In all Units 1, 2, 5 and 6: 44334000
Storage6133
Vacancy: 897

Unit6:
1884

2000
Unit3:538
Unit2:615

0

Unit5:
1542

Storage2033

New Fuel to be exported：360(Plan)

Dry Cask Temporary
Custody Facility

Export to off-site(nuclear fuelmanufacturer)

Unit1:392

Units 1-3 SFP

Units 5/6 SFP

Common Spent Fuel
Storage PoolFig. Storage status of spent fuel, etc. (as of July 25, 2019)
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Basic Policies on Solid Waste(Note) Numbered and titled by NDF for each item.

① Thorough containment and isolation
 Containment and isolation shall be thoroughly carried out so that people will not access to radioactive
materials to avoid significant radiation exposure.
② Reduction of solid waste volume
 The amount of solid waste generated during decommissioning shall be reduced to the extent possible.
③ Promotion of characterization
 To promote studies on processing and disposal of solid waste, an appropriate characterization shallbe performed in response to the increase in the number of samples for analysis.
④ Thorough storage Safe and reasonable Storage for generated solid waste according to their characteristics
 Ensuring adequate storage capacity for safe Storage within the site of the Fukushima Daiichi NPS⑤ Establishment of selection system of preceding processing methods in consideration of
disposal Before the technical requirements for disposal are determined, a method of selecting a processing(preceding processing) for stabilization and immobilization shall be established to select a preceding
processing method.
⑥ Promotion of effective R&D with a bird’s-eye-view of overall solid waste management Issues on R&D shall be identified through collaboration among the fields of characterization, treatment
and disposal, with a bird’s-eye-view on the overall solid waste management.
⑦ Efficient implementation of R&D projects from the perspective of overall solid waste
management
 For ongoing safe and steady solid waste management, a continuous operational framework including
development of adequate facilities and human resources shall be established.
⑧ Measures to reduce radiation exposure of workers
 Thorough radiation exposure control, health control, and safety management in accordance with
relevant laws and regulations shall be established.
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