National Report of JAPANfor the Fifth Review Meeting

Joint Convention on the Safety of Spent Fuel Management
and on the Safety of Radioactive Waste Management

October, 2014

ministry of Foreign Affairs
ministry of Education, Culture, Sports, Science and Technology
ministry of Health, labour and welfare
ministry of Economy, Trade and industry
Nuclear Regulation Authority

Contents
Section A Introduction.................................................................................................... 4
Section B Policies and Practices ..................................................................................... 6
B1 Spent Fuel Management Policy...........................................................................6
B2 Spent Fuel Management Practices ......................................................................7
B3 Radioactive Waste Management Policy ..............................................................8
B4 Radioactive Waste Management Practices........................................................10
B5 Criteria used to define and categorize radioactive waste ..................................10
Section C Scope of Application .................................................................................... 11
Section D Inventories and Lists .................................................................................... 12
D1

List of spent fuel management facilities...........................................................12

D2

Storage of spent fuel .........................................................................................12

D3

List of radioactive waste management facilities ..............................................12

D4

Inventories of radioactive waste .......................................................................13

D5

List and status of nuclear facilities in the process of being decommissioned ..14

D6

Usage facilities .................................................................................................15

Section E Legislative and Regulatory System .............................................................. 16
E1

Legislation in Japan ..........................................................................................18

E2 Regulatory body ................................................................................................23
Section F Other General Safety Provisions .................................................................. 27
F1

Responsibility of the license holder ..................................................................27

F2

Human and financial resources .........................................................................29

F3

Quality assurance ..............................................................................................33

F4

Operational radiation protection .......................................................................36

F5Emergency preparedness ..................................................................................41

F6

Decommissioning .............................................................................................62

Section G Safety of Spent Fuel Management ............................................................... 63
G1

General safety requirements .............................................................................65

G2

Existing facilities ..............................................................................................671

G3

Siting of proposed facilities..............................................................................68

G4

Design and Construction of Facilities ..............................................................70

G5

Assessment of the safety of facilities ...............................................................71

G6

Operation of facilities .......................................................................................72

Section H Safety of Radioactive Waste Management .................................................. 75
H1

General safety requirements .............................................................................77

H2

Existing facilities and past practices ................................................................80

H3

Siting of proposed facilities..............................................................................82

H4

Design and construction of facilities ................................................................83

H5

Safety assessment of facilities ..........................................................................86

H6

Operation of facilities .......................................................................................88

H7

Institutional measures after closure ..................................................................94

Section I Transboundary Movement ............................................................................. 99
I1 Transboundary movement ................................................................................100
I2 Prohibition of shipment to a destination south of latitude 60 degrees South ...101
Section J Disused Sealed Sources .............................................................................. 102
J1

Regulatory framework for sealed sources .......................................................102

J2Management of radioactive sources ................................................................102

J3

Reentry of returning sealed sources .................................................................104

Section K General Efforts to Improve Safety ............................................................. 105
K1

The IRRS ........................................................................................................105

K2

Response to Challenges Identified at the Previous Review Meeting .............105

Section L ANNEXES.................................................................................................. 108
L1 Inventory of spent fuel ....................................................................................109
L2

Inventory of radioactive waste........................................................................110

L3

List of spent fuel storage facilities and radioactive waste storage facilities ...117

L4

Excerpt of Regulations Relevant to Sections G and H ...................................1302

List of Acronyms and Abbreviations

Acronym
Name
DCA
Deuterium Criticality Assembly
EAL
Emergency Action Level
HLW
High Level Waste
HTR
Hitachi Ltd.’s Hitachi Training Reactor
ICRP
The International Commission on Radiological Protection
JAEA
Japan Atomic Energy Agency
JAPCO
The Japan Atomic Power Company
JNES
The Japan Nuclear Energy Safety Organization
JNFL
The Japan Nuclear Fuel Ltd.
LWRs
Light Water Reactors
METI
Ministry of Economy, Trade and Industry
MEXT
Ministry of Education, Culture, Sports, Science and Technology
MHLW
Ministry of Health, Labour and Welfare
MOE
Ministry of the Environmental
MOFA
Ministry of Foreign Affairs
NCAA
National Competent Authority for an Emergency Abroad
NCAD
The National Competent Authority for a Domestic Emergency
NISA
The Nuclear and Industrial Safety Agency
NPS
Nuclear Power Station
NRA
The Nuclear Regulation Authority
NUMO
The Nuclear Waste Management Organization of JapanNWP
The National Warning Point
OIL
Operational Intervention Level
PAZ
Precautionary Action ZonePFSB
The Pharmaceutical and Food Safety Bureau
RANET The IAEA Response Assistance Network
RFS
Recyclable-Fuel Storage Company
RUR
The Rikkyo University Institute for Atomic Energy
TEPCO
Tokyo Electric Power Company
TTR-1
Toshiba Corporation’s Training Reactor-1
UPZ
Urgent Protective action planning Zone

3

A Introduction
Section A Introduction
1 Current status of nuclear energy use in Japan
In light of the lessons learned from the Tokyo Electric Power Company’s Fukushima Daiichi
Nuclear Power Station (Fukushima Daiichi NPS) accident on March 11, 2011, the Nuclear
Regulation Authority (NRA) was established in September 2012. The NRA has centralized
responsibility not only for the administration of nuclear regulation and nuclear security, which werepreviously handled by related administrative bodies, but also for the formulation of

Nuclear

Emergency Response Guidelines in accordance with the provisions of the Nuclear Emergency Act
and the Act on Special Measures Concerning Nuclear Emergency Preparedness. The NRA has also
been responsible since April 2013 for administrative matters concerning safeguards based oninternational commitments and the regulation of activities such as radiation monitoring and the useof radioactive isotopes.
The Japan Nuclear Energy Safety Organization (JNES), and its role as a technical support
organization, were merged into the NRA effective March 1, 2014.
After the accident, each nuclear power plant was accordingly shut down at the time of its scheduled
periodic facility inspection and by May 2012, all nuclear power stations had suspended operations.
Units 3 and 4 at the Kansai Electric Power Company’s Ohi Power Station resumed operations inJune 2012, but they too subsequently underwent periodic facility inspections and as of August 2014,
there are no nuclear power stations in operation in Japan.
Japan has 48 power reactor units in service at the end of March 2014, following the decision todecommission Units 1 to 6 at the Fukushima Daiichi NPS. Japan’s other nuclear facilities are as
follows: 6 nuclear fuel fabrication facilities include 2 uranium enrichment facilities, 2 spent fuelreprocessing facilities, 2 radioactive waste interim storage facilities, 2 radioactive waste repositories,
14 research reactors, 8 research reactors currently under decommissioning, and 15 facilities which
use more than a certain quantity of uranium or other nuclear fuel material.
2 Efforts concerning the safety of spent fuel management and radioactive waste management
Japan is conducting a fundamental review of its nuclear regulations in response to the accident at the
Fukushima Daiichi NPS. The NRA put into force new regulatory requirements for nuclear power
stations in July 2013, and those for nuclear fuel facilities in December 2013. The NRA began
comformity reviews with the new regulatory requirements of nuclear power stations applied from
July 2013, and of nuclear fuel facilities applied from January 2014.
In addition, regarding Fukushima Daiichi NPS, the NRA designated the facilities needed special
control after emergency responses to the nuclear emergency situation to be as the "Specified
Nuclear Power Facilities" in November 2012, in order to control them for operational safety in4Introduction A
appropriate manners responding to the situations of the facilities, in accordance with the Act ofRegulation of Nuclear Source Material, Nuclear Fuel and Reactors which was revised with theestablishment of the NRA. Furthermore, the NRA indicated TEPCO the "items required formeasures." After that, on August 2013, the NRA approved TEPCO’s implementation plan inaccordance with the measures indicated by the NRA. The NRA conducts the inspections about thecompliance of the implementation plan approved by the NRA, and reviews the application foralteration approval of the implementation plan that considering the progress of work.
3 Preparation of the report
This report describes the steps taken for implementing the obligations under this Convention and is
a compilation of information available at the end of March 2014, unless otherwise specified.
Although taking the Guidelines on the structure of National Report (INFCIRC/604/Rev3) into
account, this report has a slightly different structure to clearly identify the responsible organizationfor each obligation of the Joint Convention. This report was mainly developed by the following
organizations and the Ministry of the Environment(MOE) provided reference information of off-site
remediation.

Chapters defined

Responsible organization

by INFCIRC/604
A

MOFA, MEXT, METI, NRA

B

METI

C

MOFA

D

NRA

E

MHLW, METI, NRA

F

NRA

G

NRA

H

NRA

I

METI

J

NRA

K

MEXT, METI, MOE, NRA

L

NRA

5

B 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 shall also
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 and radioactive waste
management in Japan and the operator’s actions based on that policy. The policy and actions for the safetyof 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.

B1 Spent Fuel Management Policy
How to manage spent fuel is a global challenge. Spent fuel is an unavoidable product of the use of nuclear
energy, and it is essential to implement measures to resolve this challenge as a responsibility of the current
generation so that the burden is not passed on to future generations. Therefore, Japan will drasticallyreinforce and comprehensively promote efforts to resolve the challenge of how to manage and dispose ofspent fuel.
As the current generation that has produced radioactive waste, the government of Japan will reinforce
measures toward final disposal of high-level radioactive waste and take the initiative in solving thisproblem. However, the process will take a long time. In the meantime, spent fuel produced by nuclear
power generation must be safely managed. It is therefore necessary to expand the capacity for storing
spent fuel and is urgently important to broaden the range of choices for managing spent fuel while
ensuring safety. It will ensure flexibility of policies and response, and contribute to medium-term energy
security.
In Japan's new Strategic Energy Plan (April, 2014 Cabinet decision), based on this concept, the storage
capacity of spent fuel will be expanded. Specifically, while studying a wide range of locations as possible
sites, regardless of whether they are inside or outside the premises of a power plant, the government ofJapan will strengthen its effort for facilitating construction and utilization of new intermediate storage
facilities and dry storage facilities.
Furthermore, the government of Japan will promote development of technologies for reducing the volume
and harmfulness of radioactive waste in order to secure a wide range of options in the future.
6

Policies and Practices B
Regarding the nuclear fuel cycle policy, the government of Japan will steadily promote reprocessing andplutonium use in Light Water Reactors (LWRs) while taking into consideration past history and will seek
the understanding of the relevant municipalities and the international community, and it will flexibly
address measures in the mid- to long-term basis.
The “Act for Deposit and Administration of Reserve Funds for Reprocessing of Spent Fuel from Nuclear
Power Generation” (see Section E) was established that requires the operators to deposit the funds forspent fuel reprocessing in a fund administration corporation. The objective of “the Act” is to ensure theproper implementation of spent fuel reprocessing, disposal of radioactive wastes generated from
reprocessing, and disassembling of reprocessing facilities. As a part of such steps, The Minister of METI
designated “Radioactive Waste Management Funding and Research Center” (public interest incorporated
foundation) as a non-profit “fund administration corporation” (October 2005) that is supervised by the
Minister through supervisory orders and on-the-spot inspection.

B2 Spent Fuel Management Practices
1.

Reprocessing of spent fuel generated from nuclear power generation

Electric utilities had sent spent fuel to the United Kingdom and French reprocessing companies since
1969; the export of spent fuel to foreign reprocessing plants closed in July 2001. Approximately
7,100MTU of spent fuel had been exported.
A part of national demand for reprocessing had been covered by the reprocessing plant of theincorporated administrative agency, JAEA, which was commissioned in December 1980, in Tokai village
in Ibaraki Prefecture (reprocessing capacity: 0.7MTU per day). This plant was built for the purpose of
establishing reprocessing technology and of training and fostering engineers and technicians in Japan.
The plant completed the reprocessing service contracted by the electric utilities in the end of March 2006.
Since then, it has been utilized as a facility for developing technologies for reprocessing spent MOX fuelin light water reactors (LWRs), spent fuel in an advanced thermal reactor and spent fuel in a fast breeder
reactor. The plant has reprocessed a total of approximately 1,100MTU of spent fuel since thecommissioning.
In response to the amendment of the Act on the Regulation of Nuclear Source Material, Nuclear Fuel
Material and Reactors in 1979, a private reprocessing company, the Japan Atomic Fuel Service Co., Ltd.
(presently, the Japan Nuclear Fuel Ltd., JNFL) was established in 1980, funded by the electric utilities.
This company commenced construction of a commercial reprocessing plant with annual reprocessing
capacity of 800MTU in Rokkasho village, Aomori Prefecture in 1993, based on the operating experienceof the reprocessing plant of Japan Atomic Energy Agency (JAEA), considering the trends of domestic
demand for reprocessing, and introducing technologies and experiences accumulated in the leading
countries in the field of reprocessing. The reprocessing plant started pre-service inspection using actual
spent fuel in 2006 aiming at commencement of operation in 2014. The plant has reprocessed a total of
approximately 430MTU for the pre-service inspection at the end of March 2014. Spent fuel storage has
already begun in a plant, completed in 1999, with the storage capacity of 3,000MTU. This plant has
7B Policies and Practices
accepted a total of approximately 3,400MTU by the end of March 2014. As of the end of March, 2014,
the amount of spent fuel stored in nuclear power plants of LWR in Japan amounts to approximately
14,000MTU.
2. Offsite interim spent fuel storage
The amendment of the Act on the Regulation of Nuclear Source Material, Nuclear Fuel Material andReactors was enforced in 2000 to incorporate provisions on interim spent fuel storage. In response to thisamendment, Tokyo Electric Power Company and Japan Atomic Power Company jointly established“Recyclable-Fuel Storage Company (RFS)” in 2005. RFS applied to the Minister of METI for the license
for the construction and operation of Recyclable-Fuel Storage Center at Mutsu city, Aomori Prefecture,
which is Japan’s first off-site interim spent fuel storage facility, in March 2007, based on the Act on theRegulation of Nuclear Source Material, Nuclear Fuel Material and Reactors. The application was
accepted in May 2010. The application for the design and method of construction was made to the
Minister of METI in June 2010, and was approved in August 2010. Upon receipt of the approval, theconstruction was started. The Recyclable-Fuel Storage Center is the facility to store spent fuel generated
from BWRs and PWRs in metallic dry casks, and is capable of storing a maximum of approximately
3,000MTU of spent fuel.
In December 2013, Nuclear Regulation Authority (NRA) developed new regulatory requirements fornuclear fuel cycle facilities including spent fuel storage facility based on TEPCO’s Fukushima Daiichi
Nuclear Power Station Accident. In January 2014, RFS applied to NRA for review of spent fuel storage
facility. Now NRA is implementing its review. RFS is scheduled to start operation in March 2015.
3.

Management of spent fuel from research reactor facilities

The spent fuel from research reactor facilities is either returned to the USA, or is reprocessed or stored inJapan.

B3 Radioactive Waste Management Policy
The government of Japan developed the policy for promoting radioactive waste disposal as described
below.
1.

Radioactive waste subject to geological disposal(1) High level radioactive waste
In Japan, a site for geological disposal of high level radioactive waste is determined through three stepsof the selection of “preliminary investigation areas”, “detailed investigation areas” and “construction siteof final disposal facility”, in accordance with the “Final Disposal Act” in May 2003. (See Section E).
The Nuclear Waste Management Organization of Japan (NUMO) was established as an organization to
implement final disposal. In addition, utilities have been deposited the reserve funds for final disposal to
NUMO. The appeal to the public for candidate areas for literature survey on possible installation of final
disposal facility was conducted by NUMO, but the literature survey has not yet been commenced.
8

Policies and Practices B
Based on the failure of Toyo-cho, Kochi Prefecture, an additional system was introduced in 2007, in
which central government offers a literature survey to the municipalities as well as research anddevelopment for the improvement of safety and reliability of geological disposal. Public hearings and PR
activities for promoting public understanding have also been carried out. However, there is no record of
the offer so far, and the literature surveys have not yet been undertaken.
Under these circumstances, in Japan's new Strategic Energy Plan (April 2014 Cabinet decision) it was
decided that Japan should take the initiative to solve the problem of high-level radioactive waste as the
responsibility of the current generation that created the waste so as not to put off the burden on to future
generations. Specifically, central government focused on promoting peoples’ understanding by indicating
the area (scientific potential land) considered higher suitability from a scientific perspective. While
making efforts on the assumption of geological disposal, it is ensured that the future generation will beable to select the best disposal method (reversibility and retrievability). The technical reliability ofgeological disposal will be evaluated while proceeding with parallel surveys and research of alternative
disposal options.
As for international cooperation, Japan has been studying, and using as reference, cases in foreigncountries where disposal site selection is in progress, and will continue to exchange views with thecountries that have final disposal programs and also to promote multinational cooperation using
cooperative frameworks of the IAEA, OECD/NEA, etc.
(2) Long-lived low-heat generating radioactive wastes (TRU wastes) to be geologically disposed of
ANRE amended the Final Disposal Act in 2007. According to this amendment, TRU wastes from
reprocessing that need to be geologically disposed of and high level radioactive wastes that are returned
from overseas reprocessing plants in exchange for TRU wastes were added to the wastes to be finallydisposed of by NUMO, and generators of such radioactive wastes were legally requested to provide thecost needed for final disposal.
2.

Radioactive wastes subject to disposal with active control

In Japan, disposal with active control is categorized by the following three types; “near surface trenchdisposal”, “near surface pit disposal” and “intermediate depth disposal.” JAEC stated in the Framework
for Nuclear Energy Policy that it is often effective and efficient to manage and dispose of radioactive
waste in an integrated fashion according to the properties of the waste material regardless of thegenerators or waste sources, and therefore, the Government should coordinate various systems
accordingly.
Low level radioactive wastes generated in nuclear power plants that are subject to near surface trenchdisposal and near surface pit disposal are already being disposed of with such methods.
However, for intermediate depth disposal system, safety regulations have not been developed.
3.

Ban on sea dumping of radioactive waste
9B Policies and Practices
In compliance with the Convention on the Prevention of Marine Pollution by Dumping of Wastes andOther Matter (1972) and its amendment to Annex I in 1993, it was decided that “the government of Japan
will eliminate the option of sea dumping as a principle of low level radioactive waste in the future.”
Based on this decision, the Reactor Regulation Act was amended in May 2005, and sea dumping ofradioactive waste was banned.

B4 Radioactive Waste Management Practices
Operators, recognizing their responsibility concerning radioactive waste management, shall manage
radioactive waste generated at their facilities in compliance with The Reactor Regulation Act, theRadiation Disease Prevention Act and relevant regulations.
B4-1

High Level Radioactive Waste Management Practices

Spent fuel generated in Japan, has been reprocessed by the Rokkasho Reprocessing Plant of JNFL, Tokai
Reprocessing Plant of JAEA and reprocessing plants in the United Kingdom and France. (JNFL has been
reprocessed in active test and plans to complete the Rokkasho Reprocessing Plant in October 2014.)
The electric power utilities in Japan have concluded reprocessing contracts with the United Kingdom andFrench companies for a total of 5,600 MTU of spent fuel from light water reactors and 1,500 MTU ofspent fuel from a gas cooled reactor. In accordance with these contracts, vitrified waste canisters are
returned to the utilities and are stored in Vitrified Waste Storage Center of JNFL. As of the end of March
2014, 1,442 vitrified canisters had been returned from the United Kingdom and France. Return shipmentof the 1,310 vitrified waste canisters from France started in 1995 and finished in 2007. Return shipmentof the vitrified waste canisters from the United Kingdom started in 2010, and about 770 vitrified waste
canisters will be returned in the next approximately five years. The Rokkasho Reprocessing Plant has
been storing 346 vitrified waste canisters which were generated in active test.
High level liquid waste generated at the Tokai Reprocessing Plant of JAEA was stored in tanks within
the facility and has been vitrified at the vitrification facility which started operation in January 1995. Asof March 2014, about 415 cubic meters of liquid waste and 247 vitrified waste canisters are in storage.
Vitrified waste is decided to undergo geological disposal based on the final disposal method.
B4-2

Low Level Radioactive Waste Management Practices

For the business of waste based on the Reactor Regulation Law, please see chapter H.

B5 Criteria used to define and categorize radioactive waste
Classification of radioactive waste based on the Reactor Regulation Law is described in chapter E.

10Scope of Application C
Section C Scope of Application
Article 3
1. This Convention shall apply to the safety of spent fuel management when the spent fuel results from theoperation 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 tobe part of spent fuel management.
2. This Convention shall also apply to the safety of radioactive waste management when the radioactive
waste results from civilian applications. However, this Convention shall not apply to waste that contains
only naturally occurring radioactive materials and that does not originate from the nuclear fuel cycle,
unless it constitutes a disused sealed source or it is declared as radioactive waste for the purposes of thisConvention 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 thisConvention by the Contracting Party. However, this Convention shall apply to the safety of management ofspent fuel and radioactive waste from military or defence programmes if and when such materials aretransferred 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, when the government acceded to the Convention. Therefore theGovernment of Japan includes the spent fuel stored in reprocessing facilities in the scope of theConvention.
The Government of Japan did not make declarations provided for in Article 3, Paragraph 2 and 3, of theConvention.

