Joint Convention
on the Safety of Spent Fuel Management
and on the Safety of Radioactive Waste
National Report of Japanffoorr tthhee tthhiirrdd R
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Government of Japan

Joint Convention on the Safety of Spent Fuel Management
and on the Safety of Radioactive Waste Management
Pont of Contact
International Affairs Office
Nuclear and Industrial Safety Agency (NISA)
Ministry of Economy, Trade and Industry (METI)
Kasumigaseki 1-3-1, Chiyoda-ku Tokyo Japan 100-8986
Tel +81-3-3501-1087
Fax +81-3-3580-5971
The National Report of Japan for the third Review Meeting is able to download via METI website“http://www.meti.go.jp/english/index.htm” with PDF format.

Joint Convention on the Safety of Spent Fuel Management and on the Safety ofRadioactive Waste Management
National Report of Japan for the third Review Meeting
Table of Contents

A

Introduction

A1
A2
A3
A4

Current Status of management of spent fuel and radioactive waste in Japan
Main theme of the National Report
Other topics
Preparation of the Report

B

Policies and Practices

B1
B2
B3
B4
B5

Spent fuel management policy
Spent fuel management practices
Radioactive waste management policy
Radioactive waste management practices
Criteria used to define and categorize radioactive waste

9
10
10
12
14

C

Scope of Application

17

D

Inventories and Lists

D1
D2
D3
D4
D5

List of spent fuel management facilities
Inventories of spent fuelList of radioactive waste management facilities
Inventories of radioactive waste
List and status of nuclear facilities in the process of being decommissioned

E

Legislative and Regulatory System

E1
E2
E3

Implementing measures
Legislative and regulatory framework
Regulatory bodyF

Other General Safety Provisions

F1
F2
F3
F4
F5
F6

Responsibility of the license holder
Human and Financial resources
Quality assurance
Operational Radiation protection
Emergency preparedness
Decommissioning

1
4
6
7

18
19
19
24
25

27
33
40

50
51
57
58
62
72

i

G

Safety of Spent Fuel Management

75

General safety requirements
Existing facilities
Siting of proposed facilities
Design and construction of facilities
Assessment of safety of facilities
Operation of facilities

77
79
79
81
82
83

H

Safety of Radioactive Waste Management

86

H1
H2
H3
H4
H5
H6
H7

General safety requirements
Existing facilities and past practices
Siting of proposed facilities
Design and construction of facilities
Assessment of safety of facilities
Operation of facilities
Institutional measures after closure

89
91
93
95
97
99
103

G1
G2
G3
G4
G5
G6

I

Transboundary Movement
I1
I2

J

Transboundary movement
Prohibition of shipment to a destination south of latitude 60 degrees South

107
108

Disused Sealed Sources
J1
J2
J3
J4

Framework of national law
Management of disused sealed source
Reentry of disused sealed sources
Compliance with the Code of Conduct on the Safety and Security of Radioactive
SourcesK

Planned Activities to Improve Safety

K1
K2

Development of laws and related rules
Measures to ensure reliability of technology by experiences, tests and analyses

L

Annexes

L1
L2
L3
L4
L5
L6

Inventories of spent fuelInventories of radioactive waste
Excerpt of Regulation Relevant to Section G
Excerpt of Regulation Relevant to Section H
Illustrations related to spent fuel storage facility
Illustrations related to radioactive waste disposal

ii

109
109
111
111

113
113

115
115
119
126
136
137

Acronyms
ACNRE

Advisory Committee for Natural Resources and Energy

AEC

Atomic Energy Commission

ANRE

Agency of Natural Resources and Energy

ATR

Advanced Thermal Reactor

BWR

Boiling Water Reactor

ERSS

Emergency Response Support System

FBR

Fast Breeder Reactor

HLW

High-level radioactive wastes

JAEA

Japan Atomic Energy Agency

JAPCO

Japan Atomic Power Company Inc.

JNESJapan Nuclear Energy Safety Organization

JNFL

Japan Nuclear Fuel Limited

LLW

Low-level radioactive wastes

METI

Ministry of Economy, Trade and Industry

MEXT

Ministry of Education, Culture, Sports, Science and Technology

MHLW

Ministry of Health, Labour and Welfare

MOFA

Ministry of Foreign Affairs

NISA

Nuclear and Industrial Safety Agency, METI

NISS

Nuclear and Industrial Safety Subcommittee

NSC

Nuclear Safety Commission

NUCIA

Nuclear Information Archive

NUMO

Nuclear Waste Management Organization of Japan

MOX fuel

Uranium and Plutonium Mix Oxide fuel

PFSB

Pharmaceutical and Food Safety Bureau, MHLW

PWRPressurized Water Reactor

SPEEDI

System for Prediction of Environmental Emergency Dose Information

STPB

Science and Technology Policy Bureau, MEXTTEPCOTokyo Electric Power Company Inc.

iii

Definitions
Category 1 waste disposal
Category 2 waste disposal
Intermediate depth disposal
Specific Radioactive Waste

TRU waste

Waste Storage

Activity of geological disposal for high-level radioactive
wastes.
Activity of the waste disposal other than geologicaldisposal for low-level radioactive wastes.
Disposal in the underground deeper than 50 meters. This
disposal method is classified in Category 2 waste
disposal.
High-level radioactive wastes generated from spent fuelreprocessing
Low-level radioactive wastes generated from MOX fuelfabrication or reprocessing facilities. Also known as“long-lived low-heat-generating radioactive wastes” in theradioactive waste regulation in Japan. Generally, thiswaste contains Trans Uranic material.
Activity to store high-level radioactive waste canisters
before disposal.

iv

Introduction

Section A

Introduction

A1

Current status of management of spent fuel and radioactive waste in Japan

A1.1

Status of utilization and management of nuclear energy in Japan

Nuclear facilities in Japan are as listed in the following table, the details of which aredescribed in Section D.
Nuclear facility

NumberOperating nuclear power plant

55

Nuclear power plant under construction

4

Nuclear power reactor at decommissioning stage

2

Nuclear fuel fabrication facility

5

Spent fuel reprocessing facility

2Radioactive waste storage facility

2Radioactive waste disposal facility

2Operating research reactor

15

Research reactor at decommissioning stage

8

Nuclear fuel material utilization facility*

16*: The facilities governed by Article 41 of the Enforcement ordinance of the
Law for the Regulation of Nuclear Source Material, Nuclear Fuel Material
and Nuclear Reactors.

The current status of the preparation of radioactive waste disposal regulation
system and the over view of spent fuel and radioactive waste management are
shown in Table A1-1 and TableA1-2 respectively.
A1.2

Major activities in the nuclear facilities in Japan since the last report

1.
Safety review of Recycle Fuel Storage Center
The Recycle Fuel Storage Company jointly established by the Tokyo Electric Power
Company Inc. (hereinafter it is referred as TEPCO) and the Japan Atomic Power Company
Inc. (hereinafter it is referred as JAPCO) filed an application for license for the Recycle
Fuel Storage Center (See Fig.L5-1) to be established in Mutsu City of Aomori Prefecture.
The proposed Recycle Fuel Storage Center has 3,000 tons (metallic uranium prior toirradiation) of the maximum storage capacity and stores spent fuel in dry metallic casks(See Fig.L5-2). The application is now under safety review by Nuclear and Industrial Safety
Agency (hereinafter it is referred as NISA) of the Ministry of Economy, Trade and Industry(hereinafter it is referred as METI).
2.

Application for clearance to the waste from decommissioning of the Tokai Power
Station of the JAPCOThe Tokai Power Station of the JAPCO terminated its operation in 1998 and is indecommissioning process since December 2001. The clearance system was introduced
upon the amendment of “Law for Regulation of Nuclear Source Material, Nuclear Fuel
Material and Nuclear Reactors” (hereinafter referred to as “Reactor Regulation Law”) in
May, 2005. A part of the waste which was generated from the dismantlement of the Tokai
Power Station was classified as cleared materials in July 2007 after the confirmation of theradioactivity concentration by NISA.

1

A

A

Introduction

3.
Decommissioning of Advanced Thermal Reactor (ATR) “Fugen”
The ATR “Fugen” terminated its operation in March, 2003 and the licensee submitted thedecommissioning program on November 7, 2006. The program was approved by thegovernment on February 12, 2008 and decommissioning work started. In 2008, moderator(heavy water) will be removed and the turbine will be dismantled.
4.
Rokkasho nuclear fuel cycle facilities
Japan focuses its nuclear policy on nuclear fuel cycle to reprocess spent fuel and toeffectively utilize the recovered uranium and plutonium. The Japan Nuclear Fuel Limited
has its nuclear fuel cycle facilities (uranium enrichment facility, reprocessing facility, waste
storage facility and low level radioactive waste (LLW) disposal facility) in Rokkasho Villageof Aomori Prefecture. All of those facilities, with the exception of the reprocessing plant
which is currently under Pre-service tests, are already in operation.
As for the Pre-service tests of the main part of the reprocessing plant, the basic functional
tests including flow test and chemical test and uranium test were already completed, andthe active test with actual spent fuel is currently being carried out to confirm theperformance of the reprocessing process.
The Rokkasho reprocessing facility is the first large-scale reprocessing facility in Japanand licensee plans the construction is going to be completed in November, 2008.
5.
Selection of the final disposal site
The Nuclear Waste Management Organization of Japan (hereinafter it is referred as
NUMO), the implementing entity of the high level radioactive waste (HLW) disposal, hasbeen inviting public offering for the preliminary investigation areas as the first step ofselecting disposal sites since December 2002.
In Toyo-Town of Kochi Prefecture, study meetings was held since September 2006, under
the auspices of the Town and other organizations, and the mayor of the Town submitted anoffer for the start of the preliminary investigation to NUMO, 2007. Upon receiving the offer
of Toyo-Town, NUMO filed the application in accordance with the Specific Radioactive
Waste Final Disposal Act (Final Disposal Act), but the Town cancelled the offer in April
2007 and the preliminary investigation is not performed.

2

3
Under discussion since May 1997
a: Completed: Major nuclear reactor facilities (March 17, 1999), Heavy water reactors, fast neutron reactors, etc.
(July 16, 2001), Nuclear fuel material use facilities (facilities dealing with irradiated fuels and materials) (April 24,2003), Radionuclide concentrations for materials not requiring treatment as radioactive wastes, generated fromdismantling etc. of reactor facilities and nuclear fuel use facilities" (December 16, 2004), (Partial amendment,
March 17, 2005)
b. Under discussion: Uranium, TRU facilities
c. Future discussion: Radioisotope facilities

3

under
geologicalCompleted
Amendment of“Basicguides for safety review forradioactive waste burial
facilities” (January 7, 1993,
March 29, 2001)

Amendment of“Basicguides for safety review forradioactive waste burial
facilities” (January 7, 1993,
March 29, 2001)

Completed“Basic guides for safety
reviewforradioactivewasteburialfacilities”(March, 1988)

Under discussion

Partially
discussion(Except for
disposal)

Future discussion

Safety review guidelines

1): Basic concept of safety regulation of near surface disposal of solid radioactive waste generated from research laboratory etc. (April 20, 2006)
2): Basic concept of safety regulation of near surface disposal of solid radioactive waste generated from radioisotope use facility etc.
*3): Waste from research facilities, etc. includes not only the waste regulated under the Reactor Regulation Law but also the waste regulated under the Radiation Hazard Prevention Law, the Medical Care Law or the Pharmaceutical Affairs Law.
*4): “Basic concept of safety regulation on low-level radioactive waste burial” (Interim Report) (July 12, 2007)

Future discussion

Completed“Policy on processing and disposal ofradioactive wastes” (August 7, 1984)“Fundamental concept of processing anddisposal of Uranium wastes” (December
14, 2000)

4

Completed“Near surface disposal of radioisotope wastes” (January
26, 2004) 2“Basic concept of safety regulation for near surface
disposal of solid radioactive waste generated fromresearch laboratories, etc.” (April 20, 2006)

Waste from research facilities,
etc.

Future discussion

Completed“Reference
radionuclide
concentration values for safety
regulations of land disposal of
low-level
radioactive solid
waste” (Third Interim Report)(September 14, 2000)

Completed“Reference
radionuclide
concentration values for safety
regulations of land disposal of
low-level
radioactive solid
waste”(Second
Interim
Report) (June 1992)

Completed“Fundamental concept of processing and disposal of wastes
generated at research laboratories, etc.”(May 28, 1998)
The report on “The approach to realize the disposal ofradioisotopes and waste from research facility etc. (to bedisposed of near surface)”(October 10, 2006)“The promotion of the approach to realize the disposal ofwaste from research facility etc.” (February 5, 2008)

Completed“Basic concept of safety regulation for land disposal of
low-level solid radioactive waste” (October 24, 1985)

Completed“Reference
radionuclide
concentration values for safety
regulations of land disposal of
low-level radioactive Solid
waste”(ThirdReport)(September 14, 2000)
Completed“Reference
radionuclide
concentration values for safety
regulation of land disposal of
low-level
radioactivesolidwaste”(Interim
Report)(February 1987)“Reference
radionuclide
concentration values for safety
regulations of land disposal of
low-level
radioactive solid
waste”(Second
Interim
Report) (June 1992)

Upper bound ofradioactive waste disposal

Partially Completed 1

Completed“Policy on processing anddisposal of radioactive wastes”(Final Report) (October 8, 1985)

NSC

Completed“Fundamental concept of processing and disposal of Uranium
wastes” (December 14, 2000)

Metal, etc.

Completed“Policy on processing
anddisposalofradioactive
wastes”(Interim
Report)(August 7, 1984)

Completed“Basic concept of safety regulation for the disposal of
low-level radioactive waste which has concentration
over existing upper bounds” (September 14, 2000)“Basic concept of safety regulation on low-level
radioactive waste burial” (Interim Report) (July 12, 2007)

Completed“Fundamental concept of processing and disposal ofradioactive wastes containing transuranic nuclides” (March
23, 2000)“Geological Disposal of Long Half Lives Low Heat Radioactive
Waste, Technical Feasibility of Co-Disposal with High Level
Radioactive Waste” (April 18, 2006)

Completed“Basic concept of disposal of low-level radioactive waste thatexceeds the concentration limit value in the ordinance”(October 16, 1998)

Completed“Fundamental Basic concept of safety regulation on low-level
radioactive waste burial” (Interim Report) (July 12, 2007)

Completed“Policy on processing and disposal of radioactive wastes”(Interim Report) (August, 1984)“Fundamental concept toward disposal of high-level
radioactive wastes” (May 1998)

Fundamental concept of safety regulation

Uranium waste

Very
low
level
Radioactive
waste

Concrete, etc.

Low-level radioactive
waste(Relatively lower
radioactive waste)

Waste of Core Structures
etc.
(Relatively higher
radioactive waste)Long Half Lives Low HeatRadioactive Waste

High-level radioactive waste

System and Responsibility

AEC

Completed“Basic concept of safety regulation on high-level radioactive waste
disposal ” (November 6, 2000)“Environmental requirements to be considered at the selection of
the preliminary investigation areas for high-level radioactive waste
disposal” (September 30, 2002)“Licensing procedure relating to the safety regulation of specified
radioactive waste disposal and involvement of Nuclear Safety
Commission in these activities” (Interim Report) (May 7, 2007)

Disposal method

Completed “Basic concept of safety regulation on low-level radioactive waste burial”(Interim Report) (July 12, 2007)

Classification

Materials that need not be treated asradioactive wastes (Waste equivalent toclearance)

Low- level radioactive waste

Classification of basic concepts for disposal and status of activities preparing relevant regulations

Concluded “Upper Bound Concentration on the disposal of low level radioactive solid
waste” (May 21, 2007)

Table A1-1

Common important issues for the safety regulation of radioactive waste disposal (June 10, 2004)
Completed

Waste from reactor facility

A

Law

The Reactor Regulation Law*3

Introduction

Published“Enforcement Ordinancefor the Reactor Regulation
Law” (November 2, 2005)

Published“Enforcement Ordinancefor the Reactor Regulation
Law” (April 2008)
Published“Enforcement Ordinancefor the Radiation Hazards
Prevention Law” (May2005)
“Enforcement Ordinancefor the Reactor Regulation
Law” (April 2008)

Published“Enforcement Ordinancefor the Reactor Regulation
Law” (December 2000)

Published“Enforcement Ordinancefor the Reactor Regulation
Law” (September 1992)

Published“Enforcement Ordinancefor the Reactor Regulation
Law”(March1987,
September 1992)

Published“Enforcement Ordinancefor the Reactor Regulation
Law” (December 2000)

Published“Enforcement Ordinancefor the Reactor Regulation
Law” (April 2008)

Published“Rules for the enforcement ofRadiation Hazards Preventionact” (June 2005)

Partially PublishedFuture discussion

Published“Rules for category 2 waste
disposal for nuclear fuelmaterial or those which arecontaminated there with” (April
1, 2008)

Partially Published“Rule for Disposal of Category
1 Waste Disposal of Nuclear
Fuel Material or Material
Contaminated with Nuclear
Fuel Material” (April 1, 2008)“Rule for Disposal of Category
2 Waste Disposal of Nuclear
Fuel Material or Material
Contaminated with Nuclear
Fuel Material” (April 1, 2008)

Published“Rules for category 1 waste
disposal for nuclear fuelmaterial or those which arecontaminated with” (April 1,
2008)

Rules

Legislation etc. on safety regulations
Government order

Introduction

AA

Introduction

Table A1-2

Over View of Policy and Practice on Spent FuelManagement and Radio-active Waste Management

Type of Liability

Long-term
management policy

Spent fuelReprocessing

Nuclear fuel cycle
waste

Non-power waste

Decommissioning
liabilities
Disused Sealed
SourceGeological,
intermediate depthor near surface
disposalGeological,
intermediate depthor near surface
disposal
Immediate
decommissioning of
NPP

Funding
Utility pays
fund forreprocessing
Utility pays
fund fordisposal of
waste

Current practice /Facilities
Domestic
reprocessing
plantsPlanned Facilities
Interim storage
facility

HLW Storage
Facility / LLW
Disposal Facility

Geological,
intermediate depthor near surface
disposal facilities

Under
discussion

On site storage

Under discussion

Operators
pays into
reserve fundDecommissioning
underway-

User

Return to
manufacturers /Storage insidefacilities-

Return to
manufacturer /Long-term storage

A2

Main theme of the National Report

A2.1

Policies and Practices

The Agency for Natural Resources and Energy (hereinafter it is referred as ANRE) amended
the Final Disposal Act, reviewed the total research and development program at the“Geological Disposal Basic Research and Development Coordinating Council” andcompiled “Overall Research Programme on Basic R & D of Geological Disposal of HLW”.
The Agency is to promote international cooperation in this field using the frameworks of the
IAEA, OECD/NEA, GNEP, etc.
The Ministry of Education, Culture, Sports, Science and Technology (hereinafter it isreferred as MEXT) amended the “the Law for the Independent Administrative Agency, Japan
Atomic Energy Agency” and designated the Japan Atomic Energy Agency (hereinafter it isreferred as JAEA) as the implementation entity of the disposal of low level radioactive
wastes generated at the facilities using radioisotopes and radiation generators and at otherlaboratories and research institutes.
The Recycle Fuel Storage Company applied for the license for the Recycle Fuel Storage
Center in March 2007. The JAPCO carried some cleared materials out of the Tokai Power
Station for the first time in Japan in June 2007 in accordance with the clearance system.
A2.2

Decommissioning

The JAEA terminated commercial operation of advanced thermal reactor “FUGEN” in March
2003 and “FUGEN” entered decommissioning stage after its decommissioning program wasapproved in February 2008.
A2.3

Legal and Regulatory systems

1.
Development of legal systems for the final disposal of HLW
The promotion of nuclear fuel cycle is an important part of Japanese energy policy andnuclear fuel cycle facilities, such as spent fuel reprocessing facility, are going to startfull-scale operation in near future. As a step for facilitating nuclear fuel cycle, thegovernment of Japan amended relevant laws in 2007 in order to take necessary measures
4

Introduction

for steady implementation of the disposal of high level radioactive wastes and long-lived
low-heat-generating radioactive wastes (hereinafter it is referred as TRU wastes)
generated in the processes of nuclear fuel cycle.
The amendments of laws are outlined below:(1) Amendment of the Final Disposal Act
In addition to the HLW, the following wastes are also added to the waste that is disposedof NUMO.
a. TRU wastes generated from spent fuel reprocessing and from MOX fuel fabrication
processb. HLW to be returned from abroad (as exchanged wastes) in exchange for TRU wastes
originally planned to be returned
In addition, TRU waste disposal costs were added to the disposal reserve funds that is
paid to NUMO by the licensees of nuclear power plants and of reprocessing facility as
the costs for the final disposal of Specific Radioactive Wastes.
(2)

Amendment of the Act for Deposit and Administration of Reserve Funds for
Reprocessing of Spent Fuel from Nuclear Power Generation.
An amendment was made to add the provisions to adjust the reserve funds for thedecrease of the radioactive waste storage and disposal costs due to receiving of theexchanged wastes(3) Amendment of the Reactor Regulation Law
The final disposal for HLW and TRU wastes exceeding a certain level of concentration
were added to the activity governed by the Law and the safety regulation system forthese disposal activities were prepared. In addition, operators of waste disposal that deal
with plutonium beyond a certain amount were obligated to take physical protection
measures.
2.

Quality improvement of regulatory activities of the NISANISA started to develop a management system for the quality improvement of regulatory
activities in fiscal 2006 and has been implementing the system since fiscal 2007.
A2.4

General provisions

1.
Human Resources
The regulatory bodies and nuclear industries in Japan are striving to develop humanresources as a part of ensuring future nuclear safety infrastructure.
In 2006, NISA established the Subcommittee for Nuclear Safety Infrastructure under the
Nuclear and Industrial Safety Subcommittee of the Advisory Committee for Natural
Resources and Energy (hereinafter it is referred as NISS/ACNRE) and the Subcommittee
is discussing measures for developing and ensuring human resources for nuclear energy
area.
MEXT and ANRE of METI are implementing the human resources development program
since 2007 focusing on the research activities in the areas of basic nuclear technology.
A2.5

Safety of radioactive waste management

1.
Development of the safety regulation system for final disposal of radioactive wastes
In order to establish nuclear safety regulation system under the Reactor Regulation Law
amended in June 2007, the Subcommittee for Radioactive Waste Safety under the
NISS/ACNRE issued the report titled “On the Safety Regulation of Geological Disposal ofHigh Level Radioactive Wastes (January 2008) .” The report prescribes the technicalstandards for high level radioactive waste disposal facilities and waste packages,
5

A

A

Introduction

measures for maintaining facility safety, periodic safety review, the steps for closing thefacility, etc. The Subcommittee also discussed the safety regulation system forintermediate depth disposal and issued the report titled “Safety Regulation on Intermediate
Depth Disposal of Low Level Radioactive Waste (January 2008)”. Concerning the waste ofcore structures etc., the report prescribes the disposal depth, requirements for design andconstruction of facilities, technical standards for waste packages, periodic safety review,monitoring and record-keeping. In addition, in March, 2008, the Subcommittee issued thereport titled “On the Safety Regulation of the Near Surface Disposal of Low Level
Radioactive Wastes”. The report published the result of the study on the technicalstandards for near surface disposal of low and very low level radioactive waste.
In response to the above discussions and studies, NISA developed the safety regulation
system for the disposal of high level radioactive wastes, streamlined the existing safety
regulation for radioactive waste disposal, established the “Rule for Disposal of Category 1
Waste Disposal of Nuclear Fuel Material or Material Contaminated with Nuclear Fuel
Material” as the basis for safety regulation for geological disposal of HLW and establishedthe “Rule for Disposal of Category 2 Waste Disposal of Nuclear Fuel Material or Material
Contaminated with Nuclear Fuel Material” as the basis for safety regulation forintermediate depth disposal and near surface disposal of low level radioactive wastes.
These safety regulation systems are described in Section H.
Waste disposal was provided in the amendment of the Law Concerning Prevention from
Radiation Hazards due to Radioisotopes, etc. (Radiation Hazards Prevention Law) in June
2004.
A3

Other topics

A3.1

International activities

It is a policy of Japan to use nuclear energy only for peaceful purposes. In line with thispolicy, Japan was actively involved in the establishment of the International Atomic Energy
Agency (IAEA) as a framework for international cooperation and has been participating inand will further contribute to the IAEA’s activities. For instance, the IAEA’s safety standard
committees have been working for developing and updating the safety standards topped by
the Safety Fundamentals (SF-1) and Japan has been striving to introduce those standards
into deliberation on the nation’s policies for peaceful use of nuclear energy.
Japan, recognizing the importance of international cooperation in ensuring safety in spent
fuel and radioactive waste management, will continuously take part in the activities of the
IAEA and the Nuclear Energy Agency of the Organization of Economic Cooperation
Development (OECD/NEA).
In October 2005, NISA hosted the IAEA’s international conference on the safety ofradioactive waste disposal. The conference was held in Tokyo with a number of participantsfrom 19 countries and 3 international organizations. After the conference, the 20th Waste
Safety Standard Committee (WASSC) Meeting was held at the Ministry of Economic, Tradeand Industry to discuss proposed safety standards documents.
In Asian region, Radioactive Waste Management project has been implemented since 1995
within the framework of the Forum for Nuclear Cooperation in Asia (FNCA). This project is
intended to contribute to the safety improvement of radioactive waste management in Asian
region through exchanging and sharing the experience, findings and information onradioactive waste management among participating countries. Japan has been playing aleading role for this activity. Particularly, this project prepares and updates, as appropriate, aconsolidated report on radioactive waste management that summarizes the activities in theparticipating countries by using this Convention as a reference.
The Radioactive Waste Management Topical Group of the Asian Nuclear Safety Network(ANSN), which is being operated as a part of the IAEA’s Extra-Budgetary Program for Asia,
helps non-contracting countries to prepare for becoming contracting parties to thisConvention by using the results of FNCA activities.
6

Introduction

In October 2006, the Japan Nuclear Energy Safety Organization (hereinafter it is referred as
JNES) held a seminar in Vietnam on the Convention on Nuclear Safety and this Joint
Convention for Vietnamese governmental officials and those involved in nuclear energy.
A3.2

Impacts of Niigataken Chuetsu-Oki earthquake

The Niigataken Chuetsu-Oki earthquake that occurred on July 16, 2007, affected
Kashiwazaki-Kariwa Nuclear Power Station of the TEPCO. The operating units wereautomatically shut down by detecting the earthquake and safety of the station was ensured.
However, a number of impacts were identified by the post-earthquake investigation. As forthe impact on spent fuel management, some equipment held on the inner wall surface of the
spent fuel pool dropped down on the fuel storage racks, however, the investigation
confirmed that there was no effect or damage to the spent fuel stored in the pool and thus
safety was ensured. As for the impact on radioactive waste management, drums that
contained radioactive wastes and were stored in the solid waste depository fell down on thefloor and lids of some drums came off, however, there was no release of radioactive material
to the outside of the depository and no safety problem was caused by this occurrence.
These occurrences were evaluated as “below scale” in the International Nuclear Event Scale(INES).
As for the impacts on other systems or equipment, the relevant organizations are analyzing
them to make use of lessens learned from the earthquake in order to ensure nuclear safety.
A4

Preparation of the report

A4.1

Structure of the report

This report describes the steps taken in Japan for implementing the obligations under the“Joint Convention on the Safety of Spent Fuel Management and on the Safety ofRadioactive Waste Management” in accordance with the provision of Article 32 of theConvention.
The report was prepared in accordance with “the Guidelines regarding the Form andStructure of National Reports”. The text of each Article of the Convention is indicated at the
top of the section.
This report is structured as described below for the purpose of comprehensive andsystematical explanation of the spent fuel management and radioactive waste management
activities in Japan. Section B describes the policy of the Government of Japan for facilitating
management of spent fuel and radioactive waste and the activities of the Licensees in linewith the policy. Section E describes the legal systems to facilitate management of spent fueland radioactive wastes as well as the legal systems for safety regulation and theorganizations responsible for safety regulation. The relevant organizations other than theregulatory bodies are also described in Section E. Section F describes, as in the previous
national report, general activities for ensuring safety, not to specific to spent fuelmanagement and radioactive waste management. Section G describes the safety regulationof spent fuel storage, as an example of the safety regulatory system for spent fuelmanagement. Section H describes safety regulation of “waste disposal” which mainly deals
with radioactive wastes, as an example of the radioactive waste management defined in theConvention.
The major items that made progress or was newly implemented during the period coveredby the report are outlined in Section A.
A4.2

Organizations involved in the preparation of the report

The report has been prepared by the NISA of METI. The major organizations involved in the
preparation of the report are as follows:

7

A

A

Introduction

Governmental organizations
The Atomic Energy Commission and the Nuclear Safety Commission of the Cabinet
OfficeAgency for Natural Resources and Energy and Nuclear and Industrial Safety Agencyof Ministry of Economy, Trade and Industry
Research and Development Bureau, Research Promotion Bureau and the Scienceand Technology Policy Bureau of the Ministry of Education, Culture, Sports Scienceand Technology
The Pharmaceutical and Food Safety Bureau and Health Policy Bureau of the Ministryof Health, Labor and Welfare
Ministry of Foreign Affairs
Business operators
The Federation of Electric Power Companies*
The Nuclear Waste Management Organization of Japan
Japan Atomic Energy Agency
In preparing the report, the NISA obtained advice from the NISS/ACNRE
In addition, cooperation was obtained from the following organizations in preparing thereport.
Japan Nuclear Energy Safety Organization
Radioactive Waste Management Funding and Research Center
Nuclear Safety Research Association
Japan Society of Newer Metals*:The Federation of Electric Power Companies consists of 10 electric power utilities, i.e.,
Hokkaido Electric Power Co. Inc., Tohoku Electric Power Co. Inc., Tokyo Electric Power Co.
Inc., Hokuriku Electric Power Co., Chubu Electric Power Co. Inc., Kansai Electric Power Co.
Inc., Chugoku Electric Power Co. Inc., Shikoku Electric Power Co. Inc., Kyushu ElectricPower Co. Inc., and Okinawa Electric Power Co. Inc. In preparing the report, theFederation of Electric Power Companies also provided information on the activities of theJapan Atomic Power Company and Japan Nuclear Fuel Limited.

8Policies and Practices

Section B

Policies and Practices

Article 32
1. In accordance with the provisions of Article 30, each Contracting Party shall submit a national
report to each review meeting of Contracting Parties. This report shall address the measures taken
to implement each of the obligations of the Convention. For each Contracting Party the report shallalso address its:(i) spent fuel management policy;(ii) spent fuel management practices;(iii) radioactive waste management policy;(iv) radioactive waste management practices;(v) criteria used to define and categorize radioactive waste.

Section B describes the national policy for promoting the spent fuel management andradioactive waste management in Japan and the operator’s actions based on that policy. The
policy and actions for the safety of spent fuel management and radioactive waste
management are described in “Section G Safety of Spent Fuel Management” and “Section H
Safety of Radioactive Waste Management”, respectively.
In Japan, the Atomic Energy Commission established “the Framework for Nuclear Energy
Policy” which provides a basic principle of Japanese nuclear energy policy. On the basis of
the basic principle provided in “the Framework for Nuclear Energy Policy”, the Agency for
Natural Resources and Energy of the Ministry of Economy, Trade and Industry establishedconcrete policies for the utilization of nuclear energy as energy source, and the Ministry of
Education, Culture, Sports, Science and Technology established concrete policies for theutilization of nuclear energy and radioisotopes for science and technology and Ministry ofForeign Affairs formulates and establishes foreign policy with regard to international
cooperation in the field of nuclear energy area.
B1

Spent Fuel Management Policy

In the Framework for Nuclear Energy Policy, the Atomic Energy Commission evaluated the“Basic Concepts of the Nuclear Fuel Cycle from the following ten viewpoints: safety,
technical feasibility, economic viability, energy security, environmental protection, nuclear
non-proliferation, international trends, issues resulting from policy changes, social
acceptability, and adaptability to emerging circumstances (adaptability to future
uncertainty)..” and the Framework concluded “When promoting nuclear power generation in
Japan, we should comprehensively consider such matters as ensuring economic viability,
working to create a sound material-cycle society, ensuring energy security, and ensuring thecapability to respond to future uncertainty.” “We have reached the conclusion that our basic
policy is, aiming at using nuclear fuel resources as effective as reasonably achievable, toreprocess spent fuel and to effectively use the recovered plutonium and uranium, while
ensuring safety, nuclear non-proliferation, environmental protection, and paying due
attention to economic viability. Spent fuel will be reprocessed, within the available
reprocessing capacity, for the time being, and the surplus volume exceeding the capacity will
be stored intermediately.”
In accordance with the basic principle provided by the Framework for Nuclear Energy Policy,
the “Act for Deposit and Administration of Reserve Funds for Reprocessing of Spent Fuelfrom Nuclear Power Generation” (see Section E) was established that requires the operators
to deposit the funds for spent fuel reprocessing in a fund administration corporation. The
objective of “the Act” is to ensure the proper implementation of spent fuel reprocessing,disposal of radioactive wastes generated from reprocessing, and disassembling of
reprocessing facilities. The amount of reserve by the end of March 2007 is about 1,390
billion yen by 10 electric utilities. As a part of such steps, The Minister of Economy, Tradeand Industry designated Radioactive Waste Management Funding and Research Center”
as a non-profit “fund administration corporation” (October, 2005) that is supervised by the
9

B

B

Policies and Practices

Minister through supervisory orders and on-the-spot inspection.
B2

Spent Fuel Management Practices

Spent fuel generated in power reactors are sent to reprocessing facilities after a certain
period of on-site cooling and storage. The spent fuel has been reprocessed overseas inaccordance with contracts with British and French companies, with the exception of a portion
reprocessed by the Tokai Reprocessing Plant of the JAEA Tokai Research and Development
Center (Hereinafter it is called Tokai Reprocessing Plant of the JAEA). In the meantime,
considering national demand for reprocessing, JNFL began constructing the Spent Fuel
Reprocessing Plant in Rokkasho village, based on operational experience accumulated at
the Tokai Reprocessing Plant and on technologies and experience from advanced countries.
The plant, as of March 2008, was undergoing active test using spent fuel, and would start
operation within 2008. Storage of spent fuel at storage facility in the plant started since 1999,
and export of spent fuel to foreign reprocessing plants ended in July 2001.
The Law for Regulation of Nuclear Source Material, Nuclear Fuel Material and Nuclear
Reactors (Reactor Regulation Law) was amended in 1999 to incorporate provisions on
interim spent fuel storage. Tokyo Electric Power Company and Japan Atomic Power
Company jointly established “Recycle Fuel Storage Company” in order to prepare forcommercial operation of the first interim fuel storage facilities in Japan by 2010. In March
2007, the company applied for the license for the construction and operation of Recycle Fuel
Storage Center at Mutsu city, Aomori Prefecture (see Fig.L5-1), and the license application
is now under the safety examination.
The spent fuel from research reactor facilities has been and is to be returned to the USA, UK
or France, or is to be reprocessed or stored in Japan.
B3

Radioactive waste management Policy

Radioactive wastes may need extraordinarily long time for their effects to attenuate to an
insignificant level and disposal of them has to be governed by four principles; “principle ofgenerators’ liability”, “principle of minimization of radioactive wastes”, “principle ofreasonable treatment and disposal” and “principle of implementation based on mutual
understanding with the public”. On the basis of such recognition, the Atomic Energy
Commission deems it important to appropriately categorize the wastes so that they may besafely treated and disposed of according to the categorization. From such viewpoint, theCommission categorized the wastes into “radioactive wastes subject to geological disposal”
and “radioactive wastes subject to managed disposal” and indicated basic strategies foreach category. In accordance with such strategies, the government of Japan developed thepolicy for promoting radioactive waste disposal as described below.
1.
Radioactive waste to be geologically disposed of(1) High level radioactive waste
In Japan, a site for geological disposal of high level radioactive waste is selected in threesteps of the selection of “preliminary investigation areas”, “detailed investigation areas”
and “construction site of final disposal facility”, in accordance with the “SpecificRadioactive Waste Final Disposal Act (Final Disposal Act)” (see Section E). Pursuant to
the Act, the Cabinet approved the “Basic Policy for Final Disposal” and the “Final
Disposal Plan” and the Nuclear Waste Management Organization of Japan (NUMO) wasestablished as an organization to implement final disposal. In addition, utilities are now
depositing the reserve funds for final disposal. The amount of reserve by the end of
March 2007 is about 500 billion yen. Open solicitation of candidate areas for literaturesearch on possible installation of final disposal facility was conducted by the NUMO andsome local authorities answered it, but selection has not yet been made.
Under such situation, the Atomic Energy Commission stated that the current activities
should be enhanced to obtain understanding and cooperation of the electricity consumers
10Policies and Practices

who are benefitted with nuclear power generation as well as the local residents of various
sectors of local communities, including local authorities, across the country.
In response to that, the Radioactive Waste Subcommittee under the Nuclear Energy
Subcommittee of the Advisory Committee for Natural Resources and Energy prepared aninterim report on the enhancement of the activities to promote the final disposal. The
report requires that the government should, by itself, ask local governments to conduct
literature search, while maintaining the present procedure of open solicitation ofcandidate areas. The report also asks the government, NUMO and electric utilities toenhance national and regional public relations, to propose regional development plans, toenhance research and development and international cooperation for promoting the
public understanding. Specifically, publicity works are conducted in each prefecture in
Japan and workshops are organized associate with non political organizations in theoutskirts of the site. It is proposed to build a “geological disposal concept demonstration
facility” with ground and underground facilities, that facilitate public understanding ofgeological disposal concept and clarifies its engineering feasibility as well as long-term
behaviors. This demonstration facility will be used for the demonstration of theemplacement of wastes, installation techniques, monitoring technology, and retrieval
technology.
The “Coordination Council for Basic Research and Development of Geological Disposal”
organized by the Agency for Natural Resources and Energy discussed and made up amaster plan for the basic research on geological disposal (December, 2006), to facilitate
effective and efficient implementation of the total research and development program by
the government, Japan Atomic Energy Agency and other research organization. As forinternational cooperation, Japan has been studying, and using as reference, the cases inforeign countries where the selection of disposal site is in progress, and will continue toexchange views with the countries that have final disposal programs and also to promote
multinational cooperation using cooperative frameworks of the IAEA, OECD/NEA, GNEP,
etc.
(2)

Long-lived low-heat generating radioactive wastes (TRU wastes) to be geologicallydisposed of
As for TRU wastes, the Atomic Energy Commission stated that the interaction in the caseof geological disposal of TRU wastes by the side of high level radioactive wastes(single-site disposal: see Fig. L6-4-2) should be evaluated and necessary implementation
steps, including function of the implementing body and government involvement, should
be studied on the basis of the evaluation results.
In response to that, the Agency for Natural Resources and Energy amended the “Final
Disposal Act”. According to this amendment, TRU wastes from reprocessing that need tobe geologically disposed of and high level radioactive wastes that are returned fromoverseas reprocessing plants in exchange for TRU wastes were added to the wastes tobe finally disposed of by the Nuclear Waste Management Organization of Japan, andgenerators of such radioactive wastes were legally requested to provide the cost needed
for final disposal.

2.
Radioactive wastes disposed with institutional control
In Japan, disposal with institutional control is categorized in the following three type;
namely “near surface trench disposal”, “near surface pit disposal” and “intermediate depth
disposal.”
The AEC, in “the Framework for Nuclear Energy Policy” stated that” It is often effective andefficient to treat and dispose of radioactive waste in an integrated fashion according to theproperties of the waste material regardless of the generators or waste sources, andtherefore, the Government should coordinate various systems accordingly.”
Low level radioactive wastes generated in nuclear power plants that are subject to nearsurface trench disposal and near surface pit disposal are already being disposed of withsuch methods.
11

B

B

Policies and Practices

The Atomic Energy Commission, considering the results of operator’s investigation andtests, indicated that necessary systems for implementing intermediate depth disposal
including safety regulation system should be established without delay. In response to that,
the Radioactive Waste Safety Subcommittee under the Nuclear and Industrial Safety
Subcommittee of the Advisory Committee for Natural Resources and Energy prepared aninterim report on safety regulation of intermediate depth disposal of low level radioactive
waste. This report shows the outline of safety regulation and further technical study items.
Considering the results of the study, the Nuclear and Industrial Safety Agency developed
an Ordinance of the Ministry of Economy, Trade and Industry based on the Reactor
Regulation Law.
Concerning the disposal of waste generated from the research, medical and industrial
facilities for using radio-isotopes and radiation generating apparatus (hereinafter referred
to as “Waste from Research Facilities, etc.”), the report of the discussions in the committee
on R&D in the Field of Atomic Energy/Sub-working Committee on Research and
Evaluation/the Council on Science, Technology and Academism was published in Sep.
2006. Based on the report, MEXT amended the Law for the Independent Administrative
Agency, Japan Atomic Energy Agency, in May 2008, and the JAEA was designated as theimplementation entity of the disposal of the Waste from Research Facilities, etc.
In the Law Concerning Prevention from Radiation Hazards due to Radioisotopes, etc.
(hereinafter referred to as “the Radiation Hazards Prevention Law”), the rules on thedisposal has been established, and the near-surface disposal of the waste from theutilization facilities of radio-isotopes are planned3.
Ban on sea dumping of radioactive waste
In compliance with the Convention on the Prevention of Marine Pollution by Dumping ofWastes and Other Matter (1972) and its amendment to Annex I in 1993, the AEC decided
on November 2, 1993 to eliminate the option of sea dumping of radioactive waste. Basedon this decision the Reactor Regulation Law was amended in May, 2005.
B4

Radioactive Waste Management Practices

Operators, recognizing their responsibility concerning radioactive waste management, shallmanage radioactive waste generated at their facilities in compliance with the Reactor
Regulation Law, the Radiation Hazards Prevention Law and relevant regulations.
B4.1

High-Level Radioactive Waste Management Practices

In Japan, spent fuel has been reprocessed by the Rokkasho Reprocessing Plant of JNFL,
Tokai Reprocessing Plant of the JAEA and reprocessing plants in France and the United
Kingdom. JNFL is conducting active test of the vitrification facility of HLW, attached to its
reprocessing plant, at Rokkasho Village in Aomori prefecture. This facility is to be completed
within 2008 and 57 vitrified waste canisters would be generated during the test. High-levelliquid waste generated at the Tokai Reprocessing Plant of the JAEA is stored in tanks within
the facility. The vitrification facility started operation in January 1995. As of March 2008,
about 400 cubic meters of liquid waste and 247 vitrified waste canisters are in storage.
Utilities in Japan have concluded reprocessing contracts with British and French companies
for a total of 5,600 tU of spent fuel from light water reactors and 1,500 tU of spent fuel from agas cooled reactor. In accordance with these contracts, vitrified waste canisters are returnedto the utilities and are stored by JNFL. By March 2008, 1310 vitrified canisters had beenreturned from France, and the canisters from United Kingdom in total of 2,200 canisters
together with those from France will be returned in the next ten-odd years.
Vitrified HLW will be disposed of by geological disposal. Based on the Final Disposal Act, theNuclear Waste Management Organization of Japan (NUMO), the responsible implementing
organization, will start disposal in mid 2030s after three steps procedure of site selection,that is, selection of the preliminary investigation areas, detailed investigation areas and final
12

Policies and Practices

disposal facility. NUMO, in 2002, started the first step by open solicitation of candidate ofsites for the preliminary investigation areas, and published the “application format”, “outlineof the disposal facility”, “investigation items” and “coexistence of disposal facility and local
community”. In case of receiving proposal of candidate areas, NUMO will assess validity of
the candidates by conducting survey of the site with existing literature on volcanic activities,
active faults and other geological conditions. NUMO will decide the preliminary investigation
areas based on the assessment.
B4.2

Low-Level Radioactive Waste Management Practices

LLW is classified into waste from power reactors, TRU waste, uranium waste and radioactive
waste from medical, industrial and research facilities. The waste management strategy foreach of these categories is as follows, while gaseous and liquid radioactive wastes aredischarged under monitoring, after attenuation of radioactivity, filtering, adsorption and/or
distillation. (See H.6.5)
1.
Waste from Power Reactors
As of March 2008, fifty-six nuclear power reactors (of which fifty-five are commercial
nuclear power reactors) were in operation*. Liquid waste concentrate is solidified withcement in drums after evaporation. Paper, clothing and other combustibles are placed indrums after incineration. Plastics, metals and other non-combustibles are placed in drums
after compaction. These drums are stored in the on-site storage facilities. Replaced steam
generators and other large-volume solid wastes are placed in depository. Replaced control
rods and channel boxes, etc. are stored in spent fuel pools and spent ion exchange resins
are stored in tanks. Near-surface disposal of drums (solidified liquid waste and compacted
and solidified non-combustible wastes) started in 1992 at the disposal facility of JNFL at
Rokkasho Village in Aomori Prefecture.
The Clearance system is in operation since December 2005 after the amendment of theReactor Regulation Law and other related cabinet and ministerial ordinances. In June 2006,
the Japan Atomic Power Co. filed an application for “the methods for measurement andassessment of radioactive concentration of waste generated from dismantling of the Tokai
Power Station” in accordance with the amended Reactor Regulation Law and obtained
approval of the government in September 2006. Clearance measurement was conductedon the waste in the Tokai Power Station and application for confirmation by the regulatory
body was filed in April 2007. In June, the certified materials cleared from regulation werecarried out from the Tokai Power Station for the first time after getting the confirmation
certification. For the time being, the cleared material is recycled at the site related to the
nuclear installations, namely they will be used as shielding material, bench and so on.
The clearance system would be applied to the wastes generated from the operation of lightwater reactors and the dismantling of “ATR-Fugen.”
JNFL, as a part of study on intermediate depth disposal of waste from power reactors,
conducted research on geological features, underground water and ground from 2002 to2006 at the site of uranium enrichment and waste disposal facilities. (See Fig.L6-3-3 andFig.L6-3-4)*: A period from the first criticality to the time before decommissioning

2.
TRU Waste
At present, in Japan, the reprocessing of spent fuel is in progress at the Tokai
Reprocessing Plant of the JAEA.
Liquid TRU waste generated at the Tokai Reprocessing Plant of JAEA is stored in tanks
and concentrated by evaporation, and a portion of it is solidified in drums. Segmented fuelcladding, used filters and sampling bottles are put in containers and other solid waste is put
in drums. These drums and the containers are being held in storage at on-site
depositories.
13

B

B

Policies and Practices

The reprocessing plant of the JNFL at Rokkasho Village, Aomori prefecture is at the stageof the integrated operational test (active test) using actual spent fuel in preparation for thecommercial operation in 2008, and full-scale operation is expected in the near future.
TRU waste generated at spent fuel reprocessing plant in France and UK will be returned toJapan after 2013.
Electric utilities are planning to build a storage facility to temporarily store the returned
wastesTRU waste generated from the fabrication of MOX fuel in Japan Atomic Energy Agency
Tokai research and development center Nuclear Fuel Cycle Engineering Laboratories isheld in storage at on-site depositories as well as TRU waste from reprocessing.
Research and development programs on TRU waste disposal have been promoted by
JAEA and utilities.
3.
Uranium Waste
Liquid waste containing uranium generated from enrichment or fuel manufacturing facilities
of JAEA or other private facilities are stored in tanks. Solid uranium waste and ash resulting
from incineration are put in drums. They are held in storage at on-site depositories.
4.
Waste from Research Facilities, etc.
Radioactive waste generated from research, medical and industrial facilities using
radioisotopes and radiation generating apparatus are collected by the license holders of
the waste management business, who store it at their own depositories after compaction or
incineration.
Radioactive waste generated in the facilities of research reactor and fuel material use of
the Japan Atomic Energy Agency (JAEA) and universities are stored at their own
depositories after compaction or incineration.
B5

Criteria used to define and categorize radioactive waste

In Japan, radioactive waste is categorized as shown in Table B5-1.
In May 2007, the Nuclear Safety Commission (NSC) issued a document which provides forupper bounds of concentration of radioactive elements in waste packages from powerreactors and in TRU waste packages. (*1) The upper bounds of concentration of radioactive
elements are so decided, that the public exposure due to waste packages is well within thereference value, and that the upper bounds are in conformity with the latest knowledge in theinternational community. Based on these concepts, disposal of radioactive waste iscategorized into Category 1 Waste Disposal (geological disposal) and Category 2 Waste
Disposal (Intermediate Waste Disposal, Near Surface Disposal with Artificial Barrier andNear Surface Disposal without Artificial Barrier).(see Fig.L6-1)
Concerning the waste that does not need to be dealt with as radioactive waste, the NSC hasstudied the clearance level of radionuclides concentrations and its calculation method,referring to the ICRP document (Pub. 46, 1985) and IAEA-TECDOC-855(*2), respectively.
The results are reported as “Clearance Level for Major Nuclear Facilities” (March, 1999),“Clearance Level for Heavy Water Reactors, Fast Neutron Reactors, etc.” (July, 2001), and“Clearance Level for Nuclear Fuel Use Facilities (Facilities dealing with irradiated fuels andmaterials” (April, 2003).
Since IAEA issued the Safety Guide “Application of the Concepts of Exclusion, Exemption
and Clearance”, Safety Standards Series No. RS-G-1.7 (2004), the NSC has made are-evaluation of the above mentioned three reports on the clearance level. The results were
issued as a report “Radionuclides Concentrations for Materials not Requiring Treatment asRadioactive Wastes, Generated from Dismantling etc. of Reactor Facilities and Nuclear Fuel
Use Facilities” in December, 2004. The NSC concluded that as the re-evaluated values andthe values of exemption level provided in the IAEA safety guide are comparable, it is suitable
to use the values in the IAEA safety guide. The Radioactive Wastes Safety Subcommittee of
the Nuclear and Industrial Safety Subcommittee also studied this matter and concluded that14

Policies and Practices

it is essentially suitable to use the values of the IAEA safety guide (“Establishment of the
Clearance System for Nuclear Facilities (December, 2004)”).
Through this process, the rule for the confirmation of radioactivity concentrations wasformulated to provide clearance levels of 33 nuclides of wastes from reactor facilities.
The NSC showed the basic concept to distinguish “solid wastes that are not radioactive
wastes” from radioactive wastes in the report “Reference Radionuclides Concentration
Values for Safety Regulations of Land Disposal of Low-level Radioactive Solid Waste (The
2nd interim report)” (June, 1992). The report clarified that “solid wastes that are notradioactive wastes” are those materials; a) materials that is clearly identified as notcontaminated or not activated, b) material where significantly contaminated portion is
identified and is deleted and contamination of the remaining portion is negligible, c)materials where significantly activated operation is evaluated and is deleted and activation of
the remaining portion is negligible.
The clearance levels for uranium and other nuclides for the exemption of regulatory control
are under discussion in the NSC.
*1: “Reference Radionuclide Concentration Values for Land Disposal of Low-level Radioactive
Solid Waste (interim report)”, NSC, December, 1986, “Reference Radionuclide Concentration
Values for Land Disposal of Low-level Radioactive Solid Waste (2nd report)”, NSC, June, 1992,“Reference Radionuclide Concentration Values for Land Disposal of Low-level Radioactive
Solid Waste (3rd report)”, NSC, September, 2000, and “Upper Bound of Radioactive
Concentration for Burial of Low-level Radioactive Solid Waste”, NSC, May, 2007
*2: “Clearance levels for radionuclides in solid materials, Application of exemption principles,Interim report for comment” (January, 1996)

15

B

B

Policies and Practices

Table B.5-1

Classification of Radioactive Wastes

Classification

ExampleOrigin of Waste
High radio-activity liquid waste or
vitrified waste canister that contains

Vitrified Waste

High-Level Radioactive Waste

Canisterfission products

like Sr-90 andCs-137 and Actinides elements like
Am-241 and Np-237 separated fromspent fuel during the reprocessing

Waste
from
Power
Reactors

Waste of Core

Control Rods

Structures etc.

