Nuclear Damage Compensation and Decommissioning Facilitation Corporation

Technical Strategic Plan 2018
for Decommissioning of the Fukushima Daiichi
Nuclear Power Station ofTokyo Electric Power Company Holdings, Inc.
(Explanatory material)
October 2, 2018
Nuclear Damage Compensation andDecommissioning Facilitation Corporation
NDF

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Contents
1. Introduction
2. Decommissioning of the Fukushima Daiichi NPS as Risk
Reduction Strategies
3. Technological Strategies toward Decommissioning of the
Fukushima Daiichi NPS
①
②
③
④
⑤
⑥

4.
5.
6.
7.

Fuel Debris Retrieval Work
Waste Management
Contaminated Water Management
Fuel Removal from Spent Fuel Pools
Other Specific Measures
Comprehensive Efforts for the Decommissioning Project of the
Fukushima Daiichi NPS

Handling Critical Enablers for Smooth Operation of the Project
R&D Initiatives
Enhancement of International Cooperation
Local Community Engagement and Further Enhancement ofCommunication
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1１．Introduction(Roles & Responsibilities of Organizations Relevant to the Fukushima Daiichi NPS Decommissioning)
Nuclear Emergency Response Headquarters (Director: Prime Minister)
Nuclear Regulation
Authority

Council for the Decommissioning of TEPCO's (Chairperson:
Fukushima
Daiichi NPS
Chief Cabinet Secretary)
Mid-and-Long-Term Roadmap

 Approval of implementation plan,
pre-service inspection, welding
inspection, etc.

The Team for Countermeasures for Decommissioning and Contaminated Water Treatment
 Progress management of each countermeasureaccording to Mid-and-Long-Term Roadmap
Report on theoutcomeGranting of
project budget

R&D organization
International Research Institute for
Nuclear Decommissioning (IRID)*
Japan Atomic Energy Agency (JAEA), R&D implementation
etc.

ReportPresentation ofimportant issues

Approve

Apply forapproval

Nuclear Damage Compensation andDecommissioning Facilitation Corporation
 Development of a mid-to-long-term strategy
 Technical support for progress management
Withdrawal planof important issues(in collaboration)
R&D planning and progress management
Strategic  Strengthen international partnership
Plan  Management of reserve fund for Reserve funds fordecommissioning
decommissioning

Share
progress andchallenges

Advice, guidance, recommendations,supervision and support
related to project management, etc.

ReportDisburse-ment

Monitoring, examination

Progressmanagement

Minister of Economy, Trade and Industry

Apply for report(Head of Team: Minister of Economy, Trade and Industry)

ReportBidirectional dialogue

Local residents and communities

Organizations related to decommissioning Decide the direction of decommissioning andcontaminated water treatment

Reserve(Fukushima Daiichi Decontamination andDecommissioning Engineering Company)
 Contaminated water management, fuel removal from spent fuel pools, fuel debris retrieval, waste disposal,
improvement of power plant site and working environment, management of Units 5 and 6, etc.
Implementation
 Through TEPCO's management reform, the funds required for decommissioning should be reserved
plan
responsibly (Implementation of new comprehensive special project plan)

Tokyo Electric Power Company Holdings, Inc.

* TEPCO, a decommissioning project operator, participates as a member of IRID and shares the needs, challenges, and results of research and development.

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１．Introduction (Positioning of the Strategic Plan)
Structure of the Strategic Plan
(Strategic Plans to date) Focusing on Fuel debris retrieval work and Waste management
as Mid-and-Long-term decommissioning strategies(Strategic Plan 2018 and later) Adding Contaminated water treatment and Fuel removal from spent fuel pool
・Providing directions with mid-and-long-term aspect by overlooking the entire project from the viewpoint of relevance and consistency
with fuel debris retrieval

Positioning of the Strategic Plan based on Reserve Fund for Decommissioning

Reflecting to ”the Policy for Preparation of Withdrawal Plan for Reserve Fund for Decommissioning” through the study for the Strategic Plan
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

Programs to be included into
Withdrawal Plan
 Contaminated water treatment
PG
 Pooled fuel retrieval PG
 Fuel debris retrieval PG
 Waste management PG
 Power plan site/Workenvironment improvements PG
 Management of Unit 5 and 6
Misc. facility/operational
management

Technological
Development

Promotion of Decommissioning project

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2.Decommissioning of the Fukushima Daiichi NPS as Risk Reduction Strategies (1/3)
Basic concept of decommissioning
To continuously and quickly reduce the radioactive risk caused by the accident that does not exist in the usual NPS

Progress of decommissioning
Contaminated water treatment【Remove】 (ongoing) Being purified with multi-nuclide removal equipment【Redirect】 (Mar. 2018) Land-side impermeable wall completed except for deep areas
Cover for fuel removal was installed (Unit3)【Retain from leakage】 (ongoing) The concentration of radioactive materials in the surrounding(Photo/video library:TEPCO)
sea area is constantly low【Stagnant water treatment in the building】(Dec.2017) In the Unit 2 - 4 turbine building, the level of the stagnant water lowered and the lowest floor’s intermediate ceiling was exposed(Dec.2017) For the condensers in Unit 1-3, draining of highly radioactive stagnant water completed

Fuel removal from spent fuel pool
•Unit 1 (Jan.2018) Rubble removal in the north of the operating floor was started•Unit 2 (Jun.2018) Opening to provide access to the operating floor was made(Jul. 2018) Investigation in the operation floor was started•Unit 3 (Feb.2018) Installation of a cover for fuel removal was completed, trial operation of fuel handling machine isbeing performed

A part of fuel assembly

Fuel debris retrieval•Unit 2 (Jan.2018) Internal investigation of PCV was conducted•Unit 3 Based on the results of investigation in July 2017, 3-D shape restoration of innerpedestal was conducted
Waste management
Deposits• (ongoing) Sampling/analysis has been made for the purpose of characterization• (Feb.2018) Operation of solid waste storage building No. 9 started
Image taken inside the pedestal (Unit2)• (Jun.2018) Storage management plan was revised
3rd International Decommissioning Forum:TEPCO
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2.Decommissioning of the Fukushima Daiichi NPS as Risk Reduction Strategies (2/3)
 Risk level is expressed as the product of “Level of Impact” and “Likelihood of Occurrence”
of the event associated with risk source The method based on the SED* developed by Nuclear Decommissioning Authority (NDA) is
used to express the magnitude of risk in the Strategic Plan
* Safety and Environmental Detriment score① Hazard Potential
 An index to indicate the level of impact, refers to the definition by SED
 It depends on the inventory(amount of the radioactive material), formof the risk source (gas, liquid, solid, etc.) and time allowable until the
manifestation of the risk when loss of safety function occurs
 Examples of reduction measures: Decrease in inventory and decay heatassociated with radioactive decay, change of form by treating
contaminated water to change into secondary waste

Example of risk levels assigned to the risk sourcesat the Fukushima Daiichi NPS② Safety Management

 An index to indicate the likelihood of occurrence of the event,
adapted the definition by SED to the Fukushima Daiichi NPS
 It depends on the integrity of the facility and containment andmonitoring status of the risk source Examples of reduction measures: Transfer of fuel in the pools to thecommon pool, replacement of rubble stored outside to the storage

Safety Management is generally to be easily achieved
Interim Goal
To bring the risk levels into the “Region of sufficiently stable
management” (pale blue area)
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2.Decommissioning of the Fukushima Daiichi NPS as Risk Reduction Strategies (3/3)
Basic Approach to Risk Reduction
 The decommissioning of the Fukushima Daiichi NPS is a project with inherent considerable uncertainty

⁻ Placing safety at the top priority, to make integrated decisions taking flexible and prompt approach, based on the
directions determined with previously obtained experience and knowledge.
⁻ To flexibly address the issues with experiences, reflecting the information obtained in advance on the subsequent works.