11

D Inventories and Lists
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 is being stored at spent fuel storage facilities within each nuclear power plant, the Tokai
Reprocessing Plant of the Tokai Research and Development Center, JAEA Nuclear Fuel Cycle
Engineering Laboratories, or the JNFL Rokkasho Reprocessing Plant and etc. Spent fuel is being
stored at spent fuel storage facilities of each research reactor. The main locations, main purposes andcharacteristics of these spent fuel management facilities are listed in the Annexes.
D2

Storage of spent fuelInventory and types of spent fuel stored in the above-mentioned spent fuel management facilities areshown in the Annexes.
D3

List of radioactive waste management facilities

Radioactive waste management facilities within nuclear power plants include the following: waste
treatment facilities; solid waste depositories where treated waste (homogeneous solidification,
fill-up solidification, other than those solids), are stored; depositories where the replaced steam
generators and other large solid wastes are stored; spent fuel pools where disused control rods anddisused channel boxes are stored; and tanks where the spent ion exchange resin is stored.
Radioactive waste management facilities within enrichment and fuel manufacturing plants include
the following: equipment to treat waste generated at the plants; and solid waste depositories where
12

Inventories and Lists D
treated waste is stored.
Radioactive waste management facilities within spent fuel reprocessing plants include: waste
treatment equipment; waste depositories where vitrified waste and high level liquid waste arestored; and waste depositories where low level liquid waste and low level solid waste are stored.
Radioactive waste management facilities licensed under the waste interim storage or disposal
business regulation include the following: radioactive waste disposal facilities; waste storage
facilities for materials held prior to disposal; and waste treatment facilities.
Radioactive waste management facilities within research reactors and major nuclear material
include the following facilities: waste treatment equipment for low-level radioactive waste
generated at the plants; and solid waste storage depositories for treated waste.
Major radioactive waste management facilities licensed under the Act concerning Prevention from
Radiation Hazards due to Radioisotopes, etc. include storage facilities for processed waste generated
at radioisotope usage facilities.
Radioactive waste management facilities licensed under the Medical Care Act include storage
facilities for processed radioactive medical waste generated from medical facilities.
The location, purpose and characteristics of such radioactive waste management facilities are listed
in the Annexes.
D4

Inventories of radioactive waste

D4-1 Inventory of Radioactive Waste Being Held in Storage
The waste stored in the above-mentioned nuclear power plant storage facilities include ca. 700,000,
200-liter drums , 32 used steam generators in steam generator storage facilities, used control rods,
disused channel boxes, spent ion exchange resin in spent fuel pools and other storage facilities, as ofthe end of March 2014. In addition rubble, trimmed trees, disused-protective clothing generated after
accident, etc.[total 201,300m3], and secondary waste from contaminated water treatment[848 cesium
absorption apparatus and absorption vessel etc. and Sludge 597m3] have been temporarily stored in
TEPCO’s Fukushima Daiichi NPS.
At facilities other than nuclear power plants, ca. 2,035 vitrified packages of HLW and ca. 415 m3 ofhigh level liquid waste are stored in spent fuel reprocessing facilities. Details of these inventories
included the other radioactive waste are indicated in Section L.
D4-2 Inventory of Radioactive Waste That Has Been Disposed ofSince 1992, LLW stored at radioactive waste management facilities operated by commercial powerreactors and that has a comparatively low concentration of radionuclides was transferred to a JNFL
radioactive waste facility for disposal. The amount of waste currently at the disposal facility is listed
in the Annexes.
13

D Inventories and Lists

The JNFL disposal facility is currently in operation and has disposed ca. 260,000 drums(200-liter-drum equivalent) of waste, as of the end of March 2014. At the JAEA Nuclear Science
Research Institute’s Tokai Research and Development Center, about 1,670 tons of very low level
waste (concrete) resulting from the dismantling of the JPDR have been disposed of.
D4-3 Inventory of Radioactive Waste Resulting from Past Practices
None is produced under The Reactor Regulation Act.
D5

List and status of nuclear facilities in the process of being decommissioned(1) Power reactors
As of the end of March 2014, nuclear power plants being decommissioned are JAPCO’s Tokai NPS,
the JAEA’s Fugen Advanced Thermal Reactor, and units 1 and 2 at the Chubu Electric Power
Company’s Hamaoka NPS.
A reactor at JAPCO’s Tokai NPS ceased operation in 1998. Decommissioning began in December
2001 with the dismantling of facilities and equipment such as the turbines, excluding the body of thereactor, and feed water pumps. The heat exchangers began to be dismantled in 2006. Dismantling of
the reactor vessel will begin in FY2020 and will take around six years. Decommissioning is
expected to be completed in FY2025.
The JAEA’s Fugen Nuclear Power Plant Advanced Thermal Reactor ceased operation at the end of
March 2003. The decommissioning application was filed in November 2006, approval was grantedin February 2008 and the facility became the Fugen Decommissioning Engineering Center. Spentfuel is being transferred to the Tokai Reprocessing Plant, which is part of the Nuclear Fuel Cycle
Engineering Laboratories at JAEA’s Tokai Research and Development Center. Decommissioning
will be completed by fiscal year 2033.
Units 1 and 2 at the Chubu Electric Power Company’s Hamaoka NPS ceased operation in January
2009. The decommissioning plan, setting out both the basic decommissioning policy for units 1 and
2 and the activities in the first stage (dismantling preparation phase), was approved in November
2009. During the initial dismantling preparation phase, shipping of spent fuel, survey andinvestigation of contamination, decontamination of systems and dismantling of systems andequipment outside the controlled area will be carried out. Decommissioning is expected to becompleted in FY2036.
TEPCO has decided to decommission units 1 to 4 at Fukushima Daiichi NPS, which were damagedby the March 2011 accident, and also units 5 and 6 at the same plant. These six units are in a state ofpermanent shutdown prior to receiving approval for the decommissioning plan prescribed in theReactor Regulation Act.
(2) Research reactors
14Inventories and Lists D
A total of 8 research reactors are in the process of being decommissioned: the JAEA’s JRR-2,
Reactor Facilities of the Nuclear Ship Mutsu, and Deuterium Criticality Assembly (DCA); Hitachi
Ltd.’s Hitachi Training Reactor (HTR); Toshiba Corporation’s Training Reactor-1 (TTR-1); the
Rikkyo University Institute for Atomic Energy (RUR); the Tokyo City University (formerly theMusashi Institute of Technology) Research Reactor (MITRR); and the University of Tokyo
Research Reactor (Yayoi).
D6

Usage facilities

Regarding facilities to which Article 41 of the Order for Enforcement of the Act on the Regulationof Nuclear Source Material, Nuclear Fuel Material and Reactors is not applicable, there are 197
facilities using nuclear fuel material and 18 facilities using nuclear source material.

15

E

Legislative and Regulatory System

Section E Legislative and Regulatory System
Article 18 Implementing Measures
Each Contracting Party shall take, within the framework of its national law, the legislative, regulatory
and administrative measures and other steps necessary for implementing its obligations under thisConvention.
Article 19 Legislative and Regulatory Framework
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)

a 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)

a 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.
Article 20 Regulatory Body
1. Each Contracting Party shall establish or designate a regulatory body entrusted with theimplementation of the legislative and regulatory framework referred to in Article 7, and provided
with adequate authority, competence and financial and human resources to fulfil 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 andin their regulation.

Overview
As well as carrying out regulatory duties to ensure the safety of spent fuel and radioactive waste inaccordance with the Act on the Regulation of Nuclear Source Material, Nuclear Fuel Material andReactors, the NRA regulates sealed sources that are no longer in use, in accordance with the Act
concerning Prevention from Radiation Hazards due to Radioisotopes, etc.. The NRA is a new16

Legislative and Regulatory System E
regulatory body established in September 2012 and the independence of its decision-making isguaranteed in law. Regulatory duties concerning spent fuel and radioactive waste that were previously
overseen by the Nuclear and Industrial Safety Agency (NISA) and the Ministry of Education, Culture,
Sports, Science and Technology (MEXT) have been integrated into the NRA. In March 2014, theJapan Nuclear Energy Safety Organization (JNES), a technical support organization, was also merged
into the NRA.

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Legislative and Regulatory System

E1 Legislation in Japan
In Japan’s legal system relating to nuclear regulation, the Atomic Energy Basic Act is the mostimportant piece of legislation and defines the basic principles of nuclear energy use. The Act on theRegulation of Nuclear Source Material, Nuclear Fuel Material and Reactors, which prescribes
government regulations, and the Act for Establishment of the Nuclear Regulation Authority, whichprescribes the competence of the regulatory authority, were enacted under this Act. Also, 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 and transparent manner. Meanwhile,
the Final Disposal Act is applicable to taking necessary steps to systematically and securely carryout the final disposal of radioactive waste to be geologically disposed, such as vitrified waste of
HLW generated from reprocessing of spent fuel. Other necessary legislation has been put in placesuch as the Act on Special Measures Concerning Nuclear Emergency Preparedness which stipulates
responses to nuclear disasters.
These laws were amended on September 19, 2012, in response to the accident at TEPCO’s
Fukushima Daiichi NPS. The NRA subsequently compiled an NRA Ordinance, detailing standards
for implementing nuclear regulations. The Act on the Regulation of Nuclear Source Material,
Nuclear Fuel Material and Reactors prescribes such procedures as the permits, approvals, andinspections required for reactor construction and operation. It expressly grants the NRA authority
to revoke permits and suspend the operation of facilities, and impose penalties for violations of its
provisions.
(1) The Atomic Energy Basic Act
The 1955 Atomic Energy Basic Act forms the basis of nuclear energy use in Japan. The objective of
the Act is to secure future nuclear energy resources use and promoting academic and industrial
development, thereby contributing to the welfare of mankind and the enhancement of life. The Act
specifically limits the research, development and utilization of nuclear energy to peaceful purposes,
prioritizes safety, ensures that operations are performed independently under democratic
management, and that relevant information shall be made public to contribute to international
cooperation.
Moreover, the Act stipulates that the Atomic Energy Commission of Japan shall be established toensure the democratic implementation of nuclear energy policy. Construction of reactors and the useof nuclear fuel materials will be governed by official regulations contained in the Act on theRegulation of Nuclear Source Material, Nuclear Fuel Material and Reactors.
The September 2012 revision carried out in response to the accident at TEPCO’s Fukushima Daiichi
NPS, included new provisions concerning the establishment of the NRA and the Nuclear Emergency
Preparedness Commission. A provision concerning the establishment of the Nuclear Safety
18Legislative and Regulatory System E
Commission of Japan, which was abolished upon the establishment of the NRA, was deleted.
(2) The Act on the Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactors(Reactor Regulation Act)The 1957 Reactor Regulation Act governs all aspects of nuclear energy use in Japan.
Based on the Atomic Energy Basic Act, this Act limits the use of nuclear source material, nuclear
fuel material, and reactors to peaceful purposes only. The Act seeks to prevent the release ofradioactive material at abnormally high levels outside a plant or site, or any other disaster caused by
nuclear materials or nuclear reactors. To ensure public safety, it seeks to protect nuclear materials by
stipulating requisite regulations of the refining, processing, storage, reprocessing and disposal
business and to address large scale natural disasters, terrorism or other criminal acts. It stipulates theregulation of International Controlled Material and the implementation of international conventions
or other international commitments on nuclear use, research and development.
Regulations involving spent fuel interim storage and radioactive waste management prescribed in
the Reactor Regulation Act establish procedures and standards for granting permits and approval,
including operating permits, Approvals for Design and Construction Methods, Pre-service
Inspections, Periodic Facility Inspections, Approvals for Operational Safety Programs, Operational
Safety Inspections and decommissioning. The Act prescribes administrative penalties such assuspension of operations, revocation of permits and criminal penalties such as imprisonment or afine should an operator fail to comply with the provisions of this Act. And radioactive waste
management has three categories of the burial of Category 1 Waste Disposal, the burial of Category
2 Waste Disposal and Waste Interim Storage/treatment under the Reactor Regulation Act(Figure
E1-1, Figure E1-2).
Furthermore, it establishes a system whereby employees and others working for nuclear operators,
can report any violation of the Reactor Regulation Act to the NRA. It stipulates that those reporting
violations via this system do not suffer any punishment.
The Reactor Regulation Act stipulates that it can be only partially applied when appropriate safetymeasures have been taken to ensure operational safety activities. Accordingly, the OrdinanceConcerning the Operational Safety of Reactor Facilities at the Tokyo Electric Power Company’s
Fukushima Daiichi Nuclear Power Station and the Protection of Specified Nuclear Fuel Material has
been enacted. This prescribes the steps to be taken to ensure safety at the Fukushima Daiichi NPS,
where the situation differs from that at other reactor facilities.

19

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Legislative and Regulatory System

FigE1-1 Radioactive Waste Management prescribed in the Reactor Regulation Act

Radioactive Waste Management prescribed in the Reactor Regulation Act
Radioactive Waste Management
Category

The burial of Category 1
Waste Disposal

The burial of Category 2
Waste Disposal

Waste Interim Storage/treatment

Intermediate Depth
Name
Pit Disposal
Trench Disposal
Storage
NA※１
Disposal
Final disposal by a method on Final disposal by a method on Final disposal by a method on Final disposal by a method on Storage of radioactive solid
the burial of radioactive waste the burial of radioactive waste the burial of radioactive waste the burial of radioactive waste waste until final disposal is※4
in the excess of criteria
at a depth of 50 m and ※５ above ground or less than ※５ above ground or less than performed.
defined by Order※２ as they up from ground, and not
50m from ground, and not
50m from ground, and nothave potential significant risks exceeding criteria defined by exceeding criterea difined by exceeding criterea difined by※３※２
to human health.
the rule (limited to methods the rule※３ (excluding for
Order .
either to fix radioactive waste methods either to fix
at waste disposal site with the radioactive waste at waste
engineered barrier struture or disposal site with theContents
fix integrally radioactive waste engineered barrier struture orat waste disposal site without fix integrally radioactive waste
the engineered barrier site)
at waste disposal site without
the engineered barrier site)

Treatment
Processing radioactive liquid
waste or radioactive solid
waste to quality suitable forfinal disposal.

※1： The name of "geological disposal" is not based on the Reactor Regulation Act, but often used in order to distinguish other waste disposal※2： The Order for Enforcement of the Act on the Regulation of Nuclear Sorce Material, Nuclear Fuel Material and Reactors※3： The Rule on Category 2 Waste Disposal of Nuclear Fuel Material and Materials Contaminated with Nuclear Fuel Material※4： Radioactive waste from fuel facility (limited to a facility solely conducting the fabrication of fuel assemblies that contain mixed uranium and plutonium oxide), research and test reactor facility,
power reactor facility or reprocessing facility※5： Radioactive waste from research and test reactor facility or power reactor facility.

Fig E1-2 Methods on the burial of radioactive waste for final disposal

20Legislative and Regulatory System E(3) Final Disposal Act

The Final Disposal Act enacted in May 2000 provides for the following basic framework forsystematically and securely carrying out the final disposal of high level radioactive wastes generated
from spent fuel reprocessing (hereinafter referred to as “Designated Radioactive Wastes”);(i)development and public announcement of a basic policy and a plan (final disposal plan) for
the final disposal of designated radioactive wastes by the Minister of METI(ii) process for site selection for final disposal of designated radioactive wastes(iii) securing of the expenses required for final disposal of designated radioactive wastes(iv) implementing organization for final disposal of designated radioactive wastes.
The amendment of the Act in June 2007 newly added TRU wastes to be the subjects of geologicaldisposal.
The Minister of METI establishes the basic policy and based on this, provides for the final disposal
plan. NUMO, which was established as an implementing organization based on the final disposal
plan, carries out final disposal activities. Utilities shall pay deposits to the fund reserved for disposal,
which is managed by RWMC designated by the Minister of METI. NUMO promotes site selection
by a three-step procedure, that is, selection of the preliminary investigation area, detailed
investigation area and the construction site for final disposal facility; NUMO obtains approval of the
Minister of METI at each step. The three-step procedure for site selection is clearly defined.
(4) Act for Deposit and Administration of Reserve Funds for Reprocessing of Spent Fuel from Nuclear
Power Generation

This law provides for the framework of deposit etc., to reserve funds for reprocessing of spent fueletc., from nuclear power generation. The fund is managed by an organization 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 the amount of electricity generated by nuclear
fuel, and utilities deposit the amount in the Fund Management Organization. This law was enacted in
October 2005.
(5) The Act concerning Prevention from Radiation Hazards due to Radioisotopes, etc. (Radiation
Hazards Prevention Act)The aim of the Radiation Hazards Prevention Act is as follows: “Based on the objectives of theAtomic Energy Basic Act, this Act seeks to prevent radiation hazards and ensure public safety by
regulating the use, dealer, lessor, storage, disposal, and other handling of radioisotopes, the use ofradiation generators, contaminated items and radioactivated items.” The Order for Enforcement of
the Radiation Hazards Prevention Act and the ordinance for enforcement thereof have been enacted
under the Radiation Hazards Prevention Act. Permitted user involved in the use, storage or disposalof radioisotopes must undergo a facility inspection before use and further periodic inspections if
they have larger than prescribed storage facilities or if they have a radiation generator. Before
21

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Legislative and Regulatory System
handling radioisotopes they must prepare rules to prevent radiation hazards, appoint a radiation
protection supervisor, and provide notification thereof. They shall comply with legal standards
governing the use of facilities, measure doses within and at the boundary of their establishment aswell as measuring the exposure dose of radiation workers, conduct education and training, andprovide health examinations. When disposing of radioisotopes from an establishment handlingradioisotopes or of items contaminated by such isotopes, users shall ensure that storage within theestablishment in question or at the business establishment of a storage and disposal contractor
complies with legal standards.
If necessary, NRA radiation inspectors conduct on-site inspections to check legal compliancestandards. Users must notify the NRA when they cease to use radioisotopes or radiation generatorsand report any necessary subsequent measures., The basic framework for regulating the disposal ofradioactive waste via burial by disposal contractors was put into place by the June 2004 revision of
the Radiation Hazards Prevention Act and further revisions of the order for enforcement andordinance for enforcement of this Act. Currently, public notices concerning the dose standards for
disposal sites and other technical details to facilitate disposal via burial are being put into place.
Following the May 2010 revision of the Radiation Hazards Prevention Act, regulations were put
into place covering the handling of items contaminated by radioisotopes but with a low radioactivity
concentration. The revision established regulations covering the handling of contaminated items
from radiation generators and strengthened measures to be taken when ceasing to use radioisotopes.

(6) The Act on Technical Standards for Prevention of Radiation Hazards
The objective of the Act on Technical Standards for Prevention of Radiation Hazards is to clarify thebasic concepts for making technical standards at the standpoint of prevention radiation hazards, toestablish the Radiation Council under the NRA so that technical standards can be reviewed withconsistency in the Council.
(7) The Act on Special Measures Concerning Nuclear Emergency Preparedness (Nuclear Emergency
Act)
In light of the specific nature of nuclear disasters, the 1999 Nuclear Emergency Act, together with
the Reactor Regulation Act, the Basic Act on Disaster Control Measures and other laws, wasdesigned to prevent nuclear disasters and protect the lives, health, and property of the general public.
This Act prescribed the responsibilities of nuclear operators in preventing nuclear disasters, the issue
of a Declaration of a Nuclear Emergency, the establishment of a Nuclear Emergency Response
Headquarters and the implementation of emergency response and other special measures. Under thislaw, nuclear operators shall take all possible steps to prevent a nuclear disaster, avoid any escalation
should such an event take place and then help to control and restore the situation to normalcy. It
stipulates that the government take requisite emergency response measures, prevention andpost-accident steps in such a disaster.
22

Legislative and Regulatory System E
Following the TEPCO’s Fukushima Daiichi NPS accident, the Nuclear Emergency Act wasamended on September 19, 2012, including the enhancement of measures to prevent nuclear
emergency, and the strengthening of the of the Nuclear Emergency Response Headquarters andother bodies.
（8）Medical Care Act
The management of radioisotope waste generated from radiopharmaceuti is conducted only by
waste management facility operators designated by the Minister of MHLW on the basis of theMedical Care Act etc. Location, structures, and equipment of the waste management facility shall becomplied with related technical criteria (standards) in order to be designated by the Minister of
MHLW. They are conducted in accordance with these laws equivalent to the Radiation Hazards
Prevention Act.
E2 Regulatory body(1) The NRA’s organization, authority, and responsibilities
The NRA regulates nuclear application in Japan, while the NRA Secretariat deals with related
administrative matters. The NRA was established as an external bureau of the Ministry of theEnvironment. The Chairman and Commissioners of the NRA are appointed by the Prime Minister,with the consent of the Diet, in accordance with the provisions of the Act for Establishment of the
Nuclear Regulation Authority, which aims for an independent, fair and neutral exercise of authority.
The NRA provides the Diet with an annual report via the Prime Minister, of its activities. The
appointment and dismissal of the NRA Secretariat personnel is at the discretion of the NRA
Chairman. The NRA can establish rules in order to implement laws and cabinet orders under its
jurisdiction. The term of office of the Chairman and Commissioners is five years, withreappointment possible. The duty of the NRA is to ensure the safe use of nuclear energy, so it has
the right to grant permission for the establishment of reactor facilities.
The NRA can formulate rules governing nuclear regulations, including measures to ensure
operational safety and the protection of specified nuclear fuel material, safety regulations, andemergency measures. The NRA approves the design and construction of facilities, inspections,approval of Operational Safety Programs and decommissioning plans. In addition, it collects
licensee reports of nuclear facilities and conducts on-site inspections, if necessary.
It has the authority to revoke permits for nuclear facilities or suspend their operations, to order
additional safety measures, the dismissal of reactor chief engineers, decommissioning measures andother steps to prevent disasters.
The NRA has under its auspices the Reactor Safety Examination Committee, which investigates thesafety of nuclear reactors, the Nuclear Fuel Safety Examination Committee, which investigates thesafety of nuclear fuel material, and the Radiation Council, which examines the technical standards
for the prevention of radiation damage.
23

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Legislative and Regulatory System
The NRA consists of the following departments: the Policy Planning and Coordination Division,
which carries out general coordination within the Secretariat, as well as policy evaluation and Public
Relations; the International Affairs Division, which liaises with international organizations and othercountries; the Regulatory Standard and Research Division, which formulates standards andguidelines; four Divisions of Research (Reactor System Safety; Severe Accident; Nuclear Fuel
Cycle and Radioactive Waste; and Earthquake and Tsunami), which conduct researches concerning
nuclear safety technology; the Emergency Preparedness and Response Policies Division,
responsible for developing emergency preparedness systems, providing an initial response in theevent of an emergency, and physical protection of nuclear material; the Radiation Monitoring
Division, which compiles summaries of nation-wide radiation monitoring; the Radiation Protectionand Safeguards Division, which implements regulations on the use of radioisotopes and safeguards
based on international commitments; the Nuclear Regulation Policy Planning Division, which puts
into place systems for regulatory examination and inspections; and seven Divisions of Regulation(BWRs; PWRs and Inspections of Nuclear Reactor Facilities; Advanced Reactors, Research
Reactors, Decommissioning; Nuclear Fuel (Fabrication and Reprocessing) Facilities and Use of
Nuclear Material; Radioactive Waste, Storage and Transport; and Earthquake and Tsunami), which
deal with the practical aspects of regulation based on the Reactor Regulation Act (Figure E2-1).
There are Nuclear Regulation Offices at 22 sites, with Operational Safety Inspectors and Nuclear
Emergency Preparedness Officers permanently stationed at those offices.
In March 2014, the NRA merged with the Japan Nuclear Energy Safety Organization (JNES), to
help increase its own expertise and strengthen its operating capabilities. Accordingly, at the end of
March 2014, the NRA Secretariat had approximately 1,000 personnel, including the Operational
Safety Inspectors and Nuclear Emergency Preparedness Officers stationed at nuclear sites.

(2) Ensuring NRA independence
The NRA’s role is to conduct independent, neutral and fair nuclear regulation while ensuring a clear
separation of nuclear promotion and regulation. The Chairman and Commissioners of the NRA are
appointed by the Prime Minister with the consent of the Diet, and the Chairman appoints the NRA
Secretariat staff. Therefore, government authorities tasked with promoting nuclear use have nointeraction in the appointment or dismissal of staff.
The NRA’s budgetary requirements are submitted to the Ministry of Finance and are funded fromthe national budget after being reviewed by the appropriate financial authorities and are deteriminedbased on the overall national financial situation. There is no financial involvement by otherauthorities tasked with promoting nuclear use.
The NRA has clear a clear mandate. It engages in independent regulatory decision-making
stipulated in the Reactor Regulation Act in such areas as permits, approvals, and inspections. Thereis no interaction with other nuclear promoting authorities.

24Legislative and Regulatory System E(3) Ministry of Health, Labour and Welfare (MHLW)MHLW administer the safety regulations for radiopharmaceuticals, the regulations for the medical
radiation, and the regulations for the structure and equipment of laboratories where radioisotopes areused for clinical in vitro examinations.
The Pharmaceutical and Food Safety Bureau (PFSB) regulates the production ofradiopharmaceuticals based on the Regulations for Structures and Equipment’s for Pharmacies, etc.
and the Regulations for Manufacturing and Handling of Radio Pharmaceuticals under the
Pharmaceutical Affairs Act. The Independent Administrative Agency, Pharmaceuticals and Medical
Devices Agency, conducts periodic inspections of manufacturing plants that produce
radiopharmaceuticals. And, PFSB also regulates storage and disposal ofradiopharmaceutical-related-products. The Health Policy Bureau regulates structures andequipment’s of hospitals and clinics where medical X-ray and/or radiopharmaceuticals are used,based on the Ordinance for Enforcement of the Medical Care Act. This ordinance also provides
standards for the facilities of storage and disposal, etc. of radioisotopes which are used for clinicalpurposes.
Structures and equipment’s of and laboratories where radioisotopes are used for clinical in vitro
examinations are regulated by the Ordinance for Enforcement of the Clinical Laboratory Technicians,
etc.Act, “Standards for Structures and Equipments of Clinical Laboratory equipped with
Radioisotope for Specimen Inspection, Provided by Clinical Laboratory Technicians, etc.Act
Enforcement Regulations Article 12, Paragraph 1. 5” (MHLW, Notification No.16, March 2, 1981).
The ordinance, etc. indicates the standard for the storage or disposal of radioisotopes for laboratory
test.