Core Internals

Low Level
Radioactive
Waste
Very Low-Level
Radioactive
Waste

LowLevelLong-lived Low HeatRadio-

Radioactive Waste

active( TRU Waste)

Waste

Liquid Waste
Filters
Used Equipment
Expendables
Concrete
MetalsParts of Fuel
Elements
Liquid waste
Filters
Expendables

Uranium Waste

Waste Generated at Power Reactors

Low

Level

Radioactive

Waste

Generated from the Operation andDismantlingofReprocessing

Facilities and MOX Fuel Fabrication
Facilities
Radioactive Waste Generated from

SludgeEnrichment

Used Equipment

Facilities

and

Fuel

Fabrication

Liquid waste
MetalsConcrete

Radioactive Waste Generated from the

Waste from Research

Plastics

facilities of Research, Medical andFacilities, etc.

Filters

Industrial

Disposable

Facilities

for

using

radioisotopes, etc.

SyringeThose waste generated from theMaterial that need not be treated asradioactive waste(Waste below the Clearance Level)

operation and dismantling of nuclear
Concrete

installations

Metalsconcentration of the waste is so low

and

the

radioactivity

that no measures to avoid radiation
hazards is necessary16Scope of Application

Section C

Scope of Application

Article 3
1. This Convention shall apply to the safety of spent fuel management when the spent fuel resultsfrom the operation of civilian nuclear reactors. Spent fuel held at reprocessing facilities as part of a
reprocessing activity is not covered in the scope of this Convention unless the Contracting Party
declares reprocessing to be part of spent fuel management.
2. This Convention shall also apply to the safety of radioactive waste management when theradioactive waste results from civilian applications. However, this Convention shall not apply towaste that contains only naturally occurring radioactive materials and that does not originate fromthe nuclear fuel cycle, unless it constitutes a disused sealed source or it is declared as radioactive
waste for the purposes of this Convention by the Contracting Party.
3. This Convention shall not apply to the safety of management of spent fuel or radioactive waste
within military or defence programmes, unless declared as spent fuel or radioactive waste for the
purposes of this Convention by the Contracting Party. However, this Convention shall apply to thesafety of management of spent fuel and radioactive waste from military or defence programmes if
and when such materials are transferred permanently to and managed within exclusively civilian
programmes.
4. This Convention shall also apply to discharges as provided for in Articles 4, 7, 11, 14, 24 and 26.

The government of Japan declared, pursuant to Article 3, Paragraph 1, of the Convention, that
reprocessing is part of spent fuel management, acceded to the Convention. Therefore Japan
includes the spent fuel stored in reprocessing facilities in these scope of the Convention.
The government of Japan did not make declarations provided for in Article 3, Paragraphs 2,
and 3, of the Convention.

17

C

D

Lists and Inventories

Section D

Inventories and Lists

Article 32
2 This report shall also include:(i) a list of the spent fuel management facilities subject to this Convention, their location, main
purpose and essential features;(ii) an inventory of spent fuel that is subject to this Convention and that is being held in storage and ofthat which has been disposed of. This inventory shall contain a description of the material and, if
available, give information on its mass and its total activity;(iii) a list of the radioactive waste management facilities subject to this Convention, their location, main
purpose and essential features;(iv) an inventory of radioactive waste that is subject to this Convention that:(a) is being held in storage at radioactive waste management and nuclear fuel cycle facilities;(b) has been disposed of; or(c) has resulted from past practices.
this inventory shall contain a description of the material and other appropriate information
available, such as volume or mass, activity and specific radionuclides;(v) a list of nuclear facilities in the process of being decommissioned and the status ofdecommissioning activities at those facilities.

D1

List of spent fuel management facilities

Spent fuel from power reactor facilities is being held in storage at spent fuel storage facilities
within power reactor facilities or the Tokai Reprocessing Plant of Tokai Research andDevelopment Center, Nuclear Fuel Cycle Engineering Laboratories, JAEA and Rokkasho
Reprocessing Plant of JNFL. Spent fuel from research reactor facilities is being held instorage at spent fuel storage facilities of the research reactor facilities. The locations, main
purposes and essential features of these spent fuel management facilities are listed inTables D1-1 and D1-2.

Table

D1-1 List of Spent Fuel Management Facilities (Related to Power Generation)

Nuclear facilities where spent fuelmanagement facilities are located
The Japan Atomic Power Co.
Tokai-No.2 Power Station
The Japan Atomic Power Co.
Tsuruga Power Station
Hokkaido Electric Power Co., Inc.
Tomari Power Station
Tohoku Electric Power Co., Inc.
Onagawa Nuclear Power Station
Tohoku Electric Power Co., Inc.
Higashidori Nuclear Power Station
Tokyo Electric Power Co., Inc.
Fukushima Daiichi Nuclear Power Station
Tokyo Electric Power Co., Inc.
Fukushima Daini Nuclear Power Station
Tokyo Electric Power Co., Inc.
Kashiwazaki Kariwa Nuclear Power Station
Chubu Electric Power Co., Inc.
Hamaoka Nuclear Power Station
Hokuriku Electric Power Co., Inc.
Shika Nuclear Power Station
The Kansai Electric Power Co., Inc.
Mihama Power Station
The Kansai Electric Power Co., Inc.
Takahama Power Station

Location

purposefeatures

IbarakiStorage

Wet storage(partly stored in dry casks)

Fukui

Storage

Wet storage

Hokkaido

Storage

Wet storage

MiyagiStorage

Wet storage

AomoriStorage

Wet storage

Fukushima

Storage

Wet storage(partly stored in dry casks)

Fukushima

Storage

Wet storage

Niigata

Storage

Wet storage

Shizuoka

Storage

Wet storage

Ishikawa

Storage

Wet storage

Fukui

Storage

Wet storage

Fukui

Storage

Wet storage

18

Lists and Inventories

The Kansai Electric Power Co., Inc.
Ohi Power Station
The Chugoku Electric Power Co., Inc.
Shimane Nuclear Power Station
Shikoku Electric Power Co., Inc.
Ikata Power Station
Kyushu Electric Power Co., Inc.
Genkai Nuclear Power Station
Kyushu Electric Power Co., Inc.
Sendai Nuclear Power Station
Japan Atomic Energy Research Agency
Fugen Decommissioning Engineering Center（Fugen）
Japan Atomic Energy Research Agency
Tokai Research and Development Center
Nuclear Fuel Cycle Engineering Laboratories
Tokai Reprocessing Plant
Japan Nuclear Fuel Limited
Rokkasho Reprocessing Plant
Japan Atomic Energy Research Agency
Fast Breeder Reactor Research and1Development Center (Monju* )*1: Pre-service inspection stage

Table

Fukui

Storage

Wet storage

ShimaneStorage

Wet storage

Ehime

Storage

Wet storage

Saga

Storage

Wet storage

Kagoshima

Storage

Wet storage

Fukui

Storage

Wet storage

IbarakiStorage

Wet storage

AomoriStorage

Wet storage

Fukui

Storage

Wet storage(As of the end of March 2008)

D1-2 List of Spent Fuel Management Facilities (Research Reactors)

Nuclear facilities where spent fuel management facilities arelocatedJapan Atomic Energy Research Agency Tokai Research andDevelopment Center Nuclear Science Research InstituteJapan Atomic Energy Research Agency Oarai Research andDevelopment Center
Kyoto University Research Reactor Institute

D2

Location

purposefeatures

IbarakiStorageDry storage

IbarakiStorage

Wet storage

Osaka

Storage
Wet storage(As of the end of March 2008)

Inventories of spent fuelSpent fuel stored in above-mentioned spent fuel management facilities are shown in Table
D2-1.
Table

D2-1 Spent Fuel Inventory

Nuclear facilities Categories
Commercial Nuclear Power Plants
Power Reactors at the stage of Research andDevelopment
Reprocessing Plants
Research Reactors

D3

Types of Fuel Elements
Inventory
Uranium Oxide Fuel Elements
12,190 ton
Uranium Oxide Fuel Elements and
70 tonMixed Oxide Fuel Elements
Uranium Oxide Fuel Elements and2,576 ton
Mixed Oxide Fuel Elements
Uranium Oxide Fuel Elements and
34 tonMixed Oxide Fuel Elements(As of the end of March 2008)

List of radioactive waste management facilities

Radioactive waste management facilities within power reactor facilities include thefollowings: waste treatment facilities where waste generated at the reactor facility is treated;
solid waste depositories where drums (homogeneous solidification, fill-up solidification,
miscellaneous solid and others), etc. filled with treated waste are being held in storage;
depositories where the replaced steam generators and other large solid wastes are being
19

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held in storage; spent fuel pools etc. where the disused control rods, the disused channel
boxes, etc. are being held in storage; and tanks where the spent ion exchange resin is being
held in storage.
Radioactive waste management facilities within enrichment and fuel manufacturing plants
include the followings; waste treatment equipments that treats waste generated at theplants; and solid waste depositories where drums filled with treated waste are held instorage.
Radioactive waste management facilities within spent fuel reprocessing plants include thefollowings; waste treatment equipments that treats waste generated at the plant; waste
depository where vitrified waste and high level liquid waste are being held in storage; andwaste depository where low level liquid waste and low level solid waste are being held instorage.
Radioactive waste management facilities licensed under the waste related activities include
the followings; radioactive waste dispose facilities where radioactive waste is disposed of,Waste Storage facilities being held in storage before disposal, waste treatment facilities
where radioactive waste is treated.
Radioactive waste management facilities within research reactors and major fuel material
use facilities include the followings; waste treatment equipments that treats low level
radioactive waste generated at those facilities; and solid waste depositories where drums
filled with treated waste are being held in storage.
Radioisotope waste management facilities licensed with waste management business under
the Law concerning Prevention from Radiation Hazards due to Radioisotopes etc.
(Radiation Hazards Prevention Law) include storage facilities, where drums, etc. filled withprocessed waste generated at radioisotopes use facilities, etc, are being held in storage.
Radioactive waste management facilities licensed on the basis of the Medical Care Laws etc.
include the storage facilities, etc., where drums, etc. filled with processed radioactive
medical waste generated at medical care facilities, etc, being are being held in storage.
The locations, main purposes and essential features of these radioactive waste
management facilities are listed in Tables D3-1 and D3-2.
Table

D3-1 List of Radioactive Waste Management Facilities (Power Reactors)

Nuclear facilities locatedradioactive waste
management facilities

Location

The Japan Atomic Power Co.
Tokai Power Station

Ibaraki

The Japan Atomic Power Co.
Tokai-No.2 Power Station

Ibaraki

The Japan Atomic Power Co.
Tsuruga Power Station

Fukui

Hokkaido Electric Power Co.,Inc.
Tomari Power Station
Tohoku Electric Power Co.,Inc.
Onagawa Nuclear Power
StationTohoku Electric Power Co.,Inc.
Higashidori Nuclear Power
StationTokyo Electric Power Co., Inc.
Fukushima Daiichi Nuclear
Power Station
Tokyo Electric Power Co., Inc.
Fukushima Daini Nuclear
Power Station

PurposeFeatures

Processing andstorage of wastefrom the power plant
Processing andstorage of wastefrom the power plant
Processing andstorage of wastefrom the power plant
Processing andstorage of wastefrom the power plant

Stored at a storage facility after
volume reduction bycompaction, incineration, etc.
Stored at a storage facility after
volume reduction bycompaction, incineration, etc.
Stored at a storage facility after
volume reduction bycompaction, incineration, etc.
Stored at a storage facility after
volume reduction bycompaction, incineration, etc.

Miyagi

Processing andstorage of wastefrom the power plant

Stored at a storage facility after
volume reduction bycompaction, incineration, etc.

Aomori

Processing andstorage of wastefrom the power plant

Stored at a storage facility after
volume reduction bycompaction, incineration, etc.

Processing andstorage of wastefrom the power plant
Processing andstorage of wastefrom the power plant

Stored at a storage facility after
volume reduction bycompaction, incineration, etc.
Stored at a storage facility after
volume reduction bycompaction, incineration, etc.

Hokkaido

Fukushima
Fukushima

20

Lists and Inventories
Tokyo Electric Power Co., Inc.
Kashiwazaki Kariwa Nuclear
Niigata
Power Station
Chubu Electric Power Co.,Inc.
Shizuoka
Hamaoka Nuclear Power
StationHokuriku Electric Power Co.,
Inc.
Ishikawa
Shika Nuclear Power Station
The Kansai Electric Power
Co., Inc.
Fukui
Mihama Power Station
The Kansai Electric Power
Co., Inc.
Fukui
Takahama Power Station
The Kansai Electric Power
Co., Inc.
Fukui
Ohi Power Station
The Chugoku Electric Power
Co., Inc.
ShimaneShimane Nuclear Power
StationShikoku Electric Power Co.,
Inc.
Ehime
Ikata Power Station
Kyushu Electric Power Co.,
Inc.
Saga
Genkai Nuclear Power Station
Kyushu Electric Power Co.,Inc.
Kagoshima
Sendai Nuclear Power Station
Japan Atomic Energy
Research Agency, Fugen
Fukui
Decommissioning
Engineering Center(Fugen)Japan Atomic Energy
Research Agency
Fukui
Fast Breeder Reactor
Research and Development
Center (Monju)

Processing andstorage of wastefrom the power plant

Stored at a storage facility after
volume reduction bycompaction, incineration, etc.

Processing andstorage of wastefrom the power plant

Stored at a storage facility after
volume reduction bycompaction, incineration, etc.

Processing andstorage of wastefrom the power plant
Processing andstorage of wastefrom the power plant
Processing andstorage of wastefrom the power plant
Processing andstorage of wastefrom the power plant

Stored at a storage facility after
volume reduction bycompaction, incineration, etc.
Stored at a storage facility after
volume reduction bycompaction, incineration, etc.
Stored at a storage facility after
volume reduction bycompaction, incineration, etc.
Stored at a storage facility after
volume reduction bycompaction, incineration, etc.

Processing andstorage of wastefrom the power plant

Stored at a storage facility after
volume reduction bycompaction, incineration, etc.

Processing andstorage of wastefrom the power plant
Processing andstorage of wastefrom the power plant
Processing andstorage of wastefrom the power plant

Stored at a storage facility after
volume reduction bycompaction, incineration, etc.
Stored at a storage facility after
volume reduction bycompaction, incineration, etc.
Stored at a storage facility after
volume reduction bycompaction, incineration, etc.

Processing andstorage of wastefrom the power plant

Stored at a storage facility after
volume reduction bycompaction, incineration, etc.

Processing andstorage of wastefrom the power plant

Stored at a storage facility after
volume reduction bycompaction, etc.
(As of the end of March 2008)

Table D3-2 List of Radioactive Waste Management Facilities (Other Than Power Reactors)
Nuclear facilities where radioactive waste
management facilities are locatedLocation

PurposeGlobal Nuclear FuelJapan Co., Ltd.

Fuel
facility

fabrication

Kanagawa

Treating and storage of
uranium waste

Mitsubishi Nuclear
Fuel Co., Ltd.

Fuel
facility

fabrication

IbarakiTreating and storage of
uranium waste

Fuelfacility

fabrication

Nuclear
Fuel
Industries, Ltd. Tokai
Works

Nuclear
Fuel
Industries,
Ltd.
Kumatori Works

Treating and storage of
uranium waste
Ibaraki

Fuel material use
facility

Treating and storage of
waste
from
fuel
material use facility

Fuel
facility

Treating and storage of
uranium waste

fabrication
Osaka

Fuel material use
facility

Storage of waste fromfuel material use facility

21

FeaturesStored at a storage facility,
etc. after volume reduction
by compaction, etc.
Stored at a storage facility,
etc. after volume reduction
by compaction, etc.
Stored at a storage facility,
etc. after volume reduction
by compaction, etc.
Stored at a storage facility,
etc. after volume reduction
by compaction, etc.
Stored at a storage facility,
etc. after volume reduction
by compaction, etc.
Stored at a storage facility,
etc. after volume reduction
by compaction, etc.

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Lists and Inventories
Japan
AtomicEnergyResearch
AgencyNingyo-toge
Environmental
Engineering CenterJapan
AtomicEnergyResearch
AgencyTokai Research andDevelopment
CenterNuclearScienceResearch InstituteJapan
AtomicEnergyResearch
AgencyTokai Research andDevelopment
Center Nuclear Fuel
Cycle Engineering
Laboratories

Okayama
Fuel material use
facility
Waste
disposalfacility
Research reactor
facility;
Fuelmaterial use facility;
Radioisotope
WasteManagement1
facility*

Treating and storage of
waste
from
fuel
material use facility
Disposal of low level
radioactive waste

Stored at a storage facility,
etc. after volume reduction
by compaction, etc.
Stored at a storage facility,
etc. after volume reduction
by compaction, etc.
Trench disposal of concrete
waste

Treating and storage ofradioactive waste frommedical, industrial andresearch facilities

Stored at a storage facility,
etc. after volume reduction
by compaction, incineration,
etc.

Treating and storage of
uranium waste

Enrichment facility

IbarakiTreating and storage of
HLW
and
Trans
uranium waste

Reprocessing
facility
Ibaraki

HLW
storedafter
vitrification,
waste
containing Trans uranic
nuclides stored after volume
reduction by incineration etc
Stored at a storage facility,
etc. after volume reduction
by compaction, incineration,
etc.

Fuel material use
facility

Treating and storage of
waste
from
fuel
material use facility

Japan
AtomicEnergyResearch
AgencyOarai Research andDevelopment
CenterWaste
management
facility;
Research
reactor facility ,Fuel material use
facility;
Radioisotope
WasteManagement1
facility*

IbarakiTreating and storage ofradioactive waste fromresearch
reactorfacility , fuel materialusefacility;
andradioisotopeusefacilities

Stored at a storage facility,
etc. after volume reduction
by compaction, incineration,
etc.

Japan
AtomicEnergyResearch
AgencyAomoriResearchandDevelopment
CenterMutsu Office

Research
facility

AomoriTreating and storage of
waste from research
reactor facility

Stored at a storage facility,
etc. after volume reduction
by compaction, etc.

Japan Nuclear Fuel
LimitedReprocessing
Business division
Japan Nuclear Fuel
LimitedEnrichment
andDisposal Office
The University ofTokyo,
Nuclear
Professional School,
SchoolofEngineering
The University ofTokyo,
Radioisotope Center
Kyoto University
Research Reactor
Institutereactor

Reprocessing
facility
Waste
facility
Waste
facility

Treating and storage of
HLW
and
Trans
uranium waste

Aomoristorage

Storage of vitrified
waste
Disposal of low level
radioactive waste
treating and storage of
uranium waste

disposal
Aomori

Enrichment facility

Research reactor
facility;
Fuelmaterial use facility
Radioisotope
WasteManagement1
facility*
Research reactor
facility
Fuel material use
facility

Temporary storage of
waste from research
reactor facility and fuelmaterial use facility

IbarakiTreating and storage of
waste
from
radioisotopeusefacility, etc
Treating and storage of
waste from research
reactor facility and fuelmaterial use facility

Tokyo

Osaka

22

Storage facility of waste
generated from spent fuelreceipt and storage facility(Reprocessing Facility is
now under construction)
A
storagefacilityfor
returned vitrified waste
No.1 Disposal facility,
No.2 Disposal facility
Stored at a storage facility
Treated in Japan Atomic
EnergyAgencyTokai
Research and Development
CenterNuclear Science ResearchInstitute
Stored at a storage facility,
etc. after volume reduction
by incineration, etc.
Stored at a storage facility,etcLists and Inventories

Rikkyo University
Institute for Atomic
EnergyMusashi Institute ofTechnology
AtomicEnergyResearch InstituteKinki University
AtomicEnergyResearch InstituteNational Institute ofRadiological
Sciences
Radiotoxicology
Building
Operations Section
National Institute ofAdvanced Industrial
ScienceandTechnology
Tsukuba Central 2
NuclearMaterial
Control Center
Rokkasho
Safeguards
Analytical
Laboratory
NuclearMaterial
Control Center
Tokai
Safeguards
CenterJapan Radioisotope
Association
The Kaya Memorial
Takizawa
Laboratory
Japan Radioisotope
Association
Kanto
Storage
Facility
Japan Radioisotope
Association
Ichihara Office
Japan Radioisotope
Association
Kanto Waste Relay
StationJapan Radioisotope
Association
Kanto Waste Relay
Station II
Japan Radioisotope
Association
Kansai Waste Relay
StationToshiba Corporation
Research Reactor
CenterToshiba Corporation
Nuclear EngineeringLab

Kanagawa

Treating and storage of
waste from research
reactorStored at a storage facility,etc

Kanagawa

Storage of waste fromresearch reactor facility

Stored at a storage facility,
etc.

Osaka

Storage of waste fromresearch reactor facility

Stored at a storage facility,
etc

Fuel material use
facility

Chiba

Storage of waste fromfuel material use facility

Stored at a storage facility,
etc.

Fuel material use
facility

IbarakiStorage of waste fromfuel material use facility

Stored at a storage facility,
etc.

Fuel material use
facility

AomoriTreating and storage of
waste
from
fuel
material use facility

Stored at a storage facility,
etc.

Fuel material use
facility

IbarakiStorage of waste fromfuel material use facility

Stored at a storage facility,
etc

Radioisotope
WasteManagement2
facility*

Iwate

Treating and storage of
waste
from
radioisotopeusefacility, etc.

Stored at a storage facility,
etc. after volume reduction
by compaction, incineration,etc

IbarakiStorage of waste fromradioisotopeusefacility, etc.

Stored at a storage facility,
etc.

Chiba

Storage of waste fromradioisotopeusefacility, etc.

Stored at a storage facility,
etc.

Chiba

Storage of waste fromradioisotopeusefacility, etc.

Stored at a storage facility,
etc.

Chiba

Treating and storage of
waste
from
radioisotopeusefacility, etc.

Stored at a storage facility,
etc. after volume reduction
by compaction, etc.

Kyoto

Storage of waste fromradioisotopeusefacility, etc

Stored at a storage facility,etc.

Kanagawa

Storage of waste fromresearch reactor facility

Stored at a storage facility,etc

Kanagawa

Storage of waste fromresearch reactor facility
and fuel material use
facility

Stored at a storage facility,etc.

Research
facility

reactorResearch
facility

reactorResearch
facility

reactorRadioisotope
WasteManagement2
facility*
Radioisotope
WasteManagement2
facility*
Radioisotope
WasteManagement2
facility*
Radioisotope
WasteManagement2
facility*
Radioisotope
WasteManagement2
facility*
Research
facility

reactorFuel material use
facility,
Research
reactor facility

23

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Hitachi, Ltd.
Power & Industrial
Systems Nuclear
System Division
Ozenji Hitachi
Training Reactor
Center
Nippon Nuclear Fuel
Development Co.,Ltd.
NFD Hot Laboratory
NuclearDevelopment
Corporation
Fuel Hot Laboratory
T.N. Technos Co.
TUKUBALABORATORIESVESTA Co., Ltd.

Research
facility

reactor

Kanagawa

Storage of waste fromresearch reactor facility

Stored at a storage facility,
etc

Fuel material use
facility

IbarakiTreating and storage of
waste
from
fuel
material use facility

Disposition on treatment to
JAEA Oarai

Fuel material use
facility

IbarakiTreating and storage of
waste
from
fuel
material use facility

Stored at a storage facility,
etc. after volume reduction
by compaction, etc.

IbarakiTreating and storage of
waste
from
radioisotopeusefacility, etc.

Stored at a storage facility,
etc. after volume reduction
by incineration, etc.

Chiba

Storage of waste fromradioisotopeusefacility, etc.

Stored at a storage facility,
etc.

Radioisotope
WasteManagement1
facility*
Radioisotope
WasteManagement1
facility*(As of the end of March 2008)*1: facility with Radioisotope Waste Management Business licensed on the basis of the Radiation
Hazards Prevention Law*2: facility with Radioisotope Waste Management Business licensed on the basis of the Radiation
Hazards Prevention Law and the Medical Care Laws etc.

D4

Inventories of radioactive waste

D4.1

Inventory of Radioactive Waste Being Held in Storage

The wastes stored in the above-mentioned radioactive waste management facilities ofnuclear power reactor facilities include approximately 630,000 drums (converted to numberof 200 litter drums) in solid waste storage facilities, 29 used steam generators in steam
generator storage facilities, used control rods, disused channel boxes, spent resin in spent
fuel pools and other facilities at the end of March 2008.
At facilities other than nuclear power reactor facilities, HLW of approximately 1,600 vitrified
packages and approximately 400m3 high level liquid waste are stored in fuel reprocessing
facilities, and LLW of approximately 590,000 drums (converted to number of 200 litter
drums) and approximately 5,400m3 low level liquid waste are stored in fuel reprocessing
facilities, fuel fabrication facilities, laboratories, research reactor facilities of universities, andstorage facilities of Japan Radioisotopes Association at the end of March 2008.
Details of these inventories are indicated in Section L.
D4.2

Inventory of Radioactive Waste That Has Been Disposed of

A portion of LLW stored at radioactive waste management facilities of commercial powerreactor facilities, which has comparatively low concentration of radionuclides, has beentransported to a radioactive waste disposal facility of JNFL and disposed of at near surface
disposal facility since 1992.
The amount of the waste emplaced at the disposal facility is listed in Table D4-1. Presently,
the disposal facility of JNFL is in operation and has disposed of about 200,000 drums (eachcarrying 200 liters) of waste, as of the end of March 2008. At the disposal facility of Tokai
Research and Development Center, Nuclear Science Research Institute of JAEA, about
1,670 tons of very low level wastes resulting from dismantling of JPDR were disposed of.
The facility has started operation in 1995, and the disposal facility has been at the24

Lists and Inventories

preservation stage since October 1997.

D4.3

Inventory of Radioactive Waste that Has Resulted from Past Practices

None.
Table D4-1 The Amount of Waste Disposed ofName of facility
Representative nuclides Disposed amountCo-60, Ni-63, Cs-137,
Japan Nuclear Fuel Limited,3
138,555 drums*
No. 1 disposal facility
Sr- 90, C-14
Enrichment and Disposal
Office, Radioactive waste
Co-60, Ni-63, Cs-137,
3
No. 2 disposal facility
62,064 drums*
1
disposal facility*
Sr- 90, C-14
Japan Atomic Energy Research
Co-60, Ni-63, Cs-137,
Agency Tokai Research andWaste disposal facility Sr- 90, Ca-41, C-14,
1670 tons
Development Center
Eu-152, H-3
Nuclear Science Research
2
Institute **1: As of the end of March 2008
*2: Disposed of very low level concrete waste resulting from the dismantling of JPDR, and shifted to thepreservation stage of the disposal facility since October 1997.
*3: 200-liter drums

D5

List and status of nuclear facilities in the process of being decommissioned

Nuclear facilities in the process of being decommissioned include Tokai Power Station of theJapan Atomic Power Co., JRR-2 of JAEA and the Advanced Thermal Reactor “Fugen” of
JAEA.
A reactor at the Tokai Power Station of the Japan Atomic Power Co. ceased the operation in1998 and has been in decommissioning stage since December 2001. Turbine, feed water
pumps, etc. started to be dismantled first. Dismantling heat exchangers started in 2006. In
2011 the dismantling reactor vessel will be started and it will last for 6 years. The
decommissioning will be completed by 2018.
Fugen Decommissioning Engineering Center of JAEA, ceased the operation of theadvanced thermal reactor “Fugen” at the end of March 2003 and on 7 November 2006 theapplication of decommissioning program was filed and permitted on 12 February. Spent fuelhas being transferred to Tokai Reprocessing Plant of Tokai Research and Development
Center Nuclear Fuel Cycle Engineering Laboratories of JAEA, and the decommissioning isplanned to be completed by fiscal year 2028.
The status of decommissioning activities, etc. is listed in Tables D5-1 and D5-2.
Table D5-1

Name of facility
Japan Atomic PowerCo.,
Tokai Power Plant
Japan Atomic Energy
Research Agency,
Fugen
Decommissioning
Engineering Center(Fugen)

List of Nuclear Facilities in the Process of Being Decommissioned andPlanned to Be Decommissioned. Status of Decommissioning Activities at
These Facilities (With Respect to Power Reactors)
Location

ReactorElectrical
Commercial
type
output (MW) operation

Status of decommissioning

Ibaraki

GCR

Jul 1966
Mar 1998

Decommissioning started in 2001

1979
Mar 2003

Termination of operation in March 2003.
Continue taking out of spent fuels andpreparation for decommissioning.
The decommissioning is planned to startfrom Feb. 2008 and be completed byfiscal year 2028.

Fukui

ATR

166

165

(As of the end of March 2008)

25

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Table D5-2

List of Nuclear Facilities in the Process of Being Decommissioned andPlanned to Be Decommissioned. Status of Decommissioning Activities at
These Facilities (With Respect to Research Reactors)

Name of facility
Japan Atomic Energy
Research Agency,
Tokai Research andDevelopment Center,
Nuclear Science
Research Institute ,JRR-2
Japan Atomic Energy
Research Agency
Tokai Research andDevelopment Center
Nuclear Science
Research Institute
VHTRC
Japan Atomic Energy
Research Agency
Aomori Research andDevelopment Center
Mutsu Office
The Reactor Facilities
Of The First Nuclear
Ship (Mutsu)
Japan Atomic Energy
Research Agency,
Oarai Research andDevelopment Center,
Deuterium Criticality
Assembly(DCA)
Hitachi Ltd. Power &Industrial Systems
Nuclear System
Division
Ozenji
HirachiTraining
ReactorCentorToshiba Corporation
Research Reactor
Center, Toshiba
Training Reactor-1(TTR-1)

Location

Reactortype

Ibaraki

Heavy
water
moderatedcoolingtankreactorIbarakiGraphitemoderated
reactor

AomoriPressurized
light watermoderatedand cooled
reactor,
PWR

Ibaraki

Heavy
water
moderated
reactor

Kanagawa

Light watermoderatedand cooled
reactor

Kanagawa

Rikkyo University
Institute for Atomic
EnergyKanagawa

Musashi Institute ofTechnology
Research Reactor

Kanagawa

Light watermoderated
inhomogeneousreactor
Zirconium
hydridemoderated
light watercooledreactor
Zirconium
hydridemoderated
light watercooledreactorServiceperiod*Status of decommissioning

10000

Oct 1960
Dec 1996

The following activities fordecommissioning have been
completed.
Shipment of spent fuel andheavy water, isolation of reactor
cooling system and reactor
body, removal of secondary
cooling system and experimental
equipment.

0.01

May1985
Jun 1999

Dismantling and removal of thereactor body and leveling ofreactor (including resin painting)have been completed.

36000

Aug 1974
Feb 1992

Dismantling has been
completed.
Accessory land facilities are
currently being maintained forthe purpose of storing solid
waste and processing liquid
waste

1

Dec 1969
Sep 2001

Deactivation
has
beencompleted.
Carry
out
heavy-water and remove coolingsystemThermaloutput (kW)Dismantling has been
completed.
Currently being proceeding are
the maintenance of the poolstoring spent fuel and thestorage and maintenance ofradioactive waste.
Permanent suspension ofoperational functions andremoval of reactor coolingsystem facilities.
Carry out spent fuel100

Dec 1961
Feb 1975

100

Mar 1962
Jan 2001

100

Dec 1961
Dec 2001

Extended-shutdown, carry out
spent fuel.

100

Jan 1963
Jan 2004

Extended-shutdown, carry out
spent fuel*: A period from the first criticality to the termination of operation

26(As of the end of March 2008)

Legal and Regulatory Systems

Section E

Legislative and Regulatory System

In Japan, legal systems are provided for promoting proper management of spent fuel andradioactive wastes, and also for safety regulation on them.
This section describes such legal systems.
E1

Implementing Measures

Article 18
Each Contracting Party shall take, within the framework of its national law, the legislative, regulatory andadministrative measures and other steps necessary for implementing its obligations under thisConvention.

In Japan, the steps necessary for implementing the obligations under this Convention aretaken in accordance with relevant laws and regulations. The “Atomic Energy Basic Law”
provides the fundamental objectives of promoting nuclear energy research and utilization;
securing of future energy resources; promotion of the progress of science and technology andindustrial development; and eventual contribution to the welfare of human society andimprovement of the level of people’s living. The Law also provides for the basic principle thatthe research, development and utilization of nuclear energy shall be made only for peacefulpurposes with ensuring safety, operating democratically and autonomously, publicizing theresults, and actively contributing to international cooperation. In accordance with theobjectives and basic principles provided by the “Atomic Energy Basic Law”, the government ofJapan has established legal systems for safety regulation on spent fuel management andradioactive waste management. The relevant laws and regulations are outlined in E2.
To implement obligations under the Convention, the following organizations have been
established to enforce legal systems described in this section. The roles of thoseorganizations are summarized below.
1.
The Atomic Energy Commission (AEC)
The AEC was established within Prime Minister’s office on January 1st 1956, in order toimplement national policy on the research, development and utilization of nuclear energy inplanned and democratic manner. (The AEC was transferred to the Cabinet Office inJanuary 2001.)
The AEC has responsibility to 1) prepare the basic policy on the research, development
and utilization of nuclear energy, 2) prepare allocation of the budget for the nuclear energy
development, 3) express opinions on the application of license standards based on the
Law for Regulation of Nuclear Source Material, Nuclear Fuel Material and Nuclear
Reactors (Reactor Regulation Law), 4) to make planning, deliberation and decisions on
coordinating the related administrative organizations in the matters that are related to theresearch, development, and utilization of nuclear energy. Based on the Law for
Establishment of the Atomic Energy Commission and the Nuclear Safety Commission (theAEC and the NSC Establishment Law), when the AEC deems it necessary as a part of its
assigned duties, the AEC may recommend the heads of relevant administrative
organizations by way of the Prime Minister, may request reports and cooperation including
submission of materials, statements of viewpoint, and explanation to the heads of relevant
administrative organizations. Under the Reactor Regulation Law, the Minister of METI or
Minister of MEXT shall, before granting a license to establish nuclear facility, receive viewsof the AEC with regard to the following items: 1) the nuclear facility will not be used for any
purposes other than peaceful purposes, 2) the license will cause no hindrance to theplanned development or utilization of nuclear energy, and 3) the applicant has an adequate
financial basis to construct and maintain the nuclear facility
In 1956, The AEC established the Long-term Program for Development and Utilization of
Nuclear Energy (hereinafter referred to as “the Long-term Program”) that showed the basic
policy and implementation plan for the nuclear research and development in Japan. Since
then the AEC revised the Long-term Program, approximately every five years. The latest
27

E

E

Legal and Regulatory Systems

version of the Long-term Program was issued in October, 2005 with a new title of“Framework for Nuclear Energy Policy”.
The AEC is composed of a chairman and four other commissioners appointed by the Prime
Minister with the consent of the Diet. General affairs of the AEC are performed by the officeof nuclear energy policy under the cabinet office. It coordinates the matters with related
administrative organizations in order to implement the AEC decisions.
Under the AEC, specialists are assigned to investigate and deliberate the specific matters,
and special committees, councils or other bodies may be established when necessary.
There are 4 special committees (committee for policy evaluation, special committee fornuclear protection, special committee for research and development and special
committee for Nuclear fusion), 2 councils (council for citizens participation and council forinternational issues). These committees and councils are deliberating assigned matters.
Specialists are appointed by the Prime Minister from persons of knowledge and experiencebased on the AEC and the NSC Establishment Law.
The discussions of meetings of the AEC including the committees and councils are open to
the public in principle and people can observe the meetings. The contents of thedeliberations are provided for the public on a website of the AEC (http://aec.go.jp/) and at
the Nuclear Energy Library.
2.
The Nuclear Safety Commission (NSC)The Atomic Energy Basic Law was partially revised on October 4, 1978 to establish the
NSC under the Prime Minister’s Office. The function of safety regulation, which had been
belonged to the AEC, was transferred to the NSC, in order to strengthen the system of
ensuring nuclear safety. (The NSC was transferred from the Prime Minister’s Office to the
Cabinet Office due to central government reform in January 6, 2001.)
The NSC is responsible for planning, deliberation and decisions on matters that are related
to ensuring safety of the research, development, and utilization of nuclear energy.
The NSC conducts its own review of the results of NISA’s examination on the applicationfrom the view points of the licensee’s technical capability and prevention of nuclear
hazards. The NSC supervises and audits the appropriateness of NISA’s regulatory activity
in construction and operation stages after Safety Review, from the viewpoint of adequacy,
effectiveness and transparency. Thus, the framework that confirms the quality,
effectiveness and transparency of the safety regulation is maintained. (see Fig E1-2)
When the NSC deems it necessary as a part of its assigned duties, the NSC may
recommend the heads of relevant administrative organizations by way of the Prime
Minister, may request reports and cooperation including submission of materials,
statements of viewpoint, and explanation to the heads of relevant administrative
organizations.
From April 2003 (partially, from October 2003), the NSC receives from NISA quarterly
reports on the regulatory activities after licensing such as Approval of the Construction
Plan, Pre-Service Inspection, Periodic Inspection, Audit of Licensee's Periodic Check
System, Audit of Licensee's Welding Check System, Approval of Operational Safety
Program, the Operational Safety Inspection and accidents and failures of nuclear
installations. The NSC also has the authority to inquire directly of the licensees, andmaintenance and inspection contractors in order to audit the safety regulation implemented
by regulatory body.
In the case of a violation of safety regulations in any of nuclear facilities, the employee candirectly allege the fact to the NSC, and the NSC has the authority to investigate theallegation.
The Minister of METI, before granting license to establish nuclear installations, mustreceive the opinion of the NSC on the following matters: (i) that the applicant for the licenseof a nuclear installation has adequate technical capability to establish and reliably operate
a nuclear reactor, and (ii) that the site, structures and equipment of the nuclear installation
would not cause any hindrance to the prevention of radiological hazards.
The NSC is composed of five commissioners appointed by the Prime Minister with the28Legal and Regulatory Systems

consent of the Diet, and these commissioners elect a chairman among them. Generalaffairs of the NSC are performed by the NSC Secretariat of the Cabinet Office. The NSC
Secretariat is composed of the Secretary-General, the General Affairs Division, theRegulatory Guides and Review Division, the Radiation Protection and AccidentManagement Division and the Subsequent Regulation Review Division and has about 100
personnel.(see Fig E1-1)
Under the NSC, two safety examination committees and sixteen other special committees
are organized as shown in Table E1-1. The Special Committees may organize working
groups under them, if necessary.
The members of the Committee on Examination of Reactor Safety and the Committee on
Examination of Nuclear Fuel Safety are appointed from persons of knowledge andexperience by the Prime Minister in accordance with the AEC and the NSC Establishment
Law. The Emergency Technical Advisory Body is composed of the commissioners of the
NSC and the experts on the nuclear emergency who are also appointed by the Prime
Minister from persons of knowledge and experience. Other special committees arecomposed of similar members.
Results of the safety examination committees and special committees are reported to the
NSC and are deliberated by the NSC. At nuclear emergency, the NSC determines
recommendation for nuclear emergency after the discussion of the Emergency TechnicalAdvisory Body.
Deliberations of all committees, including the special committees and working groups
under the NSC are open to the public. The contents of the deliberations are provided forthe public on a website (http://www.nsc.go.jp/) and at the Nuclear Energy Library.
3.
Ministry of Foreign Affairs (MOFA)
MOFA formulates foreign policy of on peaceful uses of nuclear energy and nuclear
non-proliferation. MOFA has the responsibility for ratification, interpretation andimplementation of international conventions concerned.
4.

Organizations to promote the implementation of spent fuel management andradioactive waste management(1)

Agency for Natural Resources and Energy of the Ministry of Economy, Trade andIndustry
The Agency for Natural Resources and Energy was established as an external agency of
the Ministry of Economy, Trade and Industry, to be responsible for ensuring stable andefficient sharing of mineral resources and energy and for promoting their appropriate
utilization. The Agency plans, develops and promotes comprehensive policies for mineral
resources and energy, policies for energy saving and new energy, nuclear energy policies
and basic policies for electric power resources development. It promotes utilization of
nuclear energy, ensuring energy resources and developing industry.

(2)

The Research and Development Bureau and the Research promotion Bureau of the
MEXT
The MEXT promotes nuclear energy research and development for science andtechnology. In the MEXT, the Research and Development Bureau is promoting the
research and development for fast breeder reactor (FBR) cycle technology, and fornuclear fusion including International Thermonuclear Experimental Reactor (ITER)
project. In addition, the Bureau supervises the Japan Atomic Energy Agency and deals
with nuclear liability matters.
The Research promotion Bureau promotes application of radiations, radioactive isotopes
and quantum beams. Specifically, the Bureau is promoting the Japan Proton Accelerator
Complex (J-PARC) project and research on heavy particle cancer therapy.

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5.
Regulatory bodies
The following organizations have been established for the regulation in Japan. The roles of
those organizations are summarized in E3.
(1) Nuclear and Industrial Safety Agency (NISA) of the METI
Safety regulation for nuclear energy use as energy source(2) Science and Technology Policy Bureau of the MEXT
Safety regulation for nuclear energy use for science and technology and radiation
utilization(3) Ministry of Land, Infrastructure, Transport and Tourism
Safety regulation for transportation of nuclear fuel materials for nuclear energy use(4) Ministry of Health, Labor and Welfare (MHLW)
Safety regulation for radioactive materials etc. for medical use

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Legal and Regulatory Systems

Management andCoordination Division

Prime Minister
Cabinet Office

Nuclear Safety Commission *Regulatory Guides andReview Division

SecretaryGeneral

Radiation Protection
and AccidentManagement Division* Established in accordance with the Law for
Establishment of the Atomic Energy Commission
and the Nuclear Safety Commission

Subsequent Regulation
Review Division

E1-1 NSC Organizational Chart

Establishment Permit etc.
Ministry of Education, Culture,
Sports, Scirnce and Technology
Ministry of Economy, Trade andIndustry (NISA)
Ministry of Land, Infrastructure andTransport

Nuclear safety regulation by
regulatory body〔Construction stage〕
Approval of design andconstruction methodPre-service inspection
Approval of operation safety
program〔Operating Stage〕
Periodic facility inspection
Inspection of fitness for operation
safety program etc.
〔Others〕
On the spot inspection
Report of accidents and failures
etc.