Viewpoint to make Integrated decisions (Five guiding principles) Safe (Reduction of risks posed by radioactive materials and ensuring work safety)
 Proven (Highly reliable and flexible technologies) Efficient (Effective utilization of resources (e.g. human, physical, financial and space) Timely（Awareness of time axis)
 Field-0riented (Thorough application of Three Actuals (actual field, actual things and actual situation)
Order of Priority
 TEPCO and NDF have just introduced project management mechanism

⁻ Be aware of position of each project and their mutual relationship in managing progress of overall project⁻ Aim at choosing the best option, with the viewpoint of the entire site on a long-term basis and considering time axis

Addressing temporary increase of risk level associated with the decommissioning operations
 The decommissioning work is striving for prompt risk reduction from the mid/long-term viewpoint For possibility of a temporary increase in the risk level and a rise in workers’ exposure arising from thedecommissioning work, the risk level during the work must be limited within the permissible range.
 In case the decommissioning work is delayed excessively, existing risks will remain over the long term andtheir risk levels can gradually increase as the buildings and facilities deteriorate over time. Considering thetime needed for associated preparations and work, and many other constraints, cautious andcomprehensive decision making is required for the early implementation of the decommissioning.
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63. Technological strategies toward decommissioning of the Fukushima Daiichi NPS（① Fuel debris retrieval work）

Sectoral Target (Fuel debris retrieval)(1) Retrieve fuel debris safely after thorough preparations including safety measures, andbring it to the state of stable storage that is fully managed.

(2) Toward determination of fuel debris retrieval method for the first implementing unit in
FY 2019, and start of fuel debris retrieval for the first implementing unit within 2021,
necessary approaches will be taken according to policy on fuel debris retrieval.
Policy on Fuel Debris Retrieval① Step-by-step approach－Adjust the direction flexibly as retrieval proceeds

RPV② Optimization of entire decommissioning work
－Examine as a comprehensive plan including coordination with otherconstruction work at the site

③ Combination of multiple methods－Combine optimum retrieval methods suitable for the part of each unit
where fuel debris is expected to be present④ Approach focused on partial submersion method－Base the efforts on the partial submersion method that is feasible.
⑤ Prioritizing fuel debris retrieval by access to the bottom of
the PCV from the side
－Considering accessibility to fuel debris and it could be performed at
the same time as spent fuel removal

Retrieval
Equipment
Cell

PCV
Pedestal

Basement

Image of Partial submersion-side access method

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3. Technological strategies toward decommissioning of the Fukushima Daiichi NPS（① Fuel debris retrieval work）

Sectoral Strategy (Fuel debris Retrieval)

How to proceed discussion toward fuel debris retrieval method for the first implementing unit
Internal
Investigation of
PCVs
Incorporate

R&D

Needs

Improvement of workplaceenvironment
・ Reduction of radiation dose rate
Incorporate

Study onIncorporate concept of
retrieval⁃Plan forNeeds incremental scale
expansion of
retrieval⁃Transferring andstoring method⁃Concept on how tosecure safety, etc.

Prepare a fuel debris retrieval scenario of each
unit based on the consideration on the suitableconcept of fuel debris retrieval method for each
unit and on the evaluation of its applicability.

Needs

Evaluation ofApplicability
at site⁃Safety andreliability⁃Schedule⁃Economical
efficiency
etc.

Establishmentof Fuel debris
retrieval
scenario foreach unit(Time, Safety, Consistency of the entire project)

Study on fuel retrieval
method considering
optimization of site layout
and retrieval scenario of
each unit

Determination of fuel debris
retrieval method to be
applied to the first
implementation unit

FY 2019

Apply the obtained information and study
results appropriately

Site-wide planning

Identify the most reasonable scenario
by considering multiple whole scenarios• Layout planning• Contaminated water management• Fuel removal from the spent fuel pool, etc.

First implementation unit will be selected taking reliability of knowledge on inside condition of PCV,
environment of working place of necessary preparatory works and risk assessment of each unit into account.
For instance, following must be considered;• Unprecedented undertaking of fuel debris retrieval in the environment with many uncertainties• The benefit of getting experiences and information of handling of fuel debris early
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3. Technological strategies toward decommissioning of the Fukushima Daiichi NPS（① Fuel debris retrieval work）

Sectoral Strategy (Fuel debris Retrieval)
Proceeding method of preliminary engineering
Items to be considered• Study on retrieval scenario that includes the whole related operations ranging from internal investigation,
preparations, improvement in the working environment to fuel debris storage.
• In each step, information to be gained in advance should be organized in order to secure safety and engineering
reliability on the equipment for retrieval.
• Clarification of prerequisites, evaluation on its uncertainties and forecast concerning a development of the
scenario should be conducted• Sufficient safety evaluation should be implemented for the major troubles and others assumed at present.
Items to be expected• Image of operation process to fuel debris retrieval for each unit and identification of technical issues to be solved• Engineering schedule incorporating the period of solving the technical issues

Continued internal investigation

Accelerated/prioritized R&D• It is necessary to draw up a roadmap for solving the technical issues extracted so far and identified in the process of
implementing preliminary engineering, through further internal investigation and accelerated/prioritized R&D.
＜Continued internal investigation＞• In the future internal investigation, it should be thoroughly identified what kind of data is necessary as part ofassembling the whole project, then implemented for the goal of each phase.
＜Accelerated/prioritized R&D＞
• Accelerating and prioritizing R&D are to be proceeded including technology to manage the water level in the PCV,
according to the fuel debris retrieval policy• Identify R&D tasks that their necessities have newly become clear as a result of preliminary engineering
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93. Technological strategies toward decommissioning of the Fukushima Daiichi NPS（① Fuel debris retrieval work）
Technical issues and Future Plans (Fuel debris retrieval) Concept of the step-be-step
Internal Investigation

Fuel Debris Retrieval

Image of procedure

Internal investigation(example)

Sampling (examples)

Small-scale Retrieval(examples)

Large-scale Retrieval (Side-access method)(examples)

Obtain information to identify
distribution of fuel debris
and accessibility, information
to judge ensuring safety forfuel debris retrieval operation

Obtain information to
improve the accuracy offeasibility of retrieval
method and to improve thereliability of the protective
measures for ensuringsafetyCollect and verify information to
identify the work and equipmentused for large-scale retrieval(effectiveness of work/equipmentof the fuel debris retrieval, effecton securing safety, etc.)

Based on the data obtained from the operation
until the small-scale fuel debris retrieval, more
efficient retrieval will be performed

Images of fuel debris retrieval (Unit 2)

Retrieval Device/ Equipment• Arm type access unit that can be installed without expanding X-6 penetration, etc.
• End effector is to be selected depending on internal investigation, sampling or fuelSealed cell for retrieval
RPV
debris retrieval
Access unit
Pedestal• Expansion/modification of X-6
penetration and installation of Arm withrail, etc. that is capable of large-scale
operation
RPV
RailTransportation case

PCV
Grip/suction tool

Example of Access unit
(Robot arm)

Arm

PCV

Pedestal

Outside PCVInside PCVImage of small-scale retrieval

Arm expanded

Image of large-scale retrieval
Side-access method (example)

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3. Technological strategies toward decommissioning of the Fukushima Daiichi NPS（① Fuel debris retrieval work）

Technical issues and Future Plans (Fuel debris retrieval)Comprehensive understanding of Reactor Conditions
Comprehensive analysis and evaluation results based on the information obtained so far
Unit 2

Unit 1• Distribution of fuel debris• Condition of access route andsurrounding structure were analyzed
and evaluated based on the following
data.
(The right figure shows distribution offuel debris.)

Spent fuelSpent fuel

Water Levelin PCVapprox. 2m

Reflection from survey
in future because of
non-observation

Actual measured value(Plant parameters, etc.)
Accident progression
analysis
Info from PCV internal
investigation, by
muon-based detection

Scientific know-how(experiment, etc.)

Fuel Debris

RPV Lower
Head

Pedestal
OutsideWater Level in
PCV approx.
30 cm

Water Leakage(visual observation)

Water Levelin PCVapprox. 6 m

Fuel Debris

Personal
Entrance

Water Leakage(visual observation)

Fuel DebrisLittle fuel debris remains(Stub-shaped fuels might exist in
peripheral region)

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

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

Most of the fuel debris is present

A small amount of fuel debris is present

Fuel debris may have spread on thepedestal outside through the personalentrance

The possibility of fuel debris spreadingon the pedestal outside through thepersonal entrance is low.