25

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Legislative and Regulatory System

Fig. E2-1 NRA Organization Chart

26

Other General Safety Provisions F
Section F Other General Safety Provisions
F1

Responsibility of the license holder

Article 21
1. Each Contracting Party shall ensure that prime responsibility for the safety of spent fuel or radioactive
waste management rests with the holder of the relevant license and shall take the appropriate steps toensure that each such license holder meets its responsibility.
2. If there is no such license holder or other responsible party, the responsibility rests with the Contracting
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 Atomic Energy Basic Act establishes the most basic guidelines concerning the use of nuclear
energy in Japan. This Act stipulates that “The research, development and utilization of nuclear energy
shall be limited to peaceful purposes, aimed at ensuring safety and performed independently underdemocratic management. The results therefrom shall be made public to contribute to international
cooperation.” Based on this provision, licensees bear the primary responsibility to ensure the safe andpeaceful use of nuclear energy.
Furthermore, the Atomic Energy Basic Act stipulates compliance with the regulations concerning
nuclear fuel imposed by the government. In other words, licensees bear a responsibility to comply
with regulations imposed by the government. Most of these regulations are set forth in the Reactor
Regulation Act and the Act concerning Prevention from Radiation Hazards due to Radioisotopes, etc.
(Radiation Hazards Prevention Act).
The Reactor Regulation Act explicitly states the legal responsibilities of licensees, stipulating thatthey “shall be responsible for installing equipment or apparatus contributing to the improvement of
the safety of nuclear facilities, enhancing education on operational safety, or taking any othernecessary measures for preventing disasters resulting from nuclear source material, nuclear fuelmaterial, and reactors, while taking into account the latest knowledge on safety at nuclear facilities.”
The regulations based on the Reactor Regulation Act prescribe the measures that licensees shall taketo ensure operational safety, specifically measures concerning the operation andmaintenance offacilities, and measures relating to transport, storage, and disposal. These measures are detailed in the
NRA Ordinance pursuant to the Reactor Regulation Act.
In addition to establishing Operational Safety Programs and obtaining NRA approval, licensees shallalso undergo NRA compliance inspections.
Licensees must stipulate in their Operational Safety Programs that they shall disclose noncomplianceinformation in the event that such noncompliance results in the non-fulfillment of basic operationaltargets. Measures have been put in place to ensure that licensees do not conceal noncompliance.
Licensees are subject to penalties in the event of failure to meet their statutory responsibilities; thiscan be cited as an institutional mechanism for ensuring that licensees fulfill their responsibilities.
27

F

Other General Safety Provisions

For example, in the event that a nuclear power reactor facility does not meet the technical standards
prescribed in law or that its operation contravenes regulatory requirements, the NRA may require thelicensee to adopt an operation method of the NRA’s designation or order it to take any other measuresdeemed necessary, pursuant to the provisions of the Act. If the licensee of reactor operations violates
this order, the NRA may revoke its permission or order it to suspend operation of the facility for a
specified period not exceeding one year. In the event that an operator establishes a nuclear reactor
without permission, it shall be sentenced to imprisonment with labor and/or a fine, pursuant to theprovisions of the Act. The same shall apply if the licensee fails to obtain approval for its Operational
Safety Programs or amends them without approval, or if a licensee and/or its employee(s) fails tocomply with those Operational Safety Programs.
F1-2 Steps in the event that there is no licensee or other responsible party:1
In the event of revocation of a license, if there is no successor to the operator through merger orinheritance stipulated by the Act, the current license holder shall continue to be regarded as thelicense holder and responsible for “record keeping,” “protective measures,” “Operational Safety
Program,” and “physical protection” as prescribed in the Reactor Regulation Act, and shall be subject
to regulation. In the event of the dissolution of the business of the license holder, if there is no
succession to the status of the operator through merger or inheritance stipulated by the Reactor
Regulation Act, the liquidator or bankruptcy administrator shall be regarded as the license holder andresponsible for “record keeping,” “protective measures,” “Operational Safety Program,” and“physical protection” as prescribed in the Reactor Regulation Act, and shall be subject to regulation.
In addition, the above-mentioned persons shall develop a decommissioning plan, have it approved by
the NRA, carry out decommissioning, and obtain confirmation of the completion of
decommissioning from the NRA.
The Radiation Hazards Prevention Act provides for situations in which the storage and disposal
contractor licensed under said Act has been dissolved. In the event of succession of the business inthis situation, the Act prescribes that once approval has been granted for the merger, the surviving
corporation shall succeed to the status of the operator. If there is no succession of the business, theliquidator shall take appropriate measures for decommissioning, such as removal of contamination
by radioisotopes.
As described above, provisions are in place to ensure that business succession does not create asituation in which no licensee exists and that the business in question is abolished if there is nobusiness succession.

1

Disposal contractors designated under the Medical Care Act that handle medical radiation sources may not be abolished or
dissolved until the steps required for abolishing the disposal business have been completed in accordance with said Act.

28

Other General Safety Provisions F

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 aspent fuel and a radioactive waste management facility;(ii) Adequate financial resources are available to support the safety of facilities for spent fuel andradioactive waste management during their operating lifetime and for decommissioning;(iii) Financial provision is made which will enable the appropriate institutional controls and monitoringarrangements to be continued for the period deemed necessary following the closure of a disposal
facility.

Based on the Reactor Regulation Act, the regulatory body confirms operator’s technical competence
including adequacy of human resources for installing and operating the facility appropriately in thereview process of the license application. The applicant has to verify that it has sufficient technicalcompetence to carry out its activity.
As a prerequisite for carrying out activities, the Reactor Regulation Act requires licensees to appoint
the following chief engineers from among their qualified employees, to supervise the safety ofoperation: a Chief Reactor Engineer for reactor operation, a Chief Engineer for Nuclear Fuel Material
Handling for fabrication or reprocessing, a Chief Engineer for Spent Fuel Handling in the spent fuelstorage facility, and a Chief Engineer for Radioactive Waste Handling for handling nuclear fuelmaterials and other radioactive waste in the disposal facility.
Furthermore, regarding education and training, the Reactor Regulation Act requires operators to
stipulate in the Operational Safety Program their policy on implementing operational safety education,
including the plan for its implementation, as well as the content of such education. The regulatory
body confirms compliance with these requirements through its Operational Safety Inspection.
Moreover, an operator of a business licensed under the Radiation Hazards Prevention Act is required
to select and appoint a qualified person as Chief Engineer for Radiation Protection to supervise thesafety management in the handling of radioisotopes before commencing business. The operator is also
required to specify in the “Rules for Preventing Radiation Hazards” matters related to the duties andorganization of persons engaged in safety management and handling of radioisotopes, as well as
matters related to the education and training required to prevent radiation hazards.

29

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Other General Safety Provisions

F2-1 Activities to secure human resource infrastructure(1) Human resource development by the Secretariat of the NRA:
Nuclear regulation is an administrative field requiring highly professional and technical judgments,
so it is imperative to recruit a sufficient number of highly trained professional

personnel andcontinuously enhance their expertise.
To this end, the NRA has established and systematically implemented staff training programs toenhance the expertise of its existing staff. More specifically, it conducted (1) specialist training for
its Operational Safety Inspectors and Nuclear Emergency Preparedness Officers who are required tohold legal qualifications concerning nuclear regulations, including revisions to the Reactor
Regulation Act; and (2) practical training in inspections using mock-up facilities. In addition, tomaintain and improve their knowledge of nuclear engineering, it conducted training using
postgraduate-level textbooks. To raise awareness among all staff members, the NRA held staff
lectures on matters such as quality control and the country’s approach to crisis management.
The NRA dispatched three staff members to relevant graduate schools within Japan and also
dispatched staff to overseas nuclear regulators, such as the Nuclear Regulatory Commission in theUSA, the IAEA and other international organizations.
Between its establishment and May 7, 2014, the NRA hired 35 staff members with expert
knowledge and experience, and 33 new graduates. In addition, it embarked on other initiatives
aimed at securing additional personnel, including continuing to recruit staff with practicalexperience and seeking to diversify the methods used to hire new graduates.
On March 1, 2014, the NRA merged JNES – an organization providing the NRA with technicalsupport – into the Secretariat of the NRA. It took this opportunity to fundamentally strengthen its
human resource development functions with a view to increasing the expertise of NRA staff, by
establishing an affiliated institution in the form of the NRA Human Resource Development Center.
Furthermore, the NRA has steadily implemented human resource development by systematizing
training programs, promoting knowledge management and technical tradition based on medium tolong-term policy under the fundamental Human Resource Development of NRA approved in 25th
June, 2012.
(2) Measures to secure personnel for operation:
In granting the permits for businesses prescribed in the Reactor Regulation Act, the NRA checks thatan applicant possesses the technical ability necessary to conduct said business. In the case oflicensees of power reactor operations, licensees of fabricating or enrichment activity, and licensees ofspent fuel reprocessing, the NRA checks that they have the technical capability to prevent theoccurrence and escalation of severe accidents.
The Reactor Regulation Act stipulates that licensees must take the necessary steps to ensure
operational safety, that they must set forth Operational Safety Programs before commencing theoperation of a facility, and that they must obtain the approval of the NRA for these.
30

Other General Safety Provisions F
In terms of the steps that should be taken to ensure operational safety, there are regulatory
requirements concerning the deployment of appropriate staff and the certification of technicians. For
example, the Rules on Commercial Reactors stipulate that only those with the requisite knowledge
shall operate a power reactor; that power reactors shall only be operated when the staff required forreactor operations are present; and that those with responsibility for reactor operation shall have thenecessary knowledge, skills, and experience, conform to the criteria set out by the NRA, and undergo
checks by the NRA, focused on the method used to determine whether or not they conform to thecriteria in question. Moreover, they stipulate the checks to be carried out before the reactor isstarted-up, the checks required for reactor operation and the checks to be conducted after reactor
shut-down, and require the operator to comply with these.
The Operational Safety Programs – for example, in the Rules on Commercial Reactors – prescribe
matters relating to operational safety education for those who operate and manage reactor
facilities.They stipulate what should be set out in the Operational Safety Programs, including thecontent of operational safety education and the policy on its implementation. Moreover, the quality
assurance plans in the Operational Safety Programs are required to contain human resource
provisions. These stipulate that the competences required for personnel involved in duties that affectnuclear safety shall be identified, with education, training, or other measures to be implemented in
the event of any shortfall in competences, and that the effectiveness of education and training shall be
evaluated.
Regarding Operational Safety Inspections, in the case of the Rules on Commercial Reactors forexample, the NRA conducts inspections four times a year, focusing on the status of compliance with
the Operational Safety Programs when engaged in acts of particular importance in ensuring safety. It
also conducts checks to ensure that competence management and education and training are carriedout appropriately.
As a prerequisite for carrying out activities, licensees must appoint staff with the relevant
qualifications to chief engineer posts. Licensees of power reactor operation must appoint a Chief
Reactor Engineer to supervise operational safety in reactor operation; licensees of fabricating or
enrichment and licensees of reprocessing shall appoint a Chief Engineer for Nuclear Fuel Material
Handling to supervise operational safety in the handling of nuclear fuel materials; licensees ofstorage activity must appoint a Chief Engineer for Spent Fuel Handling to supervise operationalsafety in the handling of spent fuel; and licensees of waste disposal activity shall appoint a Chief
Engineer for Radioactive Waste Handling to supervise operational safety in the handling of nuclear
fuel materials and other radioactive waste in disposal operations.
When implementing decommissioning, licensees of reactor operation must formulate Operational
Safety Programs that are tailored to decommissioning and obtain the approval of the NRA. The
provisions relating to human resources in these Operational Safety Programs employ the same system
as those in the Operational Safety Programs for reactor operation, such as the requirement to stipulatematters relating to safety education for those carrying out decommissioning, and prescribing
31

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competence management and similar matters in the quality assurance plan as well.
F2-2 Financial Resources
In the process of Permission for Establishment License of a nuclear facility except for nuclear fuelmaterial use facility in accordance with the Reactor Regulation Act, the NRA confirms that theapplicant possesses the necessary financial basis. As a prerequisite for application, the applicant has
to submit a business plan that explains the financial base of the business and has to certify that it
possesses said necessary financial basis.

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Other General Safety Provisions F

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 established andimplemented.

F3-1 Regulatory Requirements on QA of Nuclear facilities:
Under the Reactor Regulation Act, one of the criteria for obtaining approval of construction plans
for a nuclear facility is that the licensee’s quality control methods and inspection systems comply
with technical standards prescribed in the NRA Ordinance.
More specifically, this ordinance requires that a quality control supervision system incorporating
mechanisms for activities to foster a safety culture be established for the design and construction of
nuclear facilities; that the responsibility of management executives be clearly stated; and thatmanagement of human and other resources, planning and implementation of specific duties,
measurement, analysis, and continuous improvement be carried out.
Moreover, in terms of operational safety activities at nuclear facilities, licensees are required toestablish a quality assurance plan in their operational safety programs, and must make continuous
improvements to this plan, as well as planning, implementing, evaluating, and improving
operational safety activities in accordance with the plan.
For example, in the Rules on Commercial Reactors, systems for implementing quality assurance
must be operated by the senior management of licensees; have clearly identified responsibilities,
authority, and duties in relation to quality assurance; and feature mechanisms for the formulation,
implementation, evaluation, and continuous improvement of quality assurance plans.
Plans for operational safety activities are required to establish appropriate management methods inthe event of external procurement of goods or services, procedures for the appropriate managementof documents and records concerning operational safety activities, and systems for education andtraining for those involved in operational safety activities.
It is necessary to clarify individual goals and requirements during operational safety activities, andto check at appropriate times that these are being carried out in accordance with the implementation
plan. To check this, licensees of reactor operation shall conduct the requisite inspections and tests,
and establish an effective system to deal with any cases of noncompliance.
To evaluate operational safety activities, licensees must systematically conduct required monitoringand measuring of the current state of safety activities. Systematic auditing should be carried out tosecure the implementation of appropriate safety activities and such auditing should be carried out by
persons not directly involved in the items under review.
Licensees should establish procedures for ensuring the continuous improvement of operationalsafety activities and instituting preventive measures to avoid noncompliance situations that could
occur or, should one occur, for introducing remedial measures to prevent a recurrence. Preventive
33

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knowledge gained both from operational safety activities at their own power reactor facilities andfrom other facilities should be evaluated and, where appropriate, incorporated by licensees into theirown operations.

F3-2 Initiatives by licensees:
Based on the private-sector quality assurance standard for ensuring safety at nuclear power stations(JEAC 4111-2009) and the Rule on Technical Standards for Quality Control Methods Concerning
Design and Construction and for Inspection Organizations, which prescribes the regulatory
requirements at the design and construction stage for each type of nuclear facility, licensees
establish quality control supervision systems and conduct quality assurance activities, as well as
ensuring that the effectiveness of these is maintained to meet the regulatory requirements mentioned
above. NISA, which was the regulatory authority at the time that it was issued, approved JEAC
4111-2009 as being technically appropriate to serve as a standard for specifications meeting theregulatory requirements for performance standards for all nuclear facilities other than research
reactors and usage facilities. JEAC 4111-2009 reflects not only the results of the review of IAEA
Safety Standards Series No. GS-R-3, “The Management System for Facilities and Activities”, which
was issued in August 2006, but also points of reference from Safety Guide No. GS-G-3.1
Application of the Management System for Facilities and Activities. These technical standards andregulations also establish specific requirements for a quality management system, including“responsibility of top executives,” “operational management of resources,” “planning andimplementation of duties,” and “evaluation and improvement.”
The human resource requirements stipulate that staff involved in duties that affect nuclear safety
must be competent in terms of education, training, skills, and experience.
Licensees must identify the competences required and, if necessary, provide education andtraining to ensure personnel reach the necessary standard.
Licensees should conduct procurement procedures having clearly identified the requirements for
products approval procedures, processes, and equipment; personnel competence checks; and quality
management supervision systems. Moreover, the standard stipulates that procured items must be
inspected on the premises of the supplier, if necessary, to ensure that they meet set standards.
Concerning the operation of nuclear facilities, quality assurance programs are audited. To guarantee
its impartiality, an audit should be conducted by a department or external auditor capable ofproviding an objective appraisal. The auditing department should be directly under the responsible
executive officer in the company’s organizational structure, so that the officer in question can bequickly informed of any situation needing remedial action or improvement. In procurement
management, it is common for licensees to conduct audits of suppliers directly, to ensure that the
suppliers satisfy the specification sheet requirements.
In the case of products, the specification sheet detailing the requirements is given to the supplier at
the time of ordering, and the product is checked when it is delivered in order to ensure that it meets34

Other General Safety Provisions F
the requirements. If checks are required during the product manufacturing process, licensees candirectly check that process. In the case of services, the specification sheet is given to the service
provider in advance, to ensure that a person with the requisite skills is recruited. These include
checking to confirm that the provider has technicians with the required specific skills, e.g. welding.
On the issue of outsourcing, the provider must submit to the licensee a quality assurance plan, which
the licensee checks to ensure that it meets all requirements.
This prevents sub-standard outsourcing to providers with inappropriate quality assurance systems.
This provides licensees with the confidence that quality assurance systems constitute one of the
major elements for maintaining their own quality assurance systems. Accordingly, mechanisms toenable licensees themselves to conduct audits of providers and suppliers are being developed.

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F4

Operational radiation protection

Article 24
1. Each Contracting Party shall take the appropriate steps to ensure that during the operating lifetime of aspent 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 asreasonably 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 onradiation protection; and(iii) measures are taken to prevent unplanned and uncontrolled releases of radioactive materials into theenvironment.
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 nationalprescriptions for dose limitation which have due regard to internationally endorsed standards onradiation 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 releaseand mitigate its effects.

F4-1 Regulations on Radiation Protection:
Measures for radiation protection in a nuclear facility are outlined in laws such as the Reactor
Regulation Act and its secondary legislation.
Radiation protection standards comply with the recommendations of the International Commission
on Radiological Protection (ICRP) and have been incorporated into legislation. The Radiation
Council ensures consistency between relevant pieces of radiation hazards legislation.
The NRA Ordinance prescribes the legislative requirements of radiation protection. These include
measures controlling the exposure of radiation workers, and the monitoring of radioactive material
released as part of the management of gaseous or liquid waste.
Moreover, the NRA Ordinance stipulates that in the event of certain problems, licensees shallimmediately report to the NRA and submit within ten days a situation report and details of measurestaken. These include incidents when gaseous radioactive waste is released through disposal facilities
and lead to concentration limits in the air outside the Surrounding Monitored Area being breached,or when liquid radioactive waste is released through drainage facilities and the concentration limits
in water outside the boundary of the Surrounding Monitored Area are breached.
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Other General Safety Provisions F
The Notification to Establish Dose Limits in Accordance with the Provisions of the NRA Ordinance(Notification on Doses) prescribes in quantitative terms the dose limits and radioactive material
concentration limits within Radiation Controlled Areas, dose limits and radioactive material
concentration limits outside the Surrounding Monitored Area, dose limits for radiation workers anddose limits relating to emergency work.
To comply with these guidelines, licensees shall include the following provisions in their
Operational Safety Programs: matters relating to operational safety education and radiation
protection; the establishment of Radiation Controlled Areas, Conservation Areas, and Surrounding
Monitored Area and access control, exhaust gas and effluent monitoring equipment; the monitoringof doses, dose equivalent, radioactive material concentrations, and the surface density of radioactive
material of contaminated items and their decontamination; and the management of radiation
detectors. Compliance with such matters is included in the Operational Safety Programs and ischecked by Operational Safety Inspectors during periodic NRA inspections.
In addition, the NRA Ordinance requires licensees to submit reports for each business establishment,
detailing the doses received by radiation workers over the course of the year.
Japan’s radiation protection standard complies with the ICRP’s 1990 Recommendations (Publication60). This revision incorporates the ICRP Recommendations in principle, but also contains additional
consideration of the following matters:
・The standard for the boundary of Radiation Controlled Areas has been set at 1.3 mSv per threemonths, based on the special limit for the public (5 mSv per year).
・The limit for female radiation workers has been set at 5 mSv per three months, this shorter period
reflecting the need for better protection of a fetus before any pregnancy has been recognized.
・Dose limit for emergency workers is 100 mSv.[After the accident at TEPCO’s Fukushima Daiichi
NPS, based on the 2007 Recommendations of the International Commission on RadiologicalProtection (ICRP), dose limit changed remains at 250 mSv temporary from March 2011 to
December 2011.]

Table F4-1 shows the dose limits for radiation workers and the general public prescribed inordinances based on the Reactor Regulation Act and in the Notification on Doses. .

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Table F4-1 Occupational Dose Limits
Dose LimitsA

Radiation workers(1)

Effective dose limit

100 mSv/5 years and 50 mSv/year(2)

female workers

As prescribed in (1), plus 5 mSv/3 months(3)

Pregnant workers

As prescribed in (1), plus 1 mSv/user for internal
exposure from the time the pregnancy isrecognized until childbirth(4)

Equivalent dose limit for the lens of theeye

150 mSv/year(5)

Equivalent dose limit for the skin

500 mSv/year(6)

Equivalent dose limit for the abdominal

2 mSv/user from the time the pregnancy issurface in pregnant workers

recognized until childbirth

B

Radiation workers involved in emergency work(1)

Effective dose limit(2)

Equivalent dose limit for the lens of the

eye
(3)

Equivalent dose limit for the skin

100 mSv
300 v
1 Sv

F4-2 Numerical Guide to Reduce Dose to the Public in the Vicinity and Discharge Control:

In accordance with the provisions of the NRA Ordinance, licensees reduce the concentration ofradioactive materials in gaseous waste as far as possible by such means as filtration in an
exhaust gas facility, radioactive decay, or dilution, and then measure and monitor its release.
In the case of liquid waste, they reduce the concentration of radioactive materials as far as
possible by filtration in a drainage facility, evaporation, adsorption using the ion exchange
resin method, radioactive decay, or dilution, and then measure and monitor its release.
Licensees outline measures in their own Operational Safety Programs to control the release of
gaseous and liquid waste in such a way as to ensure that the legally-prescribed radioactive material
concentration limits outside the Surrounding Monitored Area are not exceeded.
To ensure that release levels are below the legal limits outside the Surrounding Monitored Area,licensees prescribe release control targets equal to the annual release quantity stipulated at the timethey received their installation permit. In their Operational Safety Programs, they guarantee thatthey will not exceed those levels and the NRA checks the status of compliance when conducting
Operational Safety Inspections.
Exhaust gas and effluent concentration limits are prescribed for the facilities of disposal businesses
pursuant to the Radiation Hazards Prevention Act, ensuring that the dose at the boundary of thebusiness establishment does not exceed 250 micro Sv/3 months.
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Other General Safety Provisions F

F4-3

Environmental Radiation Monitoring:

To evaluate the impact of radioactive materials released from nuclear facilities on the surrounding
environment, licensees monitor air radiation dose rates at the monitoring station and measureradioactivities in environmental samples so that facility is well managed. To protect the health andsafety of the public in nearby communities, local governments in prefectures where reactor facilities
are located also conduct local radiation monitoring.
After the accident at TEPCO’s Fukushima Daiichi NPS, the government developed aComprehensive Radiation Monitoring Plan (approved in August 2011, revised in March and April
2012, April 2013 and April 2014), governing environmental radiation monitoring work related to the
Fukushima Daiichi NPS accident.
Points and frequency of environmental radiation monitoring was increased after the accident, andrelevant ministries and bodies, including the government of Fukushima Prefecture, are now working
in partnership to conduct meticulous monitoring in accordance with the Comprehensive Radiation
Monitoring Plan.
Environmental radiation monitoring are available on the NRA website.
F4-4

Measures Taken to Prevent Unplanned and Uncontrolled Releases of Radioactive
Materials into the Environment:

The above-mentioned rules prescribe that the three-month-averaged concentration of radioactive
materials in air outside the Surrounding Monitored Area shall not exceed the concentration limits fordischarge of gaseous radioactive waste, that the three-month-averaged concentration of radioactive
materials in water outside the boundary of the Surrounding Monitored Area shall not exceed theconcentration limits for discharge of liquid radioactive waste by a discharge facility, and that doses
due to liquid discharge of radioactive waste from reprocessing facilities monitored at the outlet to theocean shall not exceed the dose limit for three months. The rules also stipulate that licensees shallimmediately report to the NRA when any of these limits are exceeded, and report within 10 days on
details of the event and corrective measures taken.
F4-5 Measures to Mitigate the Effects of an Unplanned or Uncontrolled Release of Radioactive
Materials into the Environment:
Licensees stipulate in their Operational Safety Programs the measures to be taken in the event of an
emergency; these include the steps to be taken in the event of an unplanned or uncontrolled release ofradioactive materials into the environment, to control the release and mitigate its effects.
For example, the Safety Examination Guide for Reprocessing Facilities, which is used insafetyexamination of reprocessing facilities with a large inventory of radioactive materials, stipulates thatfire and explosion due to fine metal particles from fuel cladding or organic solvent, criticality
accidents, leakage or loss of function due to damage or failure of equipment or piping, or spent fuel39

F

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handling failure must not subject the public to the risk of excessive radiation exposure.
If an unplanned or an uncontrolled release of radioactive materials from a nuclear facility triggers a
specific event prescribed in the Nuclear Emergency Act, emergency activities will be initiatedaccording to the procedure stipulated in accordance with the Nuclear Emergency Act. If the accident
is serious enough, a Declaration of Nuclear Emergency is issued and emergency measures such as
evacuation will be taken.