E1-2

Askingconsultation

Nuclear Safety Commission
Secondary review

Mandatory advice

Reportoftheimplementing
situation,etc.
concerning
nuclearsafetyregulation

ReportObservation andaudit

Objectives:
Promotionofcontinuous
improvement andenhancement
throughobservation andaudit of nuclear
safety regulatory
activities of theregulatory body

Emergency preparedness
Technical Capability

Regulatory investigation
Common subjects andimportantsubjects
forensuring the safety（examples）
Licensee’s
periodic
inspection
Qualityassurance
activities etc.
Importantpointed-out
subjects at the individualadministrative disposition
or at the secondary review
Licensee’s obligation tocooperatefortheinvestigation

Observation, Audit, Inspection, etc. of the Safety Regulatory Administration by
Nuclear Safety Commission

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Table E1-1

List of Special Committees within the NSC

Committee on Examination of Reactor
SafetyCommittee on Examination of Nuclear
Fuel Safety
Emergency Technical Advisory Body

I Matters concerning the safety of nuclear reactor facilities
I Matters concerning the safety of nuclear fuel material
I Technical advices pursuant to the Special Law for Nuclear
Emergency

Emergency Technical Advisory Body for
I Technical advices in emergencies/disasters of nuclear
Disaster Prevention of Nuclear Carriers
carriers and submarines
and Submarines
Emergency Technical Advisory Body for
I Technical advices in nuclear emergencies/disasters due to
Nuclear Disaster Prevention due to Armedarmed attacks
Attacks
I Matters concerning safety standards and guides of nuclear
Special Committee for Nuclear Safety
reactors, nuclear fuel facilities, and other nuclear
Standards and Guides
installations
IMatters concerning the safety assurance in radioactive
Special Committee on Radioactive Waste
waste disposal
and Decommissioning
IMatters
concerningthesafetyassuranceindecommissioning nuclear installations
Special Committee on Safety Goals
I Establishment of safety goals
Special Committee on Radiation
I Matters concerning the radiation protection considering
domestic and international trends
Protection
I Matters concerning the safety assurance in transportation
Special Committee on Safe Transport ofof radioactive materials considering domestic andRadioactive Materials
international trends.
Special Committee on Analysis and
I Analysis and evaluation of domestic and international
Evaluation of Nuclear Accidents andnuclear accidents and failures
Failures
I Planning of nuclear safety research programs
Special Committee on Nuclear Safety
I Monitoring of the nuclear safety research programs
Research
IEvaluation of the nuclear safety research programs
I Emergency preparedness in the vicinity of nuclear
Special Committee on Nuclear Disasterinstallations, etc.
I Investigation and evaluation concerning the ensuring ofInvestigatory Advisory Board on
seismic safety of nuclear facilities.
Assessment of Seismic Safety
Specifically:
ICommittee on Evaluation of• Seismic safety checks of existing nuclear facilities;
Earthquakes and Ground Motions• In-depth checks of the impacts caused by the Niigataken
Chuetsu-oki Earthquake in 2007 on the nuclear facilities at
I Committee on Assessment of thethe Kashiwazaki-Kariwa Nuclear Power Station, TEPCO,
Nuclear Power Reactor Facility Integrities
I Committee on the Guidelines for Safety
and the integrity evaluation of them;
Review concerning Geology and Ground • Relevant matters concerning the revision of the “Guidelines
for Safety Review concerning Geology and Ground ofof Nuclear Power Reactor Facilities
Nuclear Power Reactor Facilities.”
I Survey and analyses of matters relevant to the safety
Project Team on Safety Survey ofregulation activities during the test operation of the
Reprocessing Facilities
Rokkasho reprocessing facility
Advisory Board on High-level Waste
I Technical matters concerning the safety assurance in the
final disposal of high-level radioactive wastes
Repository Safety
Task Force for introduction of Safety
I Review and analyses of the issues in the introduction ofsafety regulation using risk information
Regulations Using Risk Information

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E2

Legislative and regulatory framework

Article 19
1. Each Contracting Party shall establish and maintain a legislative and regulatory framework to
govern the safety of spent fuel and radioactive waste management.
2. This legislative and regulatory framework shall provide for:(i) the establishment of applicable national safety requirements and regulations for radiation safety;(ii) system of licensing for spent fuel and radioactive waste management activities;(iii) a system of prohibition for the operation of a spent fuel or radioactive waste management facility
without a license;(iv) a system of appropriate institutional control, regulatory inspection and documentation andreporting;(v) the enforcement of applicable regulations and of the terms of the licenses;(vi) clear allocation of responsibilities of the bodies involved in the different steps of spent fuel andradioactive waste management.
3. When considering whether to regulate radioactive materials as radioactive waste, Contracting
Parties shall take due account of the objectives of this Convention.

E2.1

Legislative and Regulatory Framework

1.

Legal system for promoting spent fuel management and radioactive waste
management
In Japan, spent fuel management is carried out on the site of facilities such as nuclear
power stations and reprocessing facility. In addition, Japan has an option to alternately
store spent fuel in intermediate storage facility outside of reactor facility. The law currently
working for the promotion of spent fuel management is the “Act for Deposit andAdministration of Reserve Funds for Reprocessing of Spent Fuel from Nuclear Power
Generation” for securing the future costs for reprocessing in a safe, reliable andtransparent means.
As for radioactive waste management, a part of low level radioactive wastes (LLW) havebeen already being disposed of in a near surface disposal facility. Meanwhile, the "SpecificRadioactive Waste Final Disposal Act (Final Disposal Act)" is applicable to taking
necessary steps to systematically and securely carry out the final disposal of theradioactive wastes to be geologically disposed, such as vitrified waste of high level
radioactive wastes (HLW) generated from reprocessing of spent fuel.
(1) Final Disposal Act
Final Disposal Act enacted in May, 2000 provides for the following basic framework forsystematically and securely carrying out the final disposal of the high level radioactive
wastes generated from spent fuel reprocessing (hereinafter referred to as “SpecificRadioactive Wastes”); (i) development and public announcement of an basic policy and aplan (final disposal plan) for the final disposal of specific radioactive wastes by the
Minister of METI; (ii) process for site selecting for a final disposal of specific radioactive
wastes; (iii) securing of the expenses required for the final disposal of specific radioactive
wastes; (iv) responsible licensee for the final disposal of specific radioactive wastes. The
amendment of the Act in June, 2007 newly added TRU wastes to be the subjects ofgeological disposal.
The Minister of METI establishes the basic policy and based on this, provides for the final
disposal plan. Nuclear Waste Management Organization of Japan (NUMO), which wasestablished as an implementing organization based on the final disposal plan, carries out
the activities of final disposal. Utilities shall pay deposits to the fund reserved for disposal,
which is managed by an organization “Radioactive Waste Management Funding andResearch Center” (RWMC) designated by the Minister of METI. NUMO promotes site
selection by three steps procedure, that is, selection of the preliminary investigation area,
detailed investigation area and the final disposal facility construction site, and NUMO
obtains approval of the Minister of METI at each step of procedure.
The three step procedure for site selection is as follows, and items for investigation and
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evaluation are clearly defined.
Preliminary investigation of the area
Definition: The area to investigate by boring etc. whether the geological formation
concerned is stable for long term.
Requirements for selection: There shall be no record of noticeable change of thegeological formations by natural phenomena, such as earthquakes.
Detailed investigation of the area
Definition: The area to investigate, by constructing underground facility with testing andmeasuring equipment, whether the characteristics of the geological formation
concerned is suitable for construction of disposal facility.
Requirements for selection: Noticeable change of the geological formations by natural
phenomena, such as earthquakes, has not occurred for long term.
Selection of Final disposal facility construction site
Definition: The site where the final disposal facility is to be built.
Requirements for selection: It is expected that underground facility to be built within thegeological formation will not be exposed to an extraordinary pressure, and that physicalproperty of the geological formation is suitable for the final disposal facility.
When the Minister of METI is to advance a step further of the three-step procedure of site
selection and to put it in the final disposal plan upon receiving NUMO’s selection of anarea or a site, the minister shall ask for opinion of the AEC and the NSC and shall consult
relevant prefectural governors and mayors of municipalities and fully respect theiropinions.
(2)“Act for Deposit and Administration of Reserve Funds for Reprocessing of Spent Fuelfrom Nuclear Power Generation” (May 2005)
This law provides for the frame work of deposit and management of the reserve funds forreprocessing of spent fuel from the nuclear power generation. The fund is managed by anorganization designated by the Minister of METI (Fund Management Organization). The
Minister of METI, every fiscal year, notifies utilities of the amount of deposit based on theamount of electricity generated by the nuclear fuel, and utilities deposit the amount in theFund Management Organization. This law was enacted from the 1st of October 2005.

2.
Legislative and Regulatory Framework on the Safety of Nuclear Utilization
Major laws established for the purpose of providing safety regulations on the utilization of
nuclear energy and related laws include Reactor Regulation Law, “Electricity Utilities
Industry Law“, “the Law Concerning Prevention from Radiation Hazards due toRadioisotopes, etc.” (hereinafter referred to as “the Radiation Hazards Prevention Law”)
and the Medical Care Law, the Clinical Laboratory Technicians and Health Laboratory
Technicians Law, and the Pharmaceutical Affairs Law (These 3 laws are called “Medical
Care Law, etc.” hereafter) Also included are “the Basic Law for General Emergency
Preparedness,” “the Special Law of Emergency Preparedness for Nuclear Disaster (theSpecial Law for Nuclear Emergency Preparedness),” “the Law for Technical Standards ofRadiation Hazards Prevention” etc. Overviews of these laws are provided in the following
paragraphs.
(1) Reactor Regulation Law
In accordance with the objectives of “the Atomic Energy Basic Law”, the Reactor
Regulation Law is enacted to ensure that the uses of nuclear source material, nuclear
fuel material, and reactors are only for the peaceful purposes, and carried out in aplanned manner, to ensure public safety by preventing hazards and providing physicalprotection of nuclear fuel material and to ensure that use of internationally controlledmaterial is regulated to comply with conventions on nuclear utilization or otherinternational commitments.
The Law covers following activities and provides regulation for each of them:
Refining
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Legal and Regulatory Systems

Nuclear fuel fabrication
Establishment and operation of reactor facilities
Spent fuel storage
Spent fuel reprocessing
Radioactive waste storage and disposal
Use of nuclear fuel material
The safety of spent fuel management is ensured through the each regulation for“establishment and operation of reactors”, “storage” and “reprocessing”, and the safety ofradioactive waste management is ensured through the each regulation for “fabrication”,“establishment and operation of reactors”, “storage”, “reprocessing”, “disposal” and “useof nuclear fuel materials”.
The license for refining, fabrication, reactor establishment, storage, reprocessing,disposal and for use of nuclear fuel materials are granted on the basis that the location,
structures and systems of the facility does not impair the prevention of hazards due tonuclear fuel materials, etc. and that the applicant has sufficient technological capability.
The competent minister shall ask for opinions of the AEC and the NSC before granting
license (except for license for use of nuclear fuel material).
The regulation after granting license includes regulation for ensuring facility safety (facility
regulation) and regulation for ensuring operational safety and safety activities of theoperator (operation regulation). The facility regulation includes “approval of design andconstruction methods”, “pre-service inspection”, “approval of welding method and welding
inspection”, “periodical facility inspection” and “confirmation for waste disposal”. The“approval of design and construction methods” is to confirm that the facility has been
designed in accordance with the “permitted” conditions and the “technical standard”, andthe approval must be obtained before starting construction. The “pre-service inspection”
is to confirm that the construction has been carried out in accordance with the approved"design and construction methods” and that the facility has the prescribed capability. The
licensee cannot operate the facility without passing the pre-service inspection. Then, the“periodical facility inspection” is conducted periodically during operation to confirm thatthe facility and systems maintain the prescribed capability. The “confirmation for waste
disposal” is to confirm that the waste disposal facility and related safety measures as wellas the waste packages and related safety measures are in compliance with the technicalstandards.
Operational safety regulation for spent fuel management and radioactive waste
management includes the “approval of the Operational Safety Program and the
Operational Safety Inspection to inspect observance”, “assignment of the Chief
Technician for Nuclear Fuel or the Chief Technician for Waste Handling”, “approval of the
Physical Protection Program and the Operational Safety Inspection to inspectobservance” and “assignment of the physical protection manager”. The “the Operational
Safety Program” prescribes the measures for ensuring safety and facility maintenanceincluding “operation and management of facility”, “patrol and check”, “radiation control”
and “radioactive waste management”, and must be prepared by licensee and approvedby the regulatory body. Licensee must have “the Operational Safety Program” approved
before starting operation and must undergo periodically the “the Operational Safety
Inspection” after the commissioning.
In addition, the Reactor Regulation Law provides for restriction of ocean dumping ofradioactive wastes, reporting of facility accident and other event, measures in emergency
and penalties. Penalties are the steps to ensure the compliance with applicable regulationand license condition. If an licensee has built a nuclear facility without obtaining license,
has violated a cease-operation order, or has not take necessary measures for
emergencies, imprisonment with hard labor or fine or both is imposed on the licensee. It
is also provided for that if an operator does not observe the Operational Safety Program
or does not follow an order to amend the Operational Safety Program, the licensee issubject to penalties such as revocation of license.
The NSC establishes the Regulatory Guides for design, safety review, etc. which specify
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technical requirements for safety regulation of activities under the Reactor Regulation
Law. The guides are used in the safety review of license application as the criteria for
judging adequacy of the application. Ministerial orders for each of activities under theReactor Regulation Law provide for regulation for each activity. Safety regulation on
spent fuel management and radioactive waste management are described in Section G
and Section H, respectively.
The Reactor Regulation Law was amended as follows since the last national report:
June 2007
Establishment of the safety regulation system for the final disposal of HLWThis amendment was to establish the safety regulation system for the geological disposalof HLW and introduced a licensing system for HLW disposal. This licensing system
requires the Minister of METI to approve the design and construction methods before thestart of construction and to conducts pre-service inspection for the construction andcapability of the facility, inspection on welding method, periodical facility inspection during
operation, to approve the Operational Safety Program with the Operational Safety
Inspection to inspect observance and to approve the Physical Protection Program with
the Operational Safety Inspection to inspect observance”.
To establish an adaptable safety regulation system for radioactive waste disposal, making
two classifications in the regulatory system. The conventional radioactive waste disposalof LLW was categorized as "Category 2 waste disposal" and disposal of HLW was
categorized as "Category 1 waste disposal".
Following this amendment of the Law, ministerial ordinances prescribing detailed
procedures for the Category 1 and 2 waste disposals were established and enacted in
April, 2008. The details of the safety regulation for the Category 1 and 2 waste disposals
are described in Section H.
June 2008
Improvement of fire protection system
The Kashiwazaki-Kariwa Nuclear Power Station of the Tokyo Electric Power Co. Inc. wasextensively affected by the Niigataken Chuetsu-Oki earthquake in July 2007, including
the damages to the fire-fighting system such as main fire-fighting water pipe. The
damage made it difficult to promptly extinguish the transformer fire that broke out
immediately after the earthquake, and caused flooding of fire-fighting water into thereactor building of the unit 1.
In response to this event, the NSC revised the “Regulatory Guide for Reviewing Fire
Protection of Light Water Nuclear Power Reactor Facilities” to add fire detection, mobile
fire-fighting equipment and in-house fire-fighting squad, recognizing importance of fire
preparedness in operation in addition to design consideration against fire caused by big
earthquake.
NISA, also, called a council of the experts from Nuclear and Industrial Safety
Subcommittee of the Advisory Committee for Natural Resources and Energy to obtainadvice for fire protection in nuclear facilities. On the basis of the advice of the council,
NISA decided to add the requirement of fire protection provisions, such as in-housefire-fighting activities by operators and notification to the local fire station (initial
fire-fighting activities), to the Operational Safety Programs as a measures to maintainsafety. Specifically, NISA required the licensees to add provisions to the Operational
Safety Programs on the preparation of fire-fighting vehicle equipped with chemical fire
extinguisher, preparation of equipment to send alarm to local fire station and first
response stuff for firefighting on regular basis. NISA confirms the implementation of suchprovisions by the Operational Safety Inspection.
The MEXT required the operators that operate large-scale research reactors to confirm
the compliance with the "Regulatory Guide for Reviewing Fire Protection of Light Water
Nuclear Power Reactor Facilities” issued by the Nuclear Safety Commission and also
requested to report on the programs for enhancing fire protection measures. The Ministry36Legal and Regulatory Systems

confirms the implementation of such programs within the scope of the Operational Safety
Inspection.
(2) The Radiation Hazards Prevention Law
It is the purpose of the Radiation Hazard Prevention Law, based on the Atomic Energy
Basic Law, to prevent from possible radiation hazards and to secure public safety, byregulating the use, sale, lease, disposal and others in which radioisotopes are handled
and regulating the use of radiation generating apparatus, disposal and others in which thematerials contaminated by radioisotope are handled.
Under the Law, the Enforcement Ordinance for the Radiation Hazards Prevention Law
are established.
A license holder for use, sale, lease and waste management of radioisotopes, who has astorage facility with a capacity equal to or more than a specified amount or has radiation
generating apparatuses, shall undergo the Facility Inspection before starting operationand the Periodic Inspection after starting operation.
Those who use the facility licensed under the Radiation Hazard Prevention Law mustcompile a set of the Internal Rules for Prevention of Radiation Hazards, assign the
Supervisor of Radiation Protection, who is to supervise the prevention of radiation
hazards, and notify these matters to the regulatory body before use of facility.
Furthermore, those who use the facility have an obligation to conform to the criteria for
facilities to be used, which have been established by legislation. Other obligations
include: measuring the radiation doses within the premises or on the boundary of theestablishment; measuring the exposure doses of the occupational personnel; providing
education and training; and conducting medical surveillance, etc (with some exemption).
The management of radioisotopes or materials contaminated by radioisotopes generated
within radioisotopes use facility shall be carried out in conformity with the criteria
established by Law and regulations. They shall be stored within the premises of licensed
facility or the premises of the licensed facility of radioisotope waste management.
The basic framework for radioactive waste disposal by disposal business operators isprovided by the Radiation Hazard Prevention Law amended in June 2004 and by
subsequent amendments of the enforcement ordinances and regulations. Currently,
MEXT is developing the technical details such as dose criteria for the disposal site forprogress of waste disposal.
Those who intend to cease the use of radioisotopes or radiation generating devices shallnotify the Minister of MEXT of it, and report on the measures taken to cease operation.
If it is necessary, MEXT instructs the Radiation Inspectors to conduct an on-site
inspection in order to confirm the compliance with the standards established by laws andregulations.
(3) Medical Care Law, etc.
The management of radioisotope waste generated from medical use is conducted only by
waste management facility operators designated by the Minister of MHLW on the basis of
the Medical Care Law etc.
Site, structure, and equipment of the waste management facility shall be complied withrelated technical criteria (standards) in order to be designated by the Minister of MHLW.
In addition, Periodical Inspection, Radiation Hazard Prevention Rules, conformance orderto the standards of waste management facilities, education and training, notification ofclosure of waste management facility, etc, are provided by these laws equivalent to theRadiation Hazards Prevention Law.
(4)

The Special Law for Nuclear Emergency Preparedness and the Basic Law for
General Emergency Preparedness
The measures to be taken at a nuclear emergency are addressed by the Special Law for
Nuclear Emergency Preparedness which was enacted in December 1999. The Special
Law stipulates specific measures for nuclear emergency, including obligation of operators
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on the preparedness for nuclear emergency, the Declaration of Nuclear Emergency andestablishment of headquarters for the nuclear emergency, and enforcement ofemergency measures. The Senior Officer for Nuclear Emergency is stationed in thevicinity of each nuclear facility, to direct and advise the operator in preparing its Plan for
Nuclear Emergency Preparedness, as well as to conduct its duty to prevent occurrence of
nuclear emergency and mitigate consequences should it occur.
Moreover, in the part of the nuclear emergency measures of the Basic Plan for
Emergency Preparedness on the basis of the Basic Law for General Emergency
Preparedness, measures necessary to the stages of abnormal event, nuclear emergency
and recover from the emergency are clearly described.
(5) The Law for Technical Standards of Radiation Hazards Prevention
The objectives of the Law for Technical Standards of Radiation Hazards Prevention andits relevant regulation are to clarify the basic policy for defining technical standards forradiation hazards prevention and to establish the Radiation Council of MEXT, so thatconsistency of technical standards for radiation hazards prevention among the facilities
and activities regulated by different ministries can be realized. The Radiation Council
Orders” are stipulated under this Law.
E2.2

Clear Allocation of Responsibilities in the Different Steps

October 8, 1985, the AEC published a report titled "Policy on Radioactive Waste Processingand Disposal" prepared by the Special Committee on Radioactive Wastes. About allocationof the responsibilities, the report says that while the waste generators should bear overall
responsibility for management of the wastes, it is more appropriate to put the legal
responsibility to ensure safety on the operator of radioactive waste disposal facility when it
operates centralized facilities. And it also says that it is important the waste generator shouldmake every support for the operator of the centralized waste disposal facilities.
According to the basic concept mentioned above, in Japan, licensees of reactor facilities orother facilities are responsible for the safety of in-house management of the radioactive
wastes generated in their facilities, while a disposal operator is responsible for the safety of
waste management once the wastes are carried into the waste disposal facility. The Reactor
Regulation Law regulates in-house management of spent fuel and radioactive wastes andprovides for the measures to be taken by nuclear operators in transporting spent fuel ofradioactive wastes outside the facilities. Thus the Reactor Regulation Law, while defining thecompetent minister responsible for safety regulation, provides for a system to consistently
ensure the safety in each step of generation of spent fuel and radioactive wastes, on-site
treatment and storage, transportation to disposal facility and disposal by disposal operators.
E2.3

The NSC’s Audit on Safety Review of License

The NSC decided “Basic Guides for Safety Review for Radioactive Waste Burial Facility” inMarch 1998 and amended it in March 2001, and, based on the decision, audited the safety
review conducted by the regulatory body on radioactive waste disposal activity of JNFL.
The NSC, in preparation for license application for the Category 2 waste disposal(intermediate depth disposal, pit disposal, trench disposal) of radioactive solid waste,
decided “Upper Bounds of Radioactivity Concentration for Burial of Low-Level Radioactive
Solid Waste” in May 2007, published interim report on “Basic Concept of Safety Regulation
on Low-Level Radioactive Waste Burial” in July 2007, and started study to amend “Basic
Guides for Safety Review for Radioactive Waste Burial Facility” of the category 2 waste
disposal in November 2007.

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Planning

Act on Final Disposal ofSpecific
Radioactive
Wastes・Final Disposal Program
・Implementation Plan

Implementing Entity

Specific
Radioactive
Waste Final Disposal Act
・Reserve funds

Act on Final Disposal ofSpecific
Radioactive
Wastes・Nuclear Waste
Management
Organization ofJapan

siting

Activity

FinancingHigh Level Radioactive Wastes

Act on Final Disposal ofSpecific
Radioactive
Wastes・Selection of Preliminary
Investigation Areas etc.

Low Level Radioactive
WastesAct for Deposit and Administration of Reserve Funds
for Reprocessing of Spent Fuel from Nuclear Power
Generation

Ensuring Safety
Emergency
Preparedness

Regulation

Law for Regulation of Nuclear Source Material, Nuclear Fuel Material and Nuclear
Reactors
・Regulation of disposal

Figure E2-1

Enforcement Ordinance for the Law on the Regulation of Nuclear Source Material,
Nuclear Fuel Material and Nuclear Reactors
Rules for Category 1
Waste Disposal of
Nuclear Fuel Materials
or Materials
Contaminated with
Nuclear Fuel Material

Rules for Waste
Storage of Nuclear
Fuel Materials orMaterials
Contaminated with
Nuclear Fuel Material

Rules for Category 2 Waste
Disposal of Nuclear Fuel
Materials or Materials
Contaminated with Nuclear
Fuel Material

Basic Law on General Emergency Preparedness
Special Law of Emergency Preparedness for Nuclear Disaster

Legal System for Safety Management of Radioactive Waste Related
to Nuclear Power Generation

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E3

Regulatory Body

Article 20
1. Each Contracting Party shall establish or designate a regulatory body entrusted with theimplementation of the legislative and regulatory framework referred to in Article 19, and provided
with adequate authority, competence and financial and human resources to fulfill its assigned
responsibilities.
2. Each Contracting Party, in accordance with its legislative and regulatory framework, shall take theappropriate steps to ensure the effective independence of the regulatory functions from otherfunctions where organizations are involved in both spent fuel or radioactive waste management
and in their regulation.

The regulatory bodies in Japan are responsible for reliable implementation of regulation
provided by the Reactor Regulation Law, the Radiation Hazard Prevention Law and otherrelevant laws. The structures and duties of the regulatory bodies are clearly specified ineach Establishment Acts and financed by the government budget.
The regulatory bodies share the responsibilities for nuclear safety regulation according to
the types of nuclear energy utilization. The Minister of METI regulates the safety in theutilization of nuclear energy as an energy source, the Minister of MEXT regulates the safety
in the utilization of radioisotopes excluding medicines and in the utilization of nuclear energy
for science and technology, and the Minister of MHLW regulates the safety of the activities inmedical facilities.
The subordinate agency or bureau of each ministry takes charge of the practicalimplementation of safety regulation: NISA of the METI; the Science and Technology Policy
Bureau of the MEXT; the Pharmaceutical and Food Safety Bureau (hereinafter it is called
PFSB) and the Health Policy Bureau of the MHLW.
The NSC, whose members are appointed by the Prime Minister with the consent of the Diet,
audits the activities of regulatory bodies, and establishes fundamental policy on the safety
regulation, coordinating activities among regulatory bodies.
E3.1

Regulatory Bodies

1.
Nuclear and Industrial Safety Agency (NISA), METINISA administrates the safety regulations for nuclear installations related to the utilizationof nuclear energy. Specifically, NISA, entrusted by the Minister of METI, administers
following duties under the competence of the Minister of METI.
The Minister of METI is responsible for ensuring the safety of nuclear power facilities andnuclear fuel cycle facilities. The Minster has the authority to grant the license forestablishing such nuclear facilities and, for that purpose, examines that the location,
structures and systems of the proposed facility do not impair the prevention of hazards.
The Minister has also the authority to revoke the license, when a licensee violates theReactor Regulation Law.
The Minister of METI establishes the ordinances that provide for the operational safety,
measures to be taken for protection of specific nuclear fuel materials, the Operational
Safety Program, measures in emergency, etc. for the safety regulation of nuclear fuelmaterial processing and fabrication, establishment and operation of nuclear reactors,
storage of spent fuel, reprocessing of spent fuel, storage of radioactive wastes anddisposal of radioactive wastes. The Minister approves the design and construction
methods of facility, conducts inspection, approves the Operational Safety Program,approves decommissioning program of nuclear facility, collects reports from licensees
and carries out on-the-spot inspection when necessary.
The Minister of METI has the competence to revoke or suspend a license, to ordermeasures for operational safety, to dismiss a Chief Engineer of Reactors, to ordermeasures for decommissioning or emergency preparedness, etc.
The Minister of METI, and the Minister of MEXT, conducts examinations for Chief
Engineers of Reactors and issues the certificates. The Minister of METI has the authority
40Legal and Regulatory Systems

also to order to return such certificates in a case of violation of the law by the Chief
Engineers.
NISA has 11 divisions dedicated to the administration of the safety regulation of nuclear
installations. They are Policy Planning and Coordination Division, Nuclear Safety Public
Relations and Training Division, Nuclear Safety Regulatory Standard Division, Nuclear
Safety Special Investigation Division, Nuclear Power Licensing Division, Nuclear PowerInspection Division, Nuclear Fuel Transport and Storage Regulation Division, Nuclear
Fuel Cycle Regulation Division, Radioactive Waste Regulation Division, Nuclear
Emergency Preparedness Division and Electric Power Safety Division. The assigned
duties of those divisions are provided in Fig. E3-1.
Nuclear Safety Inspectors are assigned to each site of the nuclear installations. Fig. E3-2
shows the locations of the Nuclear Safety Inspectors Offices.
NISA has a total of approximately 350 staff engaged in the nuclear safety regulation, outof which 100 staff members are Nuclear Safety Inspectors and Senior Specialists for
Nuclear Emergency stationed at nuclear installations.
The Nuclear and Industrial Safety Subcommittee under the Advisory Committee for
Natural Resources and Energy was established as an advisory council to NISA, that
proposes policies on nuclear safety and safety of electric power. The members of thesubcommittees are assigned based on their expertise and experience from the fields ofnuclear and thermal-hydraulic design, nuclear fuel design, system design, equipment
design, seismic design, material strength, radiation control, meteorology, geology, soil
etc.
"What challenges exist in the future in order to assure safety in nuclear power generationand safety in the electric power system operation, while under rapid social andeconomical change" were entrusted to the subcommittee to be discussed. The
subcommittee and other subcommittees have deliberated on what nuclear safety
regulation systems should be, and the results were reported to NISA.
NISA, when necessary, asks for opinion from experts of the subcommittee, etc. The
Nuclear Fuel Cycle Safety Subcommittee and the Radioactive Waste Safety
Subcommittee under the Advisory Committee for Natural Resources and Energy areadvisory councils to NISA in the area of spent fuel management and radioactive waste
management. (See Table E3-2)
NISA provides a strong commitment to its mission, scientific and reasonable judgments,
transparency, neutrality and fairness as the code of conduct for their activities. In thiscontext, the Policy Planning and Coordination Division watches and assesses theperformance of other divisions of NISA in discharging their duties, and take timely
remedial actions after consulting with the senior managements. In order to improve thequality of regulatory activities, the development of the NISA Work Management Systemstarted in fiscal year 2006 and implemented from fiscal year 2007. According to the NISAWork Management System, NISA’s goals in the medium term and tasks in fiscal year
2008 were released in July, 2008
In addition, NISA makes a continuous effort to maintain the high quality of regulation
through education and training of the personnel, international activities and the hearing ofadvice from experts e.g. members of the Nuclear and Industrial Safety Subcommittee.
September 2001, NISA started information disclosure activity systematically integrating itwith the regulatory work process, and introduced public relations management program(RM) as a new effort, which makes feedback from outside into quality enhancement of theregulatory activities. The objectives of the RM are to improve stakeholders’ recognition
and understanding of NISA’s daily activities, to make appropriate response to thestakeholders’ concerns, to activate discussion of a better regulatory system, to improve
emergency preparedness and to activate internal communication.
In April 2004, NISA allocated a new budget in order to enhance further activities to hearfrom the public, and at same time, established the Nuclear Safety Public Relations andTraining Division formed in NISA, and appointed the Resident Public Relations Officers.
The main items of NISA’s information disclosure activity are as follows, (i) NISA
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executive’s visit to the local government, (ii) publication of newsletters and mailmagazines, (iii) explanation of policies and activities of the nuclear safety regulation to the
public, (public meeting on the clearance system and amendment of the Reactor
Regulation Law, Pu-thermal symposium, public meeting on seismic safety, "one-day
seminars to introduce NISA" were held in major cities and site municipalities), (iv) making
dialogue with local residents, (v) activities to hear from the public at the Nuclear Safety
Inspector's Offices, (vi) implementation of risk-communication training course for
local-government personnel etc., (vii) utilization of local CATV, website, etc. tocommunicate with the local residents, where NISA’s executives introduce its main policies
such as the new inspection system or the locally stationed Nuclear Safety Inspectors
Offices.
Also, NISA opens the Nuclear Energy Library in JNES, where the public can accessdocuments for the reactor establishment license, reports of incidents and accidents ofnuclear installations and, books and booklets on energy and nuclear power generation.
2.
Japan Nuclear Energy Safety Organization (JNES)In October 2003, JNES was established as a supporting organization for NISA in
ensuring safety in utilization of nuclear energy, and has 460 officers and staffs. The
missions of JNES are
to implement their duties effectively and rationallyto contribute to the enhancement of nuclear safety regulation,
to deliver safety information to the public by utilizing its expertise andto foster public confidence in the safety of nuclear energy.
JNES implements the following activities to accomplish the above missions:Inspection of nuclear facilities, reactor facilities, etc.;
Safety analysis and evaluation of design of nuclear facilities and reactor facilities;
Activities to prevent occurrence of nuclear emergencies, to prevent progression of a
nuclear emergency, and to recover from the nuclear disaster;
Investigation, testing, research, and training concerning ensuring safety in utilizationof nuclear power as energy; andCollection, analysis and transmission of information relating to ensure nuclear safety.
The framework for JNES to implement activities and the relation with NISA are as follows:
NISA develops a plan on each activity based on the regulatory needs, and defines
the medium-term objective in accordance with the Law of the General Rules for
Incorporated Administrative Agency, and the Minister of METI assign it to JNES.
JNES prepares a medium-term program to accomplish the medium-term objective,
submits the program to the Minister of METI, obtains approval, prepares annual plan(fiscal year) in accordance with the medium-term program, notifies the plan to theminister of METI and implements it.
The budget for JNES consists of government budget and commission of inspections.
3.

Science and Technology Policy Bureau (STPB), MEXT
The safety regulation concerning the activities on the nuclear utilization from a scientificand technological aspect and utilization of radioisotopes and radiation generating
apparatus (excluding medicines, etc.) is regulated by the Minister of MEXT as thecompetent minister, and is administered by the Science and Technology Policy Bureau(STPB). With regard to the licensing of establishment of test and research reactor
facilities and use of nuclear fuel materials under the Reactor Regulation Law and theradioisotope waste management which carried out as business under the Radiation
Hazards Prevention Law the Minister of MEXT has the authority to permit the respective
licenses, after conducting an examination of the site, structure and equipment from thestandpoint of nuclear disaster prevention. The Minister also has the authority to revoke
the licenses under certain circumstances, such as the violation of applicable laws andregulations by the license holder.
STPB contains the Nuclear Safety Division, which has a further four offices. The assigned
42Legal and Regulatory Systems

role of the divisions and offices are listed in Table E3-1. In addition, MEXT deploys aresident inspector for the safety management of nuclear facility to each site where theresearch reactor facility or the major fuel material use facility. Their missions are to
conduct examinations and inspections stipulated in the Reactor Regulation Law to
confirm the compliance with the Operational Safety Program and surveillance of reactor
operation management, investigation of implementation of education and training,
periodic licensee’s inspection and to respond to an emergency situation. The locations ofoffices of Nuclear Safety Inspectors are illustrated in Figure E.3-2. As to the educationand training programs for the staff members in charge of nuclear safety regulations are
conducted in order to enhance competency of regulatory personnel.
The Radiation Council is established within MEXT under “the Law for TechnicalStandards of Radiation Hazards Prevention”. The mandate of the Radiation Council is toclarify basic policy on establishing technical standards for prevention of radiation hazards
and to maintain consistency among related technical standards. The basic policy is thatthe radiation doses of occupational personnel and the general public shall be less thanthe dose that may cause radiation hazards. The council report to the consultation fromthe heads of the administrative organization concerning technical standards forprevention of radiation hazards, and state its opinion to the heads of administrative
organization to keep consistency among technical standards. The Radiation Council
consists of a maximum of 20 members, and the Basic Committee composed of experts
from different fields is established under the council.
The STPB holds Advisory Committee on Nuclear Safety Regulation, etc. with an objective
to contribute to the transparent and efficient administration of nuclear safety by MEXT.
Under this committee, sub-committees are held, as listed in Table E3-3, in order to study
safety regulations for research reactor, and radiation protection, etc.
As to the activities of the STPB related to the safety regulation for the nuclear facility,
Japan Nuclear Energy Safety Organization is designated as an organization for welding
inspections of the nuclear facility under the Reactor Regulation Law. Nuclear Safety
Technology Center is registered as an organization for periodic inspections of the
facilities for services of radioisotope waste management under the Radiation Hazards
Prevention Law.
4.
Ministry of Health, Labor and Welfare (MHLW)The MHLW administer the safety regulations for radioactive medicines, the regulations forthe protection against clinical radiation, and handling, etc. of radiopharmaceutical andmedical equipment at medical institutions.
The PFSB regulates the production of radioactive medicines based on the Regulationsfor Structures and Equipments for Pharmacies, etc. and the Regulations for
Manufacturing and Handling of Radio Pharmaceuticals under the Pharmaceutical Affairs
Law. The Independent Administrative Agency, Pharmaceuticals and Medical Devices
Agency, conducts periodic inspections of manufacturing plants that produce radioactive
medicines. And, the PFSB also regulates disposal of radioactive pharmaceuticals.
The Compliance and Narcotics Division regulates preventive measures against theradiation hazard caused by, and the standards for the structure and equipment of, an
X-ray device, based on the Rules for the enforcement of the Medical Care Law, etc. This
enforcement rule also provides standards for the storage, and disposal, etc. of clinicalradioisotopes, etc.
E3.2

Ensuring of effective independence of regulatory functions from other functions

Regulatory bodies have clearly defined authorities and competences on safety regulation
based on the Reactor Regulation Law. Although each of the regulatory bodies isestablished within a ministry which has departments promoting utilization of nuclear energy
or radioisotopes, etc., the competence of each regulatory body is clearly separated fromthat of promotional department by its establishment law and order. Each regulatory body
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administers safety regulation independently, and the NSC audits activity of each regulatory
body. (See Fig. E3-3)
NISA is established as “special organization” of ANRE (Agency for Natural Resources andEnergy) by the METI Establishment Law. The responsibility is clearly defined as “Agency toensure the safety in the utilization of nuclear energy” by the law.
NISA have clearly defined authorities and competences on safety regulation based on theReactor Regulation Law. Regulatory activities based on the Law such as licensing,approval of construction plan, inspection for facilities or operation safety, are conducted by
the name of Minister of METI. NISA independently makes decision or proposes of decision
to the Minister without any interference of ANRE.
The regulatory activities of NISA are supervised and audited by the NSC that is theCommission established by “the AEC and NSC Establishment Law”. The commissioners of
the NSC are designated by the Prime Minister with the consent of Diet.
NISA have to consult with the NSC before granting the license of nuclear business facility
and activities based on the Reactor Regulation Law. And NISA have to report to the NSC of
the regulatory activities such as approval of construction plan and the inspections ofoperational safety activities afterwards. The NSC has the authority to makerecommendation through Prime Minister if it deems necessary.
With these arrangements, the effective independence of NISA as a regulatory body has
been ensured.
The STPB of MEXT have clearly defined authorities and competences on safety regulation
based on the Reactor Regulation Law and the Radiation Hazards Prevention Law.
Regulatory activities based on these Laws such as licensing, approval of construction plan,inspection for facilities or operation safety, are conducted by the name of Minister of MEXT.
STPB, which is assigned to conduct these regulatory activities by the order for organizationof MEXT, independently makes decision or proposes of decision to the Minister without any
interference of promotion body.
Based on the AEC and NSC establishment Law, the NSC may require the head of eachadministrative organization to report matters necessary to accomplish the assigned
mission and make recommendation through Prime Minister if it deems necessary.
With these arrangements, the effective independence of STPB of MEXT as a regulatory
body has been ensured.

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Director-General
Vice Director-General for
Nuclear and Industrial Safety
Deputy Director-General for Nuclear Fuel Cycle
Deputy Director-General for Nuclear Power
Deputy Director-General for Nuclear Safety
Deputy Director-General for Industrial Safety and Nuclear Material Protection
Deputy Director-General for Safety Examination
Policy Planning and Coordination Division(the general affairs of NISA, personnel and staff, budget, international cooperation, etc.)
Nuclear Public Relations and Training Division(Public relations/hearing for nuclear safety, activity management of Nuclear Safety Inspectors andSenior Specialists for Nuclear Emergency

Nuclear Safety Regulatory Standard Division (Planning of basic system for technology)
Nuclear Safety Special Investigation Division(Management of allegation and litigation concerning nuclear safety)

Nuclear Power Licensing Division(Licensing for commercial reactors, approval of construction plans)

Nuclear Power Inspection Division(Inspection of commercial reactors, approval of safety regulations)

Nuclear Fuel Cycle Regulation Division(Safety regulations governing refining, processing, reprocessing facilities)

Nuclear Fuel Transport and Storage Regulation Division(Safety regulations governing nuclear fuel storage and transport of nuclear materials)

Radioactive Waste Regulation Division (Safety regulations for waste disposal andmanagement facilities and decommissioning of nuclear installations)

Nuclear Emergency Preparedness Division (Preventive measures for nuclear hazard,
response to failures and incidents at nuclear installations, physical protection for nuclear materials)
Electrical Power Safety Division(Safety of turbines and generators at nuclear power installations, and safety of electric power)

Industrial Safety Division(Safety of explosives, high-pressure gas, and petroleum industrial complexes)

Gas Safety Division (Safety of utility gas and heat supply)
Liquefied Petroleum Gas Safety Division (Safety of LPG)
Mine Safety Division (Safety of mines)

Fig. E3-1

Organization of Nuclear and Industrial Safety Agency

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1
2
3
4
5
6
7
8
9
10

11
12
13
14
15
16

Fig. E3-2

Name of Office
Tomari Nuclear Safety Inspectors Office
Higashidori Nuclear Safety Inspectors Office
Rokkasho Nuclear Safety Inspectors Office
Rokkasho Nuclear Safety Administration Office
Onagawa Nuclear Safety Inspectors Office
Fukushima-Daiichi Nuclear Safety Inspectors Office
Fukushima-Daini Nuclear Safety Inspectors Office
Kashiwazaki-Kariwa Nuclear Safety Inspectors Office
Tokai & Ooarai Nuclear Safety Inspectors Office
Ibaraki Nuclear Safety Administration Office
Kanagawakita Nuclear Safety Administration Office
Yokosuka Nuclear Safety Inspectors Office
Shika Nuclear Safety Inspectors Office
Hamaoka Nuclear Safety Inspectors Office
Tsuruga Nuclear Safety Inspectors Office
Mihama Nuclear Safety Inspectors Office
Ohi Nuclear Safety Inspectors Office
Takahama Nuclear Safety Inspectors OfficeOsaka Nuclear Safety Administration Office
Kumatori Nuclear Safety Inspectors Office
Kamisaibara Nuclear Safety Inspectors Office
Kamisaibara Nuclear Safety Administration Office
Shimane Nuclear Safety Inspectors Office
Ikata Nuclear Safety Inspectors Office
Genkai Nuclear Safety Inspectors OfficeSendai Nuclear Safety Inspectors OfficeCompetent ministry
METI
METI
METI
MEXT
METI
METI
METI
METI
METI
MEXT
MEXT
METI
METI
METI
METI
METI
METI
METI
MEXT
METI
METI
MEXT
METI
METI
METI
METI

Nuclear Safety Inspectors Offices and Nuclear Safety Administration Offices

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Ministry of Economy, Tradeand Industry
Agency for Natural Resources
and Energy
Nuclear and Industrial Safety
AgencyReporting

Regulation

Cabinet Office
Atomic Energy
Commission

Licensees

Audit

Nuclear Safety
Commission
Audit

Reporting

Ministry of Education,
Culture, Sports, Science andTechnology
Research and Development
Bureau and Research
Promotion Bureau

Reporting

Science and Technology
Policy Bureau

Regulation

Reporting

Licensees

Fig. E3-3

Relation among nuclear safety regulatory bodies in subsequent stage
regulation

The “Agency for Natural Resources and Energy (ANRE)”, which is an organization to promote
the utilization of nuclear energy as energy source, belongs to the Ministry of Economy, Trade andIndustry (METI). However, as for nuclear safety regulation, ANRE and the NISA are completely
separated to ensure the effective independence of regulatory functions. The “Research andDevelopment Bureau” and “Research Promotion Bureau”, which are organizations to promoteutilization of nuclear energy, belongs to the Ministry of Education, Culture, Sports, Science andTechnology (MEXT). However, as for nuclear safety regulation, the Science and Technology
Policy Bureau and the Research and Development Bureau / Research Promotion Bureau arecompletely separated. The Nuclear Safety Commission established in the Cabinet Office isindependent of the METI and the MEXT, requires the NISA and the Science and Technology
Policy Bureau of the MEXT to report their regulatory activities and audits those regulatory bodies.

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Table E3-1
1.

Organization of MEXT and MHLW

Ministry of Education, Culture, Sports, Science and Technology; Science andTechnology Policy Bureau

Nuclear Safety Division

General management of Nuclear Safety Division

Nuclear Safety Division
Office of Nuclear Regulation

Regulations for research reactor facility and fuel material use facility

Nuclear Safety Division
Office of Radiation Regulation

Regulations for radioisotopes, etc.

Nuclear Safety Division Office ofEmergency Planning and Environmental
Radioactivity

Nuclear emergency measures
Environmental radiation measures

Safeguards Office

Implementation of Safeguards

2.

Ministry of Health, Labor and Welfare

Pharmaceutical and Food Safety
Bureau, General Affairs Division
Pharmaceutical and Food Safety
Bureau, Compliance and Narcotics
Division
Health Policy Bureau, Guidance ofMedical Service Division
Health Policy Bureau, Economic Affairs
Division

Regulations concerning the entrustment of disposal ofradioactive medicines, etc.
Regulations for Manufacturing, etc. of Radioactive Medicines
Provision of preventive measures against the radiation hazard
and regulations for the structure and equipment, etc
Regulations for medical equipment etc. concerning
radioisotope medicines at medical institutions

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Table E3-2

The Organization of the Nuclear and Industrial Safety Subcommittee

Basic Safety Policy Subcommittee.

- General matters securing safety- Technical matters on commercial power reactors andNuclear Reactor Safety Subcommittee.
power reactors at the stage of research and development- Fabrication and reprocessing of nuclear fuel, storage of
Nuclear Fuel Cycle Safety
spent fuel, transportation of nuclear fuel material, and the
Subcommittee.
technical standards
Decommissioning Safety Subcommittee. - Decommissioning of nuclear installations
Radioactive Wastes Safety- Securing safety of disposal and storage of radioactive
Subcommittee.
wastesSeismic and Structural Design- Technical matters on seismic safety and structural
Subcommittee.
integrity of nuclear installations- Measures for incidents and failure, and general crisis
Nuclear Emergency Preparedness
management for emergencies of nuclear installations andSubcommittee.
physical protection of nuclear material- INES Evaluation on incidents and accidents of nuclear
INES Evaluation Subcommittee.
installations
Subcommittee. for the Convention on- Matters related to the Convention on Nuclear Safety andNuclear Safety
international standards on nuclear safety
Electrical Power Safety Subcommittee. - Securing safety of electrical power- Matters concerning inspection system of nuclear power
Study Group on the Way of Inspection
generation facilities and nuclear fuel cycle facilities
Subcommittee. for the Joint Convention- Matters etc. related to the Convention on Joint
on Radioactive Waste and Spent Fuel
Convention Radioactive Waste and Spent Fuel Safety
SafetySubcommittee. for the Institution of- Study of the legal system for the Institution of Nuclear
Nuclear Safety Regulation
Safety Regulation
Subcommittee. for fitness-for-service- Study of the Verification of validity in the check methods
assessment etc. of nuclear power
for nuclear power plantsystemStudy Group on Countermeasures for- Clarification of basic standards, guides etc. for aging
Aging- Study of Risk-Information usage to Nuclear Safety
Study Group on Use of Risk Information
Regulations
Nuclear Safety Infrastructure- Study of safety infrastructure,
Subcommittee- Study of safety infrastructure on codes and standards

Table E3-3

Subordinate Organization of Advisory Committee on Nuclear Safety
Regulation, etc.