Little fuel debris remains






Core

Personal
Entrance

Pedestal Inside 

Spent fuel

Core

Core

Personal
Entrance

Core Region

Unit 3

Water Leakage(visual observation)

Little fuel debris remains
Fuel debris remains on the RPV lower
head party
A small amount of fuel debris is present
in the inside and on the outer surface of
the CRD housing.
Amount of fuel debris in Unit 3 is morethan that in Unit 2.
Fuel debris may have spread on thepedestal outside through the personalentrance.

Data based on “Decommissioning and Contaminated Water Treatment Subsidy Project (Advancement of Comprehensive
understandings of internal reactor” The Institute of Applied Energy”, IRID, reported in 2017 (Issued in June 2018)

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3. Technological strategies toward decommissioning of the Fukushima Daiichi NPS（① Fuel debris retrieval work）

Technical issues and Future Plans (Fuel debris retrieval)Continuous implementation of internal investigations
 Following investigation and study should be implemented steadily to develop scenarios for fuel debris retrieval
Unit 1: Grasping distribution of structures or deposits outside the pedestal (including sampling) [scheduled in 1st half of 2019]
Unit 2: Grasping mobility of deposits at the bottom of the pedestal when force is applied [scheduled in 2nd half of 2018]
Grasping distribution of structures or deposits inside the pedestal (including sampling) [scheduled in 2nd half of 2019]
Consider to increase sampling volume [scheduled in FY2020]
Unit 3: Considering availability of internal investigation technology that was developed and proved by decommissioning andcontaminated water treatment project, in parallel to study on water level reducing in PCVConsidering necessity of further investigation in utilizing underwater ROV that was used in the former investigation
FY2018
1st

2nd

1st

Pan-tilt
camera2nd

Grasping distribution of
structures or deposits inside thepedestal (including sampling)

Approx.
1m 1m

Thruster Approx.
0.3m
0.3m

Lighting
Investigation Unit
(Ultrasonic range finder, etc.)

Investigationequipment by boat-type access with
潜水機能付ボート型アクセス・調査装置
submerging
function (Current image)（現時点のイメージ図）

Investigationequipment by arm-type access
アーム型アクセス・調査装置(Current image)（現時点のイメージ図）

Unit 2

Grasping mobility of deposits at the bottomof the pedestal when force is applied
PCV
Φ110mm(X-6)

FY2021

Consider to increasesampling volume(TBD)

Image of internal PCV investigation using guide-pipe

Unit 3

Considering availability of internal investigation technology that has been demonstrated in parallel tostudy water level reducing in PCVConsidering necessity of further investigations in utilizing ROV that was used in the previous investigation

Start of fuel debris retrieval for the first implementation unit

Grasping distribution of structures ordeposits outside the pedestal (including
sampling)

FY2020

Determine the method of fuel debris retrieval
for the first implementation unit

Unit 1FY2019

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3. Technological strategies toward decommissioning of the Fukushima Daiichi NPS（① Fuel debris retrieval work）

Technical Issues and Future Plans (Fuel debris retrieval)Technical Requirement for ensuring security

It is important to study reasonable protective measures according to the scale of fuel debris retrieval work while
taking actions to reduce the uncertainties of the PCVs’ internal conditions during the conceptual design phases.

Technical
Requirement

Technical Issue

Matters to be Considered

Establishing thecontainment
functions (gas)• Understanding of dispersion rate of α dust, etc.

• Obtain data while handling fuel debris, dispersion inhibition• Determine feasibility of negative pressure control
in PCV• Identify technical feasibility of negative pressure control based on theinformation that is obtained at each step

• Exhaust gas management check• Efficient recovery of dust, etc.

Establishing thecontainment
functions (liquid)• Inhibition of radioactivity concentration increasein cooling water through fuel debris retrieval• Obtain data while handling fuel debris• Study on diffusion inhibition by recovering dust

• PCV water seal feasibility• Applicability of water seal technology with vent tube to real units• Setting of water level in PCV• Evaluate from the viewpoint of fuel debris cooling and dust dispersion inhibition• Determine the intake site from PCV, monitor and control torus room water level

Maintaining thecooling functions• Setting of temperature target for operation andcountermeasure when abnormality occurs• Set the PCV internal temperature target to enable implementation of each
operation• Consider countermeasures, procedures, etc. at the time of occurrence ofabnormality such as recovery of instrument

Criticality control• Establishment of criticality evaluation method• Refine criticality information based on the information that is obtained at eachstep

• Local neutron measurement around retrieval
point• Select neutron detector and develop operation stop, etc. due to fluctuations inneutron flux

• Determine the feasibility of measuring noncriticality degree• Applicability to real units as well as study on retrieval system, examining
verification of each technology• Detection of criticality by PCV gas management
installations• Acceleration of criticality detection, Possibility of estimation of the level ofsubcriticality of the entire PCV

Establishing
structural integrityof the PCVs
/reactor buildings• Evaluation of Seismic Margin• Evaluation of seismic margin taking into account the impact of accidents anddeterioration• Study of countermeasures in the case of postulated damage to the structures• Corrosion mitigation measures during the fueldebris retrieval• Study of corrosion mitigation measures conforming with the water treatment
systemReduction ofradiation exposure• External and internal exposure control while• Dose reduction plan considering contamination condition
handling nuclear fuel materials containing α-nuclides • Measurement management considering the mixture of alpha nuclides
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3. Technological strategies toward decommissioning of the Fukushima Daiichi NPS（① Fuel debris retrieval work）

Technical Issues and Future Plans (Fuel debris retrieval)Technical
Requirement

Fuel debris retrieval method, Technicalrequirements regard to stable storage

Technical Issue

Matters to be Considered

Securing access route• Establish access route for transporting, installing andunloading the equipment and devices used for fueldebris retrieval, and transporting fuel debris andwaste• Removing obstacles and reducing the dose
• When establishing a new opening in the PCV, to suppress
the release of radioactive materials and maintain the
integrity of existing structures• it is considered on the premise of accessing from the top to
the inside of the RPV.

Development of device
and equipment• Develop device and equipment to retrieve fuels debris
safely, reliably and efficiently (Considering radiation
resistance, remote investigation /maintainability, anda rescue mechanism that does not disturb thesubsequent work when trouble occurs)• The development of a recovery system that can handle
various conditions of fuel debris, a fuel debris cutting system
and a dust collecting• A technique for installing retrieval equipment• Plan for mock-up tests combining the developed devices andequipment

Establishment of systemequipment and working
areas• Install system equipment to establish safety functions• Actualizing installation method of negative pressure control
system, a circulating water cooling/purification system, acriticality control system and a measurement system as aentire system• Securing space required for installing the fuel debris
retrieval equipment and related system equipment• Calculating the space required for installing each system• Study on setting up systems outside of the existing buildings

Handling of fuel debris(collecting, transferringand storing)• Establish a comprehensive fuel debris handling system
consisting of collecting, transferring and storing withsafety function such as subcritical condition,
containment function, countermeasures against
hydrogen generation and cooling.