40Other General Safety Provisions F

F5Emergency 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 radiological emergency 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

As stated in Section E, nuclear emergency responses in Japan are conducted on the basis of the
Nuclear Emergency Act. The accident at TEPCO’s Fukushima Daiichi NPS has been the catalyst forstrengthening the nuclear emergency response system, such as establishing the new Nuclear
Emergency Preparedness Commission within the Cabinet. Chaired by the Prime Minister, this will
enable the government to promote measures to prevent future nuclear emergencies as part of its
routine work, and failing that, to be prepared to deal with any crisis.
F5-1-1

Outline of the Laws and Regulations Concerning a Nuclear Emergency

Based on the experiences and lessons learned from the Fukushima Daiichi NPS accident, thegovernment revised the Atomic Energy Basic Act, the Nuclear Emergency Act, and related
legislation in September 2012 to develop new nuclear emergency responses. As a result of therevision of the Atomic Energy Basic Act, a Nuclear Emergency Preparedness Commission wasestablished in the Cabinet to facilitate emergency preparedness measures even in normal operation.
The Prime Minister serves as the Chairperson and the Chief Cabinet Secretary, the Minister of theEnvironment, and the NRA Chairman serve as Vice Chairpersons of the Commission. By the
Revision of the Nuclear Emergency Act, measures to prevent nuclear disasters are enhanced and thefunctions of the Nuclear Emergency Response Headquarters are strengthened.
Emergency measures are taken under the Basic Plan on Disaster Prevention which is drawn up inaccordance with the Basic Act on Disaster Control Measures and the Nuclear Emergency Act, andunder the Nuclear Emergency Response Guidelines which are formulated in accordance with the
Nuclear Emergency Act. The former prescribes the division of roles and responsibilities between
nuclear operators, the national government and local governments, while the latter stipulates the
specialized and technical measures required to deal with a nuclear emergency (such as references
for the extent of zoning and criteria used to make judgments in an emergency). The diagram below
provides an outline of the relevant legal system.

41

<Action Plans of Each Organization><National frameworks>

F

Other General Safety Provisions[Basic Act on Disaster Control Measures]- Establishment of the Central Disaster Prevention
Council- Implementation of emergency measures for disaster- Formulation of the Basic Disaster Management Plan
- Formulation of regional disaster prevention plans[Basic Disaster Management Plan]

National Government

Local Governments

Nuclear Operators[Act on Special Measures Concerning Nuclear Emergency Preparedness](Special law under the Basic Act on Disaster Control Measures)- Establishment of Nuclear Emergency Response Headquarters(based on the instruction from government)- Implementation of emergency response measures- Formulation of the Nuclear Emergency Response Guidelines- Formulation of nuclear operator emergency action plans(Nuclear emergency Countermeasures)*Enforcement of the national crisis management system*Preparation for protecting residents and supporting
affected people*Enhancing disaster prevention and mitigation
infrastructure[Nuclear Emergency Response
Guidelines]- Describes specialist/technicalcontent relating to disaster response
measures

Nuclear Emergency Response Manual- Manuals prescribing the roles of relevant ministries and agencies- Descriptions for the structure of the secretariat surrounding the Prime Minister’s Office and on-site/off-site operational
procedures

Regional disaster prevention plans- Plans relating to disaster prevention by prefectures and municipalities- Formulation of wider-area evacuation plans based on the establishment of the PAZ and UPZ; furnishing of materials andequipment required for disaster prevention
Nuclear operator emergency action plans- Precautions, emergency response measures, and ex post facto measures by nuclear operators- Preparation of a liaison and coordination base ; implementation of drills simulating severe accidents(1) The Act on Special Measures Concerning Nuclear Emergency Preparedness (Nuclear
Emergency Act):In the event of an emergency, such as the release of a large amount of radioactive materials, a
Nuclear Emergency Response Headquarters will be temporarily established within the government.
Following the Fukushima Daiichi NPS accident, the Nuclear Emergency Act was amended and the
Nuclear Emergency Response Headquarters was strengthened. The Prime Minister serves as
Headquarters director, and the Chief Cabinet Secretary, Minister of the Environment, and the
Chairman of the NRA as deputy directors-general, with all Ministers of State and the Deputy Chief
Cabinet Secretary for Crisis Management serving as regular members. The NRA holds primary
responsibility for technical and specialized on-site safety issues. Matters concerning the
procurement of equipment and supplies required for nuclear facilities and all matters associated with
off-site response are handled by the relevant ministries and agencies, according to the directions of
the director (the Prime Minister).
The NRA formulates specialized and technical guidelines to implement emergency
preparedness measures, emergency response and the restoration (hereinafter referred to as “Nuclear
Emergency Response Guidelines”).
The responsibility of nuclear operators outlined in the Nuclear Emergency Act is to take all possible
steps to prevent a nuclear disaster, to prevent the escalation of nuclear disaster, and to rehabilitate
any resultant damage. Operators must formulate a Nuclear Operator Emergency Preparedness
Program, formally notify the Prime Minister and the NRA, and publish a synopsis. An on-siteorganization for nuclear emergency preparedness must be established at each nuclear site and42Other General Safety Provisions F
actions to either prevent a disaster or limit any escalation and these actions must be carried out inaccordance with the Nuclear Operator Emergency Preparedness Program. Accordingly, nuclear
operators must appoint Nuclear Operator Emergency Preparedness Personnel to the on-site
emergency organization and notify the NRA, the governors of the local and neighboring prefectures,and the local mayor. The nuclear operator shall select a Nuclear Emergency Preparedness Manager
to supervise the on-site emergency organization. The NRA, the governors of the local andneighboring prefectures, and the local mayor shall also be formally notified of the appointment or
dismissal of a Nuclear Emergency Preparedness Manager. If a specified event prescribed in the
Nuclear Emergency Act occurs, the Nuclear Emergency Preparedness Manager shall alert the above
actors and the Prime Minister.
In addition, nuclear operators shall maintain radiation measurement equipment to provide
notification of specified event. Instruments for radiation protection and emergency communications
equipment required to enable the on-site emergency organization to undertake its activities must be
permanently available and regularly inspected and maintained. Radiation measurement instruments
must undergo NRA performance checks.
As part of their routine work, local governments formulate regional emergency preparedness plans
based on the Basic Plan on Disaster Response and the Nuclear Emergency Response Guidelines,
and are able to respond to any emergency.
The Prime Minister designates an off-site disaster response facility for each nuclear site (Off-site
Center), at which a local nuclear emergency response headquarters is established tocoordinate

emergency response measures.
Government emergency exercises are carried out on the basis of a plan drawn up by the Prime
Minister. Exercises conducted by nuclear operators are carried out on the basis of legislation,
emergency response plans, or Nuclear Operator Emergency Preparedness Programs> Nuclear
operators must report the results to the NRA, as well as publishing a synopsis.
(2) Basic Plan on Disaster Response:
The Central Disaster Response Council formulated a Basic Plan on Disaster Response based on the
Basic Act on Disaster Control Measures and the Nuclear Emergency Act. The section on nuclear
emergency response measures prescribes basic matters and the respective division of roles ofnuclear operators, the national government and local authorities.
The Basic Plan on Disaster Response was revised in September 2012 following the

Fukushima

Daiichi NPS accident. The major revisions are as follows:
・The revisions prescribe the immediate dispatch of the NRA Chairman to the Official Residence ofPrime Minister to strengthen the Official Residence’s decision-making and information
dissemination functions.
・A nuclear facilities rapid response center for emergency shall be established at the headquarters orother appropriate offices of the nuclear power company as the base for accident response measures,
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and a local headquarters shall be established at an off-site center to take responsibility for ensuringresidents’ safety. Measures to be taken on-site and off-site are thus clarified:

・The revisions prescribe the implementation of practical exercises simulating complex disasters andsevere accidents.
・The revisions prescribe close cooperation when multiple headquarters are established in the event of
a complex disaster.
(3)

Nuclear Emergency Response Guidelines:

In response to the accident at Fukushima Daiichi NPS, nuclear emergency preparedness measuresfor commercial power reactors were strengthened in the Nuclear Emergency Response Guidelines.
These guidelines stipulate emergency preparedness and their implementing frameworks and theestablishment of specific zones where such measures will be treated as a priority. The national
government, relevant local governments and the nuclear operators plan deals with a nuclear disasterbased on the Basic Plan on Disaster Response and the Nuclear Emergency Response Guidelines.
(The Nuclear Emergency Response Guidelines are detailed in “3 Measures for Dealing with an
Emergency” below.)
The main items indicated in the Nuclear Emergency Response Guidelines are as follows:・Basic matters concerning nuclear emergency responses‐Guideline objectives‐Characteristics of nuclear disasters‐Basic concept of radiation protection action
・Nuclear emergency preparedness measures‐Establishment of EAL and OIL, which form the standards for decision-making in an emergency‐Establishment of a PAZ (within 5km from the facility) and UPZ (within 30 km from thefacility); these are the zones for which prior measures, such as preparations for evacuation,
should be formulated‐Advance preparations, such as information dissemination, emergency radiation monitoring,
and a framework for radiation emergency medical assistance, as well as education and training
・Emergency response measures‐Prompt emergency radiation monitoring‐Prompt information dissemination for residents‐Implementation of proper protective actions (sheltering, evacuation, medication with stable iodine
agents), based on EAL and OIL
・Medium- to long-term measures in response to nuclear disasters‐Long-term evaluation of radiation effects on human health and the environment‐Implementation of decontamination measures to minimize effects
The Guidelines stipulate the following as matters for further consideration:
・Introduction of Plume Protection Planning Areas (PPA) and establishment of priority zones and44

Other General Safety Provisions F
emergency response measures for facilities other than commercial reactors
・Responses to the accident at TEPCO’s Fukushima Daiichi NPS‐Determination of approaches to the transition from an emergency exposure situation to an
existing exposure situation and a planned exposure situation‐Determination of approaches to priority zones for nuclear emergency response measures peculiar
to TEPCO’s Fukushima Daiichi NPS based on risk assessment
・Establishment of a regular forum for sharing information with local residents
F5-2

Responsibilities of Relevant Organizations Involved in Nuclear Emergency Response

The national government, local governments, and nuclear operators prepare the following systems toprevent a nuclear disaster or respond if a nuclear emergency occurs.
(1)The National Government:
・In the Nuclear Emergency Response Headquarters, the NRA holds primary responsibility fortechnical and specialized matters associated with the safety of nuclear facilities (on-site), while
matters relating to the procurement of equipment and supplies required to deal with the nuclear
facilities and all matters associated with the response outside the facilities (off-site) are handled by
the relevant ministries and agencies, based on the directions of the director (the Prime Minister).
・Nuclear Emergency Preparedness Officers stationed in regions where nuclear facilities are locatedprovide guidance and advice to prevent a nuclear emergency, such as preparing Nuclear Operator
Emergency Preparedness Programs and helping to carry out measures to prevent a disaster
escalating.
・Off-site centers have been set up in areas hosting nuclear facilities, with essential equipment andfacilities for communicating with the Prime Minister’s Official Residence, the NRA Emergency
Response Center, nuclear operators, and relevant local governments. The off-site centers arecapable of monitoring environmental radiation levels and plant status. They are linked with
monitoring posts located around the facilities so they can monitor the plant status andenvironmental radiation levels in real time. Emergency monitoring is led and organized by thenational government.
・The national government supervises emergency environmental radiation monitoring and implements
Comprehensive Nuclear Emergency Response Exercises by uniting efforts of local governments,
nuclear operators, and local residents.
(2)Nuclear Operators:
・Nuclear operators must prepare a Nuclear Operator Emergency Preparedness Program after
conducting discussions with local governments before operations begin and then formally notify
the NRA. The following must be included in the Nuclear Operator Emergency Preparedness
Program:‐The duties of the Nuclear Emergency Preparedness Manager
45

F

Other General Safety Provisions‐The composition of the organizations for nuclear emergency preparedness at each emergency
base‐The policy on implementing nuclear emergency response education for appropriate personnel‐ Equipment needed for responding to any nuclear emergency, including maintenance andinspections‐Planning, implementation, evaluation and improvement of nuclear emergency response exercises‐Measures to be taken during specified events following the declaration or termination of a nuclear
emergency

・Nuclear operators shall establish an on-site nuclear emergency preparedness organization andappoint a Nuclear Emergency Preparedness Manager.
・This Manager must notify the government and surrounding prefectures immediately following
specified events.
・Nuclear operators shall install and maintain radiation measurement equipment, radiation protection
equipment and emergency communications to undertake on-site emergency response activities.
(3)Local Governments:
・Local governments formulate and implement Regional Disaster Prevention Plans based on the Basic
Plan on Disaster Prevention and the Nuclear Emergency Response Guidelines. The main points
included in the Regional Disaster Prevention Plans are as follows:‐Multiplexing communication networks among emergency response centers to ensure reliablecommunication with the national government, local governments, and nuclear operators‐Preparation of facilities, materials and equipment and systems to enable local headquarters tocontinue activities even in the event of a severe accident; establishment of cooperation with the
NRA, designated administrative organs, public agencies, and nuclear operators; and developmentof a system to carry out extensive and adaptable emergency radiation monitoring‐Preparation of precautionary protective actions (initial emergency evacuation) within the PAZ;
formulation of extensive evacuation plans and with the national government ensuring effective
instructions for evacuation and transportation of people who need support‐Development of systems regulating the shipment of water and food
‐Ensuring a comprehensive traffic control system to transport people from prioritized areas such as
PAZ‐Preparation of a system governing iodine tablets including their timely and proper distribution
and administration; establishment of a radiation emergency medical assistance system;
development and maintenance of systems to dispatch and accept radiation emergency medical
teams‐Preparation of information systems in the event of a complex disaster・Prefectures support and coordinate administrative duties by municipalities.

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Other General Safety Provisions F
F5-3 Measures for Dealing with an Emergency
F5-3-1 Nuclear Emergency Preparedness Measures:(1) Basic Approach to Nuclear Emergency Preparedness
In case of a nuclear emergency, appropriate measures to protect local residents and others against
radiation exposure need to be taken to avoid deterministic effects and to reduce stochastic effects. In
light of the rapid progress of the Fukushima Daiichi NPS accident, it is necessary to take protective
measures such as evacuation even before the release of radioactive material. When radioactive
materials are released, prompt implementation of protective actions is required according to thedevelopment of the radiological situation.
(2) The Establishment of EAL and OIL
To establish protective actions, it is necessary to establish emergency categories based on the plantstatus and exposure risk, to share recognition of an emergency situation among stakeholders. The
NRA has deliberated on radiation exposure dose levels at which protective actions should be taken.
To enable appropriate protective actions to be implemented in various emergency categories, it isnecessary to establish operational criteria based on observations and values.
Specifically, it is necessary to stipulate Emergency Action Levels (EALs) which determine
emergency categories. They are primarily used to implement preventive protective actions in theevent of an emergency at nuclear facilities. Also, it is necessary to stipulate OILs, which are used toformulate protective actions particularly after radioactive release. They are prescribed in the form of
measurements such as the radiation dose rate envisaged in case of an emergency.
The emergency categories are divided into three:･AlertIn this phase, there are no radiation effects on the public nor any imminent risk, but caution isrequired because of the possibility of the occurrence of an ‘abnormal’ event. In the PAZ, theorganizations which take protective measures, such as a local government, begin time consuming
preparations of measures.
･Site Area Emergency
In this phase, it is necessary for local governments in the PAZ to put into place the main protective
measures around a nuclear facility which may affect public safety. They include the evacuation of
all local residents in the PAZ.
･General Emergency
This phase requires competent authorities such as a local government to implement full emergency
protective actions to avoid deterministic effects or to reduce stochastic effects, due to theoccurrence of an event which may affect public safety. In the PAZ, it is necessary to implement
protective actions such as evacuation and distribution of KI tables to all residents. Same measures
can be taken in the UPZ depending on the plant status.
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Emergency Action Levels are established as guidance whether a specific situation corresponds toone of these emergency categories, based on the status of each layer of a facility’s defense-in-depth
equipment, the status of radioactive material confinement functions, and whether or not any
external events have also occurred. Table 1 shows emergency categories relating to commercial
reactor facilities and the details of current EALs.
Nuclear operators are required to consider establishing more detailed EALs specifically relecting
conditions at each power reactor and submit them to the NRA which examines each facility’s EAL
and optimizes it if necessary.

Table 1

Emergency Categories and EALs

Emergency Category

EAL

Alert

If an earthquake with a magnitude of at least 6-minor on the Japanese seismic
intensity scale has occurred in the prefecture in which a nuclear facility is sited
If a major tsunami warning has been issued in the prefecture in which a nuclear
facility is sited
If a Tokai Earthquake Advisory has been issued:
In the event of a crucial failure of the reactor facilities that a Director-General of
the NRA Secretariat or the Director of the Accident Countermeasures Office of
the Nuclear Emergency Preparedness Division deems to necessitate an alert
In any other case in which the Chairman of the NRA deems the establishment of
an NRA Nuclear Accident Alert Headquarters to be necessary

Site Area Emergency

Leakage of reactor coolant
Failure of Emergency Core Cooling System in the High Pressure Coolant
Injection system in the event of the loss of feedwater functions
Loss of all feedwater functions to steam generators
Loss of Residual Heat Removal functions in the event of the loss of heat removal
functions from the reactor by means of the main condenser
Station blackout (continuing for at least five minutes)
If a situation in which only one power source is supplying electricity to the DC
bus continues for at least five minutes, in the event that there is only one
emergency DC bus
Decline of the water level within the Reactor Pressure Vessel while the reactor isshut down to the level at which the Emergency Core Cooling System begins toactuateLoss of all functions for cooling the reactor during outage
Unavailability of the reactor control room

General Emergency

Inability to shut-down the reactor, if required, by a conventional neutron absorber
Loss of all functions to shut-down the reactor, if emergency shut-down is48

Other General Safety Provisions F
requiredInability to inject water into the reactor in question using any of the Emergency
Core Cooling Systems
If the pressure within the Containment Vessel reaches the design-basis maximum
pressure limit
Loss of pressure control functions in the Containment Vessel, in the event thatfunctions for removing residual heat from the reactor have been lost
Loss of all functions for cooling the reactor
Loss of all emergency DC power continues for at least five minutes
Detection of radiation or temperature indicative of core meltdown
Detection of a change in the liquid level within the reactor vessel or otherphenomenon indicative of exposure of the irradiated fuel assemblies within thereactor vessel
If a situation continues for at least one hour in which the water level declines to apoint where residual heat removal functions are lost
Unavailability of the reactor control room
The liquid level in the irradiated fuel assembly storage tank declines to the levelat which the fuel assemblies in question are exposed
If a situation in which the ambient radiation dose rate at the site boundary
reaches 5 micro Sv/hour continues for at least ten minutes

If the initial phase of an emergency reaches the General Emergency level, based on the EAL judged by
the facility status, it may be necessary to begin protective actions such as precautionary evacuations to
reduce exposure of the general public. There is a possibility that high air dose rates could be observed
over a comparatively extensive area after radioactive release because of air dispersal.
Accordingly, it is necessary to conduct emergency radiation monitoring, to analyze the results basedon the appropriate criteria, and to take any requisite protective actions. The Operational Intervention
Levels using figures such as the air radiation dose rate and the concentration of radioactive materials
in environmental samples are established. The following table 2 shows the content of OILs
corresponding to each protective action.
Table 2

Emergency
protective
actions

OILs and Protective actions
Classification

Outline of Classification

Initial Figure

OIL1

Criteria for advising local
residents for evacuationor sheltering within a few
hours or shelter, toprevent radiation effects

500 micro Sv/h(air radiation dose rate when measured 1
m above the ground)49

OutlineofProtective actions
Identification of
zones
and
evacuation within
a
few
hours
(including

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OIL4

Initialprotective
actions

OIL2

Screening
criteria
forfood and drink(Response to
OIL3)

Restrictions
oningestion of
food
and
drink
OIL6

from
surfacesoil,inhalationofre-suspended radioactive
materials, or inadvertentoral ingestion
Criteria for conducting
decontamination
toprevent inadvertent oral
ingestion and external
exposurevia
skincontamination

Criteria for restricting
ingestion of local produce
andadvising
local
residents to temporarily
relocate within a week orso, to prevent radiation
effects from surface soil,
inhalationofre-suspended radioactive
materials, or inadvertentoral ingestion
Criteria for identifying
areas where measurementofradionuclide
concentrations in foodand drink should be
carried out in preparation
for possible food anddrink restrictions at OIL6
Criteria when restricting
food and drink ingestion
toprevent
radiation
exposurevia
oral
ingestion

Beta rays: 40,000 cpm(detector counting rate a few cm from theskin)Beta rays: 13,000 cpm(detector counting rate a few cm from theskin)

20 micro Sv/h(air radiation dose rate when measured 1
m above the ground)

0.5 micro SV/h(air radiation dose rate when measured
1m above the ground)

NuclideRadioactive
iodineRadioactive
cesiumAlpha-emitting
nuclidesofplutonium andtransuranicelements
Uranium

Drinking
water,
milk,
dairy
products
300
Bq/kg
200
Bq/kg

Vegetables,
cereals,
meat, eggs,
fish, other
2,000
Bq/kg
500 Bq/kg

1 Bq/kg

10 Bq/kg

20
Bq/kg

100 Bq/kg

ordering
those
who cannot easily
move
to
the
sheltering
temporarily)
Screening
evacuees basedonevacuation
standards
andpromptdecontaminationof
those
exceedingthecriteria
Identification ofzones within a
day or so andrestrictionofingestion of local
produce, as wellas
temporaryrelocation withina week or so

Identification of
zones
where
radionuclide
concentrations infood and drink
shouldbemeasured within a
few days
Analysisofradionuclide
concentrations infood and drink,
within a week,andpromptrestrictions
onfood and drink
intake if results
are in excess ofthe criteria(3) Medical Dependencies
In addition to medical assistance during a disaster, radiation emergency medical assistance

may berequired in a nuclear emergency. It is important that the medical care appropriate to address
emergency situations is available to perform properly and promptly with consideration of exposure
50Other General Safety Provisions F
doses, the extent of exposure consequence and possibility of contamination, and the need to conduct
medical control for affected populations and disabled patients. Appropriate medical proceduresshould then be provided, with various medical institutions fulfilling their respective roles (emergency
treatment, screening) taking into account the situation in each area. Effective systems and chains ofcommand should be established as a routine measure in institutions dealing with emergencies anddisasters. An issue particular to radiation medical assistance is the long-term and late effects ofradiation exposure, so it is vital to develop a knowledge of these and ensure proficiency in relevant
techniques.
From the foregoing perspective, the NRA incorporates medical dependencies during the nuclear
disasters into the Nuclear Emergency Response Guidelines, together with education, training, andpractice exercises for appropriate institutions, including the national and local governments.
Radioactive iodine/iodide is accumulated mainly in the thyroid gland and may cause thyroid cancer
when deposited dose are relatively high. Accumulation of radioactive iodine in the thyroid can be
reduced by the prior administration of KI tablets. The effectiveness of KI tablets is dependent on thetime when tablets are given. The NRA has instructed that KI tablets should be dealt as conventional
pharmaceuticals, namely in compliance with medical advice.
In the PAZ, because of the possibility of immediate evacuations in the general emergency, a system isbeing developed to enable local governments to distribute KI tablets to local residents in advance as aroutine measure, ensuring maximum effectiveness.
F5-3-2 Emergency Response Measures:(1) Basic Approach to Emergency Response Measures
In an emergency, taking the most effective and prompt protective actions is necessary to protect
local residents. In such case, concerned personnel have to take appropriate protective actions basedon the observable values.
(2) Identifying Abnormal Situations and Taking Emergency Response Measures:
Following the release or threat of abnormal levels of radioactive materials or radiation, the operator
of a nuclear facility shall immediately determine the applicable emergency category based on
available information and notify the national and local governments, proposing appropriate
protective actions. The national and local governments shall take the following emergency response
measures:・If the situation has reached Alert or Site Area Emergency status, they shall begin protective actions
in case it develops into a General Emergency, and provide information to local residents.
・If situation has reached General Emergency status, they will begin measures such as the evacuationof local residents from the PAZ, as a general rule, and from part of the UPZ, depending on thesituation at the plant.
・Depending on the results of emergency environmental radiation monitoring, measures such as
51

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evacuation, temporary relocation, and/or restrictions on food and drink intake shall be implemented
outside the areas where precautionary protective actions have already been taken.