Subcommittee. on Safety Regulation for
Research Reactors, etc.
Subcommittee. on Safety Regulation for
Radiation Protection.
Subcommittee on Nuclear Emergency
Preparedness
Subcommittee on Evaluation ofRadioactivity in Environment

Directions for safety regulation of research reactors,
nuclear fuel materials, etc.
Directions for safety regulation of radiation protection.
Comprehensive assessment of institutional andbusiness-operational aspects of the Act on Special
Measures for Nuclear Emergency Preparedness
Assessment of the Results of Survey on Radioactivity in
Environment and of the Contents of the Survey

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Section F
F1Other General Safety Provisions

Responsibility of the license holder

Article 21
1. Each Contracting Party shall ensure that prime responsibility for the safety of spent fuel orradioactive waste management rests with the holder of the relevant license and shall take theappropriate steps to ensure that each such license holder meets its responsibility.
2. If there is no such license holder or other responsible party, the responsibility rests with theContracting Party which has jurisdiction over the spent fuel or over the radioactive waste

F1.1

Steps to ensure that each license holder meets its responsibility

The prime responsibility for the safety of nuclear facility and activities of spent fuel orradioactive waste management rests with the license holder of the nuclear facility. That is,
the license holder is responsible for adopting necessary measures to fully meet theregulatory requirements stipulated either in the Law for Regulation of Nuclear Source
Material, Nuclear Fuel Material and Nuclear Reactors (Reactor Regulation Law), theElectricity Utilities Industry Law or the Law concerning Prevention from Radiation Hazards
due to Radioisotopes etc. (Radiation Hazards Prevention Law), etc. at all of the stages ofplanning, establishment, operation, maintenance and decommissioning of the nuclear facility.
In addition to meeting with regulatory requirements, the license holder is required to makeefforts for improving safety and reliability of the nuclear facility, through implementing
education and training programs of personnel, preparing operation manuals.
In accordance with the Reactor Regulation Law, the regulatory body conducts inspections toconfirm the compliance of the performance of facilities and systems with the legal technicalstandards and to confirm the observance of Operational Safety Program and Regulations by
an operator. The regulatory body also can conduct on-the-spot inspection when necessary,and can impose administrative penalties including revocation of license if an operator
violates laws and regulations.
For the radioisotope waste management facilities subject to the Radiation Hazards
Prevention Law, the regulatory body conducts the Periodic Inspection to confirm nuclear
facility’s compliance with the technical standards, and the Radiation Inspector conducts theOn-the-spot Inspection of a use facility as necessary. In case the operator does not observe
provisions of the Radiation Hazards Prevention Law, regulatory body has authority to revoke
the license or order shutdown of the operation.
In addition, on the basis of the Reactor Regulation Law and the Electricity Utilities Industry
Law, the license holder shall cooperate inquiry by the Nuclear Safety Commission (NSC)
when the NSC reconfirms the adequacy of the activities of the regulatory body.
F1.2

Steps to ensure that if there is no license holder or other responsible party exists

In Japan, there may be a case where no license holder exists when the license for a facility
and activities under the Reactor Regulation Law is revoked or an operator is dissolved. Sucha case is deemed to be a case where the facility and activity is taken over under the Reactor
Regulation Law and the legal entity surviving the merger or a legal entity incorporated upon
the merger assumes the legal status of the operator after receiving approval for the merger.
In the case of succession, the successor assumes the legal status of the operator.
In the case of revocation of the license or in the case of absence of succession following
dissolution, the license holder whose license was revoked or the liquidator or trustee inbankruptcy, respectively, shall be responsible for record keeping, taking physical protectionof nuclear materials and observing the Operational Safety Program, and shall develop a
decommissioning program, have it approved by the competent minister, carry out
decommissioning and obtain confirmation of the Minister of Economy, Trade and Industry forthe completion of decommissioning.
Under the Radiation Hazards Prevention Law, provisions similar to the Reactor Regulation
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Other General Safety Provisions

Law are applied to the case of succession following dissolution and to the case of absenceof succession. In the case of no succession of the business, a liquidating partner shall takeappropriate measures, such as removal of contamination by radioisotopes, etc, on cessationof the business.
As described above, it is ensured in Japan to avoid a case where no license holder exists
due to succession of business, and the business is closed if nobody succeeds the business.
A license holder of radioisotope waste management facility issued under to the Medical Care
Law etc. is allowed to close its operation only after it completes necessary measures for the
closure of facility and activities stipulated by the law.

F2
Human and financial resources
Article 22
Each Contracting Party shall take the appropriate steps to ensure that:(i)
Qualified staff are available as needed for safety-related activities during the operating
lifetime of a spent fuel and a radioactive waste management facility;(ii)
Adequate financial resources are available to support the safety of facilities for spent
fuel and radioactive waste management during their operating lifetime and fordecommissioning;(iii)
Financial provision is made which will enable the appropriate institutional controls andmonitoring arrangements to be continued for the period deemed necessary following
the closure of a disposal facility.
F2.1

Measures for maintain human resources1.
Human resources
The regulatory body confirms in the review for the license application that the applicant has
technical competence including human resources sufficient for installing the facility andappropriate operation. The applicant has to verify that its technical competence is sufficientfor its activity. For confirming the technical competence, objective and reasonable
examination is carried out by applying the “Examination Guide for Technical Competenceof License Holders of Nuclear Power” issued by the NSC in May, 2004. This Regulatory
Guide defines the technical competence as organizational management capability toappropriately operate the activity with ensuring safety including knowledge, technology andexpertise, and provides fundamental requirements to be met by the license applicant.
As a prerequisite to operate the activities, the Reactor Regulation Law requires licensees
to appoint the following chief engineers from qualified employees for safety supervision ofoperation; Chief Reactor Engineer for reactor operation, Chief Engineer for Nuclear Fuel
Material Handling in fabrication or reprocessing activity, Chief Engineer for Spent FuelHandling in spent fuel storage facility, and Chief Engineer for Radioactive Waste Handlingfor handling nuclear fuel materials and other radioactive wastes in disposal facility.
Furthermore, regarding education and training, the Reactor Regulation Law requires
operators to provide, in the Operational Safety Program, for the policy, the implementing
program and contents of operational safety education. The regulatory body confirms thecompliance with these requirements through the Operational Safety Inspection.
Operator of a business licensed under the Radiation Hazards Prevention Law has to selectand appoint a Chief Engineer for Radiation Protection before commencing the business.
The "Rule for Preventing Radiation Hazards" of an operator provides for the duties andorganization for the persons engaged in the safety control of radioisotopes and works that
handle radioisotopes, as well as the matters related to the education and training
necessary for preventing radiation hazards. Thus necessary technical competence isensured.
2.
Activities to ensure human resource infrastructure in Japan
In Japan, both regulatory body and nuclear industry are striving to ensure human
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resources as a part of activities for ensuring future nuclear safety infrastructure.
Nuclear and Industrial Safety Agency (NISA) is preparing a strategy to develop and secure
human resources in the area of nuclear energy at the Nuclear Safety Infrastructure
Subcommittee established in 2006 under the Nuclear and Industrial Safety Subcommitteeof the Advisory Committee for Natural Resources and Energy. This Subcommittee isworking for the development and securing of human resources starting with theidentification of technological areas that need human resources in near future (for example,
specific technology areas and basic technology areas), considering the current situation of
external experts supporting the regulatory body.
In parallel with the above activities, the Ministry of Education, Culture, Sports, Science andTechnology (MEXT) and the Ministry of Economy, Trade and Industry (METI) are
implementing a nuclear human resources development program since 2007 by focusing
on: 1) support for educational activities such as enhancement of basic nuclear education
and research, reinforcement of internship and improvement of core nuclear curriculum, and2) support for research activities in basic nuclear technologies from the view point of
human resource development for continuous research activities.
(1) Training of Experts in MEXT and NISA
Staff members, who are in charge of nuclear regulation in MEXT and NISA, are the
Senior Specialist for Nuclear Emergency, the Nuclear Safety Inspector, the Nuclear
Facility Inspector, the Electric Facilities Inspector, the Safety Examiner and the Senior
Specialist for Fire Protection.
A Senior Specialist for Nuclear Emergency is stationed at each nuclear installation,
guides and advises the licensees in preparing its Plan for Emergency Preparedness, andconducts duties necessary to prevent progression of nuclear emergency should it occur.
A Nuclear Safety Inspector is stationed at each nuclear installation, conducts the Nuclear
Safety Inspection to confirm licensee’s compliance with the Operational Safety Program,conduct investigation, communicate with the staff of nuclear installation at incident if theyoccur, and supervises operation management of a nuclear installation.
A Nuclear Facility Inspector conducts inspection activities, such as the Pre-Service
Inspection and the Periodic Inspection of a nuclear installation.
An Electric Facilities Inspector is dispatched from NISA head office, and conducts
inspection activities, such as the Pre-Service Inspection of Electric Facilities, the Fuel
Assembly Inspection, and the Periodic Inspection of Electric Facilities.
Safety Examiners conduct the Safety Examination of a nuclear installation.
A Senior Specialist for Fire Protection is stationed at each nuclear installation, guides andadvises the licensees in fire protection measures in collaboration with local fire protection
agency.
A staff of Nuclear Regulatory is required to have expertise in nuclear technology. The
system of long term and multistage education and training programs necessary for
improvement of his/her expertise is developed, taking account of his/her experience andof the nature of the facility to which he/she is assigned. In order to increase effectivenessof the training, the contents of the training being implemented are also reviewed andimproved suitably. The capability of the personnel engaged in securing safety of nuclear
installations is improved through these training. Summary of training for nuclear safety
regulation is shown in Fig. F2-1. Besides developing professional human resources asmentioned above, NISA recruits professional human resources for nuclear safety fromindustries or other ministries.
NISA has appointed six Special Inspection Instructors in December 2003. They advise
inspectors for the Nuclear Safety Inspection, the Periodic Inspection, etc. in each power
station, instruct them to equalize the levels of inspections, and they collect opinions andproposals from inspectors and licensees for the purpose of opinion exchanges at the site.
In the future, the training curriculum for the staff to acquire the required regulatory skills
effectively will be established, and a training management system that keeps andmanages every personnel's training status and offers appropriate training at suitable time52

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will be developed. Moreover, measures, such as preparation of training facilities forpractical inspection skills etc. through with mock-up will be taken.
(2) Training of Experts in JNESThe Electricity Utilities Industry Law or the Reactor Regulation Law stipulates that
activities such as Electric Facilities Inspection, the Nuclear Facility Inspection, theWelding Inspection, the Audit of Licensee's Periodic Check System, the Audit ofLicensee’s Welding Check System, the Safety Confirmation of Disposal Facility, theSafety Confirmation of Radioactive Waste Package, the Confirmation of Transportation
Packaging, and the Confirmation of Transportation Method shall be conducted by Japan
Nuclear Energy Safety Organization (JNES)’s qualified personnel under the instruction of
NISA. JNES prepares various training courses for its staff members to get appropriatequalification in their respective activities. President of JNES assigns inspectors fromthose qualified persons. JNES develops training courses for its personnel, puttingemphasis on inspection activities. JNES also is recommending its staff to obtain relevant
official qualification, and to participate outside lectures and academic seminars in order tobrush up the capability for inspection and safety review and knowledge in his specialty.
(3) Efforts by Nuclear Industry
The nuclear industry has concerns in the succession of expertise and experiences, andthe maintaining sufficient number of skilled workers. In Japan, the first generation experts
are in the age of retirement. Each organization in the industry has made various efforts
including revitalization of research and development activity, practical use of IT
technology, etc. The Japan Atomic Industrial Forum, Inc. established the "Subcommittee
for Human Resources" consisting of senior managers in the industry and experts fromoutside, and studied on human resources in the future.
The subcommittee has made the proposals for training and career development ofexperts in June 2003; establishment of an industry’s qualification system of nuclear
maintenance and repair technicians, simplification of organizations, establishment of anengineering center to share training facilities and resources of maintenance and repair
technicians, establishment of a nuclear educational network system to share common
educational infrastructure to ensure resources for future.
Main activities currently performed for human resource training and succession ofexpertise in the nuclear industry are shown in the following;a. Training of on-site technicians and succession of skills
In the area where the nuclear installation is established, the training for qualification,
training of practical skills for maintenance and repair, OJT training at the power station,etc. are implemented beyond the frame of an individual operator.
b. Study on qualification and certification system for private sectors
For the purposes of improved skills of maintenance-and-repair workers, appropriate
staffing, and ensuring future human-resources, the common standards and qualification/ certification procedures for objective evaluation of skill level are being studied. Thesestandards etc. will be made to harmonize with the licensee's in-house qualification
system.
c. Acquisition of advanced expertise
Licensees’ engineers are sent to the graduate school in nuclear engineering to acquire
advanced expertise.
Moreover, the Japan Atomic Industrial Forum, Inc., consisting of enterprises related to the
nuclear power and developing industry-wide policies, has investigated and studied thecurrent status of universities, graduate schools and research institutes, in order toimprove the effectiveness of "the nuclear human resource training program. The study
will be continued.
(4) Efforts by University and Research Institutes
The Tokyo University established a graduate school, in April 2005, consisting of three
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courses of the “Nuclear Reactor Specialist Course”, the “Nuclear Fuel Specialist Course”,
and the “Administrator Course”.
Since 1958, then JAERI, now JAEA has been operating training courses for engineers
and technicians in radioisotope, radiation and nuclear technologies. Recently, JAEA
started a course for nuclear emergency preparedness in close cooperation with national
and local governments.
(5)

Establishment of Professional Engineers System for Nuclear and Radiation
Technologies
The MEXT who has jurisdiction over the Professional Engineers System established anuclear and radiation technology department for professional engineers in 2004 fiscal
year. The qualification examination has been implemented every year, and a total of 248
people were qualified as the Professional Engineer by the end of 2007 fiscal year. The
purposes of the Professional Engineers System are such to enhance nuclear engineering
capabilities, to utilize the capability in the nuclear safety regulation, to strengthen thesafety management system in each corporation.

F2.2

Financial Resources and Financial Rules

In permission of establishment license of a nuclear facility, except for nuclear fuel material
use facility, the regulatory body, in accordance with the Reactor Regulation Law, confirmsthat the applicant for the license possesses necessary financial basis. The applicant should
submit business plan that explains about the financial base of the business.
For the financial base of the decommissioning of nuclear installations, METI stipulated theMinisterial Order established under the Electricity Utilities Industry Law on the reserves fordecommissioning of nuclear power generation facilities. Based on the Ministerial Order,
Electric Utilities internally reserved the money for the decommissioning as the expense of
dismantling and removal of commercial power reactor facilities, and as the expense of theprocessing and disposal of the waste from decommissioning. The amount of reserve by theend of March 2007 is about 1,200 billion yen by 10 electric utilities.
In addition, the electric utilities are depositing money to be used for spent fuel reprocessing
from electricity sales, in a fund administered by an administrative agency, designated by the
Minister of Economy, Trade and Industry in accordance with the “Act for Deposit andAdministration of Funds for Reprocessing of Spent Fuel from Nuclear Power Generation”
enacted in May 2005. The total funds deposited by 10 electric utilities amount to about 1,300
billion yen at the end of March 2007.
In accordance with the Specific Radioactive Waste Final Disposal Act enacted in May 2000,
operators of power reactor facilities deposit funds for disposal of high level radioactive waste
to the Nuclear Waste Management Organization of Japan, the implementing body fordisposal, who entrusts management of the fund to the Radioactive Waste Management
Funding and Research Center. The Minister of METI, every year, notifies utilities of theamount of money to be deposited to the fund. The amount of deposit per vitrified package
was 40,413,000 yen in the year of 2007. The amount of money for construction of depositoryand disposal of about 40,000 vitrified packages of high level waste is estimated about 3
trillion yen. The amount of the money deposited to the Radioactive Waste Management
Funding and Research Center at the end of March 2007 was about 500 billion yen.
As for disposal of radioactive waste from Research, Medical and Industrial Facilities, agenerator of waste must pay for the disposal under the principle of the liability of generator,
as set forth in the Framework for Nuclear Energy Policy. The largest generator of the above
waste, JAEA started funding for disposal basing on the amendment of The Law for the
Independent Administrative Agency, Japan Atomic Energy Agency in May 2008. The amountof budget plan for fiscal year 2008 is about 4.3 billion yen.
Financial basis of a license holder of nuclear fuel material use is to be confirmed throughprocedures to approve the Operational Safety Program and the steps to be taken at the timeof decommissioning.
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Financial basis of the operator of radioisotope waste management facility licensed under the
Radiation Hazards Prevention Law (except for disposal business) is to be confirmed throughthe Periodical Inspection, obligation to maintain the facility in compliance with technicalstandards, implementation of education and training programs, notification of the Internal
Rules for Prevention of Radiation Hazards and the steps to be taken at the time ofdecommissioning.
Financial basis of disposal business is an essential condition of licensee.

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Training on nuclear safety regulation

Senior expert

Meister

Commercial powerreactor

Nuclear fuelcycle facility

R&D reactor

Cross-cutting training
Nuclear emergency
preparedness,
Crisis management- Risk communication training for managers- Public-relations training for the Nuclear Safety Inspectors- Quality Assurance training for managers

Nuclearpower
generation(BWR,
PWR), advanced- Inspection techniquefor inspectors- Senior Officer for Nuclear
Emergency, advanced- Senior Officer for Nuclear
Emergency, on-site training- Emergency preparedness,
emergency measures- Off-site center desk-top drill- Off-site center management- Off-site center functional grouptraining- Nuclear power
generation(FBR),
advanced
FBR
sodiumtechnical training

Special training course on QA of nuclear installation
Special training course on QA of nuclear installation, advanced

Participation to various training
programs for the fire protection of
nuclear installations
Senior Officer for Nuclear
Emergency, basic
Nuclear Regulatory Staff training

ExpertNuclear Safety Inspector basic training
Electric Structure
Inspector (nuclear
power) training

Nuclear Facility Inspector, basic

Nuclear power station risk assessment technology

Nuclear reactor safety design, basic
Overseas training

Beginners

Radiation safety
Basic Safety Regulation
Participation to the various basic courses by the Japan Atomic Energy Research Institute

Fig.F2-1 Summary of training for nuclear safety regulation

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F3

Quality assurance

Article 23
Each Contracting Party shall take the necessary steps to ensure that appropriate quality assurance
programmes concerning the safety of spent fuel and radioactive waste management are establishedand implemented.

By the amendment of the Reactor Regulation Law enacted in October 2003 and February
2004, it is provided that the licensee establishes quality assurance plan for the operationalsafety activities, and plan, do, check and improve the operational safety activities, andimprove quality assurance plan continually. And it is provided that the quality assurance
system should be included in the Operational Safety Program. NISA confirms operator’scompliance with it through the Nuclear Safety Inspection. The quality assurance activities at
the nuclear facilities except for research reactor facilities and fuel material use facilities aredescribed in the followings.
F3.1

Regulatory Requirements on QA of Nuclear Installations

NISA’s regulatory activities on major nuclear facilities, based on the Reactor Regulation Law
and the Electricity Utilities Industry Law, include licensing, approval of design andconstruction methods, pre-service inspection, periodical facility inspection, etc., are coveringfrom planning stage to operation stage.
By the Reactor Regulation Law, an licensee is required to integrate its quality assurance
program into the Operational Safety Program. NISA approves the Operational Safety
Program and confirms the operator’s compliance with it through the Nuclear Safety
Inspection.
This establishment of the quality assurance system provides a mechanism for systematic
implementation of the activities that influence the quality. By establishing the quality
assurance system, a licensee can have confidence in its safety activities, and by achieving
its accountability for the quality assurance, the licensee can obtain public understanding.
The key points of QA activities are; i) to involve top management, ii) to be based oninternational standards on QA (ISO9001:2000), iii) to improve them by Plan-Do-Check-Act
cycle, iv) to establish an in-house independent audit organization.
The Reactor Regulation Law stipulates that licensee's QA program should include i)organization managing QA activities, ii) plan for operational safety activities, iii)
implementation of operational safety activities, iv) evaluation of operational safety activities,
and v) improvement of operational safety activities.
Note) The term, operational safety activities, means activities necessary for maintenance ofmajor nuclear facilities, use of major nuclear facilities, and shipment, storage anddisposal of nuclear fuel materials or materials contaminated by nuclear fuel materials.

Licensees prepare their QA program of the nuclear facilities and implement them, according
to JEAC 4111-2003, "Rules of Quality Assurance for Safety of Nuclear Power Plants", which
was developed by the Japan Electric Association (JEA) in autumn of 2003 based on the
ISO9001:2000 to specify QA management, top management, management of resources,business plan, and evaluation/improvement in QA program for nuclear power plant. NISA
evaluated the standard and endorsed that it meets the regulatory requirements for nuclear
facilities other than test and research reactors and use facilities.
The features of JEAC4111-2003 are as follows.
i)
It is based on ISO 9001:2000, being modified for user-friendliness.
ii)
It takes account of IAEA Safety Standards for Quality Assurance 50-C/SG-Q (1996).
iii)
The definitions of some terms are different from ISO 9001:2000, based on legal
expression in national legislature.
iv)
Explanation is added on the terms, "product", "customer", and "quality", in therequirements of ISO 9000:2000.
Moreover, NISA is studying to clarify requirements of quality assurance during not only
operating stage but also construction stage in legislation.
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As for research reactors and nuclear fuel material use facility, MEXT confirms theimplementation of QA program described in Operational Safety Program based on theReactor Regulation Law through Operational Safety Inspection.
F3.2

Confirmation of Quality Assurance by NISA

1.
Examination of the Policy for QA at Licensing StageNISA confirms the applicant’s technical capability in the process of Safety Review. In
addition, NISA requests the applicant to submit the “Policy for Quality Assurance” attachedto the application format, and examines it.
2.
Examination of QA Program in Construction StageAt the construction stage of a commercial power reactor facility, NISA requests the license
holder to submit the “Description on Quality Assurance Program” as specified in the Rules
for the Electricity Utilities Industries Law, which describes license holder’s QA activities
during detailed design, manufacturing, installation and functional tests, and examines it.
Also, NISA confirms that license holder of nuclear power reactor oversees subcontractor'squality control, material control, etc. in appropriate procedures, in addition to its QA audit ofprimary contractor and primary contractor's own management of manufacturing process.
3.
Confirmation of QA Activities Throughout Operation StageNISA confirms QA activities of the license holder throughout service life of major nuclear
facilities by the Nuclear Safety Inspection. Furthermore, at the commercial power reactor
facility, NISA, at the Periodic Safety Management Review, examines adequacy ofoperator’s organization and methods for the Licensee's Periodic Inspection.

F4

Operational radiation protection

Article 24
1. Each Contracting Party shall take the appropriate steps to ensure that during the operating lifetimeof a spent fuel or radioactive waste management facility:(i)the radiation exposure of the workers and the public caused by the facility shall be kept as low
as reasonably achievable, economic and social factors being taken into account;(ii)
no individual shall be exposed, in normal situations, to radiation doses which exceed nationalprescriptions for dose limitation which have due regard to internationally endorsed standards
on radiation protection; and(iii)
measures are taken to prevent unplanned and uncontrolled releases of radioactive materials
into the environment.
2. Each Contracting Party shall take appropriate steps to ensure that discharges shall be limited:(1)
to keep exposure to radiation as low as reasonably achievable, economic and social factors
being taken into account; and(2)
so that no individual shall be exposed, in normal situations, to radiation doses which exceed
national prescriptions for dose limitation which have due regard to internationally endorsed
standards on radiation protection.
3. Each Contracting Party shall take appropriate steps to ensure that during the operating lifetime of aregulated nuclear facility, in the event that an unplanned or uncontrolled release of radioactive
materials into the environment occurs, appropriate corrective measures are implemented to control
the release and mitigate its effects.

In Japan, necessary steps are taken as described in F4.1 and F4.2 for (i) and (ii) of Item 1 and(i) and (ii) of Item 2 of Article 24 of the Convention, in F4.3 for (iii) of Item 1, and in F4.4 forItem 3 of the Article.
F4.1

Laws, Regulations and Requirements on Radiation Protection

The national standards for radiation protection at nuclear facilities are prescribed by the58

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Reactor Regulation Law, the Electric Utilities Industry Law, the Radiation Hazards
Prevention Law, Medical Care Law, etc. and related government ordinances, ministerial
ordinances, orders and notifications, and guidelines based on these laws. The
recommendations of the International Commission on Radiological Protection (ICRP) are
given due consideration and are incorporated into national legislation and regulation. The
Radiation Council coordinates these technical standards in the laws and regulations on
prevention of radiation hazards.
In examining application of a license for a nuclear facility, it is confirmed that the application
conforms to the Examination Guides established by the NSC as well as the legislation andtechnical standards. In these guides, operators are required to reduce the radiation dose
received by the public in the vicinity of the facility site as low as reasonably achievable.
Ministerial ordinances on the basis of the Reactor Regulation Law and the Radiation
Hazards Prevention Law prescribe area control for radiation protection, radiation control of
personnel engaged in radiation activities in controlled areas, measurement and surveillanceof radiation levels, monitoring of discharged radioactive materials, and maintenance ofradiation control equipment. The Notification for Dose Limits on the basis of each of theserules prescribes dose limits and concentration limits of radioactive materials in air andsurface activity density of the material contaminated by radioactive materials insidecontrolled area and dose limits and concentration limits of radioactive materials outside
peripheral monitoring area, and dose limits and concentration limits of radioactive materials
for personnel engaged in radiation work, and dose limits for personnel engaged inemergency activities. All these limits are shown quantitatively in the Notification for Dose
Limit.
In order to ensure compliance with these regulations, in the Reactor Regulation Law for
example, operators are required to prescribe in the Operational Safety Program, i) controlledareas, access controlled areas and peripheral monitoring area and access control to theseareas, ii) monitoring equipment at air ventilation and water discharge, iii) monitoring of dose,
dose equivalent, concentration of radioactive materials in the air and density of radioactive
materials on the surface of contaminated objects, and the decontamination, and iv)
maintenance of radiation monitoring equipment. And operators are also required to keep therecords regarding occupational exposure.
F4.2

National Requirements on Radiation Protection and the Implementation

1.
Allowable Dose Limits(1) Definition of Controlled Areas
The abovementioned rules and dose limit notifications define a controlled area as an area
where dose of external radiation may exceed 1.3mSv for a period of three months, theconcentration of radioactive material in the air, excluding natural background, may
exceed the limit specified in the notification, or the density of radioactive material on thesurface of contaminated objects may exceed the limit specified in the notification, andrequest operators to take necessary measures in the area.
(2) Allowable Dose Limits for Occupational Exposure
The abovementioned rules and dose limit notifications provide for the allowable dose
limits for occupational exposure listed in Table F4-1.

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Table F4-1
Dose limits for personnel engaged in radiation work
Items
Limits
1. Effective dose limits(1) Personnel engaged in radiation work 100mSv/5 years (do not exceed 50mSv/year)
In addition to the provision (1), 5mSv/3 months(2) Female personnel
In addition to the provision (2), 1mSv for internal(3) Pregnant female personnel
exposure during a period after her employer etc.
knows her pregnancy until the childbirth
2.Equivalent dose limits
150mSv/1 year
(1) Eye lens
500mSv/1 year(2) Skin
2mSv during a period after her employer etc.
(3) Pregnant female’s abdominal region
knows her pregnancy until the childbirth
3.Dose limits for the personnel engaged in emergency radiation work
100mSv(1) Effective dose limits
300mSv(2) Equivalent dose limits for eye lens
1Sv(3) Equivalent dose limits for skin(3) Dose Limits for the Public
The abovementioned rules and dose limit notifications provide for the allowable dose
limits for the public listed in Table F4-2.
Table F4-2
Dose limits for the public
Items
Limits
Dose limits outside the peripheral monitoring area
Effective dose
1mSv/year
Equivalent dose for eye lens
15mSv/year
Equivalent dose for skin
50mSv/year
2.
Numerical Guide to Reduce Dose to the Public in Vicinity and Discharge Control
At major nuclear facilities licensed on the basis of the Reactor Regulation Law, operators
are required to keep the radiation dose received by the public in the vicinity of the facility
low taking the ALARA principle, in addition to comply with dose limits and concentration
limits of radioactive materials outside peripheral monitoring area due to the discharge ofradioactive materials.
For nuclear power reactors, the guidelines prepared by the NSC, "the Guides for the Dose
Target Value in the Vicinity of the Light Water Nuclear Power Reactors", defines the target
value for radiation doses received by the public in the vicinity of the facilities as 50µSv per
year due to the release of radioactive materials to the environment during normal operation.
Operators establish the annual numerical discharge control guide that satisfies theabove-mentioned target, put it in the Operational Safety Program, and obtain approval of
the regulatory body.
For the reprocessing facility, fabrication facility, use facility, waste disposal facility, andwaste management facility and spent fuel intermediate storage facility, the operators are
required to reduce radiation doses based on the ALARA principle at the license
examination. Operators define the control target value smaller than the dose limit of 1mSv /year, put it in the Operational Safety Program, and obtain approval of the regulatory body.
During the decommissioning, operators continue the radiation control, setting the control
target value equivalent or lower than the value during operation.
The regulatory body approves the control target value, confirms compliance with the
Operational Safety Program, and collects report from operators.
At radioisotope waste management facilities licensed on the basis of the Radiation
Hazards Prevention Law, an operator, in addition to comply with concentration limits ofgaseous and liquid discharge, makes efforts to keep dose at site boundary below 250µSv/360

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months3.
Measurement of Environmental Radiation
A licensee on the basis of the Reactor Regulation Law conducts radiation monitoring at thesite vicinity during normal operation, assesses the impact upon the environment of thedischarge of radioactive materials from the facility, and feedbacks the results in improving
discharge control and facility management.
Local governments hosting nuclear facilities also monitor radiation level independently at
the site vicinity to protect public health and safety.
Meanwhile, the NSC indicates fundamentals of the monitoring plan and its implementationand the evaluation of radiation dose in the “Guideline for Environmental Radiation
Monitoring” which was established in March 2008, integrating the existing “Guideline forEnvironmental Radiation Monitoring” and the “Guideline for Environmental Radiation
Monitoring in Emergencies”, in order to improve and standardize monitoring technology.
Local governments and licensees implement monitoring in accordance with the guide.
An operator of radioisotope waste management facility licensed on the basis of the
Radiation Hazards Prevention Law monitors radiation level and measures contamination
by radioactive materials at controlled area boundary, site boundary and any appropriate
points.
F4.3

Measures taken to prevent unplanned and uncontrolled releases of radioactive
materials into the environment

The abovementioned rules provide that three-month-averaged concentration of radioactive
materials in air outside peripheral monitoring area shall not exceed the concentration limits
for discharge of gaseous radioactive waste, that three-month-averaged concentration ofradioactive materials in water at the outside of the boundary of the peripheral monitoringarea shall not exceed the concentration limits for discharge of liquid radioactive waste with adischarge facility, and that doses due to liquid discharge of radioactive wastes from
reprocessing facilities monitored at the outlet to the ocean shall not exceed the dose limit.
The rules also provide that licensees shall immediately report to the competent ministerwhen any of these limits are exceeded, and report within 10 days on details of the event andcorrective measures taken.
F4.4

Provision for mitigate the effects by an unplanned or uncontrolled release ofradioactive materials

Licensees of Nuclear Facilities, on the basis of abovementioned rules, shall prepare the
Operational Safety Program and have them approved by the regulatory body, which providethat operators, in case of unplanned or uncontrolled release of radioactive materials, shouldtake measures against the spread of contamination by nuclear fuel materials orradioisotopes and carryout decontamination work without delay.
And as an example, the Safety Examination Guide for Reprocessing Facility, which is usedin safety examination of reprocessing facility with large inventory of radioactive materials,
provides that fire and explosion due to fine metal particles from fuel cladding or organic
solvent, criticality accident, leakage or loss of function due to damage or failure of equipment
or piping, or spent fuel handling failure do not cause excessive exposure of radiation to the
public.
When an unplanned or an uncontrolled release of radioactive materials initiates any specific
events (Table F5-1) defined in the Special Law of Emergency Preparedness for Nuclear
Disaster (Special Law for Nuclear Emergency Preparedness), emergency activities startaccording to the procedure, and the Prime Minister declares Nuclear Emergency if the initial
event progresses and exceeds the predetermined level. Nuclear emergency will be
described in detail in the ensuing section.

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F5

Emergency preparedness

Article 25
1. Each Contracting Party shall ensure that before and during operation of a spent fuel or radioactive
waste management facility there are appropriate on-site and, if necessary, off-site emergency
plans. Such emergency plans should be tested with appropriate frequency.
2. Each Contracting Party shall take the appropriate steps for the preparation and testing of
emergency plans for its territory insofar as it is likely to be affected in the event of a radiologicalemergency at a spent fuel or radioactive waste management facility in the vicinity of its territory.

F5.1

Laws, Regulations and Requirements for Nuclear Emergency Preparedness

The JCO Criticality Accident in September 1999 was a very serious accident when local
residents were instructed for sheltering or evacuation for the first time in Japan, shattering
basic premise of securing safety in promoting utilization of nuclear energy. Lessons learned
from the accident clarified the special characteristics of nuclear emergency, which would
demand quick initial response, coordinated cooperation among the national and local
governments, strengthening of the national emergency preparedness and the clarification ofoperator’s responsibilities. The Special Law for Nuclear Emergency Preparedness wasenacted in December 1999 and enforced in June 2000, addressing the special
characteristics of nuclear emergency*1 mentioned above.
The law was enacted within the legal framework already established by the Basic Law for
General Emergency Preparedness, which had defined roles of the national government,
local governments, etc. in emergencies such as earthquakes, typhoons, conflagrations andnuclear emergency.
The part of “Nuclear Emergency Preparedness” in the Basic Plan for Emergency
Preparedness based on the Basic Law for General Emergency Preparedness, wasextensively revised in accordance with the Special Law for Nuclear Emergency
Preparedness, clarifying roles and responsibilities of the national government, local
governments, and nuclear operators*2.
The NSC, taking into consideration the Special Law for Nuclear Emergency Preparedness
and the lessons learned from the JCO Criticality Accident, revised the “Guideline on
Emergency Measures for Nuclear Facilities” on technical and specialized matters for nuclear
emergency in May 2000,
to correspond to the Special Law for Nuclear Emergency Preparedness,to expand the scope for research reactors and nuclear fuel related facilities in addition to
the nuclear power stations, reprocessing facilities, etc., andto include measures against the nuclear fuel material release and the nuclear criticality
accident in addition to the noble gases and iodine release.
After that, the Guideline has been revised several times by the NSC as followings since the
2nd National Report.
to specify the purposes of the Guideline and the objective facility, and to describe theeffectiveness of preventive protection according to the international trends of IAEA andso on (May 2007). And the Guideline was adjusted with the Special Law for Nuclear
Emergency Preparedness and related guides issued by the NSC
to change the titles of reference guide according to the establishment of the Guideline
for Environmental Radiation Monitoring (March 2008)
As the Special Law for Nuclear Emergency Preparedness provides that its enforcement
situation is subject to review five years after its enforcement, the enforcement situation wasinvestigated by MEXT and METI. Results of the investigation were reported to the Special
Committee on Nuclear Disaster, the NSC in March 2006.
NISA checked the enforcement situation concerning four issues that were presupposed to
be noted when the Special Law for Nuclear Emergency Preparedness was enacted, andreported the following:
Concerning the speeding up of the initial response, non-scenario-based training should62

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be carried out, and the effort should be continued;
Concerning enhancing the cooperation between the national government and local
governments, the "Integrated Nuclear Emergency Preparedness Network", which is alarge-scale system and preparation of a fast unified network of communication among
them, should be established;
Concerning enhancing the emergency response system of the national government,
necessary renewal of materials and equipment of the Emergency Preparedness Center
should be promoted; and,In relation to clarification of the licensees’ duties, effective functioning of nuclear
emergency specialists in an emergency should be verified and improved.
In this section, emergency preparedness of main nuclear facilities in accordance with theSpecial Law for Nuclear Emergency Preparedness is described.
*1 The term “nuclear emergency” means unusual release of radioactive materials or unusual
radiation streaming outside of a nuclear facility, by operation of a nuclear reactor, fabrication,
reprocessing and use of nuclear fuel materials, storage of spent fuels, management of
nuclear fuel materials or the materials contaminated with nuclear fuel materials, and theaccompanying shipment, and the term “nuclear disaster” means the damage caused by anuclear emergency to the life, health or property of the public, according to the Special Law
for Nuclear Emergency Preparedness.
*2 The term “an operator” means a license holder for fuel manufacturing operation of nuclear
reactors, spent fuel storage , reprocessing , radioactive waste disposal , or use of nuclear fuelmaterials, according to the Special Law for Nuclear Emergency Preparedness.

F5.2

Nuclear Emergency Preparedness and the Emergency Measures

The responsibilities of related authorities for nuclear emergency preparedness and theemergency measures concerning operators and major nuclear facilities in accordance with
the Special Law for Nuclear Emergency Preparedness are as follows.
1.
Outline of Nuclear Emergency Preparedness at Nuclear Facilities (Fig. F5-1)
Quick response and coordinated cooperation among related organizations are important ina nuclear emergency.
The Special Law for Nuclear Emergency Preparedness defines specific initial events ina major nuclear facilities (see Table F5-1), the occurrence of which the operator shallimmediately notify the competent minister and the heads of related local governmentsof.
The competent minister, receiving the notification, starts activities according to theprocedure stipulated by the law. Staff with expertise in emergency measures will besent to local governments on request. The Senior Officer for Nuclear Emergency
collects information and coordinates activities preventing expansion of the events.
When the competent minister recognizes that the specific initial event exceeds thepredetermined level and has developed into an emergency, the minister immediately
reports it to the Prime Minister.
The Prime Minister declares “Nuclear Emergency”, and advises or directs related local
governments on necessary measures such as sheltering, evacuation or preventive
use of stable iodine tablets to be taken by them.
The Prime Minister establishes the "Nuclear Emergency Response Headquarters" inTokyo, which he will head, and the "Local Nuclear Emergency Response
Headquarters".
The NSC, when a nuclear emergency occurs, calls the Emergency Technical Advisory
Body that consists of members from the NSC and the Investigation Committee for
Emergency Measures and makes technical advices to the Prime Minister.
Local governments establish their own emergency response headquarters.
The national government, local governments and related operators etc. establish the"Joint Council for Nuclear Emergency Response" at the Off-Site Center in order to
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share information and coordinate their emergency measures.
2.
On-site and Off-site Nuclear Emergency Preparedness at Nuclear Facilities
Organizations related to nuclear emergency preparedness keep themselves always readyto collect and send information and start quick response against an emergency, andconduct exercises, disseminate knowledge and promote research on emergency
preparedness. Outline of roles and responsibilities of related organization are as follows.
(1) On-Site Emergency Preparedness at Nuclear Facilities
When the operator detects abnormal release of radioactive material or abnormal level ofradiation at a nuclear facility, it takes necessary measures to prevent progression of theevent into an emergency.
The operator develops Operator’s Plan for Nuclear Emergency Preparedness after
consulting with related local governments, which provides for prevention of, emergency
measures against, and post-emergency restoration from, a nuclear emergency, including
on-site and off-site cooperation with other organizations. Especially, quick and accurate
notification of occurrence of specific initial events to related organizations is a very
important obligation of the operator.
Moreover, the operator is required to take part in comprehensive exercise with relatedorganizations, and keep close contact with them.
(2) Off-Site Emergency Preparedness of Nuclear Facilities
Roles and responsibilities of the national government and local governments inemergency preparedness are defined in the Special Law for Nuclear Emergency
Preparedness and the Basic Plan for General Emergency Preparedness. Each local
government develops its own Local Plan for Emergency Preparedness. They conduct
emergency environmental radiation monitoring, and recommend or instruct evacuation,
sheltering or preventive use of stable iodine to the resident, receiving advice or direction
from the Prime Minister.
3.

Responsibility of the National Government, Local Governments and Operatorsconcerning the Nuclear Emergency Preparedness(1) Responsibility of the National Government
The national government establishes following preparation to prevent occurrence of
nuclear emergency and to take measures in emergency.
The competent minister stations a Senior Officer for Nuclear Emergency in thevicinity of each nuclear facility, who guides and advises the operator in preparing
Operator’s Plan for Emergency Preparedness and, in emergency, takes necessary
measures preventing progression of the emergency.
The NSC, when a nuclear emergency occurs, calls the Emergency TechnicalAdvisory Body that consists of members from the NSC and the Investigation
Committee for Emergency Measures and makes technical advices on dissolution of
nuclear emergency, change of area for emergency measures, and other technicalmatters to the Head of the Nuclear Emergency Preparedness Headquarter (thePrime Minister).
The competent minister designates a facility in the vicinity of a nuclear facility as
Off-Site Center to be used in an emergency. In case of an emergency, the national
government, the local governments and the operator establish at the Off-Site Center
the "Joint Council for Nuclear Emergency Response", in order to share informationand to coordinate their activities. Off-Site Centers, located on the points shown in
Fig.F5-2, have communication equipment with the Prime Minister’s Official
Residence, the Cabinet Office, the Emergency Response Centers of NISA or MEXT
and related local governments, and other necessary equipment.
The Off-site Center is provided with equipment to monitor the environmental radiation
64

Other General Safety Provisions

level in the vicinity of the facility and display it on-line. Also, it is provided withequipment to display on-line information on accident condition in the nuclear facility
except for the temporary data, and information on accident progression predicted by
ERSS (Emergency Response Support System). Also SPEEDI (System for Predictionof Environmental Emergency Dose Information) net work was developed that predict
quickly the radioactivity concentration in the air and exposure around the area basedon the radiation source information provided by ERSS, meteorological condition andtopographical data.
The national government establishes arrangements to initiate quick and coordinatedactivities in an emergency.
The national government conducts comprehensive nuclear emergency exercise oncea year according to the plan prepared by the competent minister.
(2) Responsibilities of Local Governments
The local governments are required to develop and revise Local Plan for Emergency
Preparedness in accordance with Article 40 of the Basic Law on General Emergency
Preparedness, consulting with the Prime Minister beforehand.
(3)

F.5.3

Licensee’s Responsibility
The licensee develops its own Operator’s Plan for Nuclear Emergency Preparedness
after consulting with related local governments, and submits it to the competent
minister before operation of the nuclear facilities.
The licensee establishes on-site organization for nuclear emergency preparedness,and designates a Manager for Nuclear Emergency Preparedness who administers
the organization.
The Manager for Nuclear Emergency Preparedness shall notify specific initial eventsto the competent authorities.
Implementation of the Nuclear Emergency Exercises

Plans for Nuclear Emergency Preparedness are developed in the vicinity of each nuclear
facility in accordance with the Special Law for Nuclear Emergency Preparedness, and an
Off-Site Centers is located in the vicinity of each nuclear facility. Exercises of various levels
are conducted to confirm the effectiveness of the emergency preparedness. The purpose of
exercise includes 1) to enhance understanding of the nuclear emergency preparedness by
responsible personnel of related organizations and local residents, and 2) to verify whether
emergency measures function in predetermined way, and whether information sharing andcooperation among related organizations are adequate. Exercises cover communication,
monitoring, decision making on emergency measures to be taken, sheltering or evacuation
etc., ranging from large scale national exercise to operator’s on-site exercise. Exercises in
the past years are shown below.
1.
Exercise Planned by the National Government (Table F5-2 (1))
The national government started nation-wide comprehensive exercises for nuclear
emergency involving national and local governments, designated public organizations,operators of the nuclear facility and the local residents once a year, upon enforcement of
the Special Law for Nuclear Emergency Preparedness established after the JCO Criticality
Accident, increasing its involvement in exercises planned and executed mainly by local
governments in the past. The exercise for power reactor facilities includes a scenario
assuming core damage and relevant accident management activities.
The following exercises were conducted since 2005.
On November 9 and 10, 2005, the national government, Niigata Prefecture, concerned
cities/towns/villages, Tokyo Electric Co., and other emergency-preparedness-relatedorganizations conducted a joint exercise for the Kashiwazaki-Kriwa Nuclear Power
Station (Niigata Prefecture) with a participation of about 2,600 persons including local
65

F

F

Other General Safety Provisions

residents. Field trainings for emergency dispatch of government officials and experts
and transportation of materials and equipment were conducted within this exercise.
The lessons learned from the Niigataken-Chuetsu earthquake (October 23, 2004)
were also taken into account.
On October 25 and 26, 2006, the national government, Ehime Prefecture, concerned
cities/towns/villages, Shikoku Electric Co., and other emergency-preparedness-relatedorganizations conducted a joint exercise for the Ikata Power Station (Ehime
Prefecture) with a participation of about 3,700 persons including local residents. This
exercise took account of enhanced immediate emergency measures (preparation) at
an alert stage.
On October 24, 2007, the national government, Aomori Prefecture, concerned cities,
towns, villages, Japan Nuclear Fuel Ltd., and other emergency-preparedness-relatedorganizations conducted a joint exercise for the Reprocessing Plant (Rokkasho Village,
Aomori Prefecture) with a participation of about 1,800 persons including local residents.
This was the first exercise for the reprocessing plant and a fire drill on the assumptionof radioactive material release was conducted. Enhancement of public relations
activities including information release to foreign media was also intended.
The results of the exercises are well evaluated and fed back to the items and methods ofthe exercises to be conducted in the subsequent years. The evaluation uses three types ofmethods: questionnaires to the participants, checking by the third party evaluation
organization and opinions of external experts.
2.
Exercise Planned by the NSC
The NSC implements exercise for improvement of the emergency communication system,
and for activation of the Emergency Technical Advisory Body and improvement of its
effectiveness.
3.
Exercise Planned by Local Governments (Table F5-2 (2))
The Local Plan for Emergency Preparedness prescribes local exercise to be planned andconducted by local governments, which national government and the NSC support bysending expert staffs etc.
4.
Exercise Planned by Licensees
The licensees have conducted on-site exercises including establishment and operation of
emergency response headquarters, communication, emergency environmental radiation
monitoring, etc. based on Operator’s Plan for Emergency Preparedness for each site about
once per year. The operators conduct the exercise etc. involving accident management
activities, to confirm its effectiveness.
The licensee participates in the exercise planned and executed by the local government.
5.
Participation in international exercise
Japan is a contracting party to the Convention on Early Notification of a Nuclear Accident
and the Convention on Assistance in the Case of a Nuclear Accident or Radiological
Emergency. Japan has been participating and will continue to actively participate in theinternational emergency response exercise (ConvEx) organized by the IAEA
F5.4

Response to radiological emergencies in neighboring countries

Japan is a contracting party to the "Convention on Early Notification of a Nuclear Accident"
and the "Convention on Assistance in the Case of a Nuclear Accident or Radiological
Emergency". To implement the provisions of these conventions, the Ministry of Foreign
Affairs (MOFA) is designated as "National Warning Point (NWP)" and "National Competent
Authority for an Emergency Abroad, NCA(A)" in the case of a nuclear accident and aradiological emergency out side the Japanese territory
When a radiological emergency occurs outside Japanese territory including neighboring
66

Other General Safety Provisions

countries, the MOFA through the established response system, receives notifications andforwards them to appropriate authorities to share the information and to take necessary
steps. In relation to the Assistance Convention, the response system has been reviewed for
its important by considering registration for RANET and other so that Japan as a contacting
party could dispatch personal and provide material and equipment to the extent possible
under the Convention

67

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Other General Safety Provisions

Operators

National Government

Manager for Nuclear
Emergency
Preparedness

Reportsto

Local Governments

Competent Minister
Prefectural governors- Establishes an organization to
respond to the event- Judges whether the event is a
nuclear emergency or not (see Table
F.5-1)- Orders resident Senior Officer for
Nuclear Emergency to collectinformation, etc.