• Details of equipment/systems for collecting, transferring, andstoring of the retrieved fuel debris• Storing facility adaptable to the safeguards• Mock-up test plan combined with a fuel debris retrieval
deviceTreatment of radioactive
waste during fuel debris
retrieval• Safe and proper classification and storing ofradioactive waste generated during fuel debris
retrieval work

• Develop a classification standard in order to judge retrieved
material into fuel debris or radioactive waste and actual
method of handling

Safeguard measures• Safeguard measures for fuel debris retrieval• Proposal of realistic and transparent enough material
accountancy and safeguards

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3. Technological strategies toward decommissioning of the Fukushima Daiichi NPS（① Fuel debris retrieval work）

Technical Issues and Future Plans for Fuel debris retrieval (Process chart)
2018

Fiscal Year

2019

Milestone
Internal Investigation

Study for subsidized project on dicommissioning andcontaminated water management

2020

2021

2022

Start of fuel debris retrieval
at the first implementing unit

Determination of fuel debris retrieval methods
for the first implementing unit

Preparation of investigation/ internal investigation/ Characterization of fuel debris (from retrieved samples etc.)
Access Route &Equipment for Survey

Access Route &Equipment for Survey

On-site work

Analysis technology
for fuel debris- Develoment of Technologies for In-depth Investigation

Technical studies for on-site work

Research and developmentof PCV Inside
Continue as necessary- Development of Sampling Technologies
to Retrieving Fuel Debris and Internal Structure- Development of Technologies for Grasping andAnalyzing Properties of Fuel Debris- Development of Investigation Technology of Inside RPVTransfer method to outside the site
Adaption plan for Safeguards
Additional plan for internal investigation

Engineerng for internal investigation

Preparation of small-scale retrieval

Retrieval of fuel debris

Retrieval method (Layout plan etc.)
Collecting/transfer plan
Temporary storage plan
Securing Safety

Engineering involved with fuel debris retrieval

Study for subsidized project on dicommissioning andcontaminated water management- Advancement of Retrieval Method and System of→

Small-scale retrieval &Preparation of large-scale retrieval

Retrieval equipment
Facilities for collecting, transferringand temporary storage
Radiation protection for safety(modification of existing facility)

Retrieval method (layout plan)
Collecting/transferring plan
Storage plan
Ensuring of Safety(confinement, water level control,

Preliminary engineering / Detailed engineering

Retrieval method,
system & concept design

Measurement for ensuring safety during large-scale fuelretrieval and study on safer handling of fuel debris

Continued as necessary

Fuel Debris- Advancement of Fundamental Technologies for
Retrieval and Internal Structure of Fuel Debris- Development of closed circulation systems for waterContinue as necessary

inside PCV- Development of collection, transport, and Storage
Technologies of Fuel Debris

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3. Technological strategies toward decommissioning of the Fukushima Daiichi NPS（② Waste Management）

Sectoral Target (Waste Management)(1) As the approaches of solid waste storage, the Solid Waste Storage Management Plan (hereinafter referred to as
the “Storage Management Plan”) is appropriately developed, revised and implemented including waste
prevention, volume reduction and monitoring, with updating the amount of solid waste estimated to begenerated in the next ten years periodically.
(2) As the approaches for processing/disposal, countermeasures integrated from characterization toprocessing/disposal are studied from the expert point of view, and the prospects of a processing/disposal
method and technology related to its safety should be made clear by around FY2021.

Basic Policies on Solid Waste(note : Numbers and titles were appended by NDF)

①Thorough containment and isolation• Containment and isolation of radioactive materials are implemented thoroughly to prevent their dispersion/leakage and humanaccess to them, in order not to cause harmful radiation exposure.

②Reduction of solid waste volume• The amount of solid waste generated by decommissioning is reduced as much as possible③Promotion of characterization• To proceed with study on processing/disposal method of solid waste, it is necessary to address an increase in the number of analysis
samples and proceed their characterization properly.

④Thorough storage• The solid waste generated should be stored safely and reasonably according to its characteristics.
• Storage capacity should be secured to ensure that the waste can be stored within the site of the Fukushima Daiichi NPS.

⑤Establishment of selection system of preceding processing methods in consideration of disposal• Establish selection method of processing for stabilization and immobilization (preceding processing), and selecting the method of
the preceding processing, before the technical requirements of disposal are established.

⑥Promotion of effective R&D with a bird’s-eye-view of overall solid waste management• Close cooperation should be realized between R&D fields such as waste characterization, processing/disposal, and necessary R&D
issues should be confirmed with a bird’s-eye-view of overall solid waste management.

⑦Efficient implementation of R&D projects from the perspective of overall solid waste management• In order to continue safe and steady solid waste management, the continuous operational framework system including
development of adequate facilities and human resources must be undertaken.

⑧Measures to reduce radiation exposure of workers• Radiation exposure control, safety management and healthcare programs should be implemented thoroughly based on the relevant
laws/regulations.
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3. Technological strategies toward decommissioning of the Fukushima Daiichi NPS（② Waste Management）

Sectoral Target (Waste Management)
The challenge on solid waste generated by decommissioning of the Fukushima Daiichi NPS is theexistence of a large volume of waste with various characteristics.
⁻ It is necessary to develop a flexible and rational waste stream as well as improvement of analysis
capabilities for characterization.
⁻ The relevant organizations should proceed with their efforts based on each role in line with the basic
policies of solid waste management that was compiled in the Mid-and Long-term Roadmap

The technical study on the integrated countermeasuresfrom characterization to processing/disposal of solid waste⇒It should be proceeded with the following policies at the initiative of NDF.
StorageThe fundamentals of managing solid waste are to contain not to scatter or leak.
It should be kept isolated in a properly storage place, and managed appropriately by monitoring, etc.
It is important to raise awareness on reducing the volume of solid waste to be generated.
The Storage Management Plan* released by TEPCO is necessary to be revised the estimated volume once a year
and updated as appropriate.
* It estimates the volume of solid waste that will be generated in the next ten years, and shows their policy within it such as on building required waste management facilities, etc

Further safety improvement in waste Storage
 The secondary waste generated by water treatment with high fluidity, should be stored in a more stable andreasonable way.
 There may be cases where processing for stabilization and immobilization are required although the technicalrequirements for disposal are not determined (i.e. preceding processing). Study will be continued on how to select thepreceding processing method with disposal in mind.
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3. Technological strategies toward decommissioning of the Fukushima Daiichi NPS（② Waste Management）

Sectoral Target (Waste Management)
Study on the processing/disposal policy
 The prospects of a processing/disposal method and technology related to its safety should be made clear byaround FY2021. (Roadmap)
 Since the overall picture of solid waste becomes gradually clear as the effort progresses, it will still remain in a stageof accumulating necessary information on its characteristics around FY2021. The concrete targets are compiled:
The concrete targets for prospect of a processing/disposal method and technology related its safety① Establish safe/rational disposal concept based on processing technology applicable to solid waste, and develop
safety assessment method reflecting features of the disposal concept② Clarify radiological analysis and evaluation method for characterization③ Clarify processing technology that would be expected to introduced actual equipment for stabilization andimmobilization considering disposal④ Establish method of rationally selecting preceding processing method⑤ Have prospect of setting processing/disposal measure for solid waste of which the processing technology
considering disposal is not clarified, using a series of method to be developed by 2021
⑥ Clarify issues and measures concerning storage of solid waste before conditioning＜Flow＞⑥Clarify issues andmeasures

Generation ofwaste

Storage forthe immediate
futureSelecting technology according
to the characteristics of solid waste

Storage

Characterization②Clarify analysis and evaluation method

Pretreatment/
treatment

Storage③Processing Technology forstabilization and immobilization④Establish method of selecting
preceding processing method
Solid waste that processing
technology is not clarified

Storage

Conditioning

Disposal①Establish disposal
concept, develop
safety assessment
method⑤Prospect of setting processing/disposal measure

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3. Technological strategies toward decommissioning of the Fukushima Daiichi NPS（② Waste Management）

Sectoral Target (Waste Management)
Promotion of the characterization
 JAEA Okuma Analysis and Research Center is scheduled to commerce operation at the end of FY2020.
To improve the accuracy of models to obtain evaluation data based on the limited radiological analysis data⁻⁻

The method of reflecting dispersion of radiological analysis data to inventory evaluation using analytical method
Study on concept of setting and revising radioactive inventory based on comprehensive evaluation of radiologicalanalysis data and analytical value Target of radiological analysis will be mainly on predisposal management, and review target nuclides and to develop
efficient analysis method A system, facilities/equipment and technologies for highly accurate characterization of solid waste will beestablished by the end of FY 2020

Further improvement of the Safety Storage
 Selecting processing technology and determining specification of waste package for the secondary waste generated bywater treatment expected to be applicable for actual processing.
 Regarding the methods of storing high-dose solid waste generated during fuel debris retrieval, narrow down candidate
methods for storage.
 For other solid waste, study should be proceeded on generation of hydrogen during storage together, with the timing andcontent for the case of requiring further measures to secure safety (reflects to the Storage Management Plan as needed).