(3)

Implementation of Emergency Environmental Radiation Monitoring:a Preparation and initial response to emergency environmental radiation monitoring
The national and local governments, nuclear operators, and designated public organizations makepreparations for emergency environmental radiation monitoring in an Alert status. In a Site Area
Emergency, the national government establishes and begins operating an emergency environmental
radiation monitoring center with the cooperation of local governments, and requests the necessary
personnel based on a staff deployment plan, providing those staff with disaster information withwhich to begin monitoring.
b Establishment of an emergency environmental radiation monitoring implementation plan
The national government swiftly formulates an emergency environmental radiation monitoring
implementation plan, taking into consideration such practical factors as the severity of the accident,
residence zones and population distributions, topography, weather forecasts and the results ofatmospheric dispersion predictions, and provides overall supervision of emergency environmental
radiation monitoring in the various fields.
With the assistance of local governments, the nuclear operator, and relevant designatedpublicorganizations, the national government revises the emergency environmental radiation monitoring
implementation plan as the situation evolves. If the damage prevents adequate emergency
environmental radiation monitoring, the government will consider using weather forecasts andatmospheric dispersion prediction results as the basis for a monitoring system. Should prolonged or
extensive emergency environmental radiation monitoring be required, the national government will
respond in accordance with the staff deployment plan stipulated in advance.
c Implementation of emergency environmental radiation monitoring
The national and local governments, nuclear operators, and designated public organizations
conduct emergency environmental radiation monitoring based on the emergency implementation
plan under the supervision of the emergency environmental radiation monitoring center. Initialmonitoring should focus on the measurement of air dose rates to determine future protective
actions based on OILs. The aerial concentration of radioactive materials, mainly radioactive iodine,
should also be measured. Measurement targets are to be expanded sequentially.
The origin of the accident among nuclear operators is responsible for the radiation monitoring,such as the concentration of radioactive materials discharged from the facility, and air dose rates atthe boundary of the site. The operator shall report the results to the emergency environmental
radiation monitoring center.
Depending on the severity of the situation, the emergency environmental radiation monitoring52

Other General Safety Provisions F
center shall utilize available staff, materials and equipment, focusing on measurement targets to beprioritized.
d Results of emergency environmental radiation monitoring
The emergency environmental radiation monitoring center first judges the validity of themonitoring results, and the national government collects, analyzes and evaluates the verified
results. These are utilized as a reference in determining future protective actions based on OILs.
The national government takes weather data and atmospheric dispersion predictions into accountwhen analyzing and evaluating the monitoring results and publicizes these results promptly in aneasy-to-understand manner.
(4) Providing Information to Local Residents in an Emergency
The national and local governments shall make full use of all feasible means of communication,
including diverse forms of media, in order to swiftly provide accurate, easily-understandable
information to local residents. In doing so, they should repeatedly convey the following matters to
local residents.
・The name of the affected facility, the time when it occurred, and details of the situation
・The state of the surrounding environment, such as measurements of air radiation dose rates, as well
as future projections
・Action that local residents should take, broken down by zone or settlement
When the national or local governments disseminate information, they must seek the help of themedia. In providing information, consideration must be given to those requiring assistance and those
who are only staying in the area temporarily. Information should be shared with relevantorganizations and efforts made to ensure there are no discrepancies in such information.
(5) Protective actions
When radioactive material or abnormal levels of radiation are released, or there is a risk of such an
occurrence, the following protective actions shall be taken:
a Evacuation and temporary relocation
Urgent evacuation and temporary relocation should be carried out if local residents are exposed tounacceptable levels of radiation. Moving them reduces such risk. Evacuation is carried out urgently,
to swiftly move people away from a location when the air dose rate there is high or could become so.
Temporary relocation takes place in areas where the air dose rate is lower, with the aim of moving
residents away from the area to reduce any unnecessary exposure that would result from remaining
there. The contamination status of evacuation centers must be checked. Following screening,decontamination of evacuees may be necessary to reduce internal exposure and skin surface
exposure. Evacuation and temporary relocation measures should be tailored to the Priority Zones for53

F

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Nuclear Emergency Response.

・In the PAZ, evacuation of all local residents must generally be carried out immediately when thesituation reaches General Emergency status.
・In the UPZ, it is necessary to carry out a phased evacuation, depending on the situation at thenuclear facility. Emergency environmental radiation monitoring shall be conducted, with zones
higher than OIL1 being identified and evacuated within the first few hours. Emergency
environmental radiation monitoring shall be ongoing thereafter, and identification of andtemporary relocation from zones higher than OIL2 must be carried out within a day.
・Outside the UPZ, areas higher than OIL1 and OIL2 must be identified following radioactive
releases, in the same way as in the UPZ, and evacuation or temporary relocation must be carriedout.
In implementing evacuation or temporary relocation as described above, the government’s Nuclear
Emergency Response Headquarters judges the necessity of evacuation and must clearly and without
confusion convey its decisions to residents through appropriate local governments. The Nuclear
Emergency Response Headquarters will consider transport methods and routes, and the securing of
evacuation shelters, referring to emergency environmental radiation monitoring results obtained by
the NRA, as well as weather predictions and the results of predicting atmospheric dispersion.
Special assistance must be given to residents, particularly those who need special help for physicalor psychological reasons. Attention should be paid to coordinating evacuation centers in advance ofan emergency and the possibility that these shelters may need to be relocated. Radiation protective
actions must be included at evacuation centers such as hospitals, nursing homes and community
centers which serve as temporary refuge centers for locals whose evacuation has been delayed or
patients in hospitals and nursing homes.
b Sheltering
Sheltering is a relatively easy action to be taken by local residents, and helps to reduce radiation
exposure and shield the body from neutron and gamma radiation. Residents should follow
government advice to shelter indoors while awaiting orders. At hospitals and nursing homes it issometimes necessary to prioritize the sheltering rather than the evacuation. In such situations,sheltering in a concrete building with a solid ‘shielding’ effect and air tightness is generally
effective.
Practical sheltering measures are tailored to the Priority Zones for Nuclear Emergency Response.
・In the PAZ, evacuation is generally carried out in the event of a General Emergency, but sheltering
is prioritized over evacuation.
・In the UPZ, sheltering must be implemented as a general rule, until phased evacuation orprotective actions based on the OIL are carried out.
・Outside the UPZ, sheltering is generally implemented in the same way as within the UPZ.
Accordingly, local residents must be warned that there is a possibility that temporary sheltering
54

Other General Safety Provisions Fmight be necessary if the situation reaches General Emergency phase.
It is possible that the period of sheltering will be extended if a radioactive plume stays longer orcomes one after another. In this case, a decision on evacuation can be made due to the loss of the
exposure reduction effects by the inflow of contaminated air into the shelter, and because it isdifficult to maintain normal life through longtime sheltering. In the case of sheltering inside thezones where residents should evacuate, aid supplies including medical care goods, and radiation
protective actions for such remaining people should be considered, and necessary information beprovided continuously to them.
In formulating Regional Disaster Prevention Plans (Nuclear Emergency Response Section),
consideration must be given to ensuring that buildings fulfill stringent air-tightness conditions, andsecuring evacuation shelters and routes in case of a switch in evacuation plans. It is necessary toconvey such information to the public during normal times.
c KI tablets prophylaxis（This section is quoted from the National Report of Japan for 6th Review Meeting
concerning Convention on Nuclear Safety, August 2013）
To prevent internal radioactive iodine exposure, KI tablets should be taken according to government
directives. In addition to warnings about possible side-effects, the following points should beconsidered:・KI tablets have no protective effect against any radionuclides other than radioactive iodine.
・It is necessary to take KI tablets in addition to other protective measures, such as evacuation,
sheltering, and restrictions on food and drink intake. An excessive reliance on the effects of KI
tablets, however, must be avoided and it is necessary to prevent inadvertent oral ingestion.
・When taking KI tablets, psychological anxiety could give rise to unusual reactions.
・Doses must be appropriate to the age of the patient. Particular care is required to avoid overdose ininfants and young children.
・The following methods of administering KI tablets should be used, tailored to the Priority Zones for
Nuclear Emergency Response.
・In the PAZ, the Nuclear Emergency Response Headquarters or local governments immediately issue
instructions concerning evacuation and taking KI tablets when the situation reaches the General
Emergency phase. However, persons unable to take KI tablets, as well as infants and young
children (for whom the impact of thyroid gland exposure to radiation from radioactive iodine isgreater) and their guardians should evacuate earlier upon the declaration of a Site Area Emergency,.
In such circumstances taking KI tablets is unnecessary.
・When a situation reaches the General Emergency phase outside the PAZ, the NRA determines thenecessity of taking KI tablets, in addition to possible evacuation and sheltering, after which the
Nuclear Emergency Response Headquarters or local governments issue instructions. Residents areadvised to take KI tablets in line with such instructions.
55

F

Other General Safety Provisionsd Radiation emergency medical assistance（This section is quoted from the National Report of Japan for 6th Review Meeting
concerning Convention on Nuclear Safety, August 2013）
Medical procedures shall be carried out in accordance with the medical care system developed inadvance, with a focus on affected patients or those exposed to radiation.
The NRA, which consolidates information from emergency environmental radiation monitoring,
conveys information about radiation doses to key medical personnel coordinating care in affectedareas via the Nuclear Emergency Response Headquarters. These medical personnel direct patients tothe appropriate hospital and rescue services, and instruct these institutions to accept the incoming
patients. Checks will take place to ensure that these patients have been accepted. People who areseverely affected can be taken to an advanced medical facility. If radioactive iodine has beenreleased or may be released shortly, responsible officials can direct that KI tablets are taken
promptly by the general public, in accordance with government instructions. Decontamination,
protection guidance and screening shall be carried out. If there is a strong possibility of internal
exposure, it is necessary to carry out thyroid screening and internal exposure dose measurement.
e Contamination screening and decontamination（This section is quoted from the National Report of Japan for 6th Review Meeting
concerning Convention on Nuclear Safety, August 2013）
Screening to ascertain the degree of contamination is essential to curb internal exposure via
inhalation and oral ingestion, reduce skin exposure, and prevent the spread of contamination, as wellas ensuring that medical interventions can take place smoothly.
The place for contamination screening should be selected to ensure that all screening can be carriedout (including the human body, objects, etc.) It is desirable for such screening to take place in alocation where the radiation background is as low as possible.
It is necessary to conduct contamination screening of evacuees and those temporarily relocated atconvenient centers and to carry out decontamination if the level is higher than the reference value.
(i) Body surface contamination screening
Body surface contamination screening shall be carried out primarily among evacuees. The OIL4
criteria shall determine decontamination. It is also desirable to carry out decontamination below
OIL4 if possible, so guidance shall be provided on the requisite radiation protective actions.
If OIL4 is exceeded in body surface contamination screening at evacuation centers, simple
decontamination (change of clothes, wiping of the skin, use of a simple decontamination agent or
shower) shall be implemented, taking into account the effectiveness of such measures. Nasal
smears should be taken to check contamination of the nasal cavity if there is concern about
inhalation exposure. If the individual cannot be decontaminated there, they should undergo theprocedure without delay upon returning home or reaching another suitable venue.
Medical personnel should wear two layers of gloves to prevent secondary contamination when56

Other General Safety Provisions F
examining persons suffering body surface contamination.
It is desirable to explain the results of body surface contamination screening measures whencarrying out protective actions such as decontamination.
(ii) Thyroid screening
Thyroid screening shall be carried out if concerns arise about radioactive iodine exposure
following screening and emergency environmental radiation monitoring. However, it must be
accepted that thyroid screening does not provide an accurate estimate of thyroid gland exposure
dose.
Screening should initially be carried out using a simple measurement technique. If more detailed
measurement is required, a thyroid monitor or whole body counter should be used, depending on
the nuclide(s) involved. When making detailed estimates of internal exposure, it is necessary toutilize instruments capable of carrying out such detailed measurements.
(iii) Screening of goods
The screening of goods shall be carried out to curb external and/or internal exposure among thosehandling said goods and to prevent the spread of contamination. Moreover, OIL4 shall also be
used in the screening of goods, with simple decontamination procedures being carried out on
contaminated goods.
f Restrictions on food and drink
Restrictions on food and drink consumption are enforced when radionuclide concentrations rise
above a certain level. These restrictions are designed to reduce internal exposure due to oral
ingestion, but it is vital to provide alternative food and drink from outside the affected zone if
necessary.
Practical restrictions on the consumption of food and drink should be implemented as follows:
・As well as identifying areas where the air radiation dose rate is higher than OIL2 and considering
the step of temporary relocation, consumption of local produce must be restricted. Once theradionuclide concentrations in food and drink have been ascertained, possible restriction shall be
determined on the basis of OIL6.
・Areas where air radiation dose rates are higher than the screening criteria for food and drink must be
identified and measurement of radionuclide concentrations started. If these measurements confirm
radionuclide concentrations in excess of OIL6, consumption of food or drink shall be restricted.
In implementing the aforementioned restrictions, the NRA must relay all relevant information to
local governments via the Nuclear Emergency Response Headquarters. Local governments shall inturn inform residents.
F5-3-3 Medium- to Long-term Measures in Response to Nuclear Disasters:(1) Basic Approach to Medium to Long-term Measures in Response to Nuclear Disasters
57

F

Other General Safety Provisions
In response to a nuclear disaster, proper measures need to be taken with regard to radioactive
materials discharged into the environment once the immediate crisis ends. It is therefore
important to take medium to long-term measures described below as discussions continue.

(2) Environmental Radiation Monitoring to Promote Disaster Recovery
The national and local governments must conduct continuous environmental radiation monitoring
to ascertain changes in radiation doses and concentrations of radioactive materials to enable thefollowing disaster recovery decisions to be made.
・Revision of evacuation zones
・Determination of actions to control and reduce exposure doses
・Estimates of current and future exposure doses (estimation of individual radiation doses)
A system to integrate the collection, preservation, and utilization of data must be created to enable
relevant organizations to efficiently use the information and ensure the validity of environmental
radioactivity monitoring to be conducted on a medium to long-term basis.
(3) Estimation of Individual Radiation Doses to Promote Disaster Recovery
In addition to environmental radiation monitoring, national and local governments must estimate
individual radiation doses assuming medium and long-term exposure to contamination and takeappropriate measures.
Individual radiation doses vary according to a person’s daily activities, so the results of behavioral
surveys must be checked against those of environmental radiation monitoring. Actual measured
values obtained through individual dose monitoring are also necessary. By combining these values,
individual radiation doses can be estimated with higher accuracy.
(4) Health Assessment to Promote Disaster Recovery
Residents suffer not only radiation exposure but also mental and physical stresses of living in an
abnormal environment during evacuation, sheltering and communal life over a long period of time.
National and local governments must therefore conduct long-term health assessments including themental health of residents in addition to monitoring diseases associated with radiation exposure.
Through such health assessments, officials must eliminate public fear about present and future
health problems.
(5) Decontamination Measures
Government officials must institute decontamination measures to enable residents to return to theirnormal lives as quickly as possible. Such measures must take relevant social factors into
consideration.
Government organizations must encourage public participation by providing all decontamination
information, guidance, materials, equipment and training, and by deploying specialized advisors.
58

Other General Safety Provisions F
The exposure of workers engaged in decontamination situations should be managed by relevantlaws and regulations.
(6) The transition from an emergency exposure situation to an existing exposure situation and aplanned exposure situation
An emergency exposure situation will evolve into an existing exposure situation, when theradioactive release falls to a contrable level and the radiation exposure due to residual radioactive
materials is controllable below a certain level. However, even in the aftermath of an emergency,
some areas may continue to experience both an emergency and existing exposure concurrently. The
transition between the two is a major factor in judging such issues as lifting evacuation orders andother protective actions and should be carefully considered. Once an ‘existing exposure situation’arises, measures should immediately be taken to transition to a ‘planned exposure situation’.
F5-4 Nuclear Emergency Exercises
Previously, nuclear emergency exercises were carried out by the national and local governments andnuclear operators, to check the effectiveness of emergency response systems in accordance with the
Nuclear Emergency Act. However, following the Fukushima Daiichi NPS accident, these exercises
are under review. Future exercises must now incorporate lessons learned from the Fukushima Daiichi
NPS accident, including the possibility of an unprecedented complex earthquake-tsunami-nuclear
accident disaster, as well as incorporating more realistic evacuation exercises. Such exercises range
from large-scale national government exercises to those carried out by nuclear operators within asingle facility. The following provides an explanation of these.
F5-4-1 Exercises Drawn up by the National Government
Hitherto, local governments have drawn up nuclear emergency exercises. The national government
provided support and coordination. Following the enactment of the Nuclear Emergency Act, forwhich the 1999 JCO criticality accident was the catalyst, the national government drew up plans andimplemented independent exercises.
The Fukushima Daiichi NPS accident marked the first time that such a nuclear emergency had been
declared in Japan, and the nuclear emergency response system, including the nuclear emergency
exercises, was put to the test. Based on this experience, the NRA is now reviewing the disaster
response system, as well as reviewing nuclear emergency exercises.
The key feature of the exercises is that they envisage severe accidents or complex disasters and areintended to test close collaboration between related ministries and agencies, through such aspects asevacuation of local citizens within the UPZ (within 30 km from the facility). These exercises will
form the basis for subsequent revisions of various plans and manuals.
F5-4-2 Exercises Based on Plans Drawn up by Nuclear Operators
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Nuclear operators conduct exercises approximately once a year, focusing on such aspects asestablishment and operation of a response headquarters, notification and liaison, and emergency
environmental radiation monitoring, in accordance with the Nuclear Operator Emergency
Preparedness Program prescribed for each site. Exercises check the effectiveness of organizations
implementing accident management. In addition, if a local government carries out a site exercise, themanagement of that site will also conduct a exercise at the same time.
F5-4-3 Exercises Drawn up by Local Governments
Even since the Fukushima Daiichi NPS accident, prefectures and municipalities have conducted theexercises stipulated in exercise plans in their Regional Disaster Prevention Plans.
These exercises simulate severe accidents and complex disasters, train participants without
providing them with the scenarios in advance, and use map exercises to improve the judgment ofparticipants.
F5-4-4 Participation in International Exercises
Japan is a Contracting Party to the Convention on Early Notification of a Nuclear Accident and theConvention on Assistance in the Case of a Nuclear Accident or Radiological Emergency. In order toensure that, pursuant to the provisions of these conventions, notification is provided without fail inan emergency, Japan consistently participates in the ConvEx exercises organized by the IAEA.
F5-5Information to the Public and Neighboring Countries
F5-5-1 Measures for Providing Public Information
To enhance information dissemination of disaster response plans for the public, local residents
participate in national and local government emergency exercises. Local authorities explain a disaster
response plan to residents, who then simulate evacuations to actual refugee facilities, and radiation
surveys are carried out.
The NISA launched its emergency information mailing service in July 2008 enabling people toregister their mobile phone e-mail address in advance and promptly receive emergency information.
This system was inherited by the NRA in September 2012 and is now called N-alert.
During a nuclear emergency, the media will provide information to local residents. Press briefings,
covered in television and radio broadcasts, will be held as required at the local off-site disasterprevention centers and at the Emergency Response Center in Tokyo
Websites will also provide emergency information to the public.
F5-5-2 Providing Information to Neighboring Countries
Japan is an island nation and shares no land borders with its immediate neighbors. However, its
geographical neighbors – China and South Korea – also have reactor facilities. Following the
Fukushima Daiichi NPS accident, sharing information during a nuclear emergency became an60

Other General Safety Provisions F
important issue for all neighboring countries and in August 2009, senior Japanese, Chinese and South
Korean regulators met and agreed to share such emergency information. The three countries had
earlier exchanged information as required, but Fukushima nuclear accident underlined the importanceof closer cooperation, and talks are currently underway to achieve such an outcome.
At a meeting of senior Japanese, Chinese and South Korean regulators in November 2011, the three
countries reached an agreement on a Nuclear Safety Cooperation Initiative, which includes
improving the exchange of information, cooperating in response to severe accidents, and cooperating
on disaster prevention and emergency responses.
F5-5-3 Response in the Event of a Nuclear Accident or Radiological Emergency in a Neighboring
Country
To implement the provisions of the Convention on Early Notification of a Nuclear Accident and theConvention on Assistance in the Case of a Nuclear Accident or Radiological Emergency, Japan has
designated the Ministry of Foreign Affairs as the National Warning Point (NWP) and National
Competent Authority for an Emergency Abroad (NCA(A)) for the event of a nuclear accident orradiological emergency occurring outside the territory of Japan. In the event of a radiologicalemergency outside Japan, including in a neighboring country, the Ministry of Foreign Affairs will
receive a notification and pass on the details without delay to the National Competent Authority for a
Domestic Emergency (NCA(D)) and other relevant authorities, and any necessary action will betaken. Moreover, in relation to the Convention on Assistance in the Case of a Nuclear Accident orRadiological Emergency, the National Assistance Capabilities (NAC) of relevant organizations within
Japan have been registered in RANET (the IAEA Response Assistance Network).

61

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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

F6-1 Human and financial resources(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 (Operational 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 operating nuclear facilities which aredescribed in 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 operting nuclear facilities which aredescribed in 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 Act requires the retention of important records such as inspection andradiation control records even at decommissioning stage.
Other records specific to decommissioning such as equipment or systems being dismantled, theschedule and method of dismantling will be registered at the end of each dismantling process.
Thus the regulatory body will be able to officially confirm the completion of the decommissioning
process.
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Safety of Spent Fuel Management G
Section G Safety of Spent Fuel Management
This section focuses on the regulations concerning spent fuel storage activity provisions in the Reactor
Regulation Act. These regulations were introduced in the 1999 revision of the Reactor Regulation Act andinvolve the storage of spent fuel outside reactor facilities before reprocessing.
The NRA formulated new regulatory requirements for nuclear fuel facilities, research reactors, and nuclear
waste disposal and storage/treatment facilities, which entered into force in December 2013. In January
2014, the licensee applied for permission to modify the then current basic facility design to comply withnew regulatory requirements and reviews to confirm that a new design complies with these requirements
are being carried out by the NRA.
The regulation of interim storage activity is carried out in accordance with the Reactor Regulation Act andthe Ordinance on Activity of Interim Storage of Spent Fuel (hereinafter referred to as the “Storage
Ordinance” (Annex: Table G1-1)) stipulated by said Act. Figure G-1 shows the regulatory flow.
In response of the Fukushima Daiichi NPS accident, the NRA designated the complex as a Specified
Nuclear Facility based on the provision of the Reactor Regulation Act of November 2012. TEPCO’s
Implementation Plan of the Measures for the Specified Reactor Facilities at Fukushima was approved by
the NRA in August 2013. The spent fuel at Fukushima Daiichi NPS will be managed in accordance withthis plan. The spent fuel assemblies currently stored in the reactor buildings will be transferred to the
Common Pool at the storage site. Transfer of the spent fuel stored in the unit 4 reactor building was started
in November 2013.