- Confirms occurrence ofan event to be reported(see Table F.5-1)- Onsite nuclear
emergency response
team to take emergency
measures

Request dispatchof experts

Municipal mayors
Dispatches
experts

Prime Minister- Declares

nuclearemergency,
designates emergency zone, anddirect actions to be taken.
- Establishes Nuclear Emergency
Response Headquarters

Instructs theimplementation of
emergency response
Measures

Residents

Advises

NSC

Nuclear Emergency Response
Headquarters
Head: Prime Minister
Deputy Head: Competent minister
Members: Heads of related ministries,
agencies, and related government
offices

Directs

Local governments
establish Emergency
Response Headquarters

Participates inEstablish Local Nuclear Emergency
Response Headquarters

Emergency activities
by the operator’s
onsite emergency
response team

Self-Defense
Force

Establish Joint Council for Nuclear Emergency Response at the Off-Site Center, share informationand coordinate emergency activities.
Coordinating activities of the council- to make accurate information available
Directs and requests
to the public- to advise or direct residents to evacuate - Special support: the National Institute of Radiological- to measure radiation dose in the
Sciences, Japan Atomic Energy Agency, and otherenvironment
institutions- to rescue injured persons- Fire fighting, rescue and first aid: the Fire Defense- temporary repairs
Agency- Security guard: the National Police Agency

NSC

Prime Minister
Advises- to declare Dissolution of Nuclear
Emergency
Dissolution of the Nuclear Emergency
Response Headquarters

Measures by the national and local
governments and the operator:- Contamination surveys- Health counseling- Publicity activities to prevent damage
from rumor

Fig.F5-1 Measures Based on the Special Law for Nuclear Emergency Preparedness

68Other General Safety Provisions

Kanagawa Yokosuka

Osaka Kumatori
Osaka Higashi-Osaka
Kanagawa Kawasaki

Designated by METI(16)Designated by MEXT(2)Designated by METI and MEXT(4)Fig.F5-2 Locations of Off-Site Centers

69

FOther General Safety Provisions

F

Table F5-1

Main Specific Events, Nuclear Emergencies and Responses Prescribed in
the Special Law for Nuclear Emergency Preparedness

Eventsa

Dose rate near the siteboundaryb

Detection of radioactive
materials at exhaust stackor other normal release
pointsc

Detection of radiation orradioactive materials due tofire or explosion, outsidecontrolled areasd

Individual
event
in
consideration of facility
characteristics
Failure of scram

Loss of reactor coolant
Loss of all AC power
supplies
A decrease of spent fuelpool water level at a
reprocessing facility

Criteria of Specific Event
Exceeding 5µSv/h at one point for
more than 10 minutes
Exceeding 5µSv/h simultaneously at
more than two points
Release of radioactive materials that
results in more than 50µSv of dose or
more than 5µSv/h of dose rate formore than 10 minutes
More than 50µSv/h of radiation dose
rate
Release of radioactive materials that
results in more than 5µSv/h of dose
rate

Criteria of Emergency
Exceeding 500µSv/h at one point for
more than 10 minutes
Exceeding 500µSv/h simultaneously
at more than two points
Release of radioactive materials that
results in more than 5mSv of dose or
more than 500µSv/h of dose rate formore than 10 minutes
More than 5mSv/ｈof radiation dose
rate
Release of radioactive materials that
results in more than 500µSv/h of doserate

Reactor cannot be shut down withnormal neutron absorbers

Emergency reactor shutdown isrequired, but all reactor shutdown
functions are unavailable

Emergency core cooling system(ECCS) is actuated due to reactor
coolant.
All AC power supply is unavailable
more than 5 minutes.

All ECCS injections are unavailable.
All AC power supply is lost and allcore cooling functions are lost.

Fuel assemblies are exposed due todrop of water level- The competent minister dispatchedexpert staff to local governments attheir request.
- Resident Senior Officer for Nuclear
Emergency conducts prescribed
response operations.

- Officials from concerned ministries
and agencies assemble for theaccident
response
liaisonconference (Tokyo).
- Designated parties assemble in the
Off-site Center for local accident
response liaison conference.

70

The competent minister confirms theoccurrence of nuclear emergency andreports it to Prime Minister.
Prime Minister declares nuclear
emergency and takes following
measures- To advise or instruct the local
governments on evacuating etc.
- To establish Nuclear Emergency
Response Headquarters in Tokyo
and Local Nuclear Emergency
Response
Headquarters(Off-site
Center)- To set up the Joint Council for
Nuclear Emergency Response inorder to exchange information
among the national and local
governments.

Other General Safety Provisions

Table F5-2

Records of Nuclear Emergency Exercise

Planned byDate of exercise(1) Exercise planned by National Government
2005/11/9 (Wed) -10 (Thu)National
Government

2006/01/20 (Fri)

Nuclear facility
Kashiwazaki-Kariwa Nuclear Power Station (Tokyo Electric Power
Co., Inc.)
NuclearScienceLaboratory(JRR-3),
Tokai
Research-and-Development Center, (IAA) Japan Atomic Energy
Agency.

2006/10/25(Wed) -26 (Thu)

Ikata Nuclear Power Station (Shikoku Electric Power Co., Inc.)

2007/10/24 (Wed)Fuel Reprocessing Plant, (Japan Nuclear Fuel Ltd.)(2) Exercise planned by Local Government (April, 2005 - as of March 31, 2008)
Fukui
2005/8/2 (Tue)Mihama Nuclear Power Station (Kansai Electric Power Co., Inc.)
Higashidori Nuclear Power Station (Tohoku Electric Power Co.,
Aomori2005/8/10 (Wed)Inc.)
Ibaragi
2005/9/30 (Fri)Fuel fabrication facility (Mitsubishi Nuclear Fuel Co., Inc.)
Hokkaido

2005/10/21 (Fri)Tomari Nuclear Power Station (Hokkaido Electric Power Co., Inc.)

Ehime

2005/10/21 (Fri)Ikata Nuclear Power Station (Shikoku Electric Power Co., Inc.)

Miyagi2005/10/28 (Fri)Fukushima

2005/11/15 (Tue)Shimane2005/11/17 (Thu)

Ishikawa

2005/11/17 (Thu)

Onagawa Nuclear Power Station (Tohoku Electric Power Co., Inc.)
Fukushima Daini Nuclear Power Station (Tokyo Electric Power Co.,Inc.)
Shimane Nuclear Power Station (Chugoku Electric Power Co.,Inc.)
Shika Nuclear Power Station (Hokuriku Electric Power Co., Inc.)

Kagoshima

2005/11/19 (Sat)

Sendai Nuclear Power Station (Kyushu Electric Power Co., Inc.)

Saga

2005/11/21 (Mon)Genkai Nuclear Power Station (Kyushu Electric Power Co., Inc.)

Aomori2005/11/22 (Tue)Fukui (Public
protection
2005/11/27 (Sun)exercise)

Reprocessing facility (Japan Nuclear Fuel Ltd.)
Mihama Nuclear Power Station (Kansai Electric Power Co., Inc.)

Tottori

2006/1/24 (Tue)Okayama

2006/2/9 (Thu)

Shizuoka

2006/2/15 (Wed)

Enrichment engineering facility, Ningyotoge Environmental
Engineering Center, (IAA) Japan Atomic Energy Agency
Enrichment engineering facility, Ningyotoge Environmental
Engineering Center, (IAA) Japan Atomic Energy Agency
Hamaoka Nuclear Power Station (Chubu Electric Power Co., Inc.)

Aomori

2006/7/27 (Thu.)

Rokkasho reprocessing facility (Japan Nuclear Fuel Ltd.)

Fukui

2006/8/1 (Tue)Ohi Nuclear Power Station (Kansai Electric Power Co., Inc.)

Ishikawa

2006/8/20 (Sun)Shika Nuclear Power Station (Hokuriku Electric Power Co., Inc.)

Ibaragi

2006/9/29 (Fri)Tokai No.2 Power Station (Japan Atomic Power Co.)

Miyagi

2006/10/23 (Mon) -24 (Tue)Onagawa Nuclear Power Station (Tohoku Electric Power Co., Inc.)

Hokkaido

2006/10/30 (Mon)

Niigata

2006/11/10 (Fri)

Aomori

2006/11/14 (Tue)

Kagoshima

2006/11/17 (Fri)Tomari Nuclear Power Station (Hokkaido Electric Power Co., Inc.)
Kashiwazaki-Kariwa Nuclear Power Station (Tokyo Electric Power
Co., Inc.)
Higashidori Nuclear Power Station (Tohoku Electric Power Co.,Inc.)
Sendai Nuclear Power Station (Kyushu Electric Power Co., Inc.)

Fukui

2006/11/19 (Sun)Ohi Nuclear Power Station (Kansai Electric Power Co., Inc.)

Saga

2006/11/26 (Sun)Okayama

2006/11/27 (Mon)

Shimane2007/1/30 (Tue)

Shizuoka

2007/2/1 (Thu)

Fukushima

2007/2/6 (Tue)

Kanagawa

2007/2/6 (Tue)Fukui

2007/8/2 (Thu)Genkai Nuclear Power Station (Kyushu Electric Power Co., Inc.)(Enrichment engineering facility, Ningyotoge Environmental
Engineering Center, (IAA) Japan Atomic Energy Agency
Shimane Nuclear Power Station (Chugoku Electric Power Co.,Inc.)
Hamaoka Nuclear Power Station (Chubu Electric Power Co., Inc.)
Fukushima Daiichi Nuclear Power Station (Tokyo Electric Power
Co., Inc.)
Nuclear Fuel Fabrication Facility (Global Nuclear Fuel Japan Co.,Ltd.)
Tsuruga Power Station (Japan Atomic Power Co.)

71

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Other General Safety Provisions
Experimental Fast Reactor “Joyo”, Oharai Research andDevelopment Center, (IAA) Japan Atomic Energy Agency
Prototype Uranium Enrichment Plant, Ningyo-toge Environmental
Engineering Center, (IAA) Japan Atomic Energy Agency
Fukushima Daini Nuclear Power Station (Tokyo Electric Power Co.,Inc.)
Sendai Nuclear Power Station (Kyushu Electric Power Co., Inc.)

Ibaragi

2007/09/28 (Fri)Okayama

2007/10/11 (Thu)

Fukushima

2007/10/22 (Mon) -23 (Tue)

Kagoshima

2007/10/23 (Tue)

Hokkaido

2007/10/30 (Tue)Shimane2007/11/2 (Fri)Ehime

2007/11/6 (Tue)Tomari Nuclear Power Station (Hokkaido Electric Power Co., Inc.)
Shimane Nuclear Power Station (Chugoku Electric Power Co.,Inc.)
Ikata Nuclear Power Station (Shikoku Electric Power Co., Inc.)

Fukui

2007/11/18 (Sun)

Tsuruga Power Station (Japan Atomic Power Co.)

Ishikawa

2007/11/22 (Thu)Shika Nuclear Power Station (Hokuriku Electric Power Co., Inc.)

Saga

2007/11/25 (Sun)Genkai Nuclear Power Station (Kyushu Electric Power Co., Inc.)

Miyagi2008/1/23(Wed) -24 (Thu)

Onagawa Nuclear Power Station (Tohoku Electric Power Co., Inc.)

Shizuoka

2008/2/13 (Wed)Hamaoka Nuclear Power Station (Chubu Electric Power Co., Inc.)

F6

Decommissioning

Article 26
Each Contracting Party shall take the appropriate steps to ensure the safety of decommissioning of a
nuclear facility. Such steps shall ensure that:(i) qualified staff and adequate financial resources are available;(ii) the provisions of Article 24 with respect to operational radiation protection, discharges andunplanned and uncontrolled releases are applied;(iii) the provisions of Article 25 with respect to emergency preparedness are applied; and(iv) records of information important to decommissioning are kept

The Framework for Nuclear Energy Policy issued by the Atomic Energy Commission statesthat “it is important to carry out decommissioning of a nuclear facility such as commercial
power reactor, experimental research reactor and nuclear fuel cycle facility, ensuring safety,on the operator's own responsibility, in accordance with the revised Reactor Regulation Law,under the government's regulation and obtaining local communities' understanding andcooperation."
The regulatory policy for dismantling or decommissioning of reactor facilities has been
investigated and discussed, resulting in following three reports;"Basic Philosophy to Assure Safety for the Dismantling Nuclear Reactor Facilities"(December 1985, Decision by the NSC, revised in August 2001)"Aiming at Decommissioning of Commercial Nuclear Power Facilities " (January 1997,
Nuclear Energy Subcommittee, Advisory Committee for Natural Resources and Energy )"Philosophy for Safety Assurance and Safety Regulation on the Decommissioning ofCommercial Power Reactor Facilities" (August 2001, Decommissioning Safety
Subcommittee, Nuclear and Industrial Safety Subcommittee, Advisory Committee for
Natural Resources and Energy)
Based on these reports, in order to ensure the safety during the decommissioning ofcommercial nuclear power reactors, the regulation was implemented by applying existing
provisions in the Reactor Regulation Law, such as “notification of dismantling” or “modificationof Operational Safety Program, by the operators.
So far, the decommissioning of reactor facilities was implemented at the Power
Demonstration Reactor of the Japan Atomic Energy Agency (JPDR) and the Tokai Power
Station of Japan Atomic Power Co. Inc., etc. and the development and application of
dismantling technologies have been progressed, and the know-how for decommissioning has
been accumulated through these processes.
Under such a circumstance, in October 14, 2004, the NSC pointed out, that “it is required toinvestigate the development of a graded approach in safety regulation system to cope withthe progress of dismantling processes, considering that the main activities during the period72

Other General Safety Provisions

after the cease of operation are safety management of spent fuels, dismantling works and theradiation control, and handling of radioactive wastes, and that the regulatory experiences
concerning dismantling and decommissioning of test and research reactors have been
accumulated”, as the conclusion of the regulatory activities investigation concerning the safety
regulation system during the period after the cease of operation of reactor facilities.
The Decommissioning Safety Subcommittee has investigated appropriate regulatory systemof decommissioning, based on the regulatory experiences on decommissioning of reactor
facilities under the current system. The investigation is conducted on the graded regulatory
approach to cope with the progress of the decommissioning process, the diversity of eachfacilities, reflecting the experiences of decommissioning, and development of technology inthe near future, and reported in "The Way of the Decommissioning Regulation of the Nuclear
Facilities" (December 9, 2004)).
In this investigation, the Subcommittee recognized that the decommissioning of nuclear
reactors is becoming to a routine activity, and the amendment of legislation must cope withgraded regulatory approach and clarification of the responsibilities of licensees. It isconsidered important (i) to clarify the requirement in decommissioning regulations, (ii) to keep
the transparency on procedures for the operators, and (iii) to obtain in the understanding andconfidence of the national people and local residents on decommissioning regulations.
The Subcommittee proposed the way of decommissioning regulations, as;replacing “dismantling notification by licensee”, to the “approval of the licensee’s
decommissioning plan of dismantling processes, methods etc. by regulatory body “
implementation of the decommissioning as approved in the plancompletion of decommissioning is confirmed by regulatory body and after theconfirmation of the completion of decommissioning, the operation license loses its effectthe regulatory activities during the decommissioning process (example: Periodical
Inspections, Nuclear Safety Inspections etc.) should be changed in accordance with thechanges of the functions of the facilities and safety operation activities as thedecommissioning proceeds (graded regulatory approach)On the basis of such recognition, the Reactor Regulation Law was amended on May, 2005
and the safety regulation for decommissioning of reactors and other facilities was updated. In
response to this amendment of the Law, the Enforcement Ordinance for the Reactor
Regulation Law and related ministerial ordinances (rules for Refinery, Commercial Power
Reactors, Reactors at Development Stage, Research Reactors, Fuel Fabrication, Spent Fuel
Storage, Reprocessing, Waste Disposal, Waste Storage and Use of Nuclear Material) wereamended in November, 2005 and put into force in December of the same year.
The above amendment of laws and regulations clarified the legal process of decommissioning.
An licensee applying for approval of decommissioning has to submit a decommissioning
program that describes the facility to be dismantled and dismantling method, transfer ofnuclear fuel materials, removal of contamination with nuclear fuel materials, management of
nuclear fuel materials or materials contaminated with nuclear fuel materials, process of
decommissioning work, radiation exposure control, safety assessment, systems withfunctions to be maintained and their performance, financial plan, implementation organization,etc. The regulatory body approves the decommissioning program after examining its
conformity with the technical standards. At the final stage of decommissioning, the licensee
submits a document that describes the implementation status of dismantling, transfer ofnuclear fuel materials, removal of contamination with nuclear fuel materials, management of
nuclear fuel materials or materials contaminated with nuclear fuel materials and the final
distribution of contamination with nuclear fuel materials, and requests the regulatory body’s
confirmation. The decommissioning is completed after the regulatory body confirms that themeasures for radiation hazard prevention is no more necessary and management of nuclear
fuel materials or materials contaminated with nuclear fuel materials is completed.
In addition, a graded regulation system was introduced. For example, the annual periodic
facility inspection by the government is no more conducted when nuclear fuel materials arecleared from the facility.

73

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Other General Safety Provisions

The Radiation Hazard Prevention Law requires the license holders to take steps, such astransferring the radioisotopes to another user, eliminating contamination with radioisotopes
and disposing radioisotopes or material contaminated by radioisotopes, etc, to remove
radioisotope contamination when they intend to cease the waste management business or
use of radioisotopes and/or radiation generating apparatus. The procedure of cessation isconducted adequately in a law-abiding manner.
F6.1

Qualified staff and adequate financial resources are available

1.
Human Resources
Licensees clarify, in the Operational Safety Program, safety organizations, responsibility
and roles in decommissioning processes, and planning and implementation of relevant
safety education programs necessary for managers and workers including subcontractors.
The regulatory body confirms the observance of the above-mentioned Operational Safety
Program by the inspection (Nuclear Safety Inspection).
2.
Financial Resources
Electric utilities have deposited funds for decommissioning of commercial power reactor
facilities using the Dismantling Reserve Funds. (see Section B)
F6.2

Operational radiation protection

The regulations on radiation protection applied to nuclear facilities in operation, which is
described at Article 24 (F4), are also applicable to nuclear facilities in the process of being
decommissioned.
F6.3

Emergency preparedness

The regulations on emergency preparedness applied to nuclear facilities in operation, which
is described at Article 25 (F5), are also applicable to nuclear facilities in the process of being
decommissioned.
F6.4

Records of information important to decommissioning are kept.

The Reactor Regulation Law requests to keep important records such as inspection records,
radiation control records, etc. even at decommissioning stage.
And other records specific to decommissioning such as each equipment or system being
dismantled, schedule and method for dismantling it, etc. are required to be recorded andkept at the end of each dismantling process.
Thus the regulatory body can confirm that the decommissioning has been appropriately
completed ensuring safety and in compliance with the Decommissioning Plan of that facility
by keeping records to show it.

74

Safety of Spent Fuel Management

Section G

Safety of Spent Fuel Management

The Government of Japan regulates spent fuel management on the activity basis inaccordance with the Law for Regulation of Nuclear Source Material, Nuclear Fuel Material
and Nuclear Reactors (Reactor Regulation Law). Specifically, in the licensing process of a
nuclear activity, the facility to be used for the proposed activity, i.e. a reactor facility thatgenerates spent fuel, an independent spent fuel storage facility or a reprocessing facility, isrequired to demonstrate its adequateness in terms of nuclear disaster prevention. Thisrequirement is applied to the whole facility including its spent fuel storage sub-facility.
The major safety functions required for the handling and storage of spent fuel within a facility
are "confinement of radioactive materials", "shielding of radiations", "prevention of criticality"and "removal of residual heat" which are common requirements of the laws and regulations
governing any kind of spent-fuel-related activity.
Spent fuel storage activity became practical when the Reactor Regulation Law was amended
in 1999. The first licensing application in Japan was filed in March, 2007 by Recycle Fuel
Storage Company, for a spent fuel storage facility outside of nuclear power station to store
spent fuel intermediately before reprocessing. The application is now under safety review.
The proposed spent fuel storage facility is the “Recycle Fuel Storage Center” (see Fig.L5-1)
that is planned to be built in Mutsu City of Aomori Prefecture. The capacity of the Storage
Center will be 3,000 tons in total, 2,600 tons and 400 tons for BWR and PWR spent fuel,respectively, and the fuel will be stored in dry metal casks that are used also fortransportation.
Since the Reactor Regulation Law requires almost same safety regulatory procedures for all
types of spent fuel management activities, the explanation on the procedures in this Section
focuses on “spent fuel storage activity”.

75

GSite selection

Safety of Spent Fuel Management

Application for License
Safety Review

LicenseDesign & construction

Application for Construction Plan
Approval of Construction Plan

Pre-service
Inspection

Approval of Operational Safety Program
Approval of Physical Protection Program

Periodic Facility
Inspection
Physical Protection
Inspection
Approval of Operational Safety Program Amendment
Approval of Decommissioning Program
Operational Safety
Inspection
Periodic Facility
Inspection
Application for Decommissioning Completion
Confirmation
Confirmation of Decommissioning Completion

Fig.G-1 Regulatory Flow for Spent Fuel Storage

76

Periodic Safety Review

Operation

Operational Safety
Inspection

DecommissioningGSafety of Spent Fuel Management

G1

General safety requirements

Article 4
Each Contracting Party shall take the appropriate steps to ensure that at all stages of spent fuelmanagement, individuals, society and the environment are adequately protected against radiologicalhazards.
In so doing, each Contracting Party shall take the appropriate steps to:(i) ensure that criticality and removal of residual heat generated during spent fuel management are
adequately addressed;(ii) ensure that the generation of radioactive waste associated with spent fuel management is kept tothe minimum practicable, consistent with the type of fuel cycle policy adopted;(iii) take into account interdependencies among the different steps in spent fuel management;(iv) provide for effective protection of individuals, society and the environment, by applying at thenational level suitable protective methods as approved by the regulatory body, in the framework of
its national legislation which has due regard to internationally endorsed criteria and standards;(v) take into account the biological, chemical and other hazards that may be associated with spent fuelmanagement;(vi) strive to avoid actions that impose reasonably predictable impacts on future generations greaterthan those permitted for the current generation;(vii) aim to avoid imposing undue burdens on future generations.

G1.1

Prevention of criticality and removal of residual heat

In Japan, spent fuel is handled and/or stored in commercial nuclear power plants,
reprocessing facilities and spent fuel storage facilities. The Reactor Regulation Law requires
an applicant for license for such activity to demonstrate that the location, structures andsystems of the facility to be used for the activity are adequate for preventing a
nuclear-material-related disaster.
When applying for permission for a spent fuel storage license, the applicant is required by
the relevant laws and regulations to demonstrate that the structures and systems of the
proposed spent fuel storage facility, especially those for “prevention of spent fuel criticality”
and “heat removal of spent fuel”, are safety-designed so as not to hinder disaster prevention.
In addition, prior to actually starting construction of the licensed spent fuel storage facility,
the applicant has to obtain approval of the Minister METI for design and construction plan.
The Minister gives approval after confirming that the design and construction plan isconsistent with the licensed design and is in compliance with applicable technical standards.
These standards provide safety requirements such as to take adequate measures tomaintain sub-criticality of spent fuel, for instance, through geometrically safe configurations
and to provide systems capable of safe removal of decay heat of spent fuel.
During construction, the facility must undergo the pre-service inspection conducted by the
Minister of METI. This inspection is conducted to make sure that the construction works arebeing carried out in accordance with the approved design and construction plan and theperformance of the facility meets the requirements of the technical standard. The facility has
to get through this inspection to be put into operation.
Spent fuel is stored in the depositories that are associated with a reactor facility or
reprocessing facility as well as in an independent spent fuel storage facility. Such associatedstorage facilities are regulated similarly by the laws and regulations governing the relevant
activities.
As above, it is ensured in spent fuel management in Japan that criticality and removal ofresidual heat generated during spent fuel management are adequately addressed.
G1.2

Minimization of the generation of radioactive waste

Japanese laws and regulations do not require to minimize the radioactive waste amount,however, the capacities of radioactive waste storage facilities such as those in reprocessing
facility etc. as well as the capacities of radioactive waste disposal sites are limited and,
which leads to a common understanding of the necessity to reduce the radioactive waste
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generation.
In Japan, spent fuel is reprocessed to recycle valuable nuclear materials in accordance with
the nation’s fundamental nuclear energy policy. It is understood that reprocessing of spent
fuel is more effective than direct disposal in reducing the amount of high level radioactive
wastes.
Licensees are striving to minimize the amount of radioactive wastes generated from theiractivities by appropriate measures such as evaporating and concentrating liquid radioactive
wastes and incinerating solid radioactive wastes.
By establishing the clearance system, materials of insignificant radiation level, which arepart of concrete and metals generated from decommissioning of nuclear facilities, can bereleased from regulatory control of radioactive wastes as clearance materials, and recycle ofsuch materials can result in reduction of radioactive waste amount.
G1.3

Interdependencies among the different steps in spent fuel management

Spent fuel is generated in a reactor facility, temporally stored there and then transported tospent fuel storage facility or reprocessing facility. Spent fuel that was stored in a spent fuelstorage facilities is also transferred to reprocessing facility. In reprocessing facility, spent fuelis stored for a certain period and finally reprocessed.
The information such as specifications and irradiation record of spent fuel is shared among
the licensees of the different steps in spent fuel management and the facilities for those
steps are designed considering forms, burn-up, cooling term and other properties of spent
fuel. For getting license, applicant is required by the relevant laws and regulations to clearlyshow the specifications of spent fuel that will be handled and thus it is ensured that safety is
not impaired through the different steps in spent fuel management.
G1.4

Protection of individuals, society and the environment

Description on radiation protection for the safety of spent fuel management is provided in F4.
G1.5

Biological, chemical and other hazards that may be associated with spent fuelmanagement

The Reactor Regulation Law requires that nuclear facilities are adequate for preventing adisaster that involves radioactive materials. For getting license, any spent fuel management
facility, i.e. reactor facility, spent fuel storage facility or reprocessing facility, has to take into
account the measures against the events that may affect the facility, such as leakage ofradioactive materials, fire, explosion and earthquake, to prevent radiological effects on the
public and employees. These measures have to be considered also in the detailed facility
design to get approval for the design and construction plan. Such consideration as well as
subsequent pre-service inspection ensures that the hazards that may affect spent fuelmanagement are duly taken into account.
G1.6

To avoid imposing impacts on future generations

The Government of Japan makes it a basis of its nuclear energy policy to establish anational nuclear fuel cycle in which spent fuel is reprocessed in order to make effective useof uranium resources. Spent fuel generated by nuclear power plant is considered as a usefulrecyclable fuel resource, so that all the spent fuel is reprocessed and recyclable fuel is
re-used as nuclear fuel. There is no fuel stored in future generations thus no greater impacts
than those permitted for the current generation will be considered.
G1.7

To avoid imposing undue burdens on future generations

The laws and regulations require to ensure the costs for spent fuel reprocessing not to78

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impose undue burdens on future generations. (see Section B)

G2

Existing facilities

Article 5
Each Contracting Party shall take the appropriate steps to review the safety of any spent fuelmanagement facility existing at the time the Convention enters into force for that Contracting
Party and to ensure that, if necessary, all reasonably practicable improvements are made to
upgrade the safety of such a facility.

G2.1

Review the safety of existing spent fuel management facility

Periodical Safety Review is implemented in Japan to maintain the safety of nuclear facilities.
The Rule for Interim Storage of Spent Fuel requires to make assessments, at an interval of
not exceeding 10 years, of the safety activities at the spent fuel storage facility and theintroduction of the latest technological knowledge into the safety. It is also required to makea technical assessment of aging degradation and to develop a 10-year maintenance plan forthe spent fuel storage facility based on the aging assessment, before the operation period
reaches 20 years.
The regulatory body conducts the following inspections for the spent fuel management
facilities attached to nuclear facilities. Up to now, no major modification of facility has beensuggested by those inspections for continuous operation.
1.
Periodical Inspection of Facility
The regulatory body conducts the Periodical Inspection of Facility once a year (once every
13 months in the case of commercial power plants) to confirm if the performance of the
facilities and equipment complies with the technical standards prescribed by laws andordinances.
2.
Operational Safety Inspection
The regulatory body conducts the Operational Safety Inspection by a resident Nuclear
Safety Inspector four times a year to confirm operators’ compliance with the Operational
Safety Program.

G3

Siting of proposed facilities

Article 6
1. Each Contracting Party shall take the appropriate steps to ensure that procedures are establishedand implemented for a proposed spent fuel management facility:(i) to evaluate all relevant site-related factors likely to affect the safety of such a facility during its
operating lifetime;(ii) to evaluate the likely safety impact of such a facility on individuals, society and the environment;(iii) to make information on the safety of such a facility available to members of the public;(iv) to consult Contracting Parties in the vicinity of such a facility, insofar as they are likely to beaffected by that facility, and provide them, upon their request, with general data relating to thefacility to enable them to evaluate the likely safety impact of the facility upon their territory.
2. In so doing, each Contracting Party shall take the appropriate steps to ensure that such facilities
shall not have unacceptable effects on other Contracting Parties by being sited in accordance withthe general safety requirements of Article 4.

G3.1

Evaluation of site-related factors

In Japan, evaluation of relevant site-related factors and safety impact of the proposed facility
is conducted during the licensing process of each activity. The criteria for the license are that“granting of the license does not impair the planned implementation of the nuclear
development and utilization programs; the applicant has adequate technical capability and
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financial basis to appropriately carry out the proposed activity; and the location, structureand systems of the proposed facility does not impair the prevention of the hazards due tonuclear fuel materials or the materials contaminated with nuclear fuel materials”. The
specific evaluation items for the technical capability and the prevention of hazards are listed
in a guides developed by the Nuclear Safety Commission (NSC) and are used for the review
of an application by the regulatory body.
The progress since the previous report is that an application was filed for the license of aspent fuel storage. This application will be processed according to the procedures describedin this section.
One who plans to operate a spent fuel storage facility has to be licensed by the Minister of
Economy, Trade and Industry in accordance with the provisions of the Nuclear Reactor
Regulation Law.
The license application document must include the descriptions on “the type and storage
capacity of spent fuel to be stored”, “the location, structure and systems of the spent fuelstorage facility and the storage method”, and “the method for removing spent fuel after thetermination of storage”. The document must be supplemented by explanatory materials on“the conditions of meteorology, ground structure, hydrology, seismology, social environment
at the site of the proposed spent fuel storage facility” and “the safety design of spent fuelstorage facility”. With these information, the applicant is required to make an evaluation ofsite conditions for the spent fuel storage facility.
The Ministry of Economy, Trade and Industry examines the application and confirms that“granting of the license does not impair the planned implementation of the nuclear
development and utilization programs"; "the applicant has adequate technical capability andfinancial basis to appropriately carry out the proposed activity"; and "the location, structureand systems of the proposed facility does not impair the prevention of the hazards due tonuclear fuel materials or the materials contaminated with nuclear fuel materials”. Based on
this confirmation, the Minister grants the license after consulting with the Atomic Energy
Commission and the NSC.
The NSC established "Safety Review Guide for Spent Fuel Interim Storage Facility using
Metallic Dry Casks" (see Section L Table G5-1), which is being applied to the safety
evaluation of the spent fuel storage facility currently under safety review.
The above Guide provides that the following matters shall be taken into account as basic
siting conditions to ensure the safety of the facility.
1.
Natural phenomena(1) Natural phenomena such as earthquake, tsunami, landslide, depression, typhoon,
high tide, flooding, abnormal cold weather and heavy snow(2) Geological conditions and landform etc. such as ground condition, soil bearing
capacity and faults,(3) Meteorological conditions such as wind direction, wind velocity and waterfall(4) Hydrospheric and hydraulic conditions such as rivers and underground water
2.
Social environment(1) Fires and explosions at a neighboring factory etc.
(2) Missiles etc. by air craft crash etc.
(3) Conditions of land use in relation to food production such as agriculture, livestock
farming and fishery industry, and conditions of population distribution etc.
G3.2

Information for general public

The license application documents and other related information are made open to the
public at the Nuclear Energy Library and at the Nuclear Library Room of the Japan Nuclear
Energy Safety Organization, except for the information relevant to nondisclosure causessuch as safeguards and commercial sensitiveness. Such information is also accessible andavailable at the National Diet Library. A document requested to an administrative agency
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under the ”Act on Access to Information held by Administrative Organs“ is also disclosed inaccordance with the provisions of the Act, unless it is subject to nondisclosure causes.
G3.3

Relation with neighboring contracting parties

Being an insular country, Japan is located at a considerable distance from its neighboring
countries. Therefore, as long as the safety of nuclear facilities is properly secured within
Japan, nuclear facilities in the country are unlikely to have safety impacts on the neighboring
countries. The government of Japan does not have it a rule to consult the neighboring
countries about siting of nuclear facilities. The Government of Japan provides neighboring
countries with information on nuclear energy through bilateral consultation, etc. The
government of Japan will release information promptly in the case when any significant
event has occurred at any of nuclear installation in Japan.

G4

Design and Construction of facilities

Article 7
Each Contracting Party shall take the appropriate steps to ensure that:(i) the design and construction of a spent fuel management facility provide for suitable measures tolimit possible radiological impacts on individuals, society and the environment, including those fromdischarges or uncontrolled releases;(ii) at the design stage, conceptual plans and, as necessary, technical provisions for thedecommissioning of a spent fuel management facility are taken into account;(iii) the technologies incorporated in the design and construction of a spent fuel management facility
are supported by experience, testing or analysis.

G4.1

Prevention of radiological impacts on individuals, society and the environment

A licensee for nuclear reactor establishment, spent fuel storage or reprocessing mustdescribe the design and construction methods for the relevant spent fuel storage facility inthe application document for the approval of the design and construction methods for the
proposed facility and must attach a document demonstrating the conformity of design andconstruction methods to the technical standards applicable to the proposed facility. The
Minister of Economy, Trade and Industry examines the application and gives approval after
confirming that the design and construction methods are consistent with the "contents oflicense” and the “technical standards”.
The "technical standards for the design and construction methods” for spent fuel storage
facility provides the standards for confinement function, shielding, etc., to prevent radiation
hazards (see Section L: Table G4-1).
The design, construction and inspection of a commercial nuclear power reactor facility isgoverned by the “Electricity Utilities Industry Law” instead of the “Reactor Regulation Law”,
but the requirements are essentially the same.
G4.2

Provisions for the decommissioning of a spent fuel management facility at the design
stage

Reactor facility and reprocessing facility as well as spent fuel storage facility have spent fuelstorage system which is regulated by the Reactor Regulation Law and other relevant laws
individually for each activity. When abolishing the facility, the operator has to establish adecommissioning program and get the approval for it from the Minister of Economy, Tradeand Industry.

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G4.3

Technologies incorporated in the design and construction of a spent fuelmanagement facility

At the stage of design and construction, a licensee applies the proven technologies insideand outside Japan.
The regulatory body is promoting the studies on the safety of nuclear facilities,
environmental radiations and radioactive waste. The safety studies on nuclear facilities arebeing conducted with the objectives to respond to the expansion and diversification of futurenuclear development and utilization and to promote the public consensus on the safety of
nuclear facilities. In particular, the studies for developing safety standards, safety guides andreference documents for safety review and the studies for safety improvement are being
conducted by the Japan Atomic Energy Agency (JAEA), the Japan Nuclear Energy Safety
Organization (JNES), the Central Research Institute of Electric Power Industry and otherinstitutes. For example, JNES is conducting the development of the standards, the long-term
integrity tests, and the development and improvement of safety analysis codes for theintermediate storage of spent fuel.
In the process of safety review of nuclear facilities, the regulatory body conducts, as
appropriate, independent analyses to confirm the validity of applicant’s safety analysis
results. A recent example related to this Convention is that the regulatory body conductedindependent analyses for criticality, shielding, heat removal, structures and seismic design
as a part of the safety review for the license application of the Recycle Fuel Storage Center.

G5

Assessment of Safety of facilities

Article 8
Each Contracting Party shall take the appropriate steps to ensure that:(i) before construction of a spent fuel management facility, a systematic safety assessment and an
environmental assessment appropriate to the hazard presented by the facility and covering its
operating lifetime shall be carried out;(ii) before the operation of a spent fuel management facility, updated and detailed versions of thesafety assessment and of the environmental assessment shall be prepared when deemednecessary to complement the assessments referred to in paragraph (i).

G5.1

Safety and environmental assessment of a spent fuel management facility

In Japan, activities concerning the spent fuel storage within reactor facilities, spent fuelstorage facilities, and reprocessing facilities are corresponding to spent fuel management
defined in the Convention. These activities are individually subject to the license under theReactor Regulation Law. An applicant for an each license carries out a systematic safetyassessment and an assessment of radiological impacts on the environment, including theassessment of the meteorology, ground structure, hydraulic phenomena, earthquake, social
environments around the site and safety design of the facility. On the basis of suchassessments, the regulatory body examines the appropriateness of siting and basic designof the facility, systems and components from the viewpoint of hazard prevention.
The guide "Safety Review Guide for Spent Fuel Interim Storage Facility using Metallic Dry
Casks" provides for radiation control, environmental safety, criticality safety and other safetymeasures assuming 40-60 year period of spent fuel storage.
G5.2

Update of safety and environmental assessment of a spent fuel management facility

The Reactor Regulation Law provides for the procedures for "licensing and notification ofmodification" to appropriately address a change of the descriptions in the application
documents for the license granted in accordance with the Law. Thus the procedures are inplace for updating and detailing the safety assessment and environmental assessment when
deemed necessary to complement those assessments.
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G6

Operation of facilities

Article 9
Each Contracting Party shall take the appropriate steps to ensure that:(i) the licence to operate a spent fuel management facility is based upon appropriate assessments as
specified in Article 8 and is conditional on the completion of a commissioning programmedemonstrating that the facility, as constructed, is consistent with design and safety requirements;(ii) operational limits and conditions derived from tests, operational experience and the assessments,
as specified in Article 8, are defined and revised as necessary;(iii) operation, maintenance, monitoring, inspection and testing of a spent fuel management facility are
conducted in accordance with established procedures;(iv) engineering and technical support in all safety-related fields are available throughout the operating
lifetime of a spent fuel management facility;(v) incidents significant to safety are reported in a timely manner by the holder of the licence to theregulatory body;(vi) programmes to collect and analyze relevant operating experience are established and that theresults are acted upon, where appropriate;(vii) decommissioning plans for a spent fuel management facility are prepared and updated, as
necessary, using information obtained during the operating lifetime of that facility, and are reviewed
by the regulatory body.

G6.1

Permission to operate a spent fuel management facility

The Reactor Regulation Law provides that spent fuel storage facility shall not be used before
getting through the inspections conducted by the Minister of METI for the construction andperformance of the facility. The facility passes the pre-serve inspection only if it is confirmedthat "the construction has been done in accordance with the approved design andconstruction plan" and "the performance of the facility meets the technical standards for
performance". "The technical standards for performance" are specified by the Minister of
METI as follows:
The alarm system, emergency power supply system and other emergency systems andinterlocks (devices to actuate the systems or equipment only under specific conditions)described in the license application documents or their annexes shall operate reliably
under the conditions described in those documents.
The radioactive waste disposal systems shall have more capability than described in thelicense application documents or their annexes.
The main radiation control systems shall the capability described in the license
application documents or their annexes.
Dose equivalent rate and concentrations of airborne radioactive materials in thealways-manned areas of the spent fuel storage facility, the areas with workers during theoperation of the facility, and other areas that require radiation control shall be less thanthose described in the license application documents or their annexes.
Capabilities for preventing spent fuel from reaching criticality and for confining spent fueland spent-fuel-contaminated materials within restricted areas shall meet the capabilities
described in the license application documents or their annexes.
The same steps as described above for spent fuel storage facility are taken also for reactor
facility and reprocessing facility that are within the scope of spent fuel management facilities
defined in this Convention.
As described above, steps are taken in Japan to ensure that the license to operate a spent
fuel storage facility is based upon appropriate assessments as specified in Article 8 and isconditional on the completion of the pre-service inspection demonstrating that the facility, as
constructed, is consistent with design and safety requirements.
G6.2

Operational limits and conditions

The operator regulated by the Reactor Regulation Law must establish “Operational Safety
Program” and obtain approval before starting operation of the facility. The Operational
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Safety Program have to specify concrete steps for operation of the facility, checks and themaintenance of the facility, radiation monitoring and quality assurance and so on. The
operation and maintenance of the facility have to be performed in accordance with thespecific operational limits defined in the Operational Safety Program. The operator must
undergo quarterly inspection (Operational Safety Inspection) by the regulatory body toconfirm the compliance with the Operational Safety Program. In addition, the conformity of
the facility performance to prescribed technical standards and measures for the
maintenance of the facility are confirmed by annual periodic inspection of the facility andother inspections. When any violation is found by those inspections, the Minister of METI
may order the operator to take necessary safety steps such as suspension of operation,
modification, repair, or instruction on the facility operation.
G6.3

Operation, maintenance, monitoring, inspection and testing of a spent fuelmanagement facility

When operating a spent fuel storage facility, the operator must take safety steps for“maintenance of spent fuel storage facility”, “operation of spent fuel storage facility ” and“transportation of spent fuel or transportation, storage and disposal of the materials
contaminated with spent fuel” in accordance with the provisions of the Reactor Regulation
Law. As safety steps, “access control to controlled areas”, “measures for radiation dose”,“patrol and inspection of spent fuel storage facility”, “periodical self-inspection of spent fuelstorage facility”, “operation of spent fuel storage facility”, “on-site transportation”, “on-sitewaste management”, and “Periodical Safety Review of spent fuel storage facility” areprovided in a ministerial ordinance.
The operator must establish its Operational Safety Program covering the above steps andobtain approval of the Minister of Economy, Trade and Industry before starting operation of
the facility. (Items to be described in the Operational Safety Program are shown in the
Section L Table G6-1.)
In addition, operator must undergo Safety Inspection conducted quarterly by the Minister of
Economy, Trade and Industry to check the status of compliance with the Operational Safety
Program.
The same steps are taken also for reactor facility and reprocessing facility that are within thescope of spent fuel management facilities defined in this Convention.
G6.4

Engineering and technical support in all safety-related fields

During operation of a facility, the regulatory body obtains engineering and technical advice ofexpert committees on operational management, inspection and radiation control and feeds it
back, when necessary, to the safety regulation on operation and maintenance.
For example, the NISA has a system to collect experts' engineering and technical advice
through the deliberations on the specific safety regulation policies by the advisory councils
set up under the Nuclear and Industrial Safety Subcommittee of the Advisory Committee for
Natural Resources and Energy.
Operators are accumulating the latest technological information through collecting domestic
and overseas operational experience information, technological development on their own
funds, maintenance activities, etc. Contractors, Academic Societies and Industrial
Associations are also making a variety of supporting activities.
G6.5

Report to the regulatory body in a timely manner by the licensee

The Reactor Regulation Law provides that an operator shall report without delay the statusof the event and other necessary matters when an accident accompanying personal injury(including the case with potential personal injury) or a failure or other event has occurred in areactor facility, a spent fuel storage facility, or a reprocessing facility. Reportable events are
specified by a ministerial ordinance that regulates the business concerned. Examples of84

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reportable events are shown in the Section L table G6-3.
G6.6

Programs to collect and analyze relevant operating experience

Upon receipt of a report on an accident or failure, the regulatory body immediately makes it
open, examines and evaluates the status of cause investigation and recurrence-prevention
measures and publicize the results. The information on the accident or failure is further
investigated to extract lessons on safety and to improve safety regulation as appropriate.
For the accumulation of information, the NISA instructs the JNES to maintain a system tocollect and evaluate domestic and overseas safety information. The accumulated
information is shared between NISA and JNES through the regular “Safety Information Study
Meeting” to appropriately feed back the information to a regulatory response or its follow-up.
As for international information exchange, Japan shares accident/failure information throughcooperation with international organizations such as the International Atomic Energy Agency(IAEA) and the Nuclear Energy Agency of the Organization for Economic Cooperation andDevelopment (OECD/NEA) as well as through bilateral cooperation.
The electric utilities collect and analyze domestic and overseas information on operating
experiences in their own companies and in the Central Research Institute of Electric Power
Industry. The electric utilities established the Nuclear Information Archive “NUCIA”, as a toolfor national sharing of safety information about domestic commercial nuclear power plants
including information on minor events, and released to the public on internet(http://www.nucia.jp/) in October, 2003. The electric utilities exchange information on
operating experience with foreign counterparts through the Institute of Nuclear PowerOperations (INPO) and the World Association of Nuclear Operators (WANO) Tokyo Center.
In addition, each electric utility has information exchange agreements with reactor
manufacturers and electric utilities in France, Germany, the United States and othercountries to collect information. Based of recognition of the importance of safety information
sharing and cultivation of safety culture throughout the nuclear industry, a privateorganization "NS Net" was established in December, 1999 jointly by concerned bodies tomake continuous activities including peer reviews. NUCIA and NS Net were integrated into
the Japan Nuclear Technology Institute (an intermediate corporation limited) in April, 2005
and have been actively continuing their activities.
G6.7

Decommissioning plans for a spent fuel management facility

An operator that plans to abolish its facility must take necessary steps for “decommissioning”
such as dismantling of the facility, assignment of nuclear fuel material inventory and disposalof materials contaminated with nuclear fuel materials. For that purpose, the operator has toestablish a “decommissioning program” and obtain an approval of the Minister of Economy,
Trade and Industry for it.
The criteria for approving decommissioning program are that all nuclear fuel materials havebeen removed from the facility; nuclear fuel materials are appropriately assigned; nuclear
fuel materials and materials contaminated with nuclear fuel materials are appropriately
managed and disposed; decommissioning work is appropriately implemented in a way toprevent a hazard due to nuclear fuel materials or materials contaminated with nuclear fuelmaterials. The information obtained during operation of the facility to be decommissioned
should be used for the management and disposal of contaminated material and hazard
prevention. Therefore, the decommissioning program is developed by using the information
obtained during the operating period of the facility. The procedures for “Approval for
Modification of Decommissioning Program” are provided to allow update of thedecommissioning program when necessary. In addition, the process of approval fordecommissioning program ensures that the plan is reviewed by the regulatory body.