Establishing processing/disposal concept and development of safety evaluation method
 In order to select candidate technology as a preceding processing method, selecting reasonable and feasible
candidate technologies and developing safety assessment methods will be proceeded.

Other Study on storage method for structures such as core internals and outside of reactors to be dismantled andremoved, and secondary waste generated during duel debris retrieval
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3. Technological strategies toward decommissioning of the Fukushima Daiichi NPS（② Waste Management）
Sectoral Target (Waste Management)
Fiscal year

2015

2016

2017

１．Reduction of solid waste

2018

2019

On-site work
Technical studies for on-site construction
Research and development

2020

2021

2022 and later

Carry-in control, reuse, recycling and volume reduction

２．Waste characterization
Sampling(1) Analysis data acquisition,

Analysis and measurement forverification of waste for disposal
Development/establishment of methods
on verification of waste for disposal

management, etc.

Planning/updating analysis plan, conducting analysis, characterization, accumulation/evaluation/management of analysis data
Development of sampling technique etc. (Method of sampling high-dose samples)

Establishment of Database system(2) Improvement of analysis

Development of radioactive material analysis and research facilities

capacity
Human resource development for analysis personnel(3) Improvement in efficiency ofDevelopment of characterization method with complimentarily use ofdata evaluated from nuclide migration model

waste characterization

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

３． Storage

Storage(1) Storage Management Plan

Development and review of the Storage Management Plan
Study on Storage measures of secondary waste from water treatment(2) Study and evaluation ofstorage methods(3) Study and evaluation of storage

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

methods of solid waste generated
during fuel debris retrieval

Design/prepare
Storage containers

４．Development of

Establishment of a selection system of preceding procesing

process/disposal concept andUse of a selected
systemSurvey and setting of disposal method
based on characteristics of solid waste

development of safetyassessment method

Study on safety
improvement measures

Survey and development of safetyassessment method for each disposal method
Survey on conditioning
technology

Technical development of processinhg methods related to stabilization and immobilization

Compilation of basic concept ofprocessing/disposal

Clarification of prospects on processing/disposal
method and safety technology

Study of processing/disposal

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3. Technological strategies toward decommissioning of the Fukushima Daiichi NPS（③ Contaminated Water Management)
Sectoral Target (Contaminated Water Management)(1) Under the three basic principles concerning contaminated water problems (“Removing” thecontamination source, “Redirecting” fresh water from the contamination source, and “Retaining”
contaminated water from leakage), the reinforcement and optimum operation of the water level control
system should be continued to complete the processing the stagnant water in the buildings by 2020.
(2) Considering the total decommissioning process including the full-scale fuel debris retrieval beginning innear future, the long term strategy should be examined for the measures of the contaminated water.

Sectoral Strategy
Steady execution of contaminated water management stated in the Roadmap
Preventive and multilayered drastic measures should be continued based on the three principles,
it is expected to achieve the milestones stated in the Roadmap.
Milestone (Major Target Process)Preventive Drastic Measures• Pumping up of high-concentration contaminated waterin the Underground tunnel(trench) and blockage• Purification by multi-nuclide removal equipment (ALPS)• Paving (facing) in the site to prevent storm sewage
osmosis and reduce the amount of groundwater• Groundwater bypass and pumping up of groundwaterin a well (sub drain) near the reactor buildings• Installation of a land-side impermeable wall to restrain
groundwater inflow into surroundings of the buildings• Installation of a sea-side impermeable wall forfurthersuppressing the outflow of groundwater into the ocean measuresand improvement of the ground by the water glass of the are taken
seawall side of the building

①
②
③

④

⑤

Reduction of the contaminated water generation to about
150 m3/day (by 2020)
Storing all the water treated by nuclides removal
equipment in the welded type tanks (FY 2018)
For stagnant water in the buildings, separation of thepenetrations between Units 1 and 2 and between Units 3
and 4, respectively (by 2018)
Reduction of the radioactive materials in the stagnant
water in the buildings up to approximately one tenth of
the amount at the end of FY 2014 (FY 2018)
Completion of the treatment of stagnant water in thebuildings (by 2020)（except for reactor buildings)

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3. Technological strategies toward decommissioning of the Fukushima Daiichi NPS（③ Contaminated Water Management)
Sectoral Target (Contaminated Water Management)

Study on contaminated water management based on the relation with fuel debris retrieval①Current cooling water
circulation/purification system

Turbinebuildings
Completion of the treatment of
stagnant water in the buildings

）

RPV

RPV

PCV

PCV

Countermeasures to suppress inflow of
α－particles by shielding water, a large
amount of cooling water leaks

Torus room
Reactor building

Turbinebuildings
Completion of the treatment of
stagnant water in the buildings

 Because full-scale decommissioning work including fuel debris
retrieval will start after a while, it is necessary to discuss the
optimal control of contaminated water and groundwater
together at each stage of the decommissioning process.

Ground water

Torus room
Reactor building

PCV circulation
cooling system

PCV

Cesium adsorption
apparatus

Turbinebuildings）（

Ground water

Torus room
Reactor building

RPV④Estimation in the case water
shielding is not needed as fueldebris retrieval progresses.

③Circulation system when retrieved fueldebris (estimation in the case PCV circulation
cooling system is feasible)

KURION, SARRY

PCV

Cesium adsorption
apparatus（

KURION, SARRY）

RPVGround water

Cesium adsorption
apparatus

KURION, SARRY（②Circulation system after completionof the treatment of stagnant water inthe buildings(estimation)

Torus room
Reactor building

Turbinebuildings

Ground water

To maintain the
groundwater level lowe
than the water in the toroom

Completion of the treatment of
stagnant water in the buildings

It is important to build a system thatcan stably control the groundwaterlevel for a long period, such as bycombining passive equipment withfewer machine troubles.

Technical Issues
 Reduction of occurrence of stagnant water in buildings, including countermeasures against storm sewage inflow, operation in response
to lowering of the water level in the building, enhanced contaminated water management installations
 To properly remove a substance derived from fuel debris containing alpha particle in the PCV circulation cooling system, to set theconditions for receiving a part of water treated by the PCV circulation cooling systems in the existing stagnant water circulation system.
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3. Technological strategies toward decommissioning of the Fukushima Daiichi NPS（③ Contaminated Water Management)

Technical issues and further plan on contaminated water management (Process Chart)
Fiscal Year

2018

2019

2020

2021

2022

On-site work
Technical studies for on-site construction"REMOVING " contamination sources

Additional effective doses at thesite boundary .

Treatment with purification Systems
Reducing the total amount of contraminated water to about 150m3 per day"REDIRECTING " fresh waterfrom contamination sources
Reducing the total amount ofcontraminated water to about
150m3 per day by rainwater of
average rainfall

Controle by groundwater by-pass, subdrainage and land-side impermeable walls

Paving the site, Removal of rubble from the roof, Waterproofing
To store all purified water by purificationequipments in welded type tank

"RETAINING" contaminated water

Switch frange type tank towelded type tank

To be responded properly according to
generation of contaminated water, etc.

from leakage

Securing Tank capacity
Ground stabilization, Maintenance of land-side impernmeable wall , Monitoring of groundwater/inside harbor

Treatment for the stagnant water

Reduction of radioactive materials instagnant water up to one tenthCompletion of stagnant water in the buildingsin the buildings
Lowering the level of groundwater/
stagnant water in the building

Maintaining emptied condition of turbinbuildings

Separation of the penetrations between
Units 1 and 2 and between Units 3 and 4

Determination of fuel debris retrieval methods
for the first implementing unit

Contaminated water management
in consideration of fuel debris retrieval

Start of fuel debris retrieval at the first
implementing unit

Taking required actions in accordancewith the phase of fuel debris retrival
Study for consistency between existing circulation cooling system
and PCV circulation cooling systems and monitoring method