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G Safety of Spent Fuel Management

Site
Selection

Issuance of a license

Design & construction

Application for Design and Construction

Welding Inspection

Pre-service Inspection

Periodic Facility Inspection*3

Confirmation of Decommissioning
Completion*4

Decommissioning

Approval of Decommissioning Program

Periodic
Safety Review*Operation

Operational Safety Inspection*2

1

Application for Decommissioning
Completion Confirmation
Confirmation of Decommissioning
Completion*1: (1) Assessment of the implementation status of operational safety activities and assessment of the application of thelatest technical knowledge in operational safety activities: Every 10 years or less from the date of commencing
business(2) Technical assessment concerning aging degradation: Within 20 years of the date of commencing business andevery 10 years or less thereafter*2: Operational safety program compliance inspection: Conducted quarterly (4 times a year)*3: Inspection to confirm that facility capabilities comply with the technical requirements: Conducted annually*4: Physical protection program compliance inspection: Conducted regularly

Figure G-1 Regulatory Flow for the Interim Storage Activity

64

Safety of Spent Fuel Management G
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 to theminimum 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 greater thanthose permitted for the current generation;(vii) aim to avoid imposing undue burdens on future generations.
G1-1 Prevention of criticality and removal of decay heat
(1) Prevention of criticality
The NRA Ordinance on Standards for the Location, Structure, and Equipment of Spent Fuel Interim
Storage Facilities (hereinafter referred to as the “Equipment Standards Ordinance2”) and the Ordinanceon Technical Standards for the Design and Construction Methods of Spent Fuel Interim Storage
Facilities (hereinafter referred to as the “Storage Facility Design and Construction Ordinance 3 ”)
prescribe that facilities shall have a criticality-safe geometry and observe other appropriate measures toprevent criticality of spent fuel.
(2) Removal of decay heat
The Equipment Standards Ordinance and the Storage Facility Design and Construction Ordinanceprescribe that facilities must have a function of decay heat removal from the spent fuel.
G1-2 Minimization of radioactive waste
Although Japanese laws and regulations do not require that the quantity of radioactive waste be minimized,
the spent fuel interim storage facilities currently under construction will handle waste in a sealed condition,
thereby minimizing any resultant radioactive waste produced during operations.
2 See Annex: Table G1-2
3 Annex: Table G1-3

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G Safety of Spent Fuel Management

G1-3 Interdependencies between the different steps in spent fuel management
Spent fuel is generated in nuclear power plants and temporarily stored at a temporary facility at each site
before transportation to a spent fuel interim storage or reprocessing facility. When the fuel has been stored
at a spent fuel interim storage facility for a certain period, it is moved to a reprocessing facility.
The handling and storage of spent fuel in this process is governed by standardized and integrated
regulations under the Reactor Regulation Act.
G1-4 Radiation protection based on international standards
Radiation protection related to spent fuel management is as described in F4.
G1-5 Biological, chemical and other hazards that may be associated with spent fuel management
The Reactor Regulation Act requires that spent fuel interim storage facilities shall take appropriate
measures against potential events that may affect the facility, such as the leakage of radioactive material,
fire, explosion, and earthquake.
G1-6 Consideration of any adverse effects for future generations
As described in G2, there is a mechanism for ensuring the appropriate management of the operation of
spent fuel interim storage facilities and consideration is being given to measures to ensure that there is no
increased risk in the future.
G1-7 Consideration of imposing undue burdens for future generations
As described in the previous section, consideration is being given to ensuring that any undue burden is not
imposed on future generations. Separate legislation prescribes the securing of funds to cover the cost of
spent fuel reprocessing. (See Section B)

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Safety of Spent Fuel Management G

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 andto ensure that, if necessary, all reasonably practicable improvements are made to upgrade the safety ofsuch a facility.
G2-1 Reviews to enhance the safety of existing spent fuel management facilities
There was no licensee for spent fuel storage activities when this Convention took effect in Japan.
Measures required to enhance the safety of spent fuel interim storage facilities are as follows:(1)In accordance with the Reactor Regulation Act, the NRA conducts periodic inspections of thecapabilities of spent fuel interim storage facilities and of their compliance with operational safety
programs.
In addition, under the Reactor Regulation Act, licensees shall conduct: an annual inspection to confirm
that their spent fuel interim storage facilities comply with technical standards; an assessment of theimplementation status of operational safety activities and the implementation of the latest technicalknowledge in operational safety activities every 10 years or less from the date of commencing business;a technical assessment of aging within 20 years of the date of commencing operations. Licensees must
use those results to develop a 10-year plan to implement measures to preserve the integrity of saidstorage facilities.
(2) As described in K2, the Reactor Regulation Act was amended in 2012. This enabled the NRA to orderlicensees to meet revised regulatory requirements if a facility has become ‘non compliant’ – even if thecomplex in question had already been granted a license. In addition, licensees are required to ensureongoing compliance even if future changes are made in maintenance standards.

67

G Safety of Spent Fuel Management

G3

Siting of proposed facilities

Article 6
1. Each Contracting Party shall take the appropriate steps to ensure that procedures are established andimplemented 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 nothave unacceptable effects on other Contracting Parties by being sited in accordance with the generalsafety requirements of Article 4.
G3-1 Evaluation of site-related factors
The Reactor Regulation Act requires licensees to evaluate site-related factors and their impact onsafety,
and when the effectiveness of these proposals has been confirmed, the NRA grants a license.
The criteria for the license described in the Reactor Regulation Act are that “the applicant has an adequate
technical capability and financial basis to appropriately carry out the proposed activity; and the location,
structure and systems of the proposed facility do not hinder prevention measures of any radiologicaldisaster due to nuclear fuel materials or materials contaminated with nuclear fuel materials (spent fuel ormaterials contaminated with spent fuel, in the case of spent fuel interim storage facilities)”. The specificcriteria concerning technical capability and the prevention of radiological disaster are stipulated in the
Equipment Standards Ordinance and it’s interpretation and guidelines formulated by the former Nuclear
Safety Commission of Japan (Examination Guide for Technical Competence of License Holders of
Nuclear Power).
An applicant seeking a license for a spent fuel interim storage activities must include in their application
descriptions of “the type and storage capacity of spent fuel to be stored”, “the location, structure andsystems of the spent fuel interim storage facility and the storage method”, “the spent fuel facility
construction plan”, and “the method for removing spent fuel after the termination of storage.” Thedocument shall be accompanied by explanatory materials on “the conditions of meteorology, groundstructure, hydrology, seismology, social environment at the site of the proposed spent fuel interim storage
facility” and “the safety design of the spent fuel interim storage facility”. The applicant is required to use
these to evaluate the site conditions and location of the spent fuel interim storage facility.
G3-2 Information disclosure for the general public
68Safety of Spent Fuel Management G
The NRA’s policy for transparency is; to establish a comprehensive information disclosure system; toensure open discussion; and to ensure administration based on written documents. Accordingly, the NRA
publishes the agenda, minutes, and reference materials for its commission meetings, advisory committee
meetings and study team meetings.
G3-3 Relations with neighboring contracting parties
Japan is an island nation with no land links with neighboring countries and has no legal system in place
for consultations concerning the siting of nuclear installations. However, information on nuclear facilities
can be provided within the scope of Japan’s bilateral frameworks.
In particular, Japan, China and Korea have established a framework governing senior regulators meetingproviding an opportunity for information exchanges.

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G Safety of Spent Fuel Management

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 to limit
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 the decommissioningof a spent fuel management facility are taken into account;(iii) the technologies incorporated in the design and construction of a spent fuel management facility aresupported by experience, testing or analysis.
G4-1 Radiological protection methods for construction and design of SF storage facility
Pursuant to the Reactor Regulation Act, the licensee shall submit an Application for Design andConstruction Method before beginning construction of any licensed facility. The application must include
evidence demonstrating that the design and construction methods comply with the technical standards set
forth in the Storage Facility Design and Construction Ordinance. The NRA will give approval after
confirming that the design and construction methods comply with the technical standards prescribed in theReactor Regulation Act.
G4-2 Provisions for the decommissioning of a spent fuel management facility at the design stage
Procedures for the decommissioning of a spent fuel interim storage facility are prescribed in accordancewith the Reactor Regulation Act. When decommissioning a facility, the licensee shall prepare adecommissioning plan and obtain NRA approval for it.
G4-3 Technologies incorporated in the design and construction of a spent fuel management facility
Under the Reactor Regulation Act, the licensee shall demonstrate compliance with technicalstandards in submitting an Application for Approval of the Design and Construction methods which will
be approved by the NRA after it confirms compliance. There are prescribed technical standards for quality
assurance methods focused on design, construction and inspection. These are based on the requirements
contained in the Rules of Quality Assurance for Safety of Nuclear Power Plants (JEAC 4111-2009) issued
by the Japan Electric Association and also take into account the requirements in relevant IAEA Safety
Standard (Safety Requirement No. GS-R-3). Compliance with these standards is necessary for approval ofdesign and construction methods.
Spent fuel interim storage facilities must also pass an NRA Pre-service Inspection before operations canbegin. Approval will be granted if an inspector confirms that the construction has been carried out inaccordance with the approved design and construction methods and that the facility’s capabilities comply
with the technical standards. Any welded areas in a spent fuel interim storage facility must pass a welding
inspection to confirm it meets previously approved welding methods and technical standards.
70Safety of Spent Fuel Management G

G5 Assessment of the 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 the safetyassessment and of the environmental assessment shall be prepared when deemed necessary tocomplement the assessments referred to in paragraph (i).
G5-1 Safety and environmental assessment of a spent fuel management facility be for construction
The procedures described in G3-1 and G4-1 ensure that safety and environmental assessments of a spent
fuel interim storage facility are carried out before construction.

G5-2 Update of safety and environmental assessments of a spent fuel management facility
If a licensee wishes to modify the specifics of a facility for which a license has already been granted, even
if the facility is not yet in use, they must follow the procedures prescribed in the Reactor Regulation Act toobtain permission for this modification.

71

G Safety of Spent Fuel Management

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 the results
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 theregulatory body.
G6-1 Permission to operate a spent fuel management facility
As described in G4-3.

G6-2 Operational limits and conditions
A licensee shall establish an Operational Safety Program in accordance with the Reactor Regulation Act
and obtain the NRA’s approval before starting operations. The Program shall specify the precise
operational methods of the facility, maintenance checks, radiation monitoring, and quality assurance.
Licensees shall stipulate specific limits in the Operational Safety Program, and must operate and maintainthe facility in accordance with these. Licensees shall undergo quarterly NRA inspections (Operational
Safety Inspections) to ensure compliance with their Operational Safety Program. If, the licensee’s
maintenance measures are found to violate Storage Ordinance or if the annual Periodic Facility Inspection
reveals that a facility does not comply with the technical standards prescribed in the NRA Ordinance
Prescribing Technical Standards for the Capabilities of Spent Fuel Interim Storage Facilities, the NRA
may order the licensee to take the necessary steps to ensure operational safety. This may include
suspension of operation, modification, repair, or compliance with a specified method of operating
equipment. (Annex: Table G6-1 details the matters to be specified in the operational safety program)72

Safety of Spent Fuel Management G

G6-3 Operation, maintenance, monitoring, inspection and testing of a spent fuel management facility
During operations a licensee shall implement the necessary safety measures for “maintenance of a spent
fuel interim storage facility”, “operation of a spent fuel interim storage facility “ and “transportation of
spent fuel or transportation, storage and disposal of materials contaminated with spent fuel” in accordancewith the provisions of the Reactor Regulation Act. There are legal provisions concerning operationalsafety measures in the following areas: “restrictions on access to controlled areas”, “measures concerning
radiation dose”, “walkdown and inspection of spent fuel interim storage facilities”, “periodical
self-inspection of spent fuel interim storage facilities”, “operation of spent fuel interim storage facilities”,“on-site transportation”, “on-site waste management”, and “Periodical Safety Review of spent fuel interim
storage facilities”.
Operators shall establish an Operational Safety Program covering these matters and obtain NRA approval
before starting operations.
In addition, as described in the previous section, licensees shall undergo periodic NRA Operational Safety
Inspections to confirm compliance with their Operational Safety Program.

G6-4 Measures for ensuring that engineering and technical support in all safety-related fields is available
during operation of a spent fuel management facility
When engineering or technical support is necessary to ensure the safety of a facility, licensees can, at theirown discretion, receive support from academic societies and other private sector organizations andexperts.
When a licensee outsources technical operational and management to a specialist contractor, it is vital thatsaid contractor has the requisite capabilities to ensure a facility’s safety. Accordingly, licensees mustclosely monitor and manage contractors in accordance with their Operational Safety Program. The NRA
checks their performance in this regard via Operational Safety Inspections and other measures.
G6-5 Timely licensee reports to the regulatory body on safety-related events
In the case of personal injury accidents (including incidents with the potential for personal injury) or a
failure or other events at a nuclear installation, the licensee shall report this and other related matters to the
NRA without delay, in accordance with the Reactor Regulation Act.
G6-6 Programs to collect and analyze relevant operating experience
In the case of a personal injury accident or a failure or other incidents, the licensee shall immediately
report these to the NRA in accordance with the Reactor Regulation Act. The NRA will immediately
publish the details and ascertain the licensee’s response. It will also publish details of the root cause andmeasures to be taken to prevent any recurrence once these have been determined.
After expert advice in operational management, inspections, and radiation controll, the NRA assesses the73G Safety of Spent Fuel Management
cause of any accident or failure to identify safety lessons. If necessary, it requests licensees to implement
measures to prevent a recurrence and/or reflects these lessons in its own regulatory activities.
G6-7 Development and revision of decommissioning plans for spent fuel management facilities based on
the information during operation
A licensee planning to halt activities shall implement the necessary decommissioning measures, such as
dismantling the spent fuel interim storage facility, decontamination, and disposal of contaminated spent
fuel materials, in accordance with the Reactor Regulation Act. To this end, licensees must establish adecommissioning plan and obtain NRA approval.
The criteria for approving a decommissioning plan are that all spent fuel has been removed from the spent
fuel interim storage facility; materials contaminated with spent fuel are appropriately managed, treated,and disposed of; and a decommissioning plan is appropriate to prevent hazards arising from materials
contaminated with spent fuel. Information obtained during a facility’s operation should be used for the
management and disposal of contaminated material and for hazard prevention. In addition, to allow
revision of the program as necessary, procedure of the Approval for Modification of Decommissioning
Plan has been prescribed in the Reactor Regulation Act.

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Safety of Radioactive Waste Management H
Section H Safety of Radioactive Waste Management
This section focuses primarily on provisions in the Reactor Regulation Act concerning radioactive
waste storage/treatment and disposal.
The burial of radioactive waste is classified as either Category 1 Waste Disposal or Category 2 Waste
Disposal, in accordance with the Reactor Regulation Act. It is governed by the Ordinance on Activityof Category 1 Waste Disposal of Nuclear Fuel Material and Materials Contaminated by Nuclear Fuel
Material (hereinafter referred to as the “Category 1 Waste Disposal Ordinance”) and the Ordinance on
Activity of Category 2 Waste Disposal of Nuclear Fuel Material and Materials Contaminated by
Nuclear Fuel Material (hereinafter referred to as the “Category 2 Waste Disposal Ordinance” (Annex:
Table H1-1)), respectively, under this Act. Figure H-1 shows the regulatory flow for Category 1 andCategory 2 Waste Disposal.
Category 1 Waste Disposal requires greater radiological safety care. Such waste contains highradioactivity concentrations with long half-life nuclides and because of this the waste must be isolated
from living environments for a long period. Therefore, in addition to regulation governing Category 2
Waste Disposal described below, the approval of the closure plan and procedures to check conformity
with the approved closure plan are also stipulated to ensure the proper closure of undergroundfacilities.
Category 2 Waste Disposal regulations apply to radioactive materials in solid waste radioactive
material which has a radioactivity concentration below the upper limit specified in the Order for
Enforcement of the Reactor Regulation Act. It is buried by Intermediate Depth Disposal, Near-surface
Pit Disposal, or Near-surface Trench Disposal, depending on the nuclides present in the radioactive
materials and the radioactivity concentration thereof. Consideration is given to radioactive decay inconservation and management of such waste.
Waste management other than final disposal is defined as the Interim Storage/Treatment Business ofRadioactive waste in the Reactor Regulation Act. It is governed by the Reactor Regulation Act andregulations in the Ordinance on Activity of Waste Interim Storage/Treatment of Nuclear Fuel Materialand Materials Contaminated by Nuclear Fuel Material (Annex: Table H1-2) under this Act.
At present, final waste disposal from research facilities is planned by means of either Near-surface Pit
Disposal or Near-surface Trench Disposal, as part of the first stage of operations.
Rubble and other waste from the accident at TEPCO’s Fukushima Daiichi NPS is stored at the power
station site.

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H Safety of Spent Fuel Management
Category 2 Waste Disposal (otherthan geological disposal)

Issuance ofa license

Issuance ofa license

Basic
DesignCategory 1 Waste Disposal(geological disposal)

Approval of Design andConstruction

Confirmation of
Disposal Facility

Facility Periodic
Inspection*7

Approval of Closure
programConfirmation of Disposal
Facility*3

Confirmation of Waste
Package*4
Confirmation of Disposal
Facility*5
Operational S afety
Inspection*6
Physical Protection
Inspection(only for intermediate
depth disposal)

2

Confirmation of
ClosureConfirmation of
Decommissioning

Decommissioning

Approval of
Decommissioning
ProgramApproval of
Decommissioning
ProgramOperational Safety
Inspection
Confirmation of
Decommissioning*1: Assessment of the radiation control due to nuclear fuel material, etc.: Every 20 years or less after being granted alicense, or when seeking to establish a closure plan or decommissioning plan
*2: Assessment of the radiation control due to nuclear fuel material, etc.: Every 10 years or less from the date ofcommencing business*3: Check to ensure that the facility complies with technical standards before emplacing the waste packages: Corresponds
to items 2, 3, and 7 in Article 6, paragraph 1 of the Category 2 Waste Disposal Ordinance*4: Check to ensure that the waste packages to be buried and the measures for their operational safety comply withtechnical standards: When burying the waste packages*5: Check to ensure that the facility complies with technical standards after emplacing the waste packages: Corresponds toitems 1, 4, 5, 6, and 7 in Article 6, paragraph 1 of the Category 2 Waste Disposal Ordinance*6: Operational safety program compliance inspection: Conducted quarterly (4 times a year)*7: Inspection to confirm that facility capabilities comply with the technical requirements: Conducted annually

Figure H-1 Regulatory Processes for Category 1 and Category 2 Waste Disposal

76

Periodic Safety Review*

Physical Protection
Inspection

Backfill of
Shafts and Tunnels

Periodic Safety Review*1

Operational Safety
Inspection*6

Operation

Confirmation of Waste
Package*4

Construction

Pre-service InspectionSafety of Radioactive Waste Management H

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 radiological andother 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 with radioactive
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 decay heat(1)Prevention of criticality
The Reactor Regulation Act requires operators to take steps to prevent possible criticality of thenuclear fuel material in the radioactive waste that they are handling. Currently, radioactive materials
handled at waste disposal facilities and waste interim storage/treatment facilities in Japan contains
hardly any nuclear fuel material, so there is no possibility of its reaching criticality.

(2)Removal of decay heat
The law requires that operators take appropriate steps to remove heat from radioactive waste
capable of producing decay heat.
Specifically, operators of facilities that temporarily store highly-radioactive vitrified packages
returned from overseas for reprocessing are required to apply appropriate methods for removing
decay heat, as part of the safe design of facilities.

H1-2 Minimization of the generation of radioactive waste77

H Safety of Spent Fuel Management
Although Japanese laws and regulations do not require that the quantity of radioactive waste beminimized, the Reactor Regulation Act requires that radioactive waste be rigorously and safely
managed. Operators conduct voluntary initiatives to minimize the quantity of such waste and in sodoing reduce the resources required for its management.
Under the clearance system that has been established, operators seek the Approval of Methods onRadioactivity Concentration Measurement and Evaluation for concrete, metals, and other materials
generated from the nuclear installation in question, pursuant to the provisions of the Reactor
Regulation Act. Material with a radioactivity concentration below the reference value does not need
to be handled as radioactive waste. This system produces an accurate classification of radioactive
waste and assists minimization of the generation of radioactive waste.

H1-3 Interdependencies among the different steps in radioactive waste management
The processes involved in the management of radioactive waste are governed by standardized andintegrated regulations under the Reactor Regulation Act.

H1-4 Radiation protection based on international standards
Radiation protection associated with the management of radioactive waste is described in F4.

H1-5 Biological, chemical and other hazards that may be associated with radioactive waste
management
Under the Reactor Regulation Act, operators are required to evaluate the issue of buried waste
packages, ensuring that they do not contain substances that could destroy their integrity.
A similar system has been put into place under the Act concerning Prevention from Radiation
Hazards due to Radioisotopes, etc.(Radiation Hazards Prevention Act).

H1-6 Consideration of adverse effects for future generations
As described in H2, Waste Interim Storage/Treatment and Waste Disposal Businesses that are alreadylicensed have mechanisms to ensure appropriate management. Buried radioactive waste is either
managed until it reaches a dose low enough to ensure that radiation exposure control is no longer
required or is isolated from living environments. This ensures that its impact does not increase in the
future.

H1-7 Consideration of undue burdens for future generations
78

Safety of Radioactive Waste Management H
As described in the previous section, consideration is given to ensure that undue burden is not
imposed on future generations. Separate legal provisions have been established concerning
expenditure associated with the disposal of vitrified packages and some radioactive waste with anextremely high concentration of radioactivity, as well as the management thereof (See Section B).

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H Safety of Spent Fuel Management

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 Reviews to enhance the safety of existing radioactive waste management facilities
When this Convention took effect in Japan, the existing operators were the Near-surface Pit Disposal,
Near-surface Trench Disposal which have Category 2 Waste Disposal licenses and Waste Interim
Storage/Treatment operators. Currently, there is no Category 1 Waste Disposal operator or Category 2
Waste Disposal operator conducting Intermediate Depth Disposal. When such businesses are licensed,
measures may be required to enhance the safety of facilities.
Similar to the inspections of spent fuel interim storage facilities described in G2.1, the NRA conducts
periodic inspections of radioactive waste interim storage/treatment facilities and their compliancewith Operational Safety Programs. It also requires operators to conduct their own periodic safety
reviews.
In addition to Operational Safety Inspections, the following inspections are prescribed for eachcategory of waste disposal facility.
(1) Category 1 Waste Disposal
Operators shall assess waste disposal sites every 20 years or less from the date of commencing
business, evaluating the control of exposure to radiation due to disposed waste, taking into accountthe latest technical knowledge. Based on this review, they shall take requisite steps to maintain the
integrity of the waste disposal facility. They must take the same steps when establishing closure ordecommissioning plans.

(2)Category 2 Waste Disposal
Under legislative revisions enacted in December 2013, the periodic reviews that hitherto applied
only to Intermediate Depth Disposal were also introduced for Near-surface Pit Disposal and80

Safety of Radioactive Waste Management H
Near-surface Trench Disposal. Operators must assess waste disposal sites that use these methods
every 10 years or less from the date of commencing business, evaluating the control of exposure toradiation from disposed waste, taking into account the latest technical knowledge. Based on such
reviews, they shall take the requisite steps to maintain the integrity of the waste disposal facility.
They shall take the same steps when seeking to alter operational safety measures at Category 2
Waste Disposal facilities, in response to radioactive decay.

H2-2 Past Activities
There are no past activities.

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H Safety of Spent Fuel Management

H3

Siting of proposed facilities

Article 13
1. Each Contracting Party shall take the appropriate steps to ensure that procedures are established andimplemented 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 the 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 nothave unacceptable effects on other Contracting Parties by being sited in accordance with the general safety
requirements of Article 11.

H3-1 Evaluation of site-related factors
The Reactor Regulation Act requires operators to evaluate site-related factors and their impact onsafety, and the NRA checks the adequacy of these evaluations when considering whether to grant alicense.
The licensing criteria prescribed in the Reactor Regulation Act are the same as those for spent fuelinterim storage facilities described in G3-1.