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Safety of Radioactive Waste Management

Section H

Safety of Radioactive Waste Management

In Japan, activity related to radioactive waste consists of following activities; waste treatment,
storage and disposal. Waste treatment means all activities that relate to the handling,
pretreatment, treatment, conditioning, or on-site storage of radioactive waste. Radioactive
waste management in all Japanese nuclear facilities including nuclear reactor facility andreprocessing facility is in the scope of the Convention. Since the waste management in a fuelprocessing facility, spent fuel storage facility and reprocessing facility is governed by thesimilar safety regulation system to that for the specific waste storage, the safety regulation
system for the specific waste storage is described in this section as a representative, unlessspecially noted. The design, construction and inspection of a commercial nuclear powerreactor is governed by the “Electricity Utilities Industry Law” instead of “Law for Regulation of
Nuclear Source Material, Nuclear Fuel Material and Nuclear Reactors (Reactor Regulation
Law)”, but the requirements of both Laws are essentially the same.
Therefore, this section describes the safety regulation of “waste disposal and waste storage.”
In Japan radioactive wastes are grouped into “high level radioactive waste (hereinafterreferred to as “HLW”)” that is generated from spent fuel reprocessing and other “low level
radioactive waste (hereinafter referred to as “LLW”).” The LLW is further classified into“long-lived low-heat-generating radioactive waste (hereinafter referred to as “TRU waste”)”
which is generated from operation and dismantling of reprocessing facilities or MOX fuelfabrication facilities, “uranium waste” which is generated mainly from nuclear fuel fabrication
facilities, “power-plant waste” which is generated from nuclear power plants, and“research-facility waste” which is generated from research facilities and radioisotope
utilization facilities.
Depending on radioactivity characteristics of radioactive waste to be disposed of and on theconditions of geological environment, radioactive waste is finally disposed of with any of the“geological disposal” in a stable geologic stratum, “intermediate depth disposal” in theunderground deeper than 50 meters, “near surface pit disposal” in a structure such asconcrete pit in relatively shallow underground near the surface and the “near surface trenchdisposal” directly in shallow underground (see Fig.L6-1). Wastes with very low radioactive
concentration which does not need to be dealt with as radioactive waste (wastes cleared from
regulation) can be exempted from the radioactive waste control, after confirmed by theregulatory body.
The HLW is a stabilized waste in the form of “vitrified waste.” The liquid effluent containing
fission products separated through the spent fuel reprocessing process is solidified with glass
frit at an elevated temperature and put into a stainless steel canister and sealed to form
vitrified waste. The vitrified waste is stored for 30 to 50 years for cooling in the specific waste
storage facility, and then finally disposed of (geological disposal, see Fig.6-4-1), being isolated
from the environment.
Highly radioactive “TRU waste” is to be geologically disposal of like high level radioactive
waste, and is regulated in the same way.
Geological disposal deals with high radioactive TRU waste containing many long-lived
nuclides that require very careful radiation control (see Fig.L6-4-2). Since HLW needs to beisolated from the environment over a long period of time, enhanced regulatory procedures areapplied, in addition to the safety regulation for LLW, to ensure reliable closure of anunderground facility through approval of a closure program and confirmation that the steps
have been taken as described in the approved closure program.
Low radioactive TRU wastes generated from the operation and disassembling of reprocessing
facility or MOX fuel fabrication facility and power-plant wastes are finally disposed of with anyof the “intermediate depth disposal (see Fig.L6-3-1)”, “near surface pit disposal (seeFig.L6-2)” or “near surface trench disposal”, depending on the radioactive nuclides and theirradioactivity concentration, and step-wise control is conducted according to radioactive decay.
Waste from Research Facilities, etc. is to be disposed of by the method of “near surface
trench disposal” or “near surface pit disposal”
Figure H-1 shows the safety regulation process for Category 1 disposal and Category 286

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disposal.
The amendment of the Law concerning Prevention from Radiation Hazards due toRadioisotopes etc. (Radiation Hazards Prevention Law) in June 2004 and subsequent rules
and ordinances amendment provides basic framework of disposal.

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Category 2 Waste Disposal(other than geological disposal)

Category 1 Waste Disposal(geological disposal)

2

Confirmation of
Disposal Facility

Confirmation ofWaste Package

Confirmation ofWaste Package

Operational
Safety Inspection

Operational
Safety Inspection

Physical Protection
Inspection

Operation

Periodic Safety Review *1

Confirmation of
Disposal Facility

Physical Protection
Inspection(only for intermediate
depth disposal)

Facility Periodic
Inspection

Approval of
Decommissioning
ProgramConfirmation of
Decommissioning

Decommissioning

Confirmation of
ClosureBackfill of shafts
and tunnels

Approval of
Closure Program( only for intermediate depth disposal )*Pre-Service
Inspection

Basic Design

Approval of Design
and Construction

LicenseConstruction

License

Periodic Safety Review

H

Approval of
Decommissioning
ProgramConfirmation of
Decommissionin*1: At an interval not exceeding 20 years after grant of license or when closure program or decommissioning
program of auxiliary facility is planned.
*2: At an interval not exceeding 20 years after grant of license or when stage of step-wise control advances.

Fig.H-1 Safety regulation processes for “Category 1 waste disposal” and “Category 2
waste disposal.”

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H1

General safety requirements

Article 11
Each Contracting Party shall take the appropriate steps to ensure that at all stages of radioactive waste
management individuals, society and the environment are adequately protected against radiologicaland other hazards. In so doing, each Contracting Party shall take the appropriate steps to:(i) ensure that criticality and removal of residual heat generated during radioactive waste
management are adequately addressed;(ii) ensure that the generation of radioactive waste is kept to the minimum practicable;(iii) take into account interdependencies among the different steps in radioactive waste management;(iv) provide for effective protection of individuals, society and the environment, by applying at thenational level suitable protective methods as approved by the regulatory body, in the framework of
its national legislation which has due regard to internationally endorsed criteria and standards;(v) take into account the biological, chemical and other hazards that may be associated withradioactive waste management;(vi) strive to avoid actions that impose reasonably predictable impacts on future generations greaterthan those permitted for the current generation;(vii) aim to avoid imposing undue burdens on future generations.

H1.1

Prevention of criticality and removal of residual heat1.
Measures to prevent criticality
In Japan, spent fuel is to be reprocessed and, therefore, is not dealt with as radioactive
waste.
As the radioactive wastes dealt with in Japan contain almost no fissile nuclide. When there
is no need to consider the criticality due to extremely low concentration of nuclear material
such as uranium-235 or plutonium-239, criticality-prevention capability is not required.
2.
Measures for residual heat removal
Adequate heat removal measures are taken in every step of handling process for HLW thatgenerate decay heat.
Specifically, for the “specific waste storage” to temporarily store HLW, adequate removal of
decay heat is taken into consideration in the safety design of the facility.
HLW disposal facility is designed to prevent degradation of barrier material or waste itself
by increasing temperature by residual heat. However, through the term from receive the
HLW, settlement and burial, closure, under some conditions of types, quantities
concentrations and of radioactive materials, significant heat could be generated byradioactive decay. If such heat could significantly degrade the confinement or shielding
function, cooling function should also be considered as appropriate.
H1.2

Minimization of generation of radioactive waste

Laws and regulations in Japan do not require the minimization of radioactive waste
generation, but the "Framework for Nuclear Energy Policy" provides for the principle ofminimization of radioactive waste generation. In addition, radioactive waste storage facilities
and radioactive waste disposal site have only limited capacities. Therefore, the necessity tominimize radioactive waste generation is widely recognized.
In Japan, spent fuel is reprocessed to recycle valuable materials as a part of fuel cycle inaccordance with the nation’s fundamental nuclear energy policy. It is understood that
reprocessing of spent fuel is more effective than direct disposal in reducing the amount ofhigh level radioactive wastes.
Operators are striving to minimize the amount of radioactive wastes generated from theoperation of their activity by appropriate measures such as evaporation/concentration ofliquid radioactive wastes and incineration of solid radioactive wastes.
By establishing the clearance system, a part of concrete waste generated from thedecommissioning of a nuclear facility can be dealt with as an object cleared from regulation
which does not need to be dealt with as radioactive waste. That can contribute to the
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reduction of radioactive wastes.
H1.3

Interdependencies among the different steps in radioactive waste management

The waste treatment processes for disposal are designed considering final disposal of waste.
For example, high level vitrified radioactive waste is packed enclosed into a container called
canister, the geometry of which is designed for common handling at reprocessing facility
where the waste is generated, waste storage facility for temporary storage, and Category I
waste disposal facility for final disposal.
Radioactive waste controlled by Radiation Hazards Prevention Law, is also handled in thesimilar way in the waste treatment process, considering the final disposal, etc.
H1.4

Protection of individuals, society and the environment

Japanese laws and regulations adopt the recommendations of the International Commission
on Radiological Protection (ICRP) as the criteria for radiation protection. One of the criteria
unique to radioactive waste disposal facility is the reference dose set up for the terminationof regulatory control. The “Basic Guides for Safety Review for Radioactive Waste Burial
Facilities” established by the Nuclear Safety Commission (NSC) defines the reference doseas “a dose low enough for terminating control of public exposure from a waste repository”.
The Basic Policy Subcommittee of the Radiation Council adopted 10HSv/y as the dose thatexempts regulatory control, in its report “The Dose Level for Regulatory Control Exemption
for Near Surface Disposal of Solid Radioactive Wastes (1978)”. This value was officiallyadopted by the Radiation Council on the basis of the ICRP recommendations and the IAEA
standards and is used as the reference dose that exempts radiation control.
In July 2007, the NSC made a report on the introduction of risk assessment to take theuncertainty into the consideration for very long term safety evaluation of final disposal after
the termination of regulatory control period. In the repot, based on the concept of ICRP, thethree scenarios “Basic Scenario”, “Changeable Scenario” and “Human/Very Rare Event
Scenario” were proposed for the safety evaluation. Using dose/probability resolution
approach in which the each possibility of occurrence and effect was compared with eachscenario, the risk was assessed and the criteria to the each scenario of radiation protection
were also proposed as 10HSv/y, 300HSv/y and 10-100mSv/y according to the ICRP
recommendation.
Now the NSC is in process to revise “Basic Guides for Safety Review for Radioactive Waste
Burial Facilities” basing on the above concept.
H1.5

Biological, chemical and other hazards that may be associated with radioactive
waste management

The Reactor Regulation Law requires that nuclear facilities shall not impair the prevention of
hazards due to nuclear fuel materials and materials contaminated with nuclear fuel materials,
and also requires the measures for preventing loss of functions to confine the wastes due tovarious causes. For example, in the process of radioactive waste treatment for disposal, afabrication facility is required to use waste containers of corrosion-resistant leak-tight design
to prevent leakage of waste and to take account of effects of chemicals.
In a reprocessing facility, various chemicals including organic solvent are used and they
could be entrained into the wastes generated at the facility. To cope with that, the “Rule on
the Technical Standard for the Design and Construction Methods of Reprocessing Facility”
provides for legal requirements, for example, for the handling of organic solvent to prevent
damages due to fire, the measures to prevent hydrogen gas generated from high level liquidradioactive waste from accumulating in a storage tank, and the storage methods ofextremely oxidizable solid waste like zirconium metallic powder.
As for a waste disposal facility, the “Rules on the Technical Standard for the Design andConstruction Methods of Specific Waste Disposal Facility or Specific Waste Storage Facility”
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requires that a disposal facility shall take explosion-prevention measures for the systems tohandle or manage radioactive waste that could generate hydrogen. In addition, the law andregulation on disposal business provide necessary measures to prevent a waste package
from containing materials that could impair its integrity. The similar measures are required by
Radiation Hazards Prevention Law.
H1.6

To avoid impacts on future generations

In Japan, radioactive wastes generated from the operation of individual nuclear related
activities are finally disposed of at a waste disposal site after appropriate treatment andstorage within the site. According to the safety regulation for final disposal of radioactive
waste, HLW and TRU wastes containing radioactive materials that exceed the levelspecified in the Enforcement Ordinance for the Reactor Regulation Law are disposed of in astable stratum according to radiological characteristics and geological environment, other
TRU wastes are disposed of at an intermediate depth more than 50 meters, and otherwastes are disposed of at a near surface pit or trench. These steps are to isolate radioactive
wastes from the environment appropriately according to their characteristics and conditions.
By taking such safety regulatory steps, it can be avoided as far as reasonably achievable toimpose impacts on future generations than those permitted for the current generation.
H1.7

To avoid imposing undue burdens on future generations

In order to avoid imposing undue burdens on future generations, the cost and managementof disposal are legally specified. (see Section B)

H2

Existing facilities and past practices

Article 12
Each Contracting Party shall in due course take the appropriate steps to review:(i) the safety of any radioactive waste management facility existing at the time the Convention enters
into force for that Contracting Party and to ensure that, if necessary, all reasonably practicable
improvements are made to upgrade the safety of such a facility;(ii) the results of past practices in order to determine whether any intervention is needed for reasons ofradiation protection bearing in mind that the reduction in detriment resulting from the reduction indose should be sufficient to justify the harm and the costs, including the social costs, of theintervention.

H2.1

Review the safety of existing radioactive waste management facility

In Japan, the regulatory body regularly inspects the performance of the facilities and thecompliance with the Operational Safety Program for the radioactive waste management
facilities defined in the Convention. In addition, periodic assessment system is implemented
in order to ensure the safety of nuclear facilities. For waste disposal, the ministerial
ordinance governing such activity requires as follows:
1.
Category 1 waste disposal
For the waste disposal site with geological disposal, periodic assessment of the control ofradiation exposure due to nuclear fuel materials or materials contaminated with nuclear
fuel materials shall be performed with the latest technical knowledge at an interval not
exceeding 20 years after obtaining license, and steps necessary for the preservation of thewaste disposal facility shall be taken on the basis of the assessment results. In addition,
the same steps shall be taken when a closure program or decommissioning program ofauxiliary facility is to be established.

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2.
Category 2 waste disposal
For the waste disposal site with intermediate depth disposal, periodic assessment of thecontrol of radiation exposure due to nuclear fuel materials or materials contaminated with
nuclear fuel materials shall be performed with the latest technical knowledge at an interval
not exceeding 20 years after obtaining license, and steps necessary for the preservation of
the waste disposal facility shall be taken on the basis of the assessment results. In addition,
the same steps shall be taken when the stages of step-wise control advances in responseto radioactive decay.
The above inspections conducted up to now identified no items which should be improvedfor continuous operation of the facilities.
H2.2

Review the results of past practices

As a result of review it is found that the past practices caused neither radioactive wastes nor
nuclear facilities that require any intervention for reasons of radiation protection.
In Japan, there are small amount of waste rock and mill tailings generated by past activities(test and research) as shown below.*1
Tunnel prospecting and mining and milling tests carried out in Ningyo Toge area,
Okayama prefecture from 1957 to 1978.
Tunnel prospecting carried out in Togo area, Tottori prefecture from 1958 until 1962.
Tunnel prospecting, solution mining test, and earth sciences research of geologic
environment carried out in Tono area, Gifu prefecture from 1972 until 2003.
These sites are managed as ceased mine under the Mine Safety Law. The amounts ofwaste rock and mill tailings are shown in the following table.
Table H2-1
Area
Ningyo Toge mine
Togo mine
Tono mine

The amounts of waste rock and mill tailings
Classification
Volumewaste rockabout 330000 m3
mill tailings
about 34000 m3
waste rockabout 32000 m3
waste rockabout 10000 m3

For radiation protection, these sites are managed under the Mine Safety Law so as not toexceed 1 mSv/year at the boundary of peripheral monitoring area.
The operator related to these sites is Japan Atomic Energy Agency (Independent
Administrative Agency) and the operator is studying to use these waste rocks as aconstruction material.
*1:

As these waste rock and mill tailings are not defined as radioactive wastes in Japan,
these materials are out of scope of the Convention in accordance with Article 2 of theConvention. However the status of these wastes are reported here in accordance with
Paragraph 70 of the Summary Report JC / RM.1 / 06 / Final version (••••In relation touranium mining and milling wastes, Contracting Parties with such wastes agreed toinclude them in their National reports. ••••).

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H3

Siting of proposed facilities

Article 13
1. Each Contracting Party shall take the appropriate steps to ensure that procedures are establishedand implemented for a proposed radioactive waste management facility:(i) to evaluate all relevant site-related factors likely to affect the safety of such a facility during its
operating lifetime as well as that of a disposal facility after closure;(ii) to evaluate the likely safety impact of such a facility on individuals, society and the environment,
taking into account possible evolution of the site conditions of disposal facilities after closure;(iii) to make information on the safety of such a facility available to general public;(iv) consult Contracting Parties in the vicinity of such a facility, insofar as they are likely to be affectedby that facility, and provide them, upon their request, with general data relating to the facility toenable them to evaluate the likely safety impact of the facility upon their territory.
2. In so doing, each Contracting Party shall take the appropriate steps to ensure that such facilities
shall not have unacceptable effects on other Contracting Parties by being sited in accordance withthe general safety requirements of Article 11.

H3.1

Evaluation of site-related factors

In Japan, evaluation of relevant site-related factors and safety impact of the proposed facility
is conducted during the licensing process of each activity. In the Reactor Regulation Law,
the criteria for the license are that “granting of the license does not impair the planned
implementation of the nuclear development and utilization programs; the applicant has
adequate technical capability and financial basis to appropriately carry out the proposed
activity; and the location, structure and systems of the proposed facility does not impair theprevention of the hazards due to nuclear fuel materials or the materials contaminated with
nuclear fuel materials”. The specific evaluation items for the technical capability and theprevention of hazards are listed in a guide developed by the NSC and are used for thereview of an application by the regulatory body.
The regulatory body, when approving operation of a radioisotope waste management facility
in accordance with the Radiation Hazards Prevention Law, conducts safety review to confirm
the descriptions in the application are in compliance with the siting conditions, standards on
facility, technical standards etc, provided in the Radiation Hazards Prevention Law andrelated regulations and standards, and approves when the application is confirmed
appropriate. It is provided that facilities should be located at a site where landslide andinundation are unlikely to occur.
The progress since the previous report is the development of the safety regulation system
for waste disposal. An example is described below for waste disposal.
One who plans to operate a radioactive waste disposal facility shall be licensed by the
Minister of Ministry of Economy, Trade and Industry in accordance with the provisions of theReactor Regulation Law.
The license application document must include the descriptions on “conditions and quantityof nuclear fuel material or matters contaminated with nuclear fuel material to be disposed of”,
“the location, structure and systems of the waste disposal facility and the disposal method”,
and “time schedule to advance the stages of step-wise control for the Category 2 waste
disposal facility in response to radioactive decay”. The document must be supplemented byexplanatory materials on “the conditions of meteorology, ground structure, hydrology,
seismology, social environment at the site of the proposed waste disposal facility” and “thesafety design of the waste disposal facility”. With these information, the applicant is required
to make an evaluation of site conditions for the waste disposal facility.
The Ministry of Economy, Trade and Industry (METI) examines the application and confirmsthat “granting of the license does not impair the planned implementation of the nuclear
development and utilization programs"; "the applicant has adequate technical capability andfinancial basis to appropriately carry out the proposed activity"; and "the location, structureand systems of the proposed facility does not impair the prevention of the hazards due tonuclear fuel materials or the materials contaminated with nuclear fuel materials”. Based on
this confirmation, the Minister grants the license after consulting with the Atomic Energy
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Commission (AEC) and the NSC.
As for specific radioactive waste, basing on the Specific Radioactive Waste Final Disposal
Act (Final Disposal Act), the METI has to consult for the amendment of final disposal planand basic policy on site selection of preliminary investigation areas, etc., with the AEC andthe NSC.
In September 2002 the NSC made the report on the environmental requirements, thosewere for earthquake, fault activity, volcano/volcanic activity, etc., at the stage of site selectionof preliminary investigation areas, to give necessary comments from the point of safety
regulation view and to establish the criteria to environmental requirements in the process ofamendment for final disposal plan, etc.
H3.2

Information for general public

The license application documents and other related information are made open to the
public at the Nuclear Energy Library and at the Nuclear Library Room of the Japan Nuclear
Energy Safety Organization (JNES), except for the information relevant to nondisclosure
causes such as safeguards and commercial sensitiveness. Such information is also
accessible and available at the National Diet Library. A document requested to an
administrative agency under the ”Act on Access to Information held by Administrative
Organs is also disclosed in accordance with the provisions of the Act, unless it is subject tonondisclosure causes.
Also as for the safety related information on a facility for waste disposal regulated by the
Radiation Hazards Prevention Law, a document requested under the ”Act on Access toInformation held by Administrative Organs“ is disclosed, unless it is subject to nondisclosure
causes.
In September 2006, the Radioactive Waste Subcommittee under the Nuclear Energy
Subcommittee of the Advisory Committee for Natural Resources and Energy reported to
expect the comprehensive safety explanatory (safety case), etc., when a business entity
makes the report on preliminary investigation result and detailed investigation.

H3.3

Relation with neighboring contracting parties

Being an islands country, Japan is located at a considerable distance from its neighboring
countries. And then, as long as the safety of nuclear facilities is properly secured within
Japan, nuclear facilities in the country are highly unlikely to have impacts on the neighboring
countries safety. Therefore the government of Japan does not have a rule to consult theneighboring countries about siting of nuclear facilities. The government of Japan provides
neighboring countries with information on the status of the nuclear energy of Japan throughbilateral consultation, and various exchange of opinions. Moreover, in the case when asafety significant event should occur at a facility in our country, Japan will provide promptand comprehensive information to the neighboring countries.

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H4

Design and construction of facilities

Article 14
Each Contracting Party shall take the appropriate steps to ensure that:(i) the design and construction of a radioactive waste management facility provide for suitablemeasures to limit possible radiological impacts on individuals, society and the environment,
including those from discharges or uncontrolled releases;(ii) at the design stage, conceptual plans and, as necessary, technical provisions for thedecommissioning of a radioactive waste management facility other than a disposal facility aretaken into account;(iii) at the design stage, technical provisions for the closure of a disposal facility are prepared;(iv) the technologies incorporated in the design and construction of a radioactive waste management
facility are supported by experience, testing or analysis.

H4.1

Prevention of radiological impacts on individuals, society and the environment

1.
Waste Storage facility
The holder of the license for Waste Storage must describe, in the application document for
the approval of the design and construction methods for the activity, the methods of thedesign and construction of the on-site waste treatment and storage systems for theradioactive wastes generated from the operation of the activity, and must demonstrate in
the attachments to the application document that the design and construction of the facility
are consistent with relevant technical standards. The Minister of Economy, Trade andIndustry reviews the application and issues a license when compliance with the technicalstandards is confirmed.
The “Technical Standard for the Design and Construction Methods” provides the standards
for the confinement function, shielding and other necessary features for the prevention ofradiological hazards. As an example of the technical standard for the design andconstruction methods, the “Technical Standard for the Design and Construction Methods
for Specific Waste Disposal Facility or Specific Waste Storage Facility” are shown in the
Section L Table H4-1.
2.
Category 1 waste disposal facility
The holder of the license for Category 1 waste disposal (Category 1 waste disposal
licensee) is required to obtain the approval for the design and construction methods for the
specific waste disposal facility including waste receiving system, waste handling system
and radiation control system prior to the start of construction, and to pass the Pre-Service
Inspection conducted by the Minister of Economy, Trade and Industry before starting
operation. The procedures and the technical standards for the design and construction
methods are the same as those for Waste Storage facility.
In addition, a Category 1 waste disposal facility is required to undergo Confirmation of
Disposal Facility by the Minister of Economy, Trade and Industry for the disposal site andthe shafts and tunnels for the duration of operation. The confirmation is made on thegeography, geology and groundwater at the disposal site as well as the design andstructure of the disposal facility, with the criteria “to be consistent with the contents
described in the license documents”, “not to dispose explosive materials, materials thatsignificantly corrode other materials and other hazardous materials in the waste disposalsite” and “to backfill the site as stated in the license document”. The waste to be disposedof has to undergo the Confirmation of Waste Packages carried out by the Ministry of
Economy, Trade and Industry to confirm that “the waste is encapsulated or solidified”,“radioactive concentration does not exceed the licensed level”, “the waste package has
sufficient strength to endure the loads imposed when disposed” and “the waste is not
significantly damaged.”3.
Category 2 waste disposal facility
The holder of the license for Category 2 waste disposal (Category 2 waste disposal
licensee) is not required to obtain the approval for the design and construction methods or
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to undergo pre-service inspection for the waste disposal facility by the Minister of Economy,
Trade and Industry, but is required to undergo Confirmation of Disposal facility performedby the Minister of Economy, Trade and Industry for the duration of operation. The waste to
be disposed of has to undergo the Confirmation of Waste Packages carried out by the
Ministry of Economy, Trade and Industry.
4.
Waste management facility under the Radiation Hazards Prevention Law
A person to obtain a permission of waste management service shall submit an application
for the permission to the MEXT. The application shall include the description documents on
the method of management, the locations, structures and equipments of waste refilling
facility, waste storage facility and waste management facility as attachments.
The provisions concerning the location, structure and equipment of each facility require theapplicant, in order to restrain possible radiological effects, to ensure that shielding walls,
other shields, ventilation equipments, and drainage equipments are consistent with thetechnical standards prescribed by laws and ordinances:
The license holder of the radioisotope waste management services is obligated to take
Pre-Service Facility Inspections by the Minster of MEXT or his/her representative andobtain its confirmation that the facilities comply with these technical standards.
H4.2

Provisions for the decommissioning of a radioactive waste management facility otherthan a disposal facility at the design stage

Radioactive waste depositories are installed as auxiliary facilities for the nuclear fuelfabrication facility, reactor facility, spent fuel storage facility, reprocessing facility andradioactive waste storage facility. The decommissioning procedures for each of thesefacilities are provided for by the Reactor Regulations Law and other relevant laws andregulations. At the stage of decommissioning, the license holder must establish adecommissioning program for each facility and have it approved by the Minister of Economy,
Trade and Industry.
Also, under the Radiation Hazards Prevention Law, at each stage (including
decommissioning) of license application, the license holder shall be subject to the approval
for the conformity to the technical standards applicable to the storage or processing facility
H4.3

Provisions for the closure of a disposal facility

Implementation of closure of a waste disposal facility must be described in the license
application documents for the radioactive waste disposal. When the Category 1 waste
disposal licensee plans to close the shafts and tunnels, the licensee is required to establish
a closure program and have it approved by the Minister of Economy, Trade and Industry.
H4.4

Technologies incorporated in the design and construction of a radioactive waste
management facility

When applying for approval of the design and construction methods, the operator must
demonstrate with analysis, etc. that the design and construction methods meet relevant
technical standards. The regulatory body reviews the application and issues an approval
after confirming that the design and construction methods meet relevant technicalstandards.
The operator must pass the pre-service inspection conducted by the regulatory body before
operating the facility.
Under the Radiation Hazards Prevention Law, similar process is applied.

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H5

Assessment of safety of facilities

Article 15
Each Contracting Party shall take the appropriate steps to ensure that:(i) before construction of a radioactive waste management facility, a systematic safety assessment
and an environmental assessment appropriate to the hazard presented by the facility and covering
its operating lifetime shall be carried out;(ii) in addition, before construction of a disposal facility, a systematic safety assessment and an
environmental assessment for the period following closure shall be carried out and the results
evaluated against the criteria established by the regulatory body;(iii) before the operation of a radioactive waste management facility, updated and detailed versions of
the safety assessment and of the environmental assessment shall be prepared when deemednecessary to complement the assessments referred to in paragraph (i).

H5.1

Safety and environmental assessment of a radioactive waste management facility

1.
General provisions
In Japan, fuel fabrication, establishment and operation of reactors, spent fuel storage,
reprocessing, waste storage, waste disposal and utilization of nuclear fuel materials fallwithin the scope of the radioactive waste management defined in the Convention. These
activities are individually subject to the license under the Reactor Regulation Law. An
applicant for a license carries out a systematic safety assessment and an assessment ofradiological impacts on the environment, taking into account the meteorology, groundstructure, hydraulic phenomena, earthquake, social environments around the site andsafety design of the facility. On the basis of such assessments, the regulatory bodyexamines the appropriateness of siting and basic design of the facility, systems andcomponents from the viewpoint of hazard prevention.
The guide prepared by the NSC for the safety review for each license provide, as the siting
conditions common to nuclear facilities, that “there should be no factor that could induce a
serious accident” and that “there should be little factors that could expand a disaster”. The“Basic Guides for Safety Review for Radioactive Waste Burial Facilities” is shown in
Section L Table H5-1 as an example of safety review guidelines.
2.
Waste Storage facility
The “Basic Approach for Safety Assessment of Radioactive Waste Management Facilities”
prepared by the NSC for the safety review of a Waste Storage provides that the seismic
design of a high level solid radioactive wastes storage facility shall be assessed includingthat shielding function as well as confinement function is adequately maintained during anearthquake.
In Japan, radioactive waste storage facility, same as one established with reprocessing
facility, etc., is established as an independent facility. In spite of the differences of type or
treatment process of waste, it is possible to conduct the safety evaluation of radioactive
waste storage facility in accordance with the same principal concept as reprocessing
facility, because the processes of the radioactive waste storage are involved in the waste
storage system of the reprocessing facility etc.
The general provisions described above are applied also to a waste storage.
3.
Category 1 waste disposal facility
An applicant for the Category 1 waste disposal license has to show the conditions andquantities of nuclear fuel materials or materials contaminated with nuclear fuel materials to
be disposed of, the location, structure and systems of the waste disposal facility as well as
disposal method to the Minister of Economy, Trade and Industry, and obtain license from
the Minister. The application will be reviewed, as is the case with other activities, inaccordance with the safety review guides prepared by the NSC. A basic approach to safety
review will be established by the NS in near future considering the progress of the disposal
activity.
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4.
Category 2 waste disposal facility
As for Category 2 waste disposal, the NSC prepared the “Basic Guides for Safety Review
for Radioactive Waste Burial Facilities” for “near surface disposal” (see attached tableH5-1). The safety assessment for the existing low level radioactive waste disposal has
been carried out according to this guide.
As for “intermediate depth disposal”, a basic approach to safety review will be establishedby the NSC in near future considering the progress of the disposal activity.
5.
Disposal Facility under the Radiation Hazards Prevention Law
For granting the license for the disposal facilities under the Radiation Hazards Prevention
Law, the competent regulatory body examines the appropriateness of the site conditions
and the compliance with the technical standards. Relevant guidelines and standards
require that the facility be constructed at a site that has little chance to be affected by landslide or flooding, to adopt fire-proof structures or to use incombustible materials for the
essential parts of the facility, and to provide with shielding function such as shielding walls.
H5.2

Safety and environmental assessment of after closure of a disposal facility

The safety of disposal facilities is regulated in accordance with the provisions of the Reactor
Regulation Law and its enforcement ordinance, and the Ministerial Ordinances or
Notifications such as the “Rules for Category 1 Waste Disposal” and the “Rules for Category
2 Waste Disposal.” These rules require the license application document to be attached by“explanation on the control of radiation exposure due to nuclear fuel materials, etc.” that also
describes long-term safety assessment including post-closure period. In addition, Periodic
Safety Review is conducted on the basis of the latest knowledge, to confirm that long-term
safety will be ensured also after the construction of a geological disposal facility orintermediate depth disposal facility. The assessment is performed at an appropriate timing(including timing necessary for technical succession in operators) as a part of safety steps
and the necessary measures are taken based on the assessment results. Through this
Periodic Safety Review, a systematic safety assessment and an assessment of radiologicalimpacts on the environment for the period following closure until termination of the activity
are carried out.
Regarding the period that requires radiation control, the “Basic Guides for Safety Review forRadioactive Waste Burial Facilities” provides 300 to 400 years as a target period for low
level radioactive wastes. This target period was determined considering foreign practices
and the fact that radioactivity of the nuclides important to radiation protection at waste
disposal facilities, Co-50 and Cs-137, is reduced by 1/1000 to 1/10000 after 300 to 400
years and becomes negligible. At disposal facilities without artificial barrier, only un-solidified
concrete wastes with low radioactivity are disposed of, therefore the radiation control of thesite is deemed to terminate in a reasonable period of time, as is the case with foreign
practices. The disposal stage plus subsequent 50 years of preservation stage is used as atarget of this “reasonable period of time”.
The Radiation Hazards Prevention Law is also in process to provide the same requirements.
H5.3

Update of safety and environmental assessment of a spent fuel management facility

The Reactor Regulation Law provides for the procedures for "licensing or notification ofchange of license" to appropriately address a change of the application documents for the
license granted in accordance with the Law.
The detailed design of the facility has to follow the procedures for “approval for the designand construction methods” and any change of the design or construction methods is also
subject to such procedures. In addition, the government confirms that the facility has been
built as approved through “pre-service inspection”.
The Radiation Hazards Prevention Law also provides the similar requirements.

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H6

Operation of facilities

Article 16
Each Contracting Party shall take the appropriate steps to ensure that:(i) the license to operate a radioactive waste management facility is based upon appropriate
assessments as specified in Article 15 and is conditional on the completion of a commissioning
programme demonstrating that the facility, as constructed, is consistent with design and safety
requirements;(ii) operational limits and conditions, derived from tests, operational experience and the assessments
as specified in Article 15 are defined and revised as necessary;(iii) operation, maintenance, monitoring, inspection and testing of a radioactive waste management
facility are conducted in accordance with established procedures. For a disposal facility the results
thus obtained shall be used to verify and to review the validity of assumptions made and to update
the assessments as specified in Article 15 for the period after closure;(iv) engineering and technical support in all safety-related fields are available throughout the operating
lifetime of a radioactive waste management facility;(v) procedures for characterization and segregation of radioactive waste are applied;(vi) incidents significant to safety are reported in a timely manner by the holder of the license to theregulatory body;(vii) programmes to collect and analyze relevant operating experience are established and that theresults are acted upon, where appropriate;(viii) decommissioning plans for a radioactive waste management facility other than a disposal facility
are prepared and updated, as necessary, using information obtained during the operating lifetimeof that facility, and are reviewed by the regulatory body;(ix) plans for the closure of a disposal facility are prepared and updated, as necessary, using
information obtained during the operating lifetime of that facility and are reviewed by the regulatory
body.

H6.1

Permission to operate a radioactive waste management facility

1.
Waste Storage and Category 1 waste disposal
The Reactor Regulation Law provides that Waste Storage facility and Category 1 waste
disposal facility shall not be used before getting through the Pre-Service inspections
conducted by the Minister of Economy, Trade and Industry for the construction andperformance of the facility. The facility passes the pre-serve inspection only if it isconfirmed that "the construction has been done in accordance with the approved designand construction plan" and "the performance of the facility meets the technical standards
for performance". "The technical standards for performance" are specified by the Ministerof Economy, Trade and Industry as follows:
The alarm system, emergency power supply system and other emergency systems
and interlocks (devices to actuate the systems or equipment only under specificconditions) described in the license application documents or their attacheddocuments shall operate reliably under the conditions described in those documents.
The radioactive waste disposal systems shall have more capability than described in
the license application documents or their attached documents.
The main radiation control systems shall have the capability described in the license
application documents or their attached documents.
Dose equivalent rate and concentrations of airborne radioactive materials in thealways-manned areas of the Waste Storage facility and Category 1 waste disposal
facility, the areas with workers during the operation of the facility, and other areas that
require radiation control shall be less than those described in the license application
documents or their attached documents.
2.
Category 2 waste disposal
Category 2 waste disposal requires no approval for the design and construction methods
nor pre-service inspection. However the waste disposal facility has to undergo the
Confirmation of Disposal Facility by the Minister of Economy, Trade and Industry. The
confirmation is conducted at the following timing:
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The confirmation regarding installation of the waste disposal facility is conducted when
the dimensions of the major parts of individual system become measurable, except forradiation control system.
The confirmation regarding installation of radiation control system is conducted when
the installation of the system is completed.
Confirmation regarding the shafts and tunnels (only for intermediate depth waste
disposal facility) is conducted when backfill of the shafts and tunnels and closure of themouth are carried out.
Confirmation regarding other items is conducted when the waste disposal facility iscovered with earth and sand or when the Minister of Economy, Trade and Industry
deems appropriate.
The confirmation is conducted according to the technical standards shown in the Section L
Table H6-1: “1. Technical Standard for Waste Disposal Facilities” and “2.TechnicalStandard for Radioactive Waste to be Disposed.”3.
Radioactive waste management under the Radiation Hazards Prevention Law
The operator of the waste management facility under the Radiation Hazards Prevention
Law shall be subject to the approval for the license as described in the previous section(paragraph H5.1). And the license holder shall be subject to pass the pre-service
inspection before the operation of the facility and shall not use the facility until after it has
passed the inspection.
As described above, Government of Japan takes steps to ensure that the license to operate
a waste disposal facility or waste storage facility is based upon appropriate assessments as
specified in Article 15 of the Convention and is conditional on the completion of acommissioning program demonstrating that the facility, as constructed, is consistent withdesign and safety requirements.
H6.2

Operational limits and conditions

The operator regulated by the Reactor Regulation Law must establish “Operational Safety
Program” and obtain approval before starting operation of the facility. The Operational
Safety Program have to specify concrete steps for operation of the facility, inspections ofmaintaining the facility, radiation monitoring and quality assurance. The operation andmaintenance of the facility have to be performed in accordance with the specific operational
limits defined in the Operational Safety Program. The operator must undergo quarterly
inspection (Operational Safety Inspection) by the regulatory body to confirm the compliancewith the Operational Safety Program. In addition, when the annual facility Periodic
Inspection indicates that performance of the Waste Storage facility and Category 1 waste
disposal facility does not comply with the technical standards, or the operational safetymeasures for the maintenance of the facility violate provisions of the ministerial order, theMinister of Economy, Trade and Industry may order the operator to take necessary
operational safety measures such as suspension of operation, modification, repair, or
instruction on the facility operation.
Operator licensed under the Radiation Hazards Prevention Law, before the start of operation,
shall prepare the Internal Rules for Prevention of Radiation Hazards specifying details ofinspections, radiation measuring and treatment of radioactive wastes, and notify it to the
Minister of MEXT. The Internal Rules shall specify operational requirements, and the facility
shall be operated and maintained in compliance with the Rules.

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H6.3

Operation, maintenance, monitoring, inspection and testing of a radioactive waste
management facility

1.
Waste Storage
When operating a Waste Storage facility, the operator must take operational safetymeasures for “maintenance of waste storage facility”, “operation of waste storage facility”
and “transportation and treatment (only within the premises of the facility that is installedwith the waste storage facility) of the nuclear fuel material or material contaminated by
nuclear fuel material” in accordance with the provisions of the Reactor Regulation Law.
Other measures for, “access control to controlled areas”, “measures for radiation dose”,“patrol and inspection of waste storage facility”, ”maintenance of waste storage facility”,“periodical self-inspection of waste storage facility”, “operation of facility relevant to waste
storage facility”, “Periodical Safety Review of waste storage facility”, “on-sitetransportation” and “on-site disposal” are provided for in a ministerial ordinance.
The operator must establish the Operational Safety Program covering the above measuresand obtain approval of the Minister of Economy, Trade and Industry before starting
operation of the facility. (Items to be described in the Operational Safety Program areshown in the Section L TableH6-2.)
In addition, operator must undergo Operational Safety Inspection conducted quarterly by
the Minister of Economy, Trade and Industry to confirm the status of compliance with the
Operational Safety Program.
2.
Category 1 and 2 waste disposal
For the use of waste disposal facility, the Reactor Regulation Law requires the same steps
as described above for Waste Storage facility. The Ministerial Ordinance provides for“periodic evaluation, etc. of waste disposal facility” as the steps to be taken after closure of
the waste disposal facility. Specifically, the Ministerial Ordinance requires “to evaluate theradiation exposure control due to nuclear fuel materials, etc. in the light of the latest
technical knowledge” and “to take necessary measures for the preservation of waste
disposal facility on the basis of the results of such evaluation”.
The timing of the assessment shall be: for Category 1 waste disposal, at an interval of lessthan 20 years after the date of grant of license and when a closure program ordecommissioning program is developed; and for Category 2 waste disposal of intermediate
depth disposal, at an interval of less than 20 years after the date of grant of license andwhen the stage of step-wise control.
3.
Waste management under the Radiation Hazards Prevention Law
Waste management license holder under the Radiation Hazards Prevention Law, before
the start of operation, shall prepare the Internal Rules for Prevention of Radiation Hazards
and notify it to the Minister of MEXT. The conformity to the Internal Rules shall be
confirmed through Periodic Inspections and the On the Spot Inspections conducted by the
Minister of MEXT or his representative, through these procedures the appropriate
operation of the facility is maintained. The results of the inspections are to be reflected in
the safety evaluation as it necessitate.

H6.4

Engineering and technical support in all safety-related fields

During operation of a facility, the regulatory body obtains engineering and technical advice ofexpert committees on operational management, inspection and radiation control and feeds it
back, when necessary, to operation, maintenance or safety regulation.
For example, the NISA has a system to collect experts' engineering and technical advice
through the deliberations on the specific safety regulation policies by the advisory councils
set up under the Nuclear and Industrial Safety Subcommittee of the Advisory Committee for
Natural Resources and Energy.
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Operators are accumulating the latest technological information through collecting domestic
and overseas operational experience information, technological development on their own
funds, maintenance activities, etc. Private technical support organizations are also making avariety of supporting activities.
H6.5

Characterization and classification of radioactive waste

The Reactor Regulation Law regulates the on-site waste treatment, grouping the wastes into
"gaseous waste", "liquid waste" and "solid waste", and provide for the methods of on-site
treatment of these groups of waste. Examples of the provisions are shown in Section L Table
H6-3.
In addition, the disposal methods by burial are categorized into "Category 1 disposal" and"Category 2 disposal" according to the concentrations of radioactive nuclides in the wastes
that are provided for in the Enforcement Ordinance for the Reactor Regulation Law.
By the Radiation Hazards Prevention Law, the equivalent procedures are required inaccordance with the specification of wastes except for disposal by burial that is in process ofestablishment.
H6.6

Report to the regulatory body in a timely manner by the licensee

The Reactor Regulation Law provides that an operator shall report without delay the statusof the event and other necessary matters when an accident accompanying personal injury(including the case with potential personal injury) or a failure or other event has occurred in a
milling facility, a fuel fabrication facility, a reactor facility, a spent fuel storage facility, a
reprocessing facility, waste storage facility, waste disposal facility or a fuel material use
facility. Reportable events are specified by a ministerial ordinance that regulates the activity
concerned. Examples of reportable events are shown in Section L Table H6-4.
The Radiation Hazards Prevention Law requires the operators to report to regulatory bodywithout delay about the content and counter-measure of accident in radioactive waste
management facility.
H6.7

Programs to collect and analyze relevant operating experience

Upon receipt of a report on an accident or failure, the regulatory body immediately makes
the report open to the public. It examines and evaluates the status of cause investigation
and recurrence prevention measures, and distributes the results. The information on theaccident or failure is further investigated to extract lessons on safety and to improve safety
regulation as appropriate.
For the accumulation of information, the NISA instructs the JNES to maintain a system tocollect and evaluate domestic and overseas safety information. The accumulated
information is shared between NISA and JNES through the regular “Safety Information Study
Meeting” to appropriately feed back the information to a regulatory response or its follow-up.
As for international information exchange, Japan shares accident/failure information throughcooperation with international organizations such as the International Atomic Energy Agency(IAEA) and the Nuclear Energy Agency of the Organization for Economic Cooperation andDevelopment (OECD/NEA) as well as through bilateral cooperation.
H6.8

Decommissioning plans for a radioactive waste management facility other than adisposal facility

An operator that plans to terminate its activity must take necessary steps for“decommissioning” such as dismantling of the facility, assignment of nuclear fuel material
inventory and management of materials contaminated with nuclear fuel materials. For that
purpose, the operator has to establish a “decommissioning program” and obtain an approvalof the Minister of Economy, Trade and Industry for it.
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The criteria for approving decommissioning program are that all nuclear fuel materials havebeen removed from the facility; nuclear fuel materials are appropriately transferred;materials contaminated with nuclear fuel materials are appropriately managed; anddecommissioning work is appropriately implemented in a way to prevent a hazard due tonuclear fuel materials or materials contaminated with nuclear fuel materials. The
decommissioning program is developed by using the information obtained during theoperating period of the facility. The procedures for “Approval for Modification of
Decommissioning Program” are provided for to allow update of the decommissioning
program when necessary, which ensures that the plan is reviewed by the regulatory body.
An operator of the facility of radioisotope waste management services licensed under the
Radiation Hazards Prevention Law, in order to terminate the services, shall notify to the
Minister of MEXT. The operator shall take measures such as decontamination of materials
contaminated by radioisotopes, and the action program shall be prepared by reflecting theoperational experience of the facility and the operator shall report to the Minister of MEXT
about the measures taken.
H6.9

Plans for the closure of a disposal facility

When the Category 1 waste disposal licensee plans to close the tunnels and shafts, it musttake "closure steps" including backfill of tunnels and shafts, closure of pit mouths anddismantling of the underground waste disposal structures. Prior to that, the operator must
establish a "closure program" and have it approved by the Minister of Economy, Trade andIndustry.
The criteria for approving the closure program are that the closure of the facility is carried out
according to the conditions described in the license application documents and in an
adequate way to prevent radiological hazards due to nuclear fuel materials or otherradioactive materials. The closure program is prepared using such information obtained
during the operating period of the facility. The procedures for “Approval for Modification of
Closure Program” are provided for to allow update of the Closure Program when necessary,
which ensures that the program is reviewed by the regulatory body.
An operator of the facility of radioisotope waste disposal licensed under the Radiation
Hazards Prevention Law, in order to terminate the operation of disposal facility, shall takenecessary measures to prevent radiation hazards. The action program shall be prepared byreflecting the information obtained during the operation of the disposal facility and he shallreport to the Minister of MEXT about the measures taken.

H7

Institutional measures after closure

Article 17
Each Contracting Party shall take the appropriate steps to ensure that after closure of a disposal facility:(i) records of the location, design and inventory of that facility required by the regulatory body arepreserved;(ii) active or passive institutional controls such as monitoring or access restrictions are carried out, if
required; and(iii) if, during any period of active institutional control, an unplanned release of radioactive materials
into the environment is detected, intervention measures are implemented, if necessary.