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

Sectoral Target(1) To start removing the fuel from the pool by around, 1) FY 2023 for Unit 1, 2) FY 2023 for Unit 2,3) Mid FY 2018 for Unit 3, under the rigorous risk assessment and management and taking
measures for safety and security including preventing the disperse of radioactive materials.
(2) By transferring the fuel stored in the Common Spent Fuel Storage Pool to the dry cask at theTemporary Cask Custody Area, the fuel in the spent fuel pools of Units 1 to 4 is to be stored in the
Common Spent Fuel Storage Pool appropriately.
(3) Based on the assessment of the long-term integrity and investigation for future treatment of theremoved fuel, the future treatment and storage methods will be fixed around 2020.
Progress of Fuel Removal from Spent Fuel Pool
【Unit 1】
 Removed the building cover, installed wind breaking fence Removal of a part of rubbles and measure for preventing
falling into spent fuel pool are initiated.
 To start removing fuel is targeted for FY2023.
【Unit 2】 The upper part of the reactor building is to be dismantled to
install fuel retrieval facilities.
 Installation of opening to have access to the operating floor
and a front chamber to prevent dispersion of radioactive
material have been implemented, further surveillance andcountermeasures are under way.
 To start removing fuel is targeted for FY2023.
【Unit 3】
 A cover for fuel removal was installed in February 2018.
 Once started the trial operation for fuel handling equipmentfrom March 2018, several troubles have occurred. For fuelremoval in the pool which was scheduled in November 2018,
it is being examined and reviewed by TEPCO.
【Unit 4】
 Removal completed in December 2014.
【Unit5/6】
 The fuel is also being stored under stable conditions same asa normal nuclear power
plant.
 Will be removed whensuch removal work
becomes not to affectfuel removal and fueldebris retrieval work of
Units 1 to 3.
Dose measurement of operation floor of Unit 2 by remote robot(Photo/video library:TEPCO)

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3. Technological strategies toward decommissioning of the Fukushima Daiichi NPS
Sectoral Strategy（④ Fuel removal from spent fuel pools)
Technical Issue

Storage of removal fuel【Common issues】
 To limit operation exposure during the installation work, it is necessary to
determine the final operational dosage at an appropriate time.
 Preparation of a detail plan for operation space(yard) adjustment andresource management, etc., because multiple works would be performedin parallel.
【Unit 1】
 Rubble removal on the operation floor, manipulation of the well plugs【Unit 2】
 Installing a common container for both fuel removal and fuel debris
retrieval, and a separate container exclusively for fuel removal on theoperating floor were determined by the proper timing.
 Before removing the fuel from the pool, the exhaust stuck for Units 1/2
will be dismantled.
【Unit 3】
 Appropriate measures to rubbles that is fallen into the spent fuel pool

Appropriate capacity for the fuel in the pools ofeach unit should be reserved both in common spent
fuel storage pool and temporary dry cask custody area.
For the deliberate transportation and storage ofspent fuel and fresh fuel possessed by the entire site,a fuel transport plan need to be developed taking fuelstored in the Units 5/6 into account. As well, thestorage capacity need to be increased and additional
facilities are also necessary to be procured according
to that plan.

Decision on storage and future treatment methods
 The spent fuel pools is storing flawless spent fuel, damaged one before
the accident, and that may be damaged by the rubbles falling into thespent fuel pool.
 Corrosion due to seawater sprayed and injected into the spent fuel poolof Units 2, 3, and 4 at the accident is another concern.
 In the future, necessity of further study on possibility of its long term
storage need to be evaluated based on the inspection results of the fueltaken out from Unit 3, which is experienced the severe explosion causedby the accident and may be damaged by the fallen rubble.
 Based on the assessment of the long-term integrity and investigation for
future treatment of the removed fuel, the future treatment and storage
methods of them will be fixed around 2020.

Numbers of spent fuel etc.

Issues of Fuel removal from spent fuel poolFor fuel removal from SFPs of unit1-3,unit5,6 (4999),
it is necessary
to ensure storage capacity of the Temporary Cask Custody Area,
to concider exporting fuel to off-site.

8000

Common Spent Pool,
Temporary Cask Custody Area
Available：1591

6000
unit1-3,unit5,6
All：4999

4000
unit6：
1884

2000

storage6381

unit3：566
unit2：615

0

unit5：
1542

unit1：392

units1-3

units5,6

Common SpentPoolstorage
1757

New fuel：360（Plan）

Temporary Cask
Custody Area

Export to
off-site(nuclear fuelmanufacture)

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

Technical issues and further plan on removing fuel from the spent fuel pool (Process Chart)
Fiscal year

2018

Unit 1

2019

2020

2021

Removing Rubbles, etc.
Inner investigation of Operating
Floor, etc.

Unit 2

Preparatory work

Selection of retrieval
plan for Unit 2
Proper storage of
retrieved fuel2023

Installing cover, etc.

2024

2025

Retrieving fuelDismantling upper part ofbuilding, etc.

Plan①

Placing Containers, etc.

Plan②

Covering, etc

Retrieving fuelRemoving upper part of Exhauststuck in Unit 1 and Unit 2

Surrounding
Environment

Unit 32022

Measures to prevent
Sea contamination, etc.
Covering, etc
Removing fuelStudy onSelecting plan

Submit/Approval of implementation plan
/Preparatory work

Procuring dry cask
Transfer from Common Spent Fuel Storage pool to Temporary Cask Custody Area
Removing fuel from Unit 5 and 6
Implemented at the extent of rendering no impact
to the works on Unit 1 to 3

Adding dry cask temporary storage

Study forFuture treatment/
Storing method

Determination of future treatment and stroring
method of removed spent fuel (around FY2020)

Study on long-term integrity inconsideration of fuel of Unit 3
Study for method oftreatment and storing

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3. Technological strategies toward decommissioning of the Fukushima Daiichi NPS（⑤ Other specific measures)(1) Sustaining of reactor cold shutdown status
 It is judged that a stable state of cold shutdown is maintained basedon the internal plant data of Units 1 - 3.
 To maintain the stable state in the future, maintaining and improving
reliability through maintenance and management should be continued.

(2) Radiation dose reduction and contamination expansion
prevention all over the power station① Prevention of sea contamination expansion

 The concentration of radioactive materials in the port is below the concentration
limit defined in the notification because of the various treatments. Measures toreduce the concentration of radioactive should be continued.
 Regarding contamination of the soil in the vicinity of the harbor, assessing the impact
on the ocean from a long-term perspective and future environmental restoration,
R&D should be conducted such as to clarify the near-surface nuclide migration
mechanism and refine the analytical models.

② Management of gas and liquid waste

 Monitoring of gas and liquid waste should be continued and its emission should beclosely controlled to ensure that the concentration limits defined in the Notificationis strictly observed. With this view, proper countermeasures should be taken as theirconcentrations are made as low as possible based on a reasonable methods.

③ Dose reduction through site decontamination

 TEPCO formulated “Implementation Policy of Dose Reduction on the Site” to reducethe dose for each area in the sites. Currently, the area in which it is permitted to workwith general work clothes has increased to 96% of the entire sites. The dose rateshould be maintained below 5 μSv/h and as close as possible to the situation before
the accident ultimately.

④ Reduction of environmental impact

 For the evaluation of the dose at the site boundary including additional emissions
from the entire site, reducing the effective dose is continued to address after the goal
to reduce the value to less than 1 mSv/year has been achieved at the end of 2015.

⑤ Comprehensive risk review

 TEPCO conducted a comprehensive inspection of risk sources that may affectthe outside of the site. The specific measures were discussed while taking
priorities into consideration. The Nuclear Regulation Authority created atarget map for reducing the mid-term risk.
 It is important to continue to reduce and comprehensively grasp the risk
sources like this, while taking the positioning and priority in the entire
decommissioning project into consideration for implementing each measure.

(3) Plan for decommissioning measures fornuclear reactor facilities
 TEPCO should formulate a decommissioning plan of the Fukushima
Daiichi NPS in phase 3 after commencing fuel debris retrieval.
 NDF should provide multifaceted and expert advice and guidance
based on the progress and forecast of the decommissioning, thesituation of the reactor buildings, and the trends of R&D withwisdom and knowledge from around the world.