H3-2 Information disclosure for the general public
The NRA’s transparency policy is; to establish an information disclosure system; to ensure open
discussion and administration based on written documents. Accordingly, the NRA publishes theagenda, minutes, and reference materials of commission meetings, advisory committee meetings andstudy team meetings.

H3-3 Relations with neighboring contracting parties
This is the same as for spent fuel interim storage facilities, as described in G3-3.

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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 are taken
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 effects in the design and construction of nuclear waste management
facilities(1) Waste Interim Storage/Treatment facilities
In accordance with the Reactor Regulation Act, before beginning construction work, a waste
interim storage/treatment licensee shall obtain approval for the design and construction methods ofthe waste receiving facility, waste handling facility, instrument and control facility, radiation
control facility and emergency power equipment and disposal facilities of auxiliary facilities at
waste interim storage/treatment site and pass an NRA inspection before operations start. An
Application of the Approval of Design and Construction Method will includes the design offacilities for the treatment and storage of waste generated from its operation and construction
method of such facilities. The application will also include documentary proof that the facility
design and construction method conforms to the Technical Standard for the Design andConstruction Methods for Specific Waste Disposal Facility or Specific Waste Interim
Storage/Treatment Facility (Annex: Table H4-1).
The NRA will approve the application after confirming that the design and construction methods
comply with the technical standards prescribed in the Reactor Regulation Act.

(2) Category 1 Waste Disposal facilities
Under the Reactor Regulation Act, before beginning construction work, Category 1 Waste Disposal
licensees shall obtain approval for the design and construction methods of waste receiving facility,83

H Safety of Spent Fuel Management
waste handling facility, instrument and control facility, radiation control facility and emergency
power equipment and disposal facilities of auxiliary facilities at waste disposal site and pass an
NRA inspection before operations start. The procedures and technical standards for design andconstruction methods are the same as those for waste interim storage/treatment facilities.
Category 1 Waste Disposal facilities shall undergo an NRA check of the site and its shafts andtunnels, in accordance with the Reactor Regulation Act. This check focuses not only on the designand structure, but also on the geographical, geological, and groundwater conditions of disposal sitein accordance with the Category 1 Waste Disposal Ordinance. That is, the facility must be consistent
with the content described in the application document that formed the basis for the license andlicensees do not dispose of explosive materials, materials that significantly corrode other materials,
or other hazardous materials at the waste disposal site and licensees backfill the site as stated in theapplication document that formed the basis for the license. The waste packages to be disposed ofmust be checked by the NRA before burial, to ensure that “the waste is encapsulated or solidified”,“the radioactivity concentration does not exceed the licensed level”, “the waste package has
sufficient strength to endure the loads imposed when disposed of” and “the waste is not significantly
damaged”, in accordance with the Category 1 Waste Disposal Ordinance.

(3) Category 2 Waste Disposal facilities
Category 2 Waste Disposal licensees do not need to obtain NRA Approval for Design andConstruction Methods or undergo a pre-service inspection of their waste disposal facilities, but theyshall undergo an NRA check of the facility in accordance with the Reactor Regulation Act. The
waste packages to be disposed of must also undergo an NRA check before disposal.

(4) Waste management facility under the Radiation Hazards Prevention Act
Those seeking approval for a waste disposal business under the Radiation Hazards Prevention Act
shall submit an application to the NRA. It must include information explaining the method of
disposal, and the location, structure and equipment of the waste refilling facility, waste storage
facility, and waste disposal facility. The location, structure and equipment of each facility e.g.
shielding wall or other shielding material, ventilation, drainage, shall conform with specified
technical standards to minimize radiation consequence. Licensees shall undergo a pre-service
facility inspection and a check to ensure that the facility complies with required technical standards.

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Safety of Radioactive Waste Management H
H4-2 Provisions for the decommissioning of a radioactive waste management facility other than adisposal facility at the design stage
Procedures for the decommissioning of waste management facilities are prescribed in the Reactor
Regulation Act. When decommissioning a facility, the licensee must prepare a decommissioning planand obtain NRA approval.
In addition, under the Radiation Hazards Prevention Act, at each individual license application(including decommissioning), the licensee is subject to appropriate checks to ensure conformity to
the required technical standards.

H4-3 Provisions for the closure of a disposal facility
The proposed closure of a waste disposal facility shall be described in a waste disposal license
application document. If a Category 1 Waste Disposal licensee plans to close the shafts and tunnels,
he is required to establish a closure plan and obtain NRA approval in accordance with the Reactor
Regulation Act.

H4-4 Technologies incorporated in the design and construction of a radioactive waste management
facility
As described in H6-1. Similar checks are also conducted under the Radiation Hazards Prevention
Act.

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H5

Safety assessment 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 andan 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) Disposal facility under the Reactor Regulation Act
The procedures described in H3-1 and H4-1 ensure that safety and environmental assessments of aradioactive waste management facility are carried out before construction.

(2) Disposal facility under the Radiation Hazards Prevention Act
When a license application for a disposal facility under the Radiation Hazards Prevention Act isreceived, the NRA examines the site conditions and compliance with technical standards, granting alicense if these are met. Guidelines require that a facility must be constructed at a site that has little
fear of being affected by a landslide or flooding, adopt fire-proof structures or use non-combustible
materials for the essential parts of the facility and be equipped with a shielding function, such as
shielding walls.

H5-2 Safety and environmental assessment for the period after closure of a disposal facility
Regulation of disposal facilities in Japan is governed by either the Category 1 Waste Disposal
Ordinance or the Category 2 Waste Disposal Ordinance, depending on the category of the facility, in
accordance with the Reactor Regulation Act. These Ordinances require that a license application beaccompanied by an explanation concerning the control of radiation exposure due to radioactive waste.
It must also contain a long-term assessment that includes the post-closure period. Licensees shallconduct ongoing periodic safety reviews as part of operational safety measures and implement any
required changes. These safety reviews ensure that systematic safety evaluations continue to be86

Safety of Radioactive Waste Management H
carried out until post-closure operations have been completed,and also ensure that the

pre-construction review is checked in light of the latest knowledge and appropriate action is taken in
response.
A similar system is being put into place under the Radiation Hazards Prevention Act.

H5-3 Update of safety and environmental assessment of a radioactive waste management facility
This is the same as for spent fuel interim storage facilities, as described in G5-2.
A similar system has been put into place under the Radiation Hazards Prevention Act.

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H6

Operation of facilities

Article 16
Each Contracting Party shall take the appropriate steps to ensure that:(i)the licence 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 licence to theregulatory body;(vii) programmes to collect and analyse relevant operating experience are established and that the results
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 lifetime ofthat 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 Interim Storage/Treatment and Category 1 Waste Disposal
Before beginning construction, licensees of Waste Interim Storage/Treatment and licensees ofCategory 1 Waste Disposal shall obtain NRA approval for design and construction methods, quality
control methods concerning design and construction, and an inspection regime.
Under the Reactor Regulation Act, when applying for approval of the design and construction
methods, the licensee shall demonstrate that they comply with the required technical standards. The
NRA gives approval if the design and construction methods comply with the technical standards.
There are prescribed technical standards for quality assurance methods focused on design andconstruction and organizations for the inspection thereof. These are based on requirements in the88Safety of Radioactive Waste Management H
Code of Quality Assurance for Safety of Nuclear Power Plants (JEAC 4111-2009) issued by theJapan Electric Association and also take into account overseas standards requirements, including the
IAEA Safety Standard (Safety Requirement No. GS-R-3). Compliance with these standards is arequirement for approval of the design and construction methods.
The Reactor Regulation Act prescribes that such facilities must pass an NRA inspection before
operations commence. A facility will pass the Pre-service Inspection if the inspector confirms thatthe construction has been carried out in accordance with the approved design and construction
methods and that the facility’s capabilities comply with the technical standards for performance.
These are prescribed by the NRA and major elements include are the prevention of damage due tofire, earthquake and other calamities.
Underground facilities other than underground associated facilities at Category 1 Waste Disposal
facilities undergo the same NRA checks as the Category 2 Waste Disposal facilities described in thenext paragraph.

(2) Category 2 Waste Disposal
Category 2 Waste Disposal requires no approval for the design and construction methods, so no
Pre-service Inspection is required. However, such waste disposal facilities must undergo an NRA
check in accordance with the Reactor Regulation Act. These checks take place as follows:･The structure of the waste disposal facility, apart from the radiation control facility, is checked
when the dimensions of the major elements of individual systems can be measured.
･The structure of the radiation control facility is checked when the facility has been completed.
･The closure of shafts and tunnels (in the case of Intermediate Depth Disposal facilities) is checked
when backfill of the shafts and tunnels and closure of the mouth are carried out.
･Other matters are checked when the waste disposal facility is buried or when the NRA otherwise
deems it appropriate.
These checks are carried out in accordance with the technical standards shown in Table H6-1 in the
Annex (1. Technical Standard for Waste Disposal Facilities and 2. Technical Standard for Radioactive
Waste to be disposed of).

(3) Radioactive waste management under the Radiation Hazards Prevention Act
Operators of waste management facilities under the Radiation Hazards Prevention Act are subject tolicense approval, mainly as described in the previous section. In addition, licensees must not operate
the facility unless it has passed a inspection before operations commence.
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As described above, the Government of Japan takes steps to ensure that a license to operate a waste
disposal facility or waste interim storage facility is based upon appropriate assessments as specified
in the previous Article and is conditional on the completion of a commissioning program
demonstrating that the facility, as constructed, is consistent with design and safety requirements.

H6-2 Operational limits and conditions
Licensees shall establish an Operational Safety Program in accordance with the Reactor Regulation
Act and obtain NRA approval before starting facility operations. The Operational Safety Program
shall specify the precise methods to be used in operating the facility, maintenance checks, radiation
monitoring, and quality assurance. Licensees shall stipulate the specific operational limits in the
Operational Safety Program, and must operate and maintain the facility in accordance with these.
Licensees must undergo quarterly NRA’s Operational Safety Inspections to confirm compliance with
their Operational Safety Program. In addition, if the annual Periodic Facility Inspection indicates thata Waste Interim Storage/Treatment facility or Category 1 Waste Disposal facility does not comply
with the statutory technical standards, or the measures concerning its maintenance violate the NRA
Ordinance, the NRA may order the licensee to take steps necessary to ensure operational safety,
including suspension of operation, modification, repair, or compliance with a specified method of
operating equipment.
Before starting operations, disposal operators licensed under the Radiation Hazards Prevention Act
shall prepare Rules for Preventing Radiation Hazards, specifying details of inspections, radiation
measurement, and treatment of radioactive waste, and shall notify the NRA of these rules. Licensees
shall stipulate the specific operational limits in the Rules for Preventing Radiation Hazards, and shall
operate and maintain the facility in accordance with these.

H6-3 Operation, maintenance, monitoring, inspection and testing of a radioactive waste management
facility(1) Waste Interim Storage/Treatment
When operating a facility, the licensee shall implement the necessary operational safety measuresfor “maintenance of a Waste Interim Storage/Treatment facility”, “operation of a Waste Interim
Storage/Treatment facility” and “transportation and treatment (within the premises where the Waste
Interim Storage/Treatment facility has been installed) of nuclear fuel material or materials
contaminated with nuclear fuel material” in accordance with the provisions of the Reactor
Regulation Act. There are legal provisions concerning operational safety measures in the following
90Safety of Radioactive Waste Management H
areas: “records of radiation control, (records of monitoring results)”, “restrictions on access tocontrolled areas”, “measures concerning radiation dose”, “walkdown and inspection of Waste
Interim Storage/Treatment facilities”, “maintenance of Waste Interim Storage/Treatment facilities”,“periodical self-inspection of Waste Interim Storage/Treatment facilities”, “operation of facilities
associated with Waste Interim Storage/Treatment facilities”, “Periodical Safety Review of Waste
Interim Storage/Treatment facilities”, “on-site transportation” and “on-site disposal”.
Licensees shall establish an Operational Safety Program that covers these matters and obtain NRA
approval for this before starting operations. (Annex: Table H6-2 details the matters to be specified in
the Operational Safety Program.)
In addition, as described in the previous section, licensees shall undergo periodic Operational Safety
Inspections by the NRA to confirm compliance with their Operational Safety Program.

(2) Category 1 and 2 Waste Disposal
The Reactor Regulation Act requires licensees of a waste disposal facility to take the same steps as
described above concerning waste interim storage/treatment facilities. Relevant legislationprescribes periodic evaluation of waste disposal facilities following any closure of such a facility.
Specifically, operators are required to evaluate radiation control from nuclear fuel material inaccordance with the latest technical knowledge available and to maintain the waste disposal facilityon the basis of this evaluation. In the case of Category 1 Waste Disposal, this is to be carried out
every 20 years or less from the date of obtaining a license and when establishing a closure plan ordecommissioning plan. For Category 2 Waste Disposal, this shall be done every 10 years or lessfrom the date of obtaining a license, and when seeking to alter the operational safety measures at
Category 2 waste disposal facilities, in response to radioactive decay.

(3) Radioactive waste management under the Radiation Hazards Prevention Act
Before starting operations, waste disposal operators licensed under the Radiation Hazards
Prevention Act shall notify the NRA of the Rules for Preventing Radiation Hazards. Periodic facility
inspections and on-site NRA inspections check that the radioactive waste management facility is
being operated appropriately.

H6-4 Engineering and technical support in all safety-related fields
This is the same as for spent fuel interim storage facilities, as described in G6-4.

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H6-5 Characterization and classification of radioactive waste
The Reactor Regulation Act regulates on-site waste treatment, categorizing waste as either gaseous,liquid or solid waste, and prescribing methods for on-site treatment of these various categories.
Examples of these regulations are shown in Annex: Table H6-3.
In addition, methods involving disposal by burial are categorized into Category 1 waste disposal andCategory 2 waste disposal, according to the concentration of each radionuclide in the waste, as
stipulated in the Order for Enforcement of the Reactor Regulation Act.
A similar system has already been put in place under the Radiation Hazards Prevention Act for waste
not subject to disposal by burial, and a system targeting waste subject to burial is currently being
developed.

H6-6 Timely licensee reports to the regulatory body on the safety-related events
If a personal injury accident (including incidents with the potential for personal injury) or a failure orother events occur at a nuclear installation, the licensee shall report the situation and other necessary
matters to the NRA without delay, in accordance with the Reactor Regulation Act. Such incidents
subject to reporting are specified in relevant legislation regulating the activity concerned.
The Radiation Hazards Prevention Act also requires operators to report to the regulatory bodywithout delay the details of any accidents at a radioactive waste management facility and any
subsequent measures taken.

H6-7 Programs to collect and analyze relevant operating experience
This is the same as for spent fuel interim storage facilities described in G6-6.

H6-8 Decommissioning plans for a radioactive waste management facility other than a disposal
facility
An operator licensed under the Reactor Regulation Act that plans to terminate its operation shall
implement the necessary decommissioning measures, such as dismantling the waste management
facility, removal of contamination from nuclear fuel material, and disposal of contaminated nuclear
fuel materials, in accordance with the Reactor Regulation Act. In this regard, operators shall establish
a decommissioning plan and obtain NRA approval.
Criteria to approve a decommissioning plan are that all solid nuclear fuel material being managed or
all liquid or solid nuclear fuel material being disposed of have been removed from the waste
management facility; nuclear fuel material is appropriately managed, treated, and disposed of; and92

Safety of Radioactive Waste Management H
decommissioning work is implemented to prevent hazards arising from nuclear fuel materials.
Information obtained during the operation of a facility to be decommissioned should be incorporated
into a decommissioning plan and utilized in the management and disposal of contaminated material
and for hazard prevention. The Approval for Modification of Decommissioning Plan procedure has
been prescribed to allow decommissioning plans to be updated when necessary. When terminating its
activity, the operator of a radioactive waste management facility licensed under the Radiation
Hazards Prevention Act shall notify the NRA. The operator shall take steps including the removal ofradioactive isotope contamination, and must use information gained during the operation of the
facility to prepare an action plan for this. The operator shall then report to the NRA the plan and steps
to be taken and the regulatory body will be involved where appropriate.

H6-9 Plans for the closure of a disposal facility
When a Category 1 waste disposal licensee plans to close the tunnels and shafts, it shall take closure
measures, including backfill of tunnels and shafts, closure of entrances, and dismantling of associatedfacilities underground. In this regard, operators shall first establish a closure plan and obtain NRA
approval for it, in accordance with the Reactor Regulation Act.
A closure plan shall ensure that closure activities are carried out in accordance with the license
application documents and the Reactor Regulation Act. Closure work shall ensure the prevention of
any hazards from nuclear fuel materials. Operational experience should be used in preparing aclosure plan and to bolster hazard prevention. The Approval for Modification of Closure Planprocedure has been prescribed to allow closure plans to be updated when necessary. Closure plans are
subject to examination and approval by the regulatory body.
An operator of a radioactive waste disposal facility licensed under the Radiation Hazards Prevention
Act shall implement the necessary measures to prevent radiation hazards from buried waste whenterminating the facility’s operation. The operator shall incorporate information gained during themanagement of the facility to prepare an action plan and then report to the NRA all steps to be taken.
The regulatory body will become involved where appropriate.

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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 Preservation of the requisite records(1) Category 1 Waste Disposal
Disposal operators shall preserve on-site and for a specified period the following records inaccordance with the Reactor Regulation Act.
･Records of the disposal of Category 1 waste･Records of inspections of waste receiving facility, waste handling facility, instrument and control
facility, radiation control facility and emergency power equipment and disposal facilities ofauxiliary facilities at waste disposal site
･Radiation control records･Operations records･Maintenance records･Records of accidents at the waste disposal facility･Meteorological records･Records of groundwater levels･Records of operational safety education･Documents concerning the quality assurance plan and records of planning, implementation,
evaluation, and improvement conducted in accordance with said plan･Results of periodic assessment of the waste disposal facility･Records of physical protection measures･Results of closure checks･Methods and timing of decommissioning, and names of associated facilities at the waste disposalsite to be decommissioned･Records of materials subject to clearance confirmation

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Safety of Radioactive Waste Management H(2) Category 2 Waste Disposal
As is the case for Category 1 Waste Disposal, operators shall preserve on-site and for a specified
period the following waste disposal records in accordance with the Reactor Regulation Act.
･Records of the disposal of Category 2 waste･Radiation control records･Details of alarms from alarm devices･Maintenance records･Records of accidents･Rainfall records･Records of groundwater levels･Condition of the waste disposal site and surrounding area
･Records of operational safety education･Documents concerning the quality assurance plan and records of planning, implementation,
evaluation, and improvement conducted in accordance with said plan･Results of periodic assessment of the waste disposal facility･Records of physical protection measures･Methods and timing of decommissioning, and names of associated facilities at the waste disposalsite to be decommissioned･Records of materials subject to clearance confirmation

H7-2 Active or passive institutional controls for monitoring and access control(1) Category 1 Waste Disposal
The Reactor Regulation Act prescribes the decommissioning procedures (dismantling of associatedfacilities at the waste disposal site, removal of contamination due to nuclear fuel materials, transfer
of nuclear fuel materials and other radioactive materials, and transfer of radiation control records toan organization designated by the NRA) to be implemented after closure of a Category 1 Waste
Disposal facility. Operators intending to carry out decommissioning measures shall obtain NRA
approval for their decommissioning plan. When establishing a decommissioning plan, operators are
required to evaluate radiation exposure control due to nuclear fuel materials taking into account thelatest technical knowledge and to maintain the waste disposal facility on the basis of the results ofthis evaluation.
The activity terminates when it is confirmed that no radiation hazard prevention measures are
required at the site of associated facilities to be decommissioned, as well as for facilities remaining95

H Safety of Spent Fuel Management
at the site; that disposal of nuclear fuel materials has been completed; and that transfer of radiation
control records to an organization designated by the NRA has been completed.
Institutional control of a closed facility must contribute to further reducing the possibility of
inadvertent interference with waste or other human activities, and to the promotion of public
acceptance of geological disposal and safety.
As an example of a specific institutional control, the Final Disposal Act designates the released site
as a protected area upon application by the operator and restricts excavation work within said area.

(2)Category 2 Waste Disposal
The NRA Ordinance Prescribing Standards for the Location, Structure, and Equipment of Category
2 Waste Disposal Facilities (hereinafter referred to as the “Category 2 Equipment Standards
Ordinance”) requires that operators conduct a safety evaluation after active control ends, including
an assessment of the potential radiation dose which the public may experience in two different
scenarios: possible and less likely situations. The Ordinance stipulates that the annual dose in eachscenario must not exceed 10 microsieverts and 300 microsieverts, respectively; in addition, in thenatural phenomenon scenario and human intrusion scenario, the annual dose received by the publicmust not exceed 1 millisievert, giving due consideration to site conditions. To ensure that the publicwould be exposed to the lowest achievable level, operators must manage waste disposal sites
commensurate with the type and radioactivity level of radioactive solid waste buried there until
levels no longer pose a threat to safety.
The management required under the Category 2 Equipment Standards Ordinance is as follows.
(i) Near-surface Pit Disposal4<From receipt of the radioactive waste to be buried until burial ends>
During this period, a Surrounding Monitored Area shall be established around the waste disposal
facility and access to it restricted. A disposal conservation area shall also be established subject topatrols and inspections. Monitoring will ensure that there is no leakage of radioactive materials
from the engineered barriers5 constructed at the waste disposal site. If any such leakage is
discovered, requisite measures such as repairing the engineered barriers shall be undertaken.

<From the end of burial until the start of decommissioning>
During this period, a Surrounding Monitored Area shall be established and access to this area
4

“Near-surface pit disposal” means the disposal of radioactive waste, which has been placed in containers or solidified, inthe near-surface repository of a waste disposal site equipped with an engineered barrier.
5“Engineered barrier” means an engineered structure which is installed to prevent or to reduce the leakage of radioactive
material from buried radioactive solid waste into the living environment..

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restricted, but this area may be abolished if the radiation levels potentially affecting the generalpublic has been redacted to acceptable levels by radioactive decay. If the Monitored Area isabolished, farming and other specified activities shall be prohibited or restricted in any
neighboring disposal conservation areas which will be policed by walkdown and inspections.
Any radioactive material leaking from the waste disposal site into the living environment shall bemonitored by measuring the concentration of radioactive material in groundwater and otherparameters.

(ii) Near-surface trench disposal6<From receipt of radioactive waste to be buried until the procedure is completed
During this period, a Surrounding Monitored Area shall be established around the waste disposal
facility and access restricted. A disposal conservation area shall also be established which shall be
subject to patrols and inspections. The concentration of radioactive material seeping into
surrounding areas shall be monitored by measuring the concentration of radioactive material ingroundwater and other parameters.

<From the end of burial until the start of decommissioning>
During this period, a disposal conservation area shall be established and patrols and inspections
conducted there. Farming and other specified activities shall be prohibited or restricted in saidarea.
Consequently, safety assessments of waste disposal facilities during the active control period
should be tailored to the nature of the waste management, as described above, taking into accountany decrease in effectiveness over time of the waste disposal site systems. .
Active control of pit disposal sites should be terminated within 300-400 years of burial. In thecase of trench disposal, it should be terminated within 50 years, as the buried waste is
non-solidified concrete with a low level of radioactivity.

H7-3 Intervention measures
When issuing a license, the NRA requires the operator to take the following measures during eachstage of institutional control.
If a leakage of radioactive material from engineered barriers is detected during the period from6

“Near-surface trench disposal” means the disposal of radioactive solid waste, which has not been solidified in a container,
in the near-surface repository of a waste disposal site not equipped with an engineered barrier.

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H Safety of Spent Fuel Management
receipt of the radioactive waste to be buried until burial ends, Category 2 Waste Disposal operators
seeking to conduct Near-surface Pit Disposal shall immediately repair the barriers to prevent
leakage. During the period from the end of burial until the start of decommissioning, the operator
shall monitor the status of radioactive material leakages from both engineered barriers and naturalbarriers7 and, if necessary, take steps to minimize the escape of radioactive materials. In addition,
the operator shall patrol and inspect the waste disposal site and, if necessary, restore the soil coveror take other remedial measures. A similar system has also been put in place under the Radiation
Hazards Prevention Act.