H7.1

Preserve of required records

1.
Category 1 waste disposal
Licensee shall preserve the following records concerning the waste disposal for a period oftime pursuant to the provisions of the Reactor Regulation Law.
Records on disposal of Category 1 waste
Inspection records on specific waste disposal facility
Radiation control records
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Operation records
Maintenance records
Records of accidents in waste disposal facility
Meteorological records
Level of groundwater
Records on operational safety education
Documents and records on plans, implementation, evaluation and improvement ofquality assurance program
Results of periodic assessment of waste disposal facility for geological disposal
Records on physical protection
Results of closure confirmation
Methods and time of decommissioning, and names of auxiliary systems of therepository to be decommissioned
Records on materials subject to clearance confirmation
2.
Category 2 waste disposal
As in the case of Category 1 waste disposal, licensee shall preserve the following records
concerning the disposal for a period of time pursuant to the provisions of the Reactor
Regulation Law.
Records on disposal of Category 1 waste
Radiation control records
Maintenance records
Records of accidents in waste disposal facility
Rainfall records
Level of groundwater
Records on operational safety education
Documents and records on plans, implementation, evaluation and improvement ofquality assurance program
Results of periodic assessment of waste disposal facility for intermediate depth
disposal
Records on physical protection
Methods ant time of decommissioning, and names of auxiliary systems of therepository to be decommissioned
Records on materials subject to clearance confirmation
H7.2

Active or passive institutional controls

1.
Category 1 waste disposal
The Reactor Regulation Law provides for decommissioning procedures (dismantling ofauxiliary systems of waste disposal site, removal of contamination with nuclear fuelmaterials, transfer of nuclear fuel materials and other radioactive materials and transfer ofradiation control records to an organization assigned by the Minister of Economy, Tradeand Industry) after closure of a Category 1 waste disposal. Decommissioning Program of awaste disposal facility is subject to approval by the Minister of Economy, Trade andIndustry. For establishing a decommissioning program, the operator is required to perform
an assessment of the control of radiation exposure due to nuclear fuel materials and otherradioactive materials with the latest technical knowledge and to take necessary measures
for the preservation of the waste disposal facility on the basis of the assessment.
The activity terminates after getting confirmation that no radiation hazard prevention
measure is required for the site of auxiliary facilities to be decommissioned as well as forthe remaining facilities in the site; disposal of nuclear fuel materials, etc. has been
completed; and transfer of radiation control records to an organization assigned by the
Minister of Economy, Trade and Industry has been completed.
Institutional control of a closed facility is deemed to be helpful to further reduction of undue
human activities such as careless intervention in waste and to the promotion of public
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acceptance of geological disposal and safety.
As an example of specific institutional control, the Final Disposal Act designates thereleased site as a preservation area in response to the operator's request and restricts
excavation work within the conservation area.
2.
Category 2 Waste Disposal
The “Basic Guides for Safety Review for Radioactive Waste Burial Facilities” issued by the
NSC require that operators of disposal facilities should, in accordance with the ALARA
principle, manage a disposal facility taking account of types and radioactivity levels ofwaste disposed of, until the radioactivity of waste disposed of in a near surface disposal
facility decays with time to the level as low as it poses no hazards to the public (hereinafterreferred to as Step-wise Control).
The regulatory body requests a license applicant for waste disposal to submit a plan forstep-wise control and examines the conformity to the requirements specified in the “Basic
Guides for Safety Review for Radioactive Waste Burial Facilities.”
The Radiation Hazards Prevention Law also provided the similar system.
The Step-wise Control required by the above guidelines is as follows.
(1) A disposal facility with engineered barrier*1:
1) The First Stage:
In a disposal facility, a peripheral monitoring area where access is controlled and adisposal facility preservation area where patrol and inspection are conducted should beestablished. Leakage of radioactive materials out of engineered barrier*2 is monitored,
and if leakage occurs remedial measures are taken. (Monitoring and prevention ofleakage from engineered barriers)
2) The Second Stage:
In a disposal facility a peripheral monitoring area where access is controlled, and adisposal facility preservation area where patrol and inspection are conducted, areestablished. Leakage of radioactive materials out of engineered barrier withgroundwater to the biosphere is monitored. (Monitoring of leakage and migration fromengineered barrier, and retardation of migration by natural barrier*3 and engineered
barrier)3) The Third Stage:
A disposal facility preservation area where patrol and inspection are conducted isestablished. Farming and other specific human activities in this area are restricted or
prohibited. (Retardation of migration by natural barrier, and prohibition or restriction of
specific human activities)*1: The case that wastes solidified in a container etc. are disposed of in a near surface
disposal facility with engineered barrier.
*2: “Engineered barrier” is an artificial structure such as the concrete pit, filling materials
such as soil and sand for open space between and around waste packages
emplaced, and monolithically consolidated waste packages for prevention andreduction of leakage from the wastes disposed of into the biosphere.
*3: “Natural barrier” is the soil etc. surrounding engineered barrier or waste packages andis expected to retard migration of radioactive materials leaked from the wastes
disposed of into the biosphere.

(2)
A disposal facility without engineered barrier*4
1) The Disposal Stage:
A peripheral monitoring area where access is controlled, and a disposal facility
preservation area where patrol and inspection are conducted, are established. Leakageof radioactive materials out of disposal facility with groundwater to the living
environment is monitored. (Retardation and monitoring of migration into the biosphere)
2) The Preservation Stage:
A disposal facility preservation area where patrol and inspection are conducted isestablished. Farming and other specific activities in this area are restricted or prohibited
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The control period is supposed to last 300 to 400 years for a disposal facility withengineered barrier referring to foreign cases. And, in the case of disposal without
engineered barrier, as the disposed waste is non-solidified concrete etc. with low
radioactivity level, disposal stage and the following preservation stage of about fifty years
are regarded as the “institutional control period”.
H7.3

Intervention measures

When issuing a license, the regulatory body requests the operator to take following
measures during each stage of institutional control.
In the First Stage, if a leakage of radioactive material from engineered barriers is detected,
the operator who would dispose radioactive waste in the Category 2 disposal facility without
artificial barrier should immediately repair the barriers to prevent leakage. In the Second
Stage, the operator should monitor leakages from engineered barriers and, if necessary,take measures to retard migration of radioactive material. At the same time, the operator
should conduct patrol and inspection of the disposal facility and, if necessary, restore thecover soil and others. In the Third Stage, the operator should conduct patrol and check and,if necessary, restore the soil cover and others.
The Radiation Hazards Prevention Law also requires similar control to the waste disposal in
its scope.

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Section I

Transboundary Movement

Article 27
1. Each Contracting Party involved in transboundary movement shall take the appropriate steps toensure that such movement is undertaken in a manner consistent with the provisions of thisConvention and relevant binding international instruments.
In so doing:(i) a Contracting Party which is a State of origin shall take the appropriate steps to ensure thattransboundary movement is authorized and takes place only with the prior notification andconsent of the State of destination;(ii) transboundary movement through States of transit shall be subject to those international
obligations which are relevant to the particular modes of transport utilized;(iii) a Contracting Party which is a State of destination shall consent to a transboundary movement
only if it has the administrative and technical capacity, as well as the regulatory structure, needed
to manage the spent fuel or the radioactive waste in a manner consistent with this Convention;(iv) a Contracting Party which is a State of origin shall authorize a transboundary movement only if it
can satisfy itself in accordance with the consent of the State of destination that the requirementsof subparagraph (iii) are met prior to transboundary movement;(v) a Contracting Party which is a State of origin shall take the appropriate steps to permit re-entry
into its territory, if a transboundary movement is not or cannot be completed in conformity withthis Article, unless an alternative safe arrangement can be made.
2. A Contracting Party shall not licence the shipment of its spent fuel or radioactive waste to a
destination south of latitude 60 degrees South for storage or disposal.
3. Nothing in this Convention prejudices or affects:(i) the exercise, by ships and aircraft of all States, of maritime, river and air navigation rights andfreedoms, as provided for in international law;(ii) rights of a Contracting Party to which radioactive waste is exported for processing to return, or
provide for the return of, the radioactive waste and other products after treatment to the State oforigin;(iii) the right of a Contracting Party to export its spent fuel for reprocessing;(iv) rights of a Contracting Party to which spent fuel is exported for reprocessing to return, or provide
for the return of, radioactive waste and other products resulting from reprocessing operations to
the State of origin.

The electric power utilities in Japan have concluded reprocessing contracts with British andFrench firms and had exported 7,100 tons of spent fuel between 1969 and 2001.They, in
return, receive nuclear fuel material recovered from the spent fuel and vitrified packages(HLW) generated in the reprocessing. 1,310 vitrified packages were sent back to Japanbetween 1995 and March 2008 and the remaining packages will be returned in the next
ten-odd years. As they are constructing a reprocessing plant at Rokkasho Village in Aomori
Prefecture since 1993, there would be no plan to export more spent fuel originated fromcommercial nuclear power reactors after 2002.
I1

Transboundary movement

I1.1

Steps to Ensure Prior Notification and Consent of the State of Destination

For the export of the spent fuel or the radioactive waste, the Foreign Exchange and Foreign
Trade Control Law provides that an applicant should apply for and obtain the Export Permit
from the Minister of Ministry of Economy, Trade and Industry. This Export Permit should beapplied once it is confirmed that the authorities of the State of destination recognized theadministrative and technical capacity of the importer.
I1.2

Steps to Ensure Transboundary Movement Subject to International Obligations

Japanese domestic laws, such as the Ship Safety Law, etc, have incorporated obligations
under the IAEA Regulations for the Safe Transport of Radioactive Materials and relevant
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international conventions on each mode of transport, such as International Convention for
the Safety of Life at Sea (SOLAS), etc.
I1.3

Consent as a State of Destination

After being notified by a State of origin of a transboundary movement to Japan of the spent
fuel or the radioactive waste, the government of Japan decides whether it gives consent to
the transport, and notifies its decision to the State of origin.
Japan expressed that, upon notification from a State of origin, it would consent to the importof returned radioactive waste as long as such transport would comply with the safety
regulation of Japan.
I1.4

Confirmation of the Capacity of a State of Destination

The Foreign Exchange and Foreign Trade Control Law provides that an exporter should
apply for and obtain the Export Permit from the Minister of Ministry of Economy, Trade andIndustry for the export of the spent fuel or the radioactive waste. The Minister of Ministry of
Economy, Trade and Industry judges the grant of the Export Permit after confirming thegeneral conditions of safety of the country of destination such as its regulatory structure, themembership in relevant international agreements, and the administrative and technicalcapacity of the importing body.
I1.5

Steps to Permit Re-entry in case of Uncompleted Transboundary Movement

The Import Trade Control Order allows, as special exemption, re-entry of exported goods, incase of uncompleted transboundary movement so long as original characteristics andconfiguration of exported goods are preserved, and the other case of the exemption is atransport accident. Re-entry of exported spent fuel and radioactive waste is allowed by thatprovision.
I2

Prohibition of shipment to a destination south of latitude 60 degrees SouthThe Foreign Exchange and Foreign Trade Control Law provides that an applicant should
apply for and obtain the Export Permit from the Minister of Ministry of Economy, Trade andIndustry for the export of the spent fuel or the radioactive waste. The Export Permit shall not
be granted for the export of spent fuel or radioactive waste to a destination south of latitude
60 degrees south for storage or disposal.

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J

Disused Sealed Sources

Article 28
1. Each Contracting Party shall, in the framework of its national law, take the appropriate steps toensure that the possession, remanufacturing or disposal sealed sources takes place in a safemanner.
2. A Contracting Party shall allow for reentry into its territory of disused sealed sources if, in theframework of its national law, it has accepted that they be returned to a manufacturer qualified toreceive and possess the disused sealed sources.

J1

The infrastructure for regulatory control of sealed sources

The use of radioisotope and radiation generation apparatus etc, are regulated by the Law
Concerning Prevention of Radiation Hazards due to Radioisotope etc. (the Radiation
Hazards Prevention Law), as mentioned in paragraph E2.1 Sealed sources are also
regulated by this Law.
As there are about 5000 licensees, each licensee is responsible for the safety andradioisotopes including sealed sources are properly controlled.
Ministry of Education, Culture, Sports, Science and Technology (MEXT), as the competentregulatory authority, has been carrying out safety review and on-spot inspection.
It is recognized that Radiation Hazards Prevention Law has been functioning effectively asstated below.
The person who intends to use more quantities of radioactive sources than specified
shall apply to MEXT for license, or notify MEXT.
Radiation Hazards Prevention Law provides technical criteria and requirements, suchas criteria relating to the use of facilities, dose limits for radiation workers, etc. For
example, the licensee is required, from the point of radiation safety, to; a) be equippedwith lock in all facilities for uses, storage and disposal of radioisotopes; b) install walls or
fences to restrict easy access to the boundary of controlled area; c) restrict access tocontrolled area without permission of supervisor of the facility. These safety measures
will effectively work also for security, such as physical protection.
Licensee is responsible for annually reporting to MEXT regarding facility management
such as the inventory of radioactive sources. MEXT carries out on-spot inspections of
the facility if needed, and check that the inventory of radioactive sources is in conformity
with the license.
As a result of this strict regulation system as described above, there has been no incident,such as excess exposure to the public by “orphan sources”.
J2Management of radioactive sources

The licensee is regulated by law to hand over highly radioactive sources only to license
holders who are authorized to receive and use the sources, and the disused radioactive
sources are by practice handed over from the licensees to specific licensees. Licensees
have obligation to report the results of such handover to MEXT when they terminate the useof sources.
The licensee has a responsibility to do an annual inventory check of both sealed andunsealed radioactive sources and to report the results to MEXT.
The “Radiation Hazards Prevention Law” provides for penalty and clarifies licensee have theresponsibility for safe control of the radioactive sources.
Most of sources in Japan are imported from foreign countries and the sources with long
half-life and high activity are sent back to the original foreign manufactures.
Regarding the distribution of radioisotopes and sealed sources in Japan, one supplier(Japan Radioisotope Association) carries out consistently from distribution and delivery ofalmost all radioactive sources to recovery of disused radioactive sources.
As the result of this, there have been no incidents of serious radiation hazard involving
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radioactive sources or serious radiation hazard involving orphan sources until now.
J2.1

Criteria for the Storage of Disused Sealed Radioactive Sources

The Radiation Hazards Prevention Law lays down technical criteria relating to the storage ofsealed sources as stated below.
Sealed sources shall be put in containers and stored in storage pits or bins.
Sealed sources shall not be stored in quantities exceeding storage capacity.
Appropriate measures, such as a) installing a shield, b) distancing personnel fromsealed sources, and c) shortening the time during which personnel may be exposed toradiation, shall be taken in order to prevent personnel engaged in handling ofradioactive substances from being exposed to radiation exceeding the effective dose
limit.
Appropriate measures, such as immobilizing storage bins, shall be taken in order toprevent containers storing sealed sources from being carried from one place to anotherwithout permission.
Appropriate measures shall be taken to prevent surface contamination from exceeding
the surface contamination limit.
Radioactive contaminated substance whose surface concentration exceeds one-tenthof the surface concentration limit shall not be taken out from the controlled area without
permission.
Notice showing the remarks necessary to prevent radiation hazards shall be posted at
appropriate location within the controlled area.
Appropriate measures shall be taken in order to prevent unauthorized persons fromentering the controlled area.
J2.2

Response to Missing Radioactive Sources

In case of loss of any radioactive source, the licensee shall immediately report the matter tothe police and MEXT. While MEXT orders the licensee immediately to search the sources,
the police carry out criminal investigations, if the loss relates to criminal acts.
In April 2008, MEXT introduced the notification system for evaluated rating of radioactive
source events based on the additional guidance of the International Nuclear Event Scale(INES).
J2.3

Response to Orphan Sources

In case of find of any orphan source, the police immediately take an initial action including
setting of exclusion area, radiation survey and immediate assessment of the situation.
MEXT requests the discoverer of the source and relevant people that safety measures
should be taken and also dispatch a radiation inspector to confirm that the safety measurehas been properly taken. The found orphan source is to be recovered by the experts.
J2.4

Detection for Orphan Sources

About 30 percent of the operators of scrap metal recycle industry voluntarily carry out
radiation monitoring with gate type monitors or portable monitors. At the gateway of almost
all the blast furnace or electric furnace steel companies, which use such scrap metal, carryout radiation monitoring on acceptance of the scrap metal for use.
The steel industry and the scrap metal recycle industry are voluntarily taking measures suchas development of manuals and training courses to cope with the discovery of orphan
sources.
The Customs conducts inspections to detect such sources by having set up radiation
measurement equipment and X-ray machines in main ports.

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J2.5

Response to Accident Relating Radioactive Sources

In case of accidents involving radioactive sources, the police and fire service perform initial
response immediately depending on the notification. MEXT dispatches radiation inspectors
to advise the licensee to take suitable measures.
J2.6

Progress in Establishing a System of National Registry of Sealed Sources

Users of radioactive source must obtain licenses of MEXT, or submit notification to MEXT by
the Radiation Hazards Prevention Law, and MEXT as the regulatory body oversees andverify the radioactive sources used by the licensees as follows.
Before Use:
These who intend to use radioactive sources must apply for license to MEXT. In thisapplication, the applicant has to indicate the nuclide and activity of each radioactive source,
and the number of sources.
After the beginning of use:
The licensee must perform an annual inventory check of radioactive sources, the result of
which should be included in the annual report of facility management. This report includes
not only all the sealed sources including Category 1 and 2* but also all the unsealed sources,
and MEXT verifies the consistency with the relevant license application. In case of disused
sources, MEXT asks the licensee for the report that the licensee has handed over thesources to another licensee.
MEXT requests no information by the above report regarding the source ID number and the
manufacturer, etc. The regulatory authority, however, will can such information throughsupplier, because in Japan only one supplier imports and delivers Category 1 and 2 sources
to the domestic users, and the supplier records such information.
In 2009, MEXT will introduce the system of national registry of sealed sources including
source ID number and the manufacturer, etc. at least for Category 1 and 2 sources, taking
into consideration consistency with source registration systems in other countries.
*: Classification based on RS-G-1.9 “Categorization of Radioactive Sources Safety Guide”
issued by IAEA

J3

Reentry of Returning Sealed Sources

As long as a manufacturer has license and meets the regulations specified in the Radiation
Hazards Prevention Law, reentry of approved type of sealed sources returning from abroad
are allowed within the license of storage capacity. In this case, legal procedure on export
and import that is consistent to the “IAEA Guidance on Export and Import of Radiation
Sources” (hereinafter referred to as “Guidance”) shall be applied. The manufacturer
intending to possess or renew returned sealed sources is required to store them inaccordance with the above mentioned storage criteria.
J4Compliance with the Code of Conduct on the Safety and Security of Radioactive
Sources

As mentioned in the paragraph J1 and J2 above, the Code of Conduct on the Safety ofRadioactive Sources (hereinafter referred to as “the Code”) is substantially implemented
under the regulation based on the Radiation Hazards Prevention Law and administrative
advices to the licensees, etc. Currently, the system of national registry of sealed sources isunder development for fully implementation of the Code as described in the paragraph J2.6
above. And MEXT is planning to establish an interim guideline providing the security
111

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J

Disused Sealed Sources

measurements of which the licensees should take to their facilities. MEXT made the interim
guideline as provisional edition in May 2006 and is to complete the guideline referring to theguideline for security of radioactive sources, which will be scheduled for publication by IAEA.
Regarding the Guidance, which was developed to support the import and export provisionsof the Code, it has been fully implemented from January 2006 by amendment of the “Export
Trade Control Order”.

112Planned Activities to Improve Safety

Section K
K1

Planned Activities to Improve Safety

Development of laws and related rules

There are safety examination guides and legislations, etc. to be prepared for safety
regulations of radioactive waste management from now on, such as disposal of high level
radioactive wastes (HLW), disposal of low-level radioactive wastes with a comparatively highradioactivity level, disposal of uranium wastes, disposal of wastes containing transuranic
nuclides, and the value of materials not requiring treatment as radioactive wastes. These areshown in Table A1-1 as the status of activities concerning preparation of regulation onradioactive waste disposal.
The NSC and the related regulatory bodies continue to study and prepare these safety
examination guidelines and legislations etc.
K2

Measures to ensure reliability of technology by experiences, tests and analyses

For management of radioactive wastes, especially for disposal, it is important to improve its
safety and reliability of disposal technologies.
Therefore, regulatory bodies continuously obtain specialist's engineering and technicaladvices and reflect them in operation and maintenance and safety regulations, as needed,
Following safety researches are conducted based on regulation needs of the Nuclear andIndustrial Safety Agency in the area of the safety of spent fuel management and the safety ofradioactive waste management;
Study on safety technology of radioactive waste disposal (Scheduled to be completed in
2013)
Study on related technology of decommissioning (preparation of standards,
environmental impact, site refurbishment and nuclear fuel cycle facilities: Scheduled tobe completed in 2011)
On the other hand, operators continuously promote to buildup the latest technicalinformation by collection of the internal and external information on operational experiences,
technological developments by self-finance, maintenance and repair activities, etc.
For researches and developments of reliability improvement, the implementing bodycontinues to takes charge of technical development on geological disposal of HLW, aiming at
safe operation and improvement for economical and efficient final disposal.
The national government and agencies concerned implement researches and developments
necessary for establishing safety regulations and safety evaluation for final disposal,
fundamental researches and developments such as scientific investigation of deep layer,
etc., and technical developments etc. for reliability improvement of geological disposal
technologies.
Especially, the institutes leaded by Japan Atomic Energy Agency (JAEA) promotes R&D
for scientific research on deep geological layer, confirmation of the reliability of geologicaldisposal technologies, fundamental R&D for the enhancement of safety evaluation
methodology and R&D on safety regulation along with “the basic research program on
geological disposal of high level radioactive waste” (Agency of Natural Resources andEnergy, METI and JAEA December,2006) and “Important Research Program on the Nuclear
Safety ”(The NSC 2004).
And also, these deep layer research facilities of JAEA are planned and expected to facilitate
not only as the place of research and development of geological disposal, but also used as acooperation to the activities of the government and the implementing body to deepen public
understanding of the research and development for the geological disposal in Japan.
Since fiscal year 1976, the NSC has been promoting research projects concerning thesafety of environmental radioactivity and radioactive waste at nuclear installations. The
products of these safety research projects have been reflected in the formulation of various
standards and guidelines, including principles such as safety policy and basic ideas,
standards on specific means of achieving safety, and specific guidance.
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K

K

Planned Activities to Improve Safety

The Committee, decided the “Important Research Programs on the Nuclear Safety” in July
2004, in coordination with the status of preparation of relevant regulations (Table A1-1),
requirements on geological environment for the stepwise procedure of site selection ofradioactive waste final disposal and the development schedule of the “Basic Guides forLicensing Review”.
The report "Important Research Programs on the Nuclear Safety" indicates the safety
researches on radioactive wastes and decommissioning field to be conducted intensively infive years starting from 2005.
In 2007, the steady progress of each research program was confirmed by the interim
evaluation of the research status. The program is scheduled to be completed in fiscal 2009,
and the discussion of the development of succeeding “Important Research Program on the
Nuclear Safety” beginning from fiscal 2010 has been started.
Moreover, in July 2003, the Radioactive Wastes Safety Subcommittee, Nuclear andIndustrial Safety Subcommittee, Advisory Committee for Natural Resources and Energy
showed the important research tasks which should be investigated from now on in the“Toward Ensuring Foundation for the Safety Regulation of High-Level Radioactive Waste
Disposal”, and those tasks will be promoted by the supporting organization for safety
regulations, the Japan Nuclear Energy Safety Organization, as a center, utilizing the resultsof researches of all organizations including the above-mentioned deep layer researchfacilities, and the outcomes will be reflected in the preparation of the future safety regulation
system.

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Annexes

Section L
L1

AnnexesInventory of spent fuelNuclear operators and facilities

The Japan Atomic PowerCo.
Hokkaido Electric Power
Co., Inc.
Tohoku Electric Power Co.,Inc
Tokyo Electric Power Co.,Inc.
Chubu Electric Power Co.,Inc.
Hokuriku Electric Power
Co., Inc.

Inventory (t)Tokai-No.2 Power Station
Tsuruga Power Station

320
560

Tomari Power Station

330

Higashidori Nuclear Power Station
Onagawa Nuclear Power Station
Fukushima Daiichi Nuclear Power
StationFukushima Daini Nuclear Power Station
Kashiwazaki Kariwa Nuclear Power
Station

10340

The Chugoku ElectricPower Co., Inc.
Shikoku Electric Power
Co., Inc.
Kyushu Electric Power
Co., Inc.

Japan Atomic Energy
AgencyJapan Nuclear Fuel Limited
Total

1,580
980
2,140

Hamaoka Nuclear Power Station

840

Shika Nuclear Power Station

100

Mihama Power Station
Ohi Power Station
Takahama Power Station

The Kansai Electric Power
Co., Inc.

360

Ikata Power Station

520

Genkai Nuclear Power Station
Sendai Nuclear Power Station

760
770

Reactor Decommissioning R&D Center70

FBR Research and Development Center
Tokai Research and Development
Center,Nuclear Fuel Cycle Technology
Development Directorate, Reprocessing
Facility
Tokai Research and Development
Center,Nuclear Science Research Institute
Oarai Research and Development
CenterRokkasho Reprocessing Plant

0

Inventory of radioactive waste

L2.1

High level radioactive waste

Uranium oxide fuel assemblies

290
1,200
1,090

Shimane Nuclear Power Station

L2

Stored spent fuelUranium oxide fuel assemblies
MOX fuel assemblies

41

Uranium oxide fuel assemblies
MOX fuel assemblies

18

Uranium oxide fuel assemblies
Uranium oxide fuel assemblies
MOX fuel assemblies
Uranium oxide fuel assemblies

16
2,535
14,870Vitrified waste(number of containers*)

FacilityHigh level liquid waste

Japan Atomic Energy
AgencyReprocessing facility

247

404 m3

Japan Nuclear Fuel Limited

Reprocessing facility
Waste Storage Facility

57
1,310

0
0

* : 120 litter container

L2.2

Power station waste

1.

Homogeneous solid, packed solid and miscellaneous solidPower station

The Japan Atomic
Power Co.

Tokai- Power Station
Tokai-No.2 Power Station
Tsuruga Power Station

Hokkaido ElectricPower Co., Inc.

Tomari Power Station

Homogeneous
solid (drum)
0
230
2,716

Packed solid(drum)
0158
174

Miscellaneous
solid (drum)
1393
51,53862,231

1,020

0

4,735

115

Total (drum)
1,393
51,926
65,121
5,755

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Annexes

Tohoku ElectricPower Co., Inc

Tokyo
Electric
Power Co., Inc.

Chubu
Electric
Power Co., Inc
Hokuriku ElectricPower Co., Inc.
The Kansai ElectricPower Co., Inc.
The
ChugokuElectric Power Co.,Inc.
Shikoku ElectricPower Co., Inc.

Onagawa Nuclear Power
StationHigashidori Nuclear Power
StationFukushima Daiichi Nuclear
Power Station
Fukushima Daini Nuclear
Power Station
Kashiwazaki Kariwa Nuclear
Power Station
Hamaoka Nuclear Power
Station

2,792

022,51625,308

0

0

2,524

2,524

13,680

4,089

161,524

179,293

599

2,603

14,716

17,9180022,37822,378

3,295

1,116

31,62736,038

Shika Nuclear Power Station

8

440

3,836

4,284

Mihama Power Station
Takahama Power Station
Ohi Power Station

2,196
4,669
3,207

1,066
0
2,409

23,91935,108
19,621

27,181
39,777
25,237

Shimane Nuclear Power
Station239

833

26,32727,3991,577

026,44428,021

Ikata Power Station

Genkai Nuclear Power3,550
025,666
StationSendai Nuclear Power
2,131
0
11,751
StationReactor Decommissioning
2,016
0
16,890R&D Center
Japan Atomic
Energy Agency
Prototype
Fast
Breeder
20
03,592
Reactor “Monju”
Inventories are in the number of 200 litter drums (or converted into number of drums for miscellaneous solid).

29,216

Kyushu ElectricPower Co., Inc.

2.

18,906
3,612

Steam generator (SG)Power station

Number of SGs
7
6
8
4
4

Mihama Power Station
The Kansai Electric Power Co., Inc.

Takahama Power Station

Shikoku Electric Power Co., Inc.

Ikata Power Station

Kyushu Electric Power Co., Inc.

Genkai Nuclear Power Station

Ohi Power Station

3.

13,882Control rod, channel box, etc.
Power station

The Japan Atomic
Power Co.
Hokkaido ElectricPower Co., Inc.
Tohoku ElectricPower Co., Inc

Tokyo
Electric
Power Co., Inc.

Chubu
Electric
Power Co., Inc
Hokuriku ElectricPower Co., Inc.

Tokai- Power Station
Tokai-No.2 Power Station
Tsuruga Power Station Unit 1
Tsuruga Power Station Unit 2

Control rod(number)*
91 m3
235
165
346

Channel box(number)
0
3,248
1,893
0

Others
(m3)
1,310
14
47
0

Resin, etc.
(m3)
60
874
825
80

Tomari Power Station

270

0

0

75

Onagawa Nuclear Power Station
Higashidori Nuclear Power Station
Fukushima Daiichi Nuclear Power
StationFukushima Daini Nuclear Power
StationKashiwazaki Kariwa Nuclear Power
Station

110

2,610
78

1
0

433
23

1,175

19,871

182

3,579

561

8,287

32

4,714

616

12,0440

2,261

Hamaoka Nuclear Power Station

437

9,301

23

2,564

Shika Nuclear Power Station

35

731

0

103

676
1,320
1,085

0
0
0

0
0
0

110
111
105

220

4,210

56

820

The Kansai ElectricPower Co., Inc.

Mihama Power Station
Takahama Power Station
Ohi Power Station

The
ChugokuElectric Power Co.,Inc.

Shimane Nuclear Power Station

116Annexes

Shikoku ElectricPower Co., Inc.
Kyushu ElectricPower Co., Inc.

Japan Atomic
Energy Agency

Ikata Power Station
Genkai Nuclear Power Station
Sendai Nuclear Power Station

633

0

0

139

691
412
Control rod(number)00

Neutron detector(number)

Others(number)

150
128
Resin, etc.
(m3)

5

102

0

216

Reactor Decommissioning R&D
CenterControl rod drive mechanism guide tube, etc.(number)Japan Atomic
Energy Agency

Prototype“Monju”

Fast

Breeder

Reactor5* For other than Tokai Power Station.

L2.3

Long-lived low heat generation radioactive waste

Japan Atomic
Energy Agency
Japan Nuclear Fuel
LimitedBituminizedsolid(drums)Plastic solid(drums)Other waste(drums)Total(drums)

31,72629,967

1,812

11,73375,2389,236*10012,152

21,388Drum(drums)Facility
Reprocessing facility
Reprocessing plant

Japan Atomic
Energy Agency
Japan Nuclear Fuel
LimitedReprocessing facility
Reprocessing plant

4,892

302

157*2

0
Sludge(m3)

Low activity concentrated
liquid waste (m3)Japan Atomic
Energy Agency

Reprocessing facility

2,685

Total
(number)

Sample bottle(drums)Spent filter(drums)Sheared cladding(drums)

1,328

6,522

0

157

Waste solvent
(m3)
1,117

106

The storage unit is (or is converted into) 200 litter drum.
*1: Including 784 drums of wastes dtored in the Waste Storage Facility located in Reprocessing Site.
*2: The sheared cladding pieces are stored in 1,000 litter drums.

L2.4

Uranium waste

Global Nuclear Fuel - Japan Co., Ltd.
Mitsubishi Nuclear Fuel Co., Ltd.
Nuclear
Fuel Tokai Works
Industries, Ltd.
Kumatori Works
Prototype Uranium
Japan Atomic
Enrichment Plant
Energy Agency
Japan Nuclear
Enrichment
andFuel Limited
Disposal OfficeDrum(drums)11,817
9,560
4,924
6,459

Other waste(drums)
3,913
1,041
1,190
149

Total
(drums)15,73010,601
6,114
6,608

Low level liquid waste
(m3)
0
1.74
8.05
11.4

497

56

553

0

4,101

400

4,533

0

The storage unit is (or is converted into) 200 litter drum.

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Annexes

L2.5 Waste stored in research facilities<Waste Inventory data reported under the Reactor Regulation Law>
Solid
waste
(drums)Liquidwaste(m3)

Description

Tokai Research and Development Center
Nuclear Science Research Institute135,574−

Reactor facility, using facility for nuclear material(hereinafter referred to as “using facility”)

Tokai Research and Development Center
Nuclear Fuel Cycle Engineering Laboratories

61,762−Using facilities

Oarai
ResearchCenter(North Area)

andDevelopment

29,614−

Reactor facility, Using
management facility

Oarai
ResearchCenter(South Area)

andDevelopment

121
(*1)

0.03
(*2)

(*1)Reactor facility (temporary storage)(*2)Using facility

14,401

10.1

Using facility

1,053

22.4

Reactor facility

24
(*1)

5.3
(*2)

(*1)Reactor facility, Using facility (temporarystorage)(*2)Reactor facility.

Kyoto University, Research Reactor Institute

60

0.0

Reactor facility, Using facility

National Institute of Radiological Science
Nuclear
Tokai Safeguards Center
Material
Rokkasho
Safeguards
Control
Laboratory
CenterRikkyo University
Institute for Atomic Energy
Musashi Institute of Technology
Atomic Energy Research InstituteKinki University
Atomic Energy Research Institute768−

Using facility

59−

Using facility

84−

Using facility

15

6.6

Reactor facility

5−

Reactor facility

3−

Reactor facility

6,114

8.1

Using facility(same in the Table L2.4; this facility
is also categorized as fabrication facility)

FacilityJapan
AtomicEnergyAgencyNingyo-toge Environmental Engineering
Center
Aomori Research and Development Center
Mutsu Office
The University of Tokyo,
Nuclear Professional School, School of Engineering

Analytical

Nuclear Fuel Industries, Ltd,
Tokai Works
Nippon Nuclear Fuel Development Co., Ltd.

195

9.1

Using facility

1,630

−

Using facility

Research Reactor Center

72−

Reactor facility

Nuclear Engineering Lab.

1,597
(*1)

0.7
(*2)

(*1)Reactor facility, Using facility(*2)Using facility.

494−

Reactor facility

Nuclear Development Corporation
Toshiba
Corporation

facilities,

Hitachi, Ltd. Power & Industrial Systems Nuclear System
Division Ozenji Hitachi Training Reactor Center

Waste

The sum of solid waste inventory and liquid
waste inventory* This data includes the data of inventory of Long-lived low hear generation radioactive waste and Uranium waste which
generated in the using facilities. The storage unit is (or is converted into) 200 litter drum.
Other small Using Facilities（189 facilities）

78388 drums<Waste Inventory data reported under the Radiation Hazards Prevention Law>
Waste
(drums)-Facilities of the waste management business
The University of Tokyo, Radioisotope Center
Kanto Waste Relay Station
Japan
Radioisotope
Association

1
14,875

Kanto Waste Relay Station Ⅱ
The Kaya Memorial Takizawa Laboratory
Ichihara OfficeKansai Waste Relay Station
Kanto Storage Facility

9,330
15,261
72,3000
0
7,006

VESTA Co., Ltd.
Japan Atomic
Energy Agency

Description

Tokai Research and Development Center
Nuclear Science Research Institute135,574

Oarai Research and Development Center (North Area)

28,157This data is also reported under
the Reactor Regulation Law.
This data is also reported under
the Reactor Regulation Law

T.N. Technos Co., Ltd. TSUKUBA LABORATORIES
238
Facilities of the using radioisotopes, etc.
12,541The storage unit is (or is converted into) 200 litter drum. This data includes the inventory of liquid waste.

118

Annexes

L3

Excerpt of Regulation Relevant to Section G

Table G4-1

Technical Standard for the design and construction methods of Spent Fuel
Storage Facility(Prevention of spent fuel criticality)
Article 3 A spent fuel storage facility shall be provided with adequate measures such as criticality-safe
geometries to eliminate the possibility of spent fuel going critical.
(Prevention of fire damage)
Article 4 If the safety of a spent fuel storage facility could be significantly impaired by a fire, the facility
shall be provided with fire extinguishing and alarm systems as appropriate (limited to systems that
automatically detect a fire and set off an alarm, such as automatic fire-alarm box and electric fire
alarm system).
2 Any failure, damage or malfunction of the fire extinguishing system and alarm system in thepreceding paragraph shall not significantly impair the safety of the spent fuel storage facility.
3 A System important to safety, such as emergency power supply system, that could be damaged by afire shall consist of noncombustible or nonflammable materials as far as possible and shall be
provided with adequate fire protection measures such as fire walls where necessary.
(Seismic design)
Article 5 A spent fuel storage facility shall be designed so as not to have a serious radiological impact
on the public when damaged by seismic forces applied on it.
2 The seismic forces mentioned in the preceding paragraph shall be estimated taking account of theconditions of foundation ground, degree of earthquake damages in the region estimated from pastearthquake records, characteristics of seismic activities and other various factors, on the basis of thestructures of the spent fuel storage facility and the degree of hazards due to the damages to thefacility.
(Materials and structures)
Article 6 The materials and structures of the vessels, pipes and support structures in a spent fuelstorage facility that are important to ensure the safety of the facility (hereinafter in this Article referred
to as “vessels”) shall be adequate for ensuring the strength and corrosion resistance required by thedesign of the vessels.
2 The vessels and pipes in the spent fuel storage facility that are important to ensure the safety of the
facility shall be designed so as to endure appropriate pressure test or leakage test without significant
leakage.
(Heat removal)
Article 7 A spent fuel storage facility shall be designed so as to safely remove the decay-heat of spent
fuels.
(Confinement function)
Article 8 A spent fuel storage facility shall be so designed to have the function for confining spent fuelor materials contaminated with spent fuel (hereinafter referred to as “spent-fuel-contaminatedmaterials”) within restricted areas pursuant to the following requirements:(1) The structure of a container containing spent fuel shall not allow any leakage of spent fuel orspent-fuel-contaminated materials to the outside.
(2) When a pipe delivering any liquid not containing spent-fuel-contaminated materials is connected
to a vessel or pipe containing spent-fuel-contaminated materials, the structure shall ensure thatthe contaminated liquid does not flow back into the pipe delivering liquid not containing
spent-fuel-contaminated materials.
(3) A facility that has equipment for handling any liquid contaminated with spent fuel (solely for thoseareas where leakage of the liquid contaminated with spent fuel may expand), shall be designed
pursuant to the following requirements:(a) The surfaces of floors and walls inside of the facility shall have structures to inhibit the leakageof the liquid contaminated with spent.
(b) The periphery of a facility handling the liquid contaminated with spent fuel or gateways leading
to the outside of the facility or its vicinity shall be provided with lashers to prevent the liquidcontaminated with spent fuel from leaking outside the facility, unless the floors inside of the
facility are lower than the floors of the adjacent facilities or the ground surface and the liquidcontaminated with spent fuel cannot leak to the outside of the facility.

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Annexes(c) The floors of a spent fuel storage facility shall be above the discharge water channels thatdischarge effluent to the outside of the facility site (excluding ground water drainage channels
which have no opening in the controlled areas that could be contaminated with materials
contaminated with spent fuel), unless those discharge water channels are provided with thesystem that safely disposes the effluent containing spent-fuel-contaminated materials andinstrumentation to monitor the items listed in Article 15-2.
(Shielding)
Article 9 Shielding with capability required for preventing radiation hazards shall be provided if theprevention of the radiation hazards due to external radiation in a spent fuel storage facility site isrequired. For the prevention of radiation hazards. In such case, measures to prevent radiation
leakage shall be taken if necessary to prevent radiation hazards due to any opening, pipe or otherpenetration in the shielding structures.
(Ventilation)
Article 9-2 Ventilation system that meets the following requirements shall be provided, if it is required
to prevent radiation hazards due to the air contaminated with spent fuel or spent-fuel-contaminatedmaterials in the spent fuel storage facility:(1) The ventilation system shall have necessary capability for preventing radiation hazards.
(2) The structure of the ventilation system shall prohibit reverse flow of the air contaminated withspent fuel or spent-fuel-contaminated materials.
(3) Filtering system, if it is installed, shall be capable for appropriate maintenance of its filteringfunction and shall have a structure to allow easy removal of the materials contaminated withspent fuel or spent-fuel-contaminated materials or easy replacement of the system.
(4) The ventilation system shall have air intake ports that prohibit intake of the air contaminated withspent fuel or spent-fuel-contaminated materials.
(Prevention of contamination by spent-fuel-contaminated materials)
Article 10 As for the spent fuel storage facility buildings that are frequently accessed, the surfaces of
their walls, floors and other parts, that could be contaminated by spent-fuel-contaminated materials
and could be touched by people, shall be easy to remove the spent-fuel-contaminated materials.
(Systems important to safety)
Article 11 The systems important to safety such as emergency power supply system shall be designed
to meet the following requirements:(1) If a system is shared among two or more nuclear facilities (such as fabrication facility, reactor
facility, spent fuel storage facility, reprocessing facility, waste disposal facility and nuclear
material utilization facility), the functions to ensure the safety of spent fuel storage facility shall not
be impaired by such sharing.
(2) Inspection or test to confirm the functions to ensure the safety of spent fuel storage facility, andmaintenance or repair for maintaining the integrity of such functions shall be possible.
(Transportation and receiving systems)
Article 12 The systems used for the transportation and receiving of containers containing spent fuelshall be designed to meet the following requirements:(1) The systems for the transportation and receiving of containers containing spent fuel shall havecapability for safe handling of the containers.
(2) The containers containing spent fuel shall be safely retained in case of loss of power supply forthe transportation and receiving systems.
(Instrumentation and control systems)
Article 13 A spent fuel storage facility shall be provided with the instrumentation to measure thefollowing parameters. If it is difficult to directly measure any of such parameters, indirect
instrumentation may be used as an alternative:(1) Surface temperature of container containing spent fuel.
(2) Pressure at the closure head of container containing spent fuel for monitoring seal performanceof the head (excluding welded closure head).
(3) Temperatures of air supply and exhaust of the buildings where spent fuel is stored.
2 A spent fuel storage facility shall be provided with the devices for reliable detection and quick
alarming of such situations as: when safety of spent fuel storage facility could be significantly
impaired due to loss of equipment function, malfunction or any other cause; when the concentration ofradioactive materials described in Article 15 (ii) or the dose equivalent of external radiation describedin Article 15 (iv) shows significant increase; or when significant amount of liquid radioactive materials

120Annexes
could leak from liquid radioactive waste disposal system.
(Disposal systems)
Article 14. Radioactive waste disposal system (excluding radioactive waste retaining system) shallmeet the following requirements:(1) Radioactive waste disposal system shall be capable of disposing radioactive wastes generated in
the spent fuel storage facility so that concentration of airborne radioactive materials outside theenvironmental monitoring area and concentration of radioactive materials in the water at the outerboundary of the environmental monitoring do not exceed the values specified by the Minister of
Economy, Trade and Industry.
(2) Radioactive waste disposal system shall be installed separately from non-radioactive waste
disposal system, unless the system that leads non-radioactive liquid waste to radioactive liquid
waste disposal system is provided with the measures to prohibit for radioactive liquid waste toflow back into non-radioactive liquid waste systems.
(3) Gaseous radioactive waste disposal system shall not discharge gaseous wastes at any part ofthe system other than exhaust port.
(4) If filtering system is installed in the gaseous radioactive waste disposal system, it shall be capable
for appropriate maintenance of its filtering function and shall have a structure to allow easy
removal of the materials contaminated with spent fuel or spent-fuel-contaminated materials oreasy replacement of the system.
(5) Liquid radioactive waste disposal system shall not discharge liquid waste at any part of thesystem other than water discharge outlet.
(Radiation control system)
Article 15 A spent fuel storage facility site shall be provided with the radiation instrumentation tomeasure the values listed below. If it is difficult to directly measure any of such parameters, indirect
instrumentation may be used as an alternative:(1) Dose equivalent rate at the side wall of radiation shielding structure of spent fuel storage facility(2) Concentration of radioactive materials in exhaust gases at or near the gaseous radioactive waste
exhaust port
(3) Concentration of radioactive materials in discharge water at or near the liquid radioactive waste
discharge outlet(4) Dose equivalent of external radiation, concentration of airborne radioactive materials anddensities of radioactive materials on the surface of contaminated items in the controlled area
(5) Dose equivalent of external radiation in the environmental monitoring area
(Emergency Power Supply System)
Article 16 A spent fuel storage facility shall be provided with power generating system driven byinternal combustion engine, or other power generating system with equal or more capability, in orderto maintain the function of the systems necessary for ensuring the safety of the facility in the event ofloss of electric power supply from off-site power grid.
2 Systems especially important for ensuring the safety of spent fuel storage facility shall be provided
with an uninterruptible power supply device or other power supply system with equal or morecapability.

Table G5-1

Regulatory Guide for Reviewing Safety Assessment of the Spent FuelInterim Storage Facility Using Metal Dry Casks

Siting Condition
Guideline 1 Basic conditions
The following events shall be investigated for the site and its surroundings of the spent fuel interim
storage facility, and it shall be confirmed that the adverse conditions for ensuring safety does notexist.
1. Natural environment(1)Natural phenomena such as earthquake, tsunami, landslides, depression, typhoon, high tide,
flood, abnormal cold weather, heavy snowfall.
(2)Geological conditions and landform etc. such as ground conditions, soil bearing capacity, fault.
(3) Meteorological conditions such as wind direction, wind velocity, waterfall.
(4) Hydrological and hydraulic conditions of rivers, underground water, etc.
2. Social environment(1) Fire, explosion at a neighboring factory etc.

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Annexes(2) Missiles etc. by air craft crash, etc.
(3)Conditions of land use in relation to food production such as agriculture, livestock farming, fisheryindustry and condition of population distribution etc.
Guideline 2 Normal conditions
The dose in normal condition of the general public due to the spent fuel interim storage facility shall belower than the dose limit specified by the law and regulation, and it shall be as low as reasonably
achievable.
Guideline 3 Accident conditions
Under the assumption of the occurrence of the maximum credible accident at the spent fuel interim
storage facility, the general public shall not receive excessive radiation exposure.
1. Selection of accidents
In the design of the spent fuel interim storage facility, accidents, which occurrence is technicallypossible to be assumed in the worst case and is considered important in view of radiation exposure to
the general public, shall be selected by thoroughly studying the possibility of occurrence of accidents
that may significantly fail the fundamental safety functions of metal casks from the technical point ofview considering aging of metal cask components by long term storage, such as:(1)Collision or fall of metal cask caused by wrong operation etc. during transfer in the facility(2)Natural disaster etc.
2. Calculation of release amount of radioactive materials etc.
The release amount of radioactive materials etc. shall be calculated for each accident selected inaccordance with the paragraph 1 above, applying appropriate analytical model and parameters andsetting appropriate conditions with safety margin, by thoroughly studying the followings:(1)Amount of leakage of radioactive materials from the fuel cladding(2)Integrity of metal casks concerning their confinement function and radiation shielding function(3)Number of metal casks to be assumed for leakage of radioactive materials(4)Conditions of atmospheric dispersion of radioactive materials(5)Period of release for the evaluation
3. Dose evaluation
It shall be confirmed that the general public does not receive excess radiation exposure from the doseeven in case of the maximum credible accident, which is defined as an accident which effect to thegeneral public is the maximum among accidents selected by the paragraph 1 as the result from thecalculation in accordance with the paragraph 2 above. However, this evaluation is not required when
there is no radiation exposure to the general public due to the accident selected by the paragraph 1.
Radiation Control
Guideline 4 Confinement function
The spent fuel interim storage facility shall be designed to confine radioactive materials in the limitedarea with the following measures.
1. The metal cask shall be designed to maintain the negative pressure in the space where spent fuelassemblies are contained throughout the design storage period.
2. The metal cask shall be designed to isolate the space where spent fuel assemblies are contained
from outside of the cask with the multi-layered confinement structure at the cap portion. And its
confinement function shall be monitored.
3. The metal cask shall be designed with considerations of the restoration capability of confinement
function such a design as that allows the attachment of an additional cap to cope with unlikely eventof confinement function abnormality of cap structure.
4. The metal cask shall be designed to maintain the temperature of fuel claddings low throughout thedesign storage period in view of maintaining the integrity of fuel cladding.
5. The metal cask shall be designed to keep the temperature within the range to maintain the integrityof the structures throughout the design storage period in view of maintaining its confinement function.
Guideline 5 Radiation shielding
The spent fuel interim storage facility shall be appropriately shielded to lower the exposure dose of
the general public by the direct and sky shine ray.
In addition, the sufficient radiation shielding shall be provided considering working conditions of
personnel engaged in radiation work.
In case the radiation shielding of concrete etc is used, in addition to the metal cask, the shielding
material shall be designed to maintain the temperature low enough not to impair its radiation shielding
capability.
Guideline 6 Radiation exposure control
1. Radiation exposure control in working environments

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Annexes(1) In order to monitor and control working environments of personnel engaged in radiation work,
the monitoring system and measuring equipment for dose rates etc. and alarm system forunusual increase in the dose rate should be prepared.
(2) The important information from the above-mentioned monitoring system and alarm systemshould be designed that the centralized monitoring is possible at an appropriate place.
2. Equipments, such as dosimeters required for individual exposure control for personnel engaged inradiation work should be prepared.
3. The control area of the spent fuel interim storage facility shall be designed so that the appropriate
access control could be implemented in accordance with the dose rate and surface contamination
density.
Environmental safety
Guideline 7 Discharge control of radioactive wastes
The spent fuel interim storage facility should be designed so that the concentration of radioactive
materials released to the environment is as low as reasonably achievable with appropriate treatmentof radioactive wastes generated during the storage.
Guideline 8 Consideration for long-term storage etc.
The spent fuel interim storage facility should be designed to maintain the integrity of spent fuelassemblies and the integrity of the components that have fundamental safety functions throughout
the design storage period by taking the following measures, in considerations of degradation etc.
accompanied by the long-term storage.
1. Components of metal cask important to maintain fundamental safety functions should be designed
not to lose required safety function maintaining required strength and performance by selecting
materials that have sufficient reliability in the environments such as temperature and radiation
during design storage period and to the degradation such as corrosion, creeping, and stresscorrosion cracking under the above environments.
2. The metal cask should contain and store the spent fuel assemblies together with sealing inert
gases.
3. The metal cask should be designed to be able to remove the decay heat from spent fuels in view ofmaintaining the integrity of spent fuel assemblies and the integrity of the components that havefundamental safety functions.
4. The storage building should be designed to be able to maintain the room temperature in thebuilding low in view of the heat removal from the surface of a metal cask. And, it should bedesigned to be able to monitor that the room temperature in the storage building will not elevate to
the unusual level.
Guideline 9 Radiation monitoring
The spent fuel interim storage facility should be provided with measures to monitor the concentration
etc. of radioactive materials in the release path of radioactive wastes appropriately. Moreover,measures to monitor the dose rates, concentrations etc. of radioactive materials in the surrounding
environment should be taken appropriately in consideration to the potential release of radioactive
materials.
Criticality
Guideline 10 Criticality safety of a single metal cask
A single metal cask in the spent fuel interim storage facility should be designed to prevent thecriticality under any technically conceivable conditions when spent fuel assemblies are contained in
the cask.
In case the internal basket shares the criticality prevention function, the metal cask should bedesigned to keep the structural integrity of the basket throughout the design storage period.
Guideline 11 Criticality safety of multiple metal casks
The spent fuel interim storage facility should be provided with measures to prevent the criticality
under any technically conceivable conditions considering the neutron interference among metal casks
in the facility.
Guideline 12 Consideration for nuclear criticality accidents
If any possibility of a nuclear criticality accident caused by operational error etc. at the spent fuelinterim storage facility should not be neglected, appropriate measures for the unlikely event of nuclear
criticality accident shall be prepared.
When Guideline 10 and Guideline 11 are conformed and when spent fuels are contained in the metalcask, criticality could not physically occur, so that the application of this guideline is exempted.

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Other safety measures
Guideline 13 Consideration for earthquake
The spent fuel interim storage facility should be designed to maintain the fundamental safetyfunctions against design earthquake force considered to be the most appropriate referring to theresults of site investigation of past records at the site and its peripheral area.
Guideline 14 Consideration for natural phenomena other than earthquakes
The facilities important to safety of the spent fuel interim storage facility should be designed
considering the severest natural force of natural phenomena other than earthquake referring to theresults of site investigation of past records at the site and its peripheral area.
Guideline 15 Consideration for fire and explosion
The spent fuel interim storage facility should be provided with appropriate measures to prevent
occurrence of a fire and a explosion, and measures to prevent propagation of fire and explosion, andto control excessive release of radioactive materials into the outside of facility.
1. The spent fuel interim storage facility should be designed to use nonflammable or fire-retardantmaterials as much as reasonably possible.
2. In case flammable material is used in the spent fuel interim storage facility, appropriate measures
such as elimination of fire source, prevention of unusual temperature rise, prevention ofleakage-out or leakage-in of flammable material etc. should be taken.
3. In order to prevent propagation of a fire, the appropriate measures to reduce the influence by fireshould be taken in addition to installation of appropriate detection and alarm systems and the fire
protection equipment.
Guideline 16 Consideration for loss of electric power
A power supply system with sufficient capacity and reliability to operate following equipments required
for safety should be installed in the spent fuel interim storage facility to be prepared for the loss offunction of external power supply systems such as blackout.
1. Monitoring equipment for confinement function of metal casks
2.Radiation monitoring equipment
3.Equipment such as fire alarm equipment, emergency communication equipment, and emergency
lightning equipment
Guideline 17 Consideration for transfer of metal casks
The spent fuel interim storage facility should be provided with appropriate measures for shipping-out
of metal casks containing spent fuels considering the basic safety functions.
Guideline 18 Consideration of accident
The spent fuel interim storage facility should be provided with the appropriate measures for, such as
alarm, communication and evacuation of radiation workers depending on the accident condition.
1. Appropriate radiation measuring devices, the radiation protection equipment etc. should beavailable as required.
2. In the design of the facility, the lighting equipment for evacuation, which function is not lost in acase of loss of normal lighting power source, should be installed and safety evacuation passages
with simple, clear and durable signs should be established.
Guideline 19 Consideration for sharing of facilities
The facilities important to safety of spent fuel interim storage facility, which are shared with nuclear
facilities other than the concerned spent fuel interim storage facility or shared within the concerned
spent fuel interim storage facility, should not cause any inconvenience on the safety of the concerned
spent fuel interim storage facility by the sharing judged by its function, structure etc.
Guideline 20 Applicable codes and standards
The design, material selection, manufacturing, construction, and inspection of the facilities importantto safety of the spent fuel interim storage facility should be in conformity with codes and standards
recognized as appropriate.
1. The spent fuel interim storage facility should be in conformity with Japanese laws and regulations
such as the "Reactor Regulation Law", "Construction Standard Law", "Fire Protection Law" etc.
2. The design, material selection, manufacturing, construction, inspection etc. of facilities important tosafety should be in conformity with domestic codes and standards recognized as appropriate. For
items for which no domestic applicable codes or standards is exist, the codes or standards offoreign countries that are experienced and reliable may be applied.
Guideline 21 Consideration for inspection, repair etc.
The spent fuel interim storage facility should be made to be able to perform inspection, test,
maintenance and repair with appropriate methods according to the importance to safety and theneeds.

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Table G6-1

Contents of the Operational Safety Program for the Spent Fuel Interim
Storage Facility (Article 37 paragraph 1 of the Rule for Interim Storage of
Spent Fuel)(1) The duties of personnel engaged in the operation and management of the spent fuel storage facility
and organization(2) The following items with respect to the operational safety education for radiation workers at the
spent fuel storage facility(a) Policy for the operational safety education(including preparation of education program)(b) The contents of the operational safety education as follows
1) Relevant laws and the Operational safety program2) Structure, performance and operation of the spent fuel storage facility3) Radiation management4) Handling of nuclear fuel materials and objects contaminated by them5) Measures to be taken in emergencies(c) Other necessary items for the operational safety education of the spent fuel storage facility(3) Operation of the equipment especially necessary to be managed in view of safety preservation.
(4) Designation of controlled areas, and environment monitoring areas, and restriction of access tothese areas(5) Matters related to gaseous and liquid discharge monitoring equipment(6) Monitoring of the dose, the dose equivalent, the concentration of radioactive materials and thedensity of radioactive materials on the surface of objects contaminated by radioactive materials, andthe decontamination(7) Management of radiation measuring instruments and the method of radiation measurement(8) Patrols and checks of the spent fuel storage facility and their associated measures(9) Voluntary periodical inspections of the spent fuel storage facility(10) Receipt, delivery, transport, storage and other handling of spent fuels(11) Disposal of radioactive waste(12) Measures to be taken in emergency(13) Records on safety preservation of the spent fuel storage facility (including observance status)(14) Periodic Assesment of the spent fuel storage facility(15)Quality assurance of the spent fuel storage facility(16) Other necessary items for safety preservation of the spent fuel storage facility

Table G6-2

Contents of Decommissioning-related Operational Safety Program (Article
37 paragraph 2 of the Rules for Interim Storage of Spent Fuel)

In order to obtain the license for decommissioning program of a spent fuel storage facility, the operator
shall revise the Safety Rules and Regulations for the following points and shall get approval for therevision.
(1) Duties and organization of a person who will carry out decommissioning work.
(2) The following safety training items for radiation workers for decommissioning:(a) Implementation principle of safety training (including development of an implementation plan)(b) Safety training contents on the following items:
1) Relevant laws and regulations and Safety Rules and Regulations.
2) Structures and performance of the spent fuel storage facility.
3) Decommissioning of the spent fuel storage facility.
4) Radiation control.
5) Handling of nuclear fuel materials and materials contaminated with nuclear fuel materials.
6) Measures to be taken at an emergency.
(c) Other necessary matters for safety training on the spent fuel storage facility.
(3) Operation of systems requiring special control for safety.
(4) Establishment f the controlled area, conservation area, and environmental monitoring area, andaccess control to those areas.
(5) Exhaust monitoring system and discharge water monitoring system.
(6) Monitoring of radiation dose, dose equivalent, concentration of radioactive materials andradioactive material density on the surface of items contaminated with radioactive materials, andremoval of contamination.
(7) Control of radiation measuring devices and radiation measurement methods.
(8) Periodic self-imposed inspection of the spent fuel storage facility.
(9) Patrol of the spent fuel storage facility and handling of findings.

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Annexes(10) Disposal of radioactive wastes.
(11) Measures to be taken at an emergency.
(12) Records on the safety of the spent fuel storage facility (including the compliance with the Safety
Rules and Regulations).
(13) Records on the safety of the decommissioning (including the compliance with the Safety Rules
and Regulations).
(14) Quality assurance for the spent fuel storage facility.
(15) Quality assurance for the decommissioning work.
(16) Decommissioning management.
(17) Other necessary items for the safety and decommissioning of the spent fuel storage facility.

Table G6-3

Incident and Failure Reporting Standards at the Spent Fuel Interim Storage
Facility (Article 43-13 of the Rule for Interim Storage of Spent Fuel)

Upon the occurrence of any of the following events, operators of spent fuel storage facilities shallimmediately give notice to that effect to the Minister of Economy, Trade and Industry, and shall reportto the minister about the situation of the event and corrective actions taken within ten days of the event:(1) The spent fuel is stolen or its whereabouts is unknown;(2) A failure of the spent fuel storage facility is found (excluding a failure that cause minor
affection on spent fuel storage);(3) The concentration of radioactive material in air on the boundary outside a peripheral
monitoring area has exceeded the concentration limits provided in the Ministerial Ordinance of
METI Minister due to the gaseous radioactive waste release through discharge facilities;(4) The concentration of radioactive material in water on the boundary outside a peripheral
monitoring area has exceeded the concentration limits provided in the Ministerial Ordinance of
METI Minister due to the liquid radioactive waste release through discharge facilities;(5) Spent fuel etc. has leaked outside the controlled area;(6) Leakage of spent fuel or spent-fuel-contaminated materials inside a radiation controlled area
due to a failure of the spent fuel storage system or other unexpected situation except for thefollowing cases (excluding the cases that access control to the leakage area has been
implemented, a new measures such as key control have been taken, or leaked material has
spread outside of the radiation controlled area) where:(a) Leakage of liquid spent fuel or materials contaminated with spent fuel has not spread out of
the lasher provided around the leaked equipment.
(b) The function of relevant ventilation system has been properly maintained when gaseous
spent fuel or materials contaminated with spent fuel has leaked.
(7) Workers engaged in the radiation work have been exposed to radiation that exceeds or is
likely to exceed the dose limits provided in he Ministerial Ordinance of METI Minister; or(8) In addition to the events of the above paragraphs, a hazard to personnel (excluding minor
hazards other than radiation hazards) has occurred or is likely to occur at the spent fuelstorage facility.

L4

Excerpt of Regulation Relevant to Section H

Table H4-1

“Technical Standard for the Design and Construction Methods for theSpecific Waste Disposal Facility or Specific Waste Storage Facility”(Prevention of fire damage)
Article 3 If the safety of a specific waste disposal facility or specific waste storage facility could besignificantly impaired by a fire, the facility shall be provided with fire extinguishing and alarm systems
as appropriate (limited to systems that automatically detect a fire and set off an alarm, such as
automatic fire-alarm box and electric fire alarm system).
2 Any failure, damage or malfunction of the fire extinguishing system and alarm system in thepreceding paragraph shall not significantly impair the safety of the specific waste disposal facility or
specific waste storage facility.
3 A system important to safety, such as emergency power supply system, that could be damaged by a126

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fire shall consist of noncombustible or nonflammable materials as far as possible and shall be
provided with adequate fire protection measures such as fire walls where necessary.
4 Systems for handling or managing radioactive wastes that could generate hydrogen shall be
designed to prohibit retention.
5 Cells and rooms containing systems for handling or storage radioactive wastes that could generatehydrogen (excluding non-explosive systems) shall be provided with appropriate measures to prohibithydrogen retention and to prevent explosion in case of hydrogen leakage from those systems.
(Seismic design)
Article 4 A specific waste disposal or storage facility shall be designed so as not to have a serious
radiological impact on the public when damaged by seismic forces applied on it.
2 The seismic forces mentioned in the preceding paragraph shall be estimated taking account of theconditions of foundation ground, degree of earthquake damages in the region estimated from pastearthquake records, characteristics of seismic activities and other various factors, on the basis of thestructures of the specific waste disposal facility or specific waste management facility and the degreeof hazards due to the damages to the facility.
(Materials and structures)
Article 5 The materials and structures of the vessels, pipes and support structures in a specific waste
disposal facility or specific waste storage facility that are important to ensure the safety of the facility(hereinafter in this Article referred to as “vessels”) shall be adequate for ensuring the strength andcorrosion resistance required by the design of the vessels.
2 The vessels and pipes in the specific waste disposal facility or specific waste storage facility that areimportant to ensure the safety of the facility shall be designed so as to endure appropriate pressure
test or leakage test without significant leakage.
(Confinement functions)
Article 6 A specific waste disposal facility or specific waste storage facility shall be provided with thefunctions to confine radioactive wastes within restricted areas pursuant to the following requirements:(1) When a pipe delivering liquid not containing radioactive waste is connected to a vessel or pipe
containing liquid radioactive waste, the structure shall ensure that the liquid radioactive waste
does not flow back into the pipe delivering the liquid not containing radioactive waste.
(2) The air flow at the opening of a hood for handling of non-sealed radioactive waste shall bemaintained at an appropriate speed.
(3) Inner pressure of a room where contamination by radioactive waste could occur shall bemaintained negative as required.
(4) A facility that has a liquid radioactive waste handing system (solely for those areas where leakageof liquid radioactive waste could expand), shall be designed pursuant to the following
requirements:(a) The surfaces of floors and walls inside of the facility shall have structures to inhibit the leakage ofliquid radioactive waste.
(b) The periphery of a facility handling liquid radioactive waste or gateways leading to the outside of
the facility or its vicinity shall be provided with lashers to prevent the liquid radioactive waste fromleaking outside the facility, unless the floors inside of the facility are lower than the floors of theadjacent facilities or the ground surface and the liquid radioactive waste cannot leak to theoutside of the facility.
(c) The floors of a specific waste disposal facility or specific waste storage facility shall be above thedischarge water channels that discharge effluent to the outside of the facility site (excluding
ground water drainage channels which have no opening in the controlled areas that could becontaminated with radioactive waste), unless those discharge water channels are provided withthe system that safely disposes the effluent contaminated with radioactive waste and the
instrumentation to monitor the items listed in Article 15-3.
(Shielding)
Article 7 Shielding with capability required for preventing radiation hazards shall be provided if theprevention of radiation hazards due to the external radiation in a specific waste disposal facility or
specific waste storage facility site is required. In such case, measures to prevent radiation leakage
shall be taken if necessary to prevent radiation hazards due to any opening, pipe or other penetrationin the shielding structures.

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Article 8 Ventilation system that meets the following requirements shall be provided, if it is required toprevent radiation hazards due to the air contaminated with spent fuel or spent-fuel-contaminatedmaterials in the specific waste disposal facility or specific waste storage facility:(1) The ventilation system shall have necessary capability for preventing radiation hazards.
(2) The structure of the ventilation system shall prohibit reverse flow of the air contaminated withspent fuel or spent-fuel-contaminated materials.
(3) Filtering system, if it is installed, shall be capable for appropriate maintenance of its filteringfunction and shall have a structure to allow easy removal of the materials contaminated with spent
fuel or spent-fuel-contaminated materials or easy replacement of the system.
(4)The ventilation system shall have air intake ports that prohibit intake of the air contaminated withspent fuel or spent-fuel-contaminated materials.
(Prevention of contamination by spent-fuel-contaminated materials)
Article 9 As for the specific waste disposal facility or specific waste management facility buildings thatare frequently accessed, the surfaces of their walls, floors and other parts, that could becontaminated by spent-fuel-contaminated materials and could be touched by people, shall be easy toremove the spent-fuel-contaminated materials.
(Receiving system or management system)
Article 10 The radioactive waste receiving system of specific waste disposal facility or radioactive
waste management system of specific waste storage facility that could be overheated by decay heatand radiations from radioactive waste shall be provided with measures necessary for cooling.
(Treatment and disposal systems)
Article 11 Radioactive waste disposal system (excluding radioactive waste retaining system) shallmeet the following requirements:(1) Radioactive waste disposal system shall be capable of disposing radioactive wastes generated in
the specific waste disposal facility or specific waste storage facility so that concentration of
airborne radioactive materials outside the environmental monitoring area and concentration ofradioactive materials in the water at the outer boundary of the environmental monitoring do not
exceed the values specified by the Minister of Economy, Trade and Industry.
(2) Radioactive waste disposal system shall be installed separately from non-radioactive waste
disposal system, unless the system that leads non-radioactive liquid waste to radioactive liquid
waste disposal system is provided with the measures to prohibit for radioactive liquid waste to flow
back into non-radioactive liquid waste systems.
(3) Gaseous radioactive waste disposal system shall not discharge gaseous wastes at any part of thesystem other than exhaust port.
(4) If filtering system is installed in the gaseous radioactive waste disposal system, it shall be capable
for appropriate maintenance of its filtering function and shall have a structure to allow easy
removal of the materials contaminated with spent fuel or spent-fuel-contaminated materials oreasy replacement of the system.
(5) Liquid radioactive waste disposal system shall not discharge liquid waste at any part of the systemother than water discharge outlet.
(Systems important to safety)
Article 12 The systems important to safety such as emergency power supply system shall be designed
to meet the following requirements:(1) If a system is shared among two or more nuclear facilities (such as fabrication facility, reactor
facility, spent fuel storage facility, reprocessing facility, waste disposal facility and nuclear material
utilization facility), the functions to ensure the safety of specific waste disposal facility or specificwaste storage facility shall not be impaired by such sharing.
(2)If necessary for maintaining the functions to maintain the safety of specific waste disposal facility or
specific waste storage facility, the system or its parent system shall have appropriate redundancy.
(3)Inspection or test to confirm the functions to ensure the safety of specific waste disposal facility or
specific waste storage facility, and maintenance or repair for maintaining the integrity of suchfunctions shall be possible.
(Transport system)
Article 13 Transport system for radioactive wastes (excluding those which have no significant impact

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on personal safety ) shall be designed to meet the following requirements:(1) Transport system shall be capable of normal transport of radioactive wastes.
(2) When Radioactive wastes shall be safely retained in case of loss of power supply for thetransportation of radioactive waste.
(Instrumentation and control system)
Article 14 A specific waste disposal facility or specific waste storage facility shall be provided with thedevices for reliable detection and quick alarming of such situations as: when the safety of the facility
could be significantly impaired due to loss of equipment function, miss-operation or any other cause;
when the concentration of radioactive materials provided in Article 15 (2) or the dose equivalent
provided in Article 15 (4) shows significant increase; or when significant amount of liquid radioactive
materials could leak from the liquid radioactive waste disposal system.
2 A specific waste disposal facility or specific waste storage facility shall be provided with the circuits toactuate the necessary systems immediately and automatically, when the safety of the facility could besignificantly impaired due to loss of equipment function, miss-operation or any other cause and it isrequired to quickly actuate the system to maintain the function to confine radioactive waste within
restricted areas or the system to prevent fire or explosion.
(Radiation control system)
Article 15 A specific waste disposal facility or specific waste storage facility site shall be provided withthe radiation instrumentation to measure the values listed below. If it is difficult to directly measure
any of such parameters, indirect instrumentation may be used as an alternative:(1) Dose equivalent rate provided by the Minister of METI at the side wall of radiation shielding
structure of waste storage facility and waste receiving facility.
(2) Concentration of radioactive materials in exhaust gases at or near the gaseous radioactive waste
exhaust port
(3) Concentration of radioactive materials in discharge water at or near the liquid radioactive waste
discharge outlet(4) Dose equivalent of external radiation, concentration of airborne radioactive materials anddensities of radioactive materials provided by the Minister of METI on the surface of contaminateditems in the controlled area
(5) Dose equivalent of external radiation provided by the Minister of METI in the environmental
monitoring area
(Emergency Power Supply System)
Article 16 A specific waste disposal facility or specific waste storage facility shall be provided withpower generating system driven by internal combustion engine, or other power generating systemwith equal or more capability, in order to maintain the function of the systems necessary for ensuring
the safety of the facility in the event of loss of electric power supply from off-site power grid.
2 Systems especially important for ensuring the safety of specific waste disposal facility or specificwaste storage facility shall be provided with an uninterruptible power supply device or other power
supply system with equal or more capability.

Table H5-1

Fundamental Guidelines for Licensing Review of Land Disposal Facilities of
Low-Level Radioactive Waste (Excerpt)

Fundamental Site Conditions
It shall be considered that the initiating event to the big accident does not occur in or around the site of
the waste disposal facility. Moreover, if the accident occurs, events shall be seldom to escalate theeffect.
Dose Evaluation
1 Evaluation under Normal Conditions
The radiation dose of the general public in normal times shall be as low as reasonably achievable in
the planning of a step-wise control, in the design of the waste disposal facility, and in relation withthe situation of the site and ite vicinity.
2 Safety Evaluation
When it is presupposed that the technically assumed abnormal event occurs, excessive radiation
exposure shall not be imposed to the general public.
Radiation Control
1 The Function of Enclosure
In the case of disposal at the waste disposal facility installed with engineered barriers, the design
shall be provided with function to enclose radioactive materials in the restricted area of the waste

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disposal facility in the first step.
2 Inhibition of Radioactive Nuclides Migration
In the case of disposal at the waste disposal facility not installed with engineered barriers,
appropriate measures shall be taken with due consideration of migration inhibition of radioactive
nuclides from the waste disposal facility to the human environment in the disposal step.
3 Radiation Protection(1) The waste disposal facility shall be installed with radiation shields to reduce the radiation dose of
the general public as low as reasonably achievable by direct gamma ray and the sky shine
gamma ray.
(2) In the case of disposal in non-engineered barriers type disposal facility, and when there is thepossibility of scattering of radioactive materials, measures shall be taken to reduce the radiationdose of the general public by the scattering as low as reasonably achievable.
(3) The waste disposal facility shall be installed with appropriate radiation shields and the ventilation
etc. with due consideration of the working conditions of the personnel engaged in radiation work.
4 Radiation Exposure Control
Measures for monitoring and controlling of the radiation doses of the personnel engaged in radiation
work shall be taken at the waste disposal facility.
Environmental Safety
1 Discharge Control of Radioactive Gaseous and Liquid Wastes
Concentrations of radioactive materials discharged to the environment shall be controlled as low asreasonably achievable at the waste disposal facility by appropriate processing of radioactive
gaseous waste and the radioactive liquid waste generated at the associated facilities in the waste
disposal facility.
2 Radiation Monitoring(1) Measures shall be taken at the waste disposal facility to appropriately monitor the concentrationof radioactive materials etc. on the discharge route of radioactive gaseous and liquid wastes thatis discharged from the associated facilities of the waste disposal facility.
Measures shall be taken to appropriately monitor the radiation dose, the concentration etc. ofradioactive materials in the environment in accordance with the amount of released radioactive
materials.
(2) Measures shall be taken at the waste disposal facility to appropriately monitor the concentrationof radioactive materials etc. leaking out from the waste disposal facility to the underground water
etc. and migrating to the human environment in the 1st step and the 2nd step, or in the disposal
step.
Other Safety Measures
1 Design Considerations to Earthquakes
The waste disposal facility shall be designed for the design base earthquake force to preserve safetyfunctions required for the appropriate time period.
This design base earthquake force shall be defined corresponding to the C class facility in theclassification of importance for seismic design specified in the "Examination Guide for Seismic
Design of Nuclear Power Reactor facilities".
2 Design Considerations to Natural Phenomena other than Earthquake
The waste disposal facility shall be designed taking into considerations of the expected natural
phenomena other than the earthquake to preserve required safety functions required for theappropriate time period referring to the past record, at-the-spot observation, etc. in the site and its
vicinity.
3 Considerations to Fire and Explosion
Measures shall be taken at the waste disposal facility to prevent occurrence of the fire andexplosion, and to prevent excessive release of radioactive materials to the outside of the facility evenat the emergency of fire and explosion.
4 Considerations to Loss of Power Supply
Measures shall be taken at the associated facilities of the waste disposal facility responding to theloss of function of the external power supply system.
5 Conformity to Standards and Criteria
The waste disposal facility shall be designed and constructed based on the standards and thecriteria accepted as appropriate.
Termination of Control Time Period
Management and control of the waste disposal facility carried out from a viewpoint of the exposure
control may be terminated by the end of the limited time span, and the radiation dose of the generalpublic assumed to be imposed from the waste disposed shall be low enough so as the control is no
more necessary after the termination of the control.

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Table H6-1
Technical standards for Waste Disposal Facilities etc.
1.
The Technical standards for radioactive waste disposal facility(1) Technical standards provided in Article 7 of the Rule for Disposal of Category 1
Waste Disposal of Nuclear Fuel Material or Material Contaminated with Nuclear Fuel
Material(1) A waste repository shall be in consistent with the license application documents set forth in Article
51-2 paragraph 1 or Article 51-5 paragraph 1 of the Law and a document describing the conditions
for the license granted in accordance with Article 62-2 paragraph 1 of the Reactor Regulation Law(hereinafter referred to as "the license documents").
(2) Tunnels and shafts shall be in consistent with the license documents.
(3) The total radioactivity of specific radioactive materials contained in the radioactive wastes disposedin a waste disposal facility site shall not exceed, due to disposal, the total radioactivity described in
the license documents.
(4) Explosive materials, materials that significantly corrode other materials and other hazardous
materials shall not be disposed in a waste repository.
(5) A waste repository shall be backfilled in the way described in the license documents.

(2)

Technical standards provided in Article 6 of the Rule for Disposal of Category 2
Waste Disposal of Nuclear Fuel Material or Material Contaminated with Nuclear Fuel
Material

Article 6(1) The total amount of the radioactivity for each type of radioactive materials contained in theradioactive waste to be emplaced at the place of business where the waste disposal facility isconstructed shall not exceed the total amount of radioactivity for each type of radioactive materials
indicated on the application concerning the license as provided in the provisions of Article 51-2
paragraph 1 or Article 51-5 paragraph 1 of the Law, and the document which describe the conditions
required for the license as provided in the provision of Article 62-2 Paragraph 1 of the Law ("referred
to as "the application etc.", hereinafter in this article, Article 6-3 and Article 8);(2) Before starting waste repository disposal, the stagnant water at the places for disposal in the waste
disposal facility (when the waste disposal facility is demarcated with internal partition equipment of
Subparagraph (3) of the following article, the demarked area for the waste repository disposal, thesame, hereinafter in this subparagraph) shall be removed, and at the time of waste repository
disposal, measures shall be taken to prevent the infiltration of rain water etc. into the places
concerned;(3) In the case of waste repository disposal of solidified concrete etc., measures shall be taken toprevent the scattering of radioactive materials when there is a possibility that the materials may
disperse out of the waste disposal facility;(4) The waste disposal facility shall be taken measures by filling up with the soil etc., so that a void
does not remain after waste repository disposal is completed in the waste disposal facility
concerned;(5) Explosive materials, materials that corrode other materials remarkably, and other hazardous
substances shall not be disposed of in the waste disposal facility;(6) The waste disposal facility where the disposal is completed, the surface shall be covered with thesoil, so that the disposed materials and the equipment installed in the waste disposal facility does
not expose easily; and(7) Waste disposal facilities shall have the structure and equipment described in the application etc.
other than those provided in the preceding subparagraphs.
2 In case where waste repository disposal is carried out by disposal facility with outer artificial barrier
shall be as described in the following subparagraphs, in addition to those provided in the preceding
paragraphs:(1) It shall be constructed following the methods provided by the Minister of METI for the prevention ofradiation hazards;(2) The artificial barrier structure shall be in conformity with the following requirements;(a)The structure shall be safe from the view point of yield strength against the self weight, earthpressure, seismic force, etc.; and(b)The measure shall be taken for the effective corrosion prevention according to the quality of thesurface water, underground water, and the soil.
(3) The waste disposal facility, which area of opening exceeds 50 square meters or which disposal
volume exceeds 250 cubic meters, shall be in conformity with the requirements of the precedingarticle, and for the prevention of radiation hazards, the place shall be demarcated so that one
demarcated area shall not exceed about 50 square meters or one demarcated disposal volume
not exceed about 250 cubic meters by a method applied with the internal partition equipment

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provided by the Minister of METI;(4) When the waste repository disposal is carried out, the artificial barrier structure and the internal
partition equipment described in Subparagraph (3) shall be inspected at any time, and when there
is a possibility of destruction of these equipments or leak of radioactive materials, required
measures shall be taken to prevent destruction of these equipments, or leak of radioactive
materials; and(5)Waste disposal facility where the waste repository disposal is completed, or where the place isdemarcated by the internal partition equipment described in Subparagraph (3), the demarcatedarea where the disposal is completed, shall be covered by the method provided in the
Subparagraph (2) and provided by the Minister of METI for the prevention of radiation hazards asprovided in Subparagraph (6) of the preceding article, soon before covering with the soil.
3 In the case of waste repository disposal is carried out by disposal facility without outer artificial
barrier shall be as described in the following subparagraphs, in addition to those provided Paragraph1:(1) It shall be constructed following the methods provided by the Minister of METI for the prevention ofradiation hazards; and(2) Radioactive waste materials etc. solidified in one piece shall be in conformity with therequirements described in Subparagraph (2) of the preceding Paragraph, and the volume shall not
exceed about 500 cubic meters,

2.
(1)

Technical standards for radioactive wastes to be disposed
Technical standards provided in Article 12 of the Rule for Disposal of Category 1
Waste Disposal of Nuclear Fuel Material or Material Contaminated with Nuclear Fuel
Material(1) Radioactive waste to be disposed shall be waste form.
(2) Technical standards of radioactive waste form shall be as described in the following subparagraphs:(a) For the prevention of radiation hazards, radioactive wastes shall be enclosed or solidified in thecontainer;(b) The radioactivity concentration shall not exceed the maximum radioactivity concentration
indicated in the application etc.;(c) Any materials with a possibility of spoiling the integrity of waste form;(d) It shall have enough strength to bear the potential load that may be extended during waste
repository disposal;(e) There shall be no marked damage; and(f) Waste form etc. shall be labelled with tag with serial number identifying the waste form asprovided by application of the preceding Article. These tag should use the method which does
not disappear easily, and be marked at visible spot

(2)

Technical standards provided in Article 8 of the Rule for Disposal of Category 2
Waste Disposal of Nuclear Fuel Material or Material Contaminated with Nuclear Fuel
Material

Article 8(1) For intermediate depth disposal(a) Radioactive waste to be disposed shall be from a plant or site provided with a fabrication facility(limited to a facility that fabricates only uranium-plutonium mixed oxide fuel), reactor facility or
reprocessing facility.
(b) Radioactive waste to be disposed shall be waste packages.
(c) Waste packages shall meet the following requirements.
(2) For pit disposal(a) Radioactive waste to be disposed shall be from a plant or site with a reactor facility..
(b) Radioactive waste to be disposed shall be waste package or solidified concrete waste.
(c) The waste package or solidified concrete waste shall meet the following requirement or therequirements described in paragraph 3.
(3) For trench disposal(a) Radioactive waste to be disposed shall be from a plant or site with a reactor facility.
(b) Radioactive waste to be disposed shall be solidified concrete waste.
(c) The solidified concrete waste shall meet the requirement described in paragraph3.
2 Technical standards of radioactive waste form for intermediate depth disposal and for disposal withartificial barrier shall be as described in the following subparagraphs:(1) For the prevention of radiation hazards, radioactive wastes shall be enclosed or solidified in thecontainer using the methods provided by the Minister of METI;(2) The radioactivity concentration shall not exceed the maximum radioactivity concentration indicatedin the application etc.;132Annexes(3) The density of radioactive materials on the surface shall not exceed one tenth of the surface density
limit specified in Article 14 Paragraph 1 Item (c);(4) Any materials with a possibility of spoiling the integrity of radioactive waste materials shall not be
contained;(5) It shall have enough strength to bear the potential load that may be extended during waste
repository disposal;(6) There shall be no marked damage; and(7)Waste form etc. shall be labelled with tag indicating the radioactive waste with serial number
identifying the waste form as provided by the application of the preceding Article. These tag should
use the method which does not disappear easily, and be marked at visible spot
3 The technical standards to wastes, such as solidified concrete waste shall be as described in thefollowing subparagraphs:(1) An explosive material shall not be included;(2) The measure to compare with items described in the application shall be taken for the solidified
concrete waste. and(3) The radioactivity concentration shall not exceed the maximum radioactivity concentration indicatedin the application etc.

Table H6-2

Items that should be described in Operational Safety Program (Article 63
paragraph 1 of the Rule for Disposal of Category 1 Waste Disposal of
Nuclear Fuel Material or Material Contaminated with Nuclear Fuel Material)(1) Duties and organization of personnel engaged in management of the radioactive waste disposal
facility(2) Safety education for personnel engaged in radiation work at the disposal facility concerning:(a) Safety education policy (including its implementation plan);(b) Details of safety education concerning:
1) related laws, regulations and the Operational Safety Program;
2) structure, performance and operation of disposal facility;3) radiation control;4) handling of nuclear fuel material ; and5) emergency preparedness;(c) Other necessary matters concerning safety education concerning waste disposal facilities.
(3) Operation of systems to be specially controlled for safety reasons(4) Establishment of a controlled area, a peripheral monitoring area and preservation area of a disposal
facility, and restriction of access to these areas;(5) Gaseous and liquid discharge monitoring equipment;(6) Monitoring of dose, dose equivalent, radioactive material concentration and surface contamination
density by radioactive materials, and decontamination;(7) Management of radiation measurement equipment and measuring method;(8) Patrol and inspection of disposal facility and measures to be taken after patrol and inspection;(9) Self-imposed periodic facility inspection of waste disposal facility(10) Receipt, transport, storage and handling of radioactive waste;(11) Emergency preparedness;(12) Records of the safe operation of disposal facility (including compliance with the Operational Safety
Program); and(13) Periodic assessment of waste disposal facility(14) Quality assurance for waste disposal facility(15) Other matters necessary for the safe operation of disposal facility.

Table H6-3

Methods for Disposal (summary of Article 61 of the Rule for Disposal of
Category 1 Waste Disposal of Nuclear Fuel Material or Material
Contaminated with Nuclear Fuel Material)

1. Gaseous waste disposal
Gaseous wastes shall be disposed of by any of the following methods:(1) Discharge through ventilation facilities;
The concentration of radioactive materials under ventilation shall be controlled as low as possible
by filtering, decay radioactivity, dilution with a lot of air, etc. at the ventilation facilities. In this case,the concentration of radioactive materials in the air at the ventilation port, or at the exhaust
monitoring equipment shall be monitored, so as not to exceed the concentration limits provided by
the Minister of METI at outside boundary of peripheral monitoring area;(2) Retain and store in a gaseous waste storage tank that is effective for the prevention of radiation
hazards.

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2.Liquid waste disposal
Liquid wastes shall be disposed of by any of the following methods:(1) Discharge through discharge facilities;
The concentration of radioactive materials under discharge shall be made as low as possible
by filtering, evaporation, adsorption by an ion exchange resin method etc., decay radioactivity,
dilution by plenty of water, and other methods at the discharge facility. In this case, theconcentration of radioactive materials in the underwater at the discharge port, or at the discharge
water monitoring equipment, shall be monitored so as not to exceed the concentration limits at
outside boundary of peripheral monitoring area provided by the Minister of METI;(2) Retain and store in a liquid waste storage tank that is effective for the prevention of radiation
hazards;(3) Enclose in a container or solidify in a container, and store in a storage facility that is effective forthe prevention of radiation hazards;(a) When enclosing radioactive wastes in a container, the container concerned shall be inconformity with the following standards:
The structure shall have low permeability, corrosion resistant and low leakage of radioactive
wastes;There shall be no possibility of crack or damage; andThe lid of the container shall not be taken off easily.
(b) When solidifying radioactive wastes in a container, the container used for solidifying theradioactive wastes shall be protective against dispersion or leakage of the radioactive waste;(c) When storing in a storage facility that is capable of prevention of radiation hazards, thefollowing items shall be subjected:
When radioactive wastes are enclosed in a container, and are stored, the container
concerned shall be wrapped with materials which are capable to absorb all of the enclosed
radioactive wastes, or provided with a saucer which is capable to accommodate all of thewastes, when a crack or a damage arises to prevent spread of the contamination;
The container in which radioactive wastes were enclosed or solidified, shall be attached withmarks that shows that the content is radioactive wastes, and a serial number corresponding
to the radioactive waste whose recorded content based on the provisions of Article 44 shallbe displayed to compare; andPost up notes for administration and control of the disposal facility concerned in the place
easily visible.
(4) Incinerate by an incineration facility that is effective for the prevention of radiation hazards(5) Solidify by a solidifying facility that is effective for the prevention of radiation hazards; or(6) Waste repository disposal in a waste disposal facility in accordance with the technical standards
for disposal facility and radioactive waste to be disposed;
The concentration of radioactive materials in the underwater at the boundary of the outside of an
peripheral monitoring area shall be controlled not to exceed the concentration limits provided by
the Minister of METI by monitoring the concentration of radioactive materials in the underwater ofthe peripheral monitoring area
3. Solid waste disposal
Solid wastes shall be processed and stored of by any of the following methods:(1) Incinerate by an incineration facility that is effective for the prevention of radiation hazards;(2) Enclose in a container or solidify in a container, and store in a storage facility that is effective forthe prevention of radiation hazards, and dispose;(a) When enclosing radioactive wastes in a container, the container concerned shall be inconformity with the following standards:
The structure shall have low permeability, corrosion resistant and low leakage of radioactive
wastes;There shall be no possibility of crack or damage; andThe lid of the container shall not be taken off easily.
(b) When solidifying radioactive wastes in a container, the container used for solidifying theradioactive wastes shall be protective against dispersion or leakage of the radioactive waste;(c) When storing in a storage facility that is capable of prevention of radiation hazards, thefollowing items shall be subjected:
The container in which radioactive wastes were enclosed or solidified, shall be attached withmarks that shows that the content is radioactive wastes, and a serial number corresponding
to the radioactive waste whose recorded content based on the provisions of Article 44 shallbe displayed to compare; andPost up notes for administration and control of the disposal facility concerned in the place

134Annexes
easily visible.
(3) Radioactive waste such as a large machine, which is very difficult to process by the method of
Item (2) or any radioactive waste that needs the decay of radio-activities with time, shall be stored
in a depository that is effective for the prevention of radiation hazards, and dispose; Post up notes
for administration and control of the disposal facility concerned in the place easily visible.
(4) Waste repository disposal in a waste disposal facility in accordance with the technical standards
for disposal facility and radioactive waste to be disposed;
The concentration of radioactive materials in the underwater at the boundary of the outside of an
peripheral monitoring area shall be controlled not to exceed the concentration limits provided by
the Minister of METI by monitoring the concentration of radioactive materials in the underwater ofthe peripheral monitoring area

Table H6-4

The Incidents Reporting Criteria (Article 89 of the Rule for Disposal of
Category 1 Waste Disposal of Nuclear Fuel Material or Material
Contaminated with Nuclear Fuel Material)

Upon occurrence of any of the following incidents, the Licensee of a Category 1 Waste Disposal shallimmediately give notice to the Minister of METI, and report within ten days on the details of theincidents and corrective measures taken:(1) Theft or loss of nuclear fuel material;(2) Failures of a disposal facility that disturb category 1 waste disposal work as special measures areneeded for repair of the failure;(3) Failures of a disposal facility that disturb category 1 waste disposal work as a result of loss or
potential loss of confinement function of nuclear fuel materials etc. in the limited area, radiation
shielding function to prevent radiation hazards by external radiation, or fire or explosion protection
function in a waste disposal facility;(4) Abnormal condition of discharge of gaseous radioactive wastes at ventilation facility or dischargeof liquid radioactive wastes from a discharge facility due to failures of a disposal facility or otherunexpected events;(5) Atmospheric radio-nuclides concentrations by radiation monitoring outside peripheral monitoringarea exceeding limit provided by the Minister of METI because of discharge of gaseous radioactive
waste;(6) By radiation monitoring, radio-nuclides concentrations in discharged water at the outer boundaryof peripheral monitoring area exceeding limits provided by the Minister of METI ;(7) Leakage of nuclear fuel materials, etc. outside the controlled area;(8) Leakage of nuclear fuel materials, etc. inside the controlled area due to a failure of disposal facility
or other unexpected events excluding following cases (excluding the case when the measures
such as access control or key control for the area related to the leakage or when the leakedmaterial spreads outside the controlled area);
When the leaked liquid nuclear fuel materials etc. does not spread outside the curb readily
installed around the equipment for prevention of spreading of leakage;
The function of ventilation related to the area of the leakage of gaseous nuclear fuel materials
etc. is maintained appropriately;
The amount of radioactivity of leaked nuclear fuel materials etc. is very small or the degree ofleakage is minor.
(9) Effective dose by radiation exposures of personnel in the controlled area exceeding or likely to
exceed dose limits of 5mSv for radiation workers and 0.5mSv for non-radiation workers due to a
failure of a disposal facility or other unexpected events;(10) Radiation exposures of radiation workers exceeding or likely to exceed the dose limits specified
by the Minister of METI ;(11) Any other hazards to personnel occurring or likely to occur at the facility (excluding minor
non-radiation hazards).

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L5 Illustrations related to spent fuel storage

Image of storage building of Recycle Fuel Storage Center (3,000 tons)

Fig. L5-1 Conceptual Drawing of Recycle Fuel Storage Center(Source: Home page of Recycle Fuel Storage Company)

Pressure
sensor
圧力センサーBasketバスケット

Primary
lid
一次蓋

二次蓋
Secondarylid
Fuelassembly
燃料集合体

Shell
胴
Heat transfer fin
伝熱フィン

Neutron shielding
中性子遮へい材Outer
外筒 cylinder
Trunnion
トラニオン

Fig. L5-2 Concept of metallic cask
(Source: Home page of Recycle Fuel Storage Company)

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L6 Illustrations related to waste disposal
L6.1 Categorization of waste disposal methods
Near surface
pit disposal

Low

Power station waste

TRU waste

Uranium waste

Near surface
trench disposal

Intermediate
depth disposal

Radiation level

High level radioactive waste

Geologic stratum deeper than 300 m

Geological disposal

High

Fig. L6-1 Categorization of radioactive waste disposal methods in Japan(Source: Home page of the Agency for Natural Resources and Energy)

L6.2 Near surface pit disposal

Cover
soil

(More than 4 m)

Covering withbentonite mixed soil

Drum
Inspection
Cementpath
Drainagefillerpipe
Bed rock

About
8m

Porousconcrete
layer

Reinforced
concrete pit

Fig. L6-2 Example of near surface pit disposal(Source: Home page of the Agency for Natural Resources and Energy)

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L6.3 Intermediate depth disposal
Disposalcavity
処分空洞

Perimetriccorridor
周辺通路

Accesscorridor
アクセス通路To ground facility
地上施設へ

Fig. L6-3-1 Underground structure of waste disposal facility(Source: "Safety Regulation on Intermediate depth disposal of low level radioactive
waste", Waste Safety Subcommittee, Subcommittee on Nuclear and Industrial Safety,
Advisory Committee for Natural Resources and Energy, January 2008)

Sprayedconcrete
吹き付けコンクリート
Secondary
二次覆工covering
Backfill埋戻し材
material
Concretepit
コンクリートWaste
package layer
廃棄体層(surrounded with mortar（周囲はモル
grout)
タル充てん）

ピット

Low diffusiveness
layer
低拡散層
Low percolation
低透水層layer

Fig. L6-3-2 Vertical sectional view of disposal cavity(Source: "Safety Regulation on Intermediate depth disposal of low level radioactive
waste", Waste Safety Subcommittee, Subcommittee on Nuclear and Industrial Safety,
Advisory Committee for Natural Resources and Energy, January 2008)

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拡散
Diffusion
Advection
移流分散
Dispersion

Skeleton躯体
concreteLow
diffusion
低拡散barrier

ｺﾝｸﾘｰﾄDiffusion
拡散
Advection
移流分散
Dispersion

ベント
Bentonite
ナイト

バリア

Diffusion
拡散
Advection
移流分散
Dispersion

均
一
混
合
層

生物圏
Rock

岩

Fig. L6-3-3 Performance evaluation model for safety evaluation(Source: "Safety Regulation on Intermediate depth disposal of low level radioactive
waste", Waste Safety Subcommittee, Subcommittee on Nuclear and Industrial Safety,
Advisory Committee for Natural Resources and Energy, January 2008)

Inspection tunnel (large)
調査坑（大）

Entrance
坑口

about
5約５m
m
about
7
m
約７m

Instrument
計測坑Ｂ tunnel B
Instrument
計測坑Ｃ tunnel C

Test試験空洞
cavityInstrument
計測坑Ａ tunnel A
about
約２m
2m
about
2m
約２m
水平ボーリング
Horizontal
boring

about
約16m
16
m
Inspection
tunnel (small)
調査坑（小）
約２m 2 m
about

about
18 m
約18m

約２m
about
2m

図−2 調査坑鳥瞰図

図−3 試験空洞

Fig. L6-3-4 Inspection tunnel(Source: "Safety Regulation on Intermediate depth disposal of low level radioactive
waste", Waste Safety Subcommittee, Subcommittee on Nuclear and Industrial Safety,
Advisory Committee for Natural Resources and Energy, January 2008)

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公
衆
の
被
ば
く
Public exposure

Waste
package
廃棄体
Filler
充填材

Diffusion
拡散
Advection
移流分散
Dispersion

Biosphere

間隙
Homogeneous
濃度
porosity
一様

Homogeneous mixed layer

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L6.4 Geological disposal
Flow from construction
to operation

Ground facility: about 1 km2

Inside Control Bldg.

Construction of tunnels

Boring hole

Access tunnel

Installation of vitrified waste
Backfill completed

In operation

Under construction

Disposal panel

Connection tunnel

Backfill of disposal tunnels

Underground facility: about 10 km2

Fig. L6-4-1 Concept of geological disposal(Source: Home page of Nuclear Waste Management Organization of Japan)

Common ground facility

High level radioactive waste
TRU waste
Appropriate distance, e.g. approx. 300 m

Fig. L6-4-2 Concept of single-site disposal(Source: Home page of the Agency for Natural Resources and Energy)

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