(4) Concrete efforts toward securing safety①Efforts to ensure work safety

 It is important to evaluate the environment according to input resourcesfrom the viewpoint of "justification and optimization," aiming to ensure thesafety of the working environment as well as suppressing personal dose.
 It is necessary to formulate a detailed work plan for each work step, to takepreventive measures concerning troubles that may occur, and to consider
ways to cope with unexpected situations.
 Measures for industrial accident prevention will be taken and reviewed
continuously, medical preparedness will be planned in anticipation ofindustrial accidents, and measures will be taken to reduce occupational risk
exposure as much as possible. It is important to ensure a perfect system ofwork safety by continuing these efforts.

②Efforts for facilities safety Measures are implemented to maintain and improve equipment reliability
based on the maintenance plan for every piece of equipment.
 Particularly, for equipment vital to securing safety for cooling fuel debris, it
is important to continue thorough measures that will be taken to prevent
their important function from stopping from management and operation
standpoints.
 When installed new equipment or facility, steady quality assurance should
be conducted through design reviews and testing and examinations.

③Security enhancement

 As a great quantity of nuclear fuel material is stored, same as a normal
nuclear plant, measures to confirm the reliability of each individual, enhance
nuclear security training, prevent unauthorized intrusion into the sites, etc.
are being implemented.
 Continuing with these efforts, it is implemented appropriate measures for
operation to allow accepting the visits of inspectors.

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3. Technological strategies toward decommissioning of the Fukushima Daiichi NPS（⑥ Comprehensive efforts for the decommissioning project of the Fukushima Daiichi NPS)
Comprehensive efforts for the decommissioning project of the Fukushima Daiichi NPS
 It is important to optimize resource allocation and scheduling while ensuring the consistency and feasibilityof the entire efforts to be promoted concurrently while having interrelations.
 While this complicated and multilayer project should be controlled based on individual tasks ofappropriate scale and control size, the entire decommissioning project should make progresscomprehensively in consideration of the mutual relationship among the smaller projects.
 From a time-based perspective, the overall plan of the decommissioning project should beformulated and discussed while setting reasonable intermediate targets from a facility-wide longterm perspective.
Present● Fuel debris retrieval

Determine fuel debris▼ retrieval policy

Establish the fuel debris retrieval▽ method for the first reactor

Discuss fuel debris retrieval method and develop necessary technologies
Start of fuel debris retrieval

Specific activities to prepare
for retrieval (preliminary
engineering, etc.)● Waste management▽ at the first implementing unit

Preparatory work & retrieval work

Consider consistency
with other activities

Waste from fueldebris retrieval

Store and manage solid waste
Secondary waste fromwater treatment, etc.

Rubble, etc.
on operating floor● Contaminated water management

Complete the treatment of▽ stagnant water in buildings

Operation methodof circulatory coolingsystem during fueldebris retrieval

Implement preventive and redundant measures under the basic principles of "remove,“"keep away" and "prevent leakage."● Fuel removal from spent fuel pools

Prevent leakage of stagnant
water in reactor buildings
Secure space for
concurrent work

Assess the status of the operating floor in eachreactor unit and discuss removal method▼ Completed removal from
Preparatory work
Removal work

Unit 4 (December 2014)▽ Start removal from Unit 3

Start removal from

▽ Units 1 and 2

Preparatory/removal work in each reactor unit

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4. Handling critical enablers for smooth operation of the project (1／3)
Actions toward improvement of working environment and conditions

 A good working environment is the basis for ensuring safe and steady progress of thedecommissioning project of the NPS, which will be carried out over the long term.
 TEPCO is improving the working environment infrastructure byconsolidating and removing existing rest stations and setting up
alternative rest stations, etc. Moreover, variety of measures aretaken such as management for safety and sanitation,
preventing heatstroke, exposure management, dose reduction
measures in the site.
 It is necessary to deal with for improvement in the labor
environment and labor conditions properly.

Cafeteria in a Large rest station(Photo/video library:TEPCO)

Concept of securing safety and promotion of cooperation

 In conducting tasks for which no preceding experience exists in the world, principle of securing safety
should be established according to the situation of the Fukushima Daiichi NPS.
 In light of this, NDF, TEPCO, the Agency for Natural Resources and Energy and other organizations
will cooperate with each other, communicate actively with the Nuclear Regulation Authority, andtake appropriate actions such as presenting policies and observation data related to ensuring safety at
an early stage.
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4. Handling critical enablers for smooth operation of the project (2／3)
Enforced management structure for steady mid-and-long-term decommissioning It is necessary to shift the organization management to project-oriented management and reinforce
the organization and functions to coordinate the projects.
 Therefore, at TEPCO, in addition to the conventionally located Program Manager (PGM) and ProjectManager (PJM), a Program Management Office (PMO) responsible for project control has been set up.
NDF, as the supervisory and supporting organization, recently established a Program Supervision &Support Office (PSO) Withdrawal Plan in the Reserve Fund for the Decommissioning System have been created according to
the planning of the project. It is necessary to enable TEPCO to manage its engineering and make it
function, in order to make a structure of project management work effectively based on a deep
understanding of the technical work of individual tasks.

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4. Handling critical enablers for smooth operation of the project (3／3)
Developing and securing human resources
Developing and securing operators and engineers The Decommissioning R&D Partnership Council has
prepared a draft technology map to grasp the overview
of necessary technologies and decommissioning
personnel, to utilize it for developing and securing
human resources.
 It requires specialized personnel with the ability to
manage projects from a comprehensive perspective
including the consideration of relationship between the
projects based on the overview of the entire
decommissioning process. Companies are expected to
improve employees’ skills, such as by encouraging for
obtaining related licenses.
Conference for R&D Initiative on Nuclear Decommissioning
Technology by the Next Generation (NDEC)

Award Ceremony

Oral session

Poster session

Fostering the next generation to play roles in theDecommissioning of the Fukushima Daiichi NPS in the
future Industry, academia, and the government related tonuclear power should steadily continue efforts forhuman resources. They should show a variety of career
paths of researchers and engineering in the Fukushima
Daiichi NPS decommissioning.
 “Conference for R&D Initiative on Nuclear
Decommissioning Technology by the Next Generation(NDEC)” intended for students, and “Creative Robot
Contest for Decommissioning,” intended for technicalcollege students are held.
Creative Robot Contest for Decommissioning

Standard test field

Naraha Summer School

Participants

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５．R&D initiatives (1／3)
Entire perspective of R&D
 Various problems exist in the decommissioning of the Fukushima Daiichi NPS, and R&D activities for solving these
problems are being conducted by variety of industrial-academic-governmental institutions engaged through theareas of basic/fundamental research, applied research and development/utilization.
 To organically link these activities and efficiently solve the on-site problems through R&D, NDF regularly holds
meetings of the Decommissioning R&D Partnership Council.
※８

METI

※９

Support

MEXT

SupportCenter of World Intelligence Project for Nuclear S&T
and Human Resource Development

Project of Decommissioning andContaminated Water Management

Steering committee

Management
Expenses Grant
Funding

Fund Establishment Organization
Fund for Decommissioning andContaminated Water Management

Grant

Project Management
OfficeNDF

JAEA

Decommissioning
Strategy Committee

Sector Fukushima R&D

SupportFunding

Assignment

CLADS

Decommissioning
R&D PartnershipCouncil

Assignment

Cooperation※7

Cooperative
relationship

Naraha Remote Technology
Development Center（Member）
NDF,JAEA,TEPCO,
IRID, Plant Makers,
Related Experts, METI,
MEXT

Okuma Analysis andResearch Center

Foreign
Governmental
Agencies

Project
Management
OfficeContract/
collaborative
Research

Fukushima Environmental
Safety Center

Administering

Administering

Sharing/planning
R&D information

Project
Management
Operation

Request for study
and Support

Subsidized Project Operating Entities
Other
makers, etc.
(including
foreignenterprises)

IRID

Commissioned Research Institutes

Information
sharingNational R&D Agency
Plant makers
Electric power Companies, etc.

TEPCO
Commission

Domestic / Foreign Enterprises
※１
※２
※３
※４
※５
※６

※７
※８
※９

Exchange of
researchneeds/seeds

Platform of Basic
Research for
Decommissioning

Human Resource
Development andResearch Program for
Decommissioning ofFukushima Daiichi NPS

Participation

Adopteduniversities, etc .

Acceleration
Program for Reactor
Decommissioning

Adopteduniversities, etc .

Foreign
Universities/
Joint
ResearchResearch

Institutes

Domestic universities,
Research institutes, etc.

Decommissioning R&D Partnership was established in NDF according to a decision of Team for Countermeasures for Decommissioning and Contaminated Water Treatment.
Bold solid arrow mean supply of R&D and management expenses (except for facilities expense).Light solid arrow means cooperati on. Dotted line arrow means participation in
Decommissioning R&D Partnership Council.
Some institutions including JAEA are at the multiple positions.
Each institution has their own cooperation with foreign institution based on MOU, etc.
R&D activities by other institutions including Central Research Institute of Electric Power Industry are abbreviated.
Among the promotion projects of nuclear energy science technology/human resource development that require collective know -how, the adopted projects up to 2017
were entrusted by MEXT to the trustee, which are not shown in this figure.
Subsidies for the promotion projects of nuclear energy science technology/human resource development that require collective know-how are delivered to JAEA, but expressed
as being delivered to CLADS for the sake of clarity here.
For Decommissioning and Contaminated water treatment subsidy project, NDF drafts the next R&D plan and METI determines it based on the policies on Roadmap and the Strategic Plan and R&D progress.
NDF participates in the steering committee of human resource development promotion project of Nuclear Science Technology that gathers wisdom and intelligence, as a constituent.

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５．R&D initiatives (2/3)
R&D of decommissioning required for on-site work/engineering R&D tasks that engineering studies clarified its importance should be shared and implemented timely andaccurately. For the time being, R&D tasks are going to be identified according to the progress of the preliminary
engineering, and then, it is presumable that the timing to implement such tasks will be determined through the
project management process.
 To realize an R&D management system under such project-based schedule, appropriate information-sharing
should be carried out under the project management system enforced jointly by NDF and TEPCO. To this end, it isnecessary to marshal the details of R&D currently in progress, and R&D tasks required in the future under the
project management system clarifying when the problem must be solved and which project needs it.
 As specific processes become apparent, it will be required for TEPCO to make efforts to raise the ratio oftechnological development to improve the safety and efficiency of the decommissioning work. Under theReserve Fund system, it is important for TEPCO to steadily figure out and implement the required technologicaldevelopment.

On-site Work (TEPCO)

Preliminary Engineering

R&D Tasks,
Schedule

Appropriate
information-sharing
and organizing
under the project
management system

R&D required for on-site
Technological Development (by TEPCO)
Research and Development(the Project of Decommissioning andContaminated Water Management)

R&D Achievement

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５．R&D initiatives (3／3)
Enhancement of basic study and R&D infrastructure for the success of the decommissioning project To facilitate the decommissioning project in a safely steady andeffective manner, it is essential to develop mid-and-long-term R&D
strategies including scientific and technological investigation basedon understandings of the principles and the theories. For thispurpose, NDF has built a “Task Force on Research Collaboration” andspecified the 6 Essential R&D Themes that should be preferentiallyand strategically targeted. The Platform of Basic Research for
Decommissioning investigated on the themes and compiled R&D
strategies for the Themes.
 Also, it is essential to work on developing R&D infrastructure andaccumulating technological knowledge.
According to a proposition by NDF, the Center of WorldIntelligence Project for Nuclear S&T and Human Resource
Development by the Ministry of Education, Culture, Sports,
Science and Technology (MEXT) is implemented under the
structure centered on JAEA/CLADS from the newly adopted
issues since FY2018.
R&D infrastructures aiming at mid-and-long-term vision arebeing set up mainly in Fukushima Prefecture.

Six Essential R&D Themes① To identify process of characteristic changes in fueldebris over time
② To elucidate corrosion mechanisms underunusual/extreme circumstances③ Radiation measurement technologies adopting
innovative approaches④ To clarify behavior of radioactive particles
generated during decommissioning (incl. alpha dust
treatment)⑤ To understand fundamental mechanisms ofradioactive contamination⑥ Environmental fate studies of radioactive materials
generated during decommissioning• JAEA Naraha Remote Technology Development Center(Naraha-machi, in Fukushima prefecture, in service in April 2016)• Fukushima Prefectural Centre for Environmental Creation(Miharu-machi, in Fukushima prefecture, opened in July 2016)• The building for international research collaboration of JAEA/CLADS(Tomioka-machi, in Fukushima prefecture, opened in April 2017 )• The facility management building of JAEA Okuma Analysis and Research Center（Okuma-machi, in Fukushima prefecture, opened in march 2018）

The facility management building of
JAEA Okuma Analysis and Research Center(source: JAEA’s website)

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６．Enhancement of International Cooperation
Significance of international cooperation
 In order to make steady progress on decommissioning of
the Fukushima Daiichi NPS, it is important to learn thelessons of decommission experience from accident
reactors and legacy sites in the world as well as actively
utilize the world’s best technologies and personnel
resources.

 To secure and maintain understanding and support frominternational communities, it is also important to engage
in decommissioning with open to international societies.
It should strengthen to distribute easily understandable
information, for helping accurate comprehension frominternational society.

Facilitation of international cooperation activities
Enhancement of partnership with overseas
decommissioning agency
 It is essential to strengthen sustainable partnership withoverseas decommissioning agencies.

Dissemination to global society

 NDF takes dissemination of information about thesituation of the Fukushima Daiichi NPS
decommissioning globally through holding side events
Integrating and utilizing wisdom and knowledge in the worldof IAEA General Meeting and giving speeches at key
international meeting.
 In regard to decommissioning of the Fukushima Daiichi NPS,
wisdom and knowledge in the world that our country should
obtain is implemented with a variety of approaches such assystem /policy, providing strategy, project plan /operation,
ensuring security, regional communications, and so forth, notonly in technical aspect but operational aspect. In order to
use the highest level of technologies and human resources in
the world, it should be updated the latest status.
Side event of IAEA General Meeting

Close cooperation with relevant domestic organization
 Ensuring consistency of international cooperative activities in Japan from a viewpoint of implementing effective
international cooperation, the close relationship of relevant domestic organizations should be further enhanced.
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７．Local community engagement and further enhancement of communication
Approaches for local community engagement
and further enhancement of communication

Further spread of communication andmeasures to reputational damages

 In implementing decommissioning of the Fukushima Daiichi NPS
steadily, local community engagement is the major premise, and it
should be seeking for decommissioning to contribute to therestoration in local communities while trying to establish trustfulrelationships closely with the region.
 It is a starting point to listen to the voice from various standpoints
including local communities sincerely. While not only providing
information but also communicating interactive on progresses ofapproach to safety measures and relevant work and on radioactive
safety appropriately, further decommissioning should be proceededby establishing common understandings about risk reduction policy.
 On the foundation of communication like this, it is necessary toinitiate specific efforts that decommissioning and its relevant
activities become locally-oriented industries through in contributing
to the restoration and revitalization of the region.

 When delays in responding to
reputational damages or troubles on
decommissioning work occur, it is themost important to promptly reduce
existing risks while making efforts forproper safety management, in order toprevent from a vicious cycle such as
downgrading evaluation from society foraddressing decommissioning then it
causes the further delay of activities. It isnecessary to enrich communication with
consumers including overseas as well as
local residents, media, market
participants and distributors.

NDF hosts International Forum on the Decommissioning of the
Fukushima Daiichi NPS annually for providing information andvigorous dialogue about decommissioning with the local citizens

The 3rd International Forum on the Decommissioningof the Fukushima Daiichi NPS“Hairo-no-iroha” a brochure prepared by NDF
that disseminates decommissioning in plain words (Cover)

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