7

“Natural barrier” means the host rock or the ground that exists around the engineered structure or the buried radioactive
solid waste, which is expected to restrict migration into the living environment of any radioactive material leaking from theburied radioactive solid waste.

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Transboundary Movement

I

Section I Transboundary Movement
Article 27
1.

Each Contracting Party involved in transboundary movement shall take the appropriate steps to ensurethat such movement is undertaken in a manner consistent with the provisions of this Convention andrelevant 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 and consent 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 cansatisfy itself in accordance with the consent of the State of destination that the requirements of
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 with this
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 forthe return of, radioactive waste and other products resulting from reprocessing operations to the Stateof origin.
The electric power utilities in Japan have concluded reprocessing contracts with the United Kingdom andFrench companies and exported 7,100MTU of spent fuel between 1969 and 2001. They, in return, receive
nuclear fuel material recovered from the spent fuel and vitrified waste generated in the reprocessing. 1,422
vitrified waste canisters were sent back to Japan between 1995 and March 2014 and the remaining
packages will be returned in the next approximately five years. As they are constructing a reprocessing
99

I

Transboundary Movement

plant at Rokkasho Village in Aomori Prefecture since 1993, there has not been any contract of spent fuelwith the United Kingdom and French companies 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 METI.
This Export Permit should be applied once it is confirmed that the authorities of the State of destination
recognized the administrative 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 international conventions on eachmode 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 theradioactive 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 import of 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 andobtain the Export Permit from the Minister of METI for the export of the spent fuel or the radioactive waste.
The Minister of METI judges the grant of the Export Permit after confirming the general conditions ofsafety of the country of destination such as its regulatory structure, the membership in relevant international
agreements, and the administrative and technical capacity 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, in case of
uncompleted transboundary movement so long as original characteristics and configuration of exported
100

Transboundary MovementI

goods are preserved, and the other case of the exemption is a transport accident. Re-entry of exported spent
fuel and radioactive waste is allowed by that provision.

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 andobtain the Export Permit from the Minister of Ministry of Economy, Trade and Industry for the export ofthe spent fuel or the radioactive waste. The Export Permit shall not be granted for the export of spent fuelor radioactive waste to a destination south of latitude 60 degrees south for storage or disposal.

101

J

Disused Sealed Sources

Section J Disused Sealed Sources
Article 28
1. Each Contracting Party shall, in the framework of its national law, take the appropriate steps to ensurethat the possession, remanufacturing or disposal of disused sealed sources takes place in a safe manner.
2. A Contracting Party shall allow for reentry into its territory of disused sealed sources if, in the frameworkof its national law, it has accepted that they be returned to a manufacturer qualified to receive and possessthe disused sealed sources.

J1 Regulatory framework for sealed sources
The use and disposal of radioisotopes and the use of radiation generation apparatuses is regulated by
the Act concerning Prevention from Radiation Hazards due to Radioisotopes, etc.(Radiation Hazards
Prevention Act), as mentioned in paragraph E2.1. Sealed sources are also regulated by this Act. Eachof an estimated 8,000 licensees is responsible for safety and ensuring that radioisotopes are properly
controlled.
The NRA, as the competent regulatory authority, conducts safety reviews and on-site inspections.
The safety of radioactive sources are effectively ensured through regulation under this Act, as
described below.
･A person who intends to use a larger quantity of radioactive sources than specified shall apply to theregulatory authority for a license, or notify said authority.
･The Radiation Hazards Prevention Act prescribes technical criteria and requirements for the use of
facilities and other criteria such as dose limits for radiation workers. For example, to ensureradiation safety, the licensee must: a) limit access to storage facilities through the use of locks; b)
install walls or fences to restrict easy access to the boundary of controlled areas; and c) prohibit
entry into controlled areas without permission of the facility supervisor.
･The licensee is responsible for annually submitting to the regulatory authority a facility management
report, including the inventory of radioactive sources at the end of the fiscal year. The regulatory
authority carries out on-site facility inspections, if needed, and checks that the inventory ofradioactive sources corresponds to the amount permitted to the license.
･In accordance with the IAEA’s Code of Conduct on the Safety and Security of Radioactive Sources,business operators must report to the NRA details of the specification, receipt and issue of any
sealed radioactive isotopes above a set amount which have potential significant risks to humanhealth. In addition, they must provide the NRA with a report on any such radioactive sources intheir possession at the end of each fiscal year.
As a result of this strict regulatory system, there have been no occurrences that pose significant risks
to the public, such as exposure to “orphan sources”.
J2 Management of radioactive sources
Legal restrictions are imposed to ensure that the licensee only hands over high activity sealed
radioactive sources to authorized license holders. There is a well-established mechanism for thehandover of disused radioactive sources to licensees with the requisite expertise. Licensees are102

Disused Sealed SourcesJ

obliged to submit notification of a decommissioning plan to the regulatory authority when theyterminate the use of sources, and to report the outcome of the handover.
All licensees shall conduct an annual inventory check of both sealed and unsealed radioactive sourcesin their possession and report the results to the regulatory authority, to prevent the occurrence oforphan sources. The Radiation Hazards Prevention Act prescribes penalties and underlines that
responsibility for managing the safety of radioactive sources lies with the licensee.
Most sources in Japan are imported from overseas; sources with a long half-life and high activity are
returned to the original foreign manufacturers. Regarding the distribution of radioisotopes and sealed
sources in Japan, a single supplier (the Japan Radioisotope Association) organizes the entire process,from distribution and delivery of almost all radioactive sources to the recovery of disused radioactive
sources.
As a result, there have been no serious radiation hazard incidents involving radioactive sources ororphan sources to date.
J2-1 Criteria for the storage of disused sealed radioactive sources
The Radiation Hazards Prevention Act prescribes the following technical criteria relating to thestorage of sealed sources.
(1) Sealed sources shall be put in containers and stored in storage pits or bins.
(2) Sealed sources shall not be stored in quantities exceeding storage capacity.
(3) Appropriate measures, such as a) installing shields, b) distancing personnel from sealed sources,
and c) shortening the time during which personnel may be exposed to radiation, shall be taken toprevent radiation workers being exposed to levels exceeding the effective dose limit.
(4) Appropriate measures, such as immobilizing storage bins, shall be taken to prevent containers
storing sealed sources from being transferred from one place to another without permission.
(5) Appropriate measures shall be taken to prevent surface contamination from exceeding thesurface contamination density limit.
(6) Radioactive contaminated substances whose surface concentration exceeds one-tenth of thesurface contamination density limit shall not be taken out of the controlled area without
permission.
(7) A notice showing the precautions necessary to prevent radiation hazards shall be posted at an
appropriate location within storage facilities.
(8) Appropriate measures shall be taken to prevent unauthorized persons entering a controlled area.
J2-2 Response to missing radioactive sources
In case of loss of any radioactive sources, the licensee shall immediately report the matter to thepolice and the regulatory authority. The regulatory authority will order the licensee to conduct an
immediate search for the lost source, while the police will carry out a criminal investigation if the103

J

Disused Sealed Sources
loss is associated with a criminal act.
The NRA will also conduct an INES rating of the loss, in accordance with the additional guidance forrating events related to radiation sources, and will report the resultant rating to the IAEA.

J2-3 Response to orphan sources
If an orphan source is found, the police will immediately take initial action, including setting up an
exclusion area, conducting a radiation survey and immediately assessing the overall situation. The
regulatory authority will instruct the person who found the source and other relevant people to takesafety precautions. The regulatory authority will dispatch a radiation inspector to confirm that proper
safety measures have been taken. The orphan source will be recovered by an appropriate expert.
J2-4 Response to accidents involving radioactive sources
In the event of an accident involving a radioactive source, the police and fire service will carry out
immediate measures depending on the notification. The regulatory authority will dispatch radiation
inspectors to instruct the licensee on the proper measures to be implemented.
J2-5 Long-term management of sealed radioactive sources unreturnable to the manufacturers
As previously described, most sealed radioactive sources used in Japan are manufactured abroad,imported and then returned to foreign manufacturers after use. Therefore, Japan has few sealed
radioactive sources that are unreturnable to the manufacturers. The storage and management of someunreturnable sealed radioactive sources are carried out pursuant to the Radiation Hazards Prevention
Act. Accordingly, there are no specific issues at present concerning unreturnable sealed sources.
J3 Reentry of returning sealed sources
The reentry of approved sealed sources which have been returned from abroad by a manufacturer
licensed under the Radiation Hazards Prevention Act is allowed within the scope of the storage
capacity stipulated in the license. In this situation, licensees, when importing and exporting such
sources, shall comply with legislation or procedures concerning import-export management
consistent with the IAEA’s Guidance on the Import and Export of Radioactive Sources. A
manufacturer intending to possess or renew the returned sealed sources is required to store them inaccordance with the storage criteria prescribed in the Radiation Hazards Prevention Act.

104

General Efforts to Improve Safety K
Section K General Efforts to Improve Safety
K1 The IRRSIn December 2013, the NRA discussed the IAEA (International Atomic Energy Agency) Integra
ted Regulatory Review Service (IRRS) mission and agreed (1) to aim to host the mission at the end of 2015; and (2) to move forward with preparations including liaison with the IAEA. Th
e NRA submitted an IRRS request to the IAEA that month and obtained the IAEA’s approval
for the mission to go ahead. The NRA has established an IRRS Office within the NRA Secretariat and is preparing for the IRRS mission.
K2 Response to Challenges Identified at the Previous Review MeetingK2-1 Effective independence of the regulatory authority
The decision-making independence of the NRA is prescribed in law and details are provided in
Section E.
K2-2 Strengthening of the regulatory requirements for the management of spent fuel and radioactivewaste
The Reactor Regulation Act was revised in 2012. Revisions included adoption of state-of-the-art
knowledge, the introduction of backfit systems to which even already authorized nuclear facilities
will be required to conform, and the introduction of an approval system allowing the operational
period of power reactors to be extended once only beyond the current period of 40 years from thecommissioning, as long as permission is received before that 40-year period has elapsed.
This section describes regulations governing spent fuel interim storage activity, waste interim
storage/treatment activity, and waste disposal activity in Japan.
K2-2-1 Spent fuel interim storage activity
The new regulatory requirements concerning spent fuel interim storage activity focus on facilities
that store spent fuel in metallic dry storage casks (hereinafter referred to as “metal casks”) that areused for both transport and storage purposes. Based on the earlier Basic Guide for Safety Review of
Nuclear Fuel Cycle Facilities (decision of the Nuclear Safety Commission, February 7, 1980) and
Safety Examination Guidelines for Spent Fuel Interim Storage Facilities Using Metallic Dry Casks(decision of the Nuclear Safety Commission, October 3, 2002), they prescribe standards for thelocation, structures, and equipment of spent fuel interim storage facilities. They have strengthened
the requirements used in earthquake and tsunami evaluation, concerning the method for establishing
the Design Basis Earthquake Ground Motion and the prevention of tsunami damage to spent fuelinterim storage facilities. They also require the maintenance of spent fuel interim storage facilities inaccordance with the earlier regulations. The basic safety functions required under the new regulatory
requirements are as follows.
105

K General Efforts to Improve Safety- Confinement function: confines the spent fuel placed in metal casks so that it does not poseradiation hazards to the public or workers- Shielding function: shields against radiation from the spent fuel placed in metal casks so that it
does not pose radiation hazards to the public or workers- Criticality prevention function: prevents the spent fuel reaching criticality- Heat removal function: removes decay heat from the spent fuel placed in metal casks to maintainthe integrity of both the spent fuel and the components of the metal casks
K2-2-2 Waste interim storage/treatment activity
The new regulatory requirements have clarified the requirements for the storage and treatment ofradioactive waste, taking into account the property of the waste interim storage/treatment facility.
They have also strengthened the requirements used in earthquake and tsunami evaluation concerning
the method for determining the Design Basis Earthquake Ground Motion and the prevention oftsunami damage to waste interim storage/treatment facilities. A new regulation requires that licensees
conduct regular evaluations, including the aging management, as measures to ensure operationalsafety.
K2-2-3 Waste disposal activity
The new regulatory requirements have strengthened the standard concerning the prevention ofearthquake and tsunami damage to waste disposal facilities and those concerning the maintenance ofwaste disposal site. They have also clarified the criteria for ending the management of such facilities.
To ensure operational safety, a new regulation requires that business operators also assess theradiation control program for radiation exposure from nuclear fuel material at Category 2 Waste
Disposal facilities conducting near-surface disposal, taking into account the state-of-the-art
knowledge concerning facility maintenance,.
K2-3 Ensure the availability of management routes for the expected SF and RW inventories arisingfrom the Fukushima Dai-ichi NPP accident.
K2-3-1 Sammary of Decommissioning and Contaminated Water Management
Page that the link represents information on works and steps for the decommissioning,
contaminated water countermeasures and status of seawater monitoring, etc..
http://www.meti.go.jp/english/earthquake/nuclear/decommissioning/pdf/20140731_e.pdf

K2-3-2 Decontamination and Management of Waste Contaminated with Radioactive Materials at
off-siteSee Supplemental data attached separately.

106General Efforts to Improve Safety K
K2-4 Geological disposal of high-level radioactive waste
The Final Disposal Act enacted in May 2000 provides for the basic framework for systematically andsecurely carrying out the final disposal of the high level radioactive wastes generated from spent fuelreprocessing.
As this situation where an investigation has not been launched to select a repository site after adecade since the creation of the disposal system in 2000 was taken with sincerity, a review was
conducted to fundamentally reassess the efforts which have taken up until now to achieve final
disposal. Specifically, that reversibility and retrievability be assured and that a system be put in place
which, including the future generation, allows for the reconsideration of decisions concerning final
disposal, also, that the government explains from a scientific viewpoint the properties of the area’s
geological environment by indicating regions believed to be more scientifically suitable, and request
the reasoning for siting of such a facility.

(See Section B)

K2-5 Siting criteria for radioactive waste disposal from non-nuclear power plant field
MEXT amended a part of the “Law for the Incorporated Administrative Agency, JAEA”, in June.
2008, and JAEA was designated as the implementing entity of the disposal of the waste fromresearch facilities, etc. MEXT issued the “Basic Policy for Implementation of Waste Disposal”
together with METI. JAEA established the “Plan for Implementation of Waste Disposal” according
to the Basic Policy and received approval from Ministers of MEXT and METI in November 2009．
Concept design for the burial facility and architecture of equipment was completed in
2011.Implementation plan was changed based on concept design in 2012. In light of above, JAEA
has been organized result of consideration for siting criteria and technical matters of process.
Currently, JAEA has been designing the criteria and process.

107

L

ANNEXES

Section L ANNEXES
L1

Inventory of spent fuel

L2

Inventory of radioactive waste

L3

List of spent fuel storage facilities and radioactive waste storage facilities

L4

Excerpt of Regulations Relevant to Sections G and H

108

ANNEXES L

L1 Inventory of spent fuel*1
Inventory

Facility(tons)
Tokai No. 2 Power Station

370

Tsuruga Power Station

580

Tomari Power Station

400

Tohoku Electric Power

Higashidori Nuclear Power Station

100

Co., Inc.

Onagawa Nuclear Power Station

420

JAPCO
Hokkaido ElectricPower Co., Inc.

Fukushima Daiichi Nuclear Power- *2

StationTEPCO

Fukushima Daini Nuclear Power Station
Kashiwazaki-Kariwa Nuclear Power
StationChubu Electric Power
Co., Inc.
Hokuriku ElectricPower Co., Inc.

1,120

Type of spent fuelUranium oxide fuelassemblies

2,370

Hamaoka Nuclear Power Station

1,140

Shika Nuclear Power Station

150
Uranium oxide fuelThe Kansai ElectricPower Co., Inc.

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

Mihama Power Station390

assemblies, MOX fuelassemblies

Ohi Power Station

1,420

Takahama Power Station

1,160

Shimane Nuclear Power Station390
Uranium oxide fuelIkata Power Station

610

Genkai Nuclear Power Station

870

Sendai Nuclear Power Stationassemblies

890
Uranium oxide fuelReactor Decommissioning R&D Center
JAEA

70

assemblies, MOX fuelassembliesFBR Research and Development Center
Reprocessing Facility of the Nuclear
Fuel Cycle Engineering Laboratories,

109

0
41

Uranium oxide fuelassemblies, MOX fuelL

ANNEXES
Tokai Research and Development Center

assemblies

Nuclear Science Research Institute,

18

Tokai Research and Development Center

Uranium oxide fuelassemblies
Uranium oxide fuelOarai Research and Development Center

16

assemblies, MOX fuelassemblies

JNFL

Rokkasho Reprocessing Faclityt

2,951

Total

Uranium oxide fuelassemblies

16,869*1 Data is provided by the Federation of Electric Power Companies of Japan.
*2 The measurement method is under consideration.
L2

Inventory of radioactive waste

L2-1

High-level radioactive waste
Vitrified waste

High-level liquid(number ofradioactive

containers*)

waste

Reprocessing facility

247

415 m3

Reprocessing facility

346

0

Waste storage facility

1,442

0

2,035

415 m3

Facility

JAEA
JNFL
Total

*Unit: JAEA: 120-liter container, JNFL (reprocessing facilities): 160-liter container; JNFL (waste
storage facilities): 170-liter container
L2-2

Power station waste

1.

Homogeneous solid, packed solid and miscellaneous solid
Homogeneous

Packed solid

Miscellaneous

Total (drumsolid (drumｓ)(drumｓ)solid (drumｓ)ｓ)

Tokai Power Station

0

0

1,503

1,503

Tokai No. 2 Power Station

498

1,373

57,11358,984Tsuruga Power Station

2,548

771

65,276

68,595

884

0

8,434

9,318

1,972

140

25,42027,5320010,404

10,404

Power station

JAPCO

Hokkaido
Electric PowerTomari Power Station

Co., Inc.
Tohoku ElectricPower Co., Inc.

Onagawa Nuclear Power
StationHigashidori Nuclear Power110

ANNEXES L
StationFukushima Daiichi Nuclear

15,784

2,789

167,077

185,650*

644

1,717

17,376

19,7370855

30,27331,128

3,334

2,568

29,17135,073

8

786

5,696

6,490

Power Station
Fukushima Daini Nuclear
TEPCO

Power Station
Kashiwazaki-Kariwa Nuclear
Power Station

Chubu Electric

Hamaoka Nuclear PowerPower Co., Inc.

StationHokuriku ElectricPower Co., Inc.

Shika Nuclear Power Station

The Kansai

Mihama Power Station

2,296

2,618

23,39928,313

Electric Power

Takahama Power Station

4,809

0

39,19144,000Co., Inc.

Ohi Power Station

3,803

4,016

24,31332,132278

1,073

25,482

26,833

1,258

844

25,77527,877The Chugoku
Electric Power
Co., Inc.
Shikoku ElectricPower Co., Inc.

Shimane Nuclear Power
StationIkata Power Station

Kyushu Electric

Genkai Nuclear Power Station

3,969

2,732

30,60337,304

Power Co., Inc.

Sendai Nuclear Power Station

2,175

0

19,31021,4852,016

016,95818,974

20

0

5,544

5,564

46,29622,282

628,318

696,896

Reactor Decommissioning
R&D Center
JAEA

Fast Breeder Reactor Monju,
Research and Development
CenterTotal

Unit: 200-liter drum; For miscellaneous solids, values include those equivalent to 200 liters per drum.
*In addition, rubble, trimmed trees, disused-protective clothing generated after accident, etc.[total
201,300m3], and secondary waste from contaminated water treatment[848 cesium absorption
apparatus and absorption vessel etc. and Sludge 597m3] have been temporarily stored.
2.

Steam generator (SG)
Number of stored

Power station

SGs

The Kansai Electric

Mihama Power Station

7

Power Co., Inc.

Takahama Power Station

6

111

L

ANNEXESOhi Power Station

8

Ikata Power Station

4

Kyushu Electric PowerGenkai Nuclear Power Station

4Co., Inc.

Sendai Nuclear Power Station

3

Shikoku Electric Power
Co., Inc.

Total

3.

32

Control rods, channel boxes, others
Control rod

Power station

1(number)*

Channel box (number)

Others (m3)Resin,(m3)

Tokai Power Station

91 m3

0

1,290

60

Tokai No. 2 Power

306

3,621

17

898

173

1,850

49

845

353

0

0

92

312

0

0

103

231

3,112

1

464

67

644

0

132

1,448

22,291

193

3,522

699

9,233

43

5,250

800

13,547

0

2,592

550

11,020

33

2,678

69

1,094

0

157

StationJAPCO

Tsuruga Power Station(Unit 1)
Tsuruga Power Station(Unit 2)

Hokkaido
Electric PowerTomari Power Station

Co., Inc.
Onagawa Nuclear Power
Tohoku Electric

StationPower Co., Inc.

Higashidori Nuclear
Power Station
Fukushima Daiichi
Nuclear Power Station

TEPCO

Fukushima Daini Nuclear
Power Station
Kashiwazaki-Kariwa
Nuclear Power Station

Chubu Electric

Hamaoka Nuclear PowerPower Co., Inc.

StationHokuriku
Electric Power
Co., Inc.

Shika Nuclear Power
StationThe Kansai

Mihama Power Station

696

0

0

102

Electric Power

Takahama Power Station

1,336

0

0

121

112

ANNEXES L
Co., Inc.

Ohi Power Station

The Chugoku
Electric Power
Co., Inc.

Shimane Nuclear Power

1,134

0

0

112

285

4,478

56

851

686

0

0

165

778

0

0

174

460

0

0

150

70,892(1,682m3)(18,468m3)

OthersResin, etc.

(number)

(m3)

0

216

StationShikokuElectric Power

Ikata Power Station

Co., Inc.
Genkai Nuclear Power
Kyushu Electric

StationPower Co., Inc.

Sendai Nuclear Power
Station

10,383

Subtotal+(91 m3)
Control rod

Neutron detector (number)(number)
Reactor
JAEA

Decommissioning

54

128

R&D Center
Tubes for guiding the drive mechanisms of control rods
(number)
Fast Breeder Reactor
JAEA

Research andDevelopment Center5(Monju)*1: Figures of the Tokai Power Station are not included.

L2-3

Long half-life low heat generating radioactive waste

Facility

JAEA

JNFL

JNFL

Reprocessing
facility
Reprocessing
facility

waste storage
facility

Drum

Bituminized

Plastic solid

Other waste

Total(number)solid (drums)(drums)(drums)(drums)

32,07529,967

1,812

12,20576,05916,3180021,55037,868

1,004

0

0

48

1,052

113

L

ANNEXES

Subtotal

43,634

Reprocessing

JAEA

facility
Reprocessing

JNFL

facility

29,967

1,812

28,031

103,444

Sheared cladding

Spent filter (drumSample bottle

Total(drumｓ)ｓ)(drumｓ)(drumｓ)

4,958

315

1,360

6,633

219*1

0

0

219

Sludge (m3)

Waste solvent (m3)

1,158

101

Low activity
concentrated liquid
waste (m3)
Reprocessing

JAEA

facility

2,887

Unit: 200-liter drum, including values equivalent to 200 liters per drum
*1: Unit for a piece of sheared cladding: 1,000-liter drum
L2-4

Uranium waste
Drum

Other waste

Total (drumLow-level liquid(number)(drumｓ)ｓ)

waste (m3)Global Nuclear Fuel-Japan Co., Ltd.

16,3842,550

18,934

0.096

Mitsubishi Nuclear Fuel Co., Ltd.

9,566

606

10,172

1.80

Nuclear FuelTokai Works

5,535

843

6,378

6.35

Industries, Ltd.

Kumatori Works

7,696

494

8,190

13.2

531

56

587

0

5,191

1,472

6,703

2.17

44,903

6,021

50,96323.616

Prototype
JAEA

Uranium
Enrichment
Plant

JNFL
Total

Enrichment andDisposal Office

Unit: 200-liter drum, including values equivalent to 200 liters per drum
L2-5

Waste stored in research facilities

This table shows streamlined data collected from a variety of reports. It includes data from FY2013
Radioactive Waste Management Status Reports, which were submitted based on the Periodic Report on
Management of the Radioactive Waste (notice), issued by the director of the Nuclear Safety Division,
Science and Technology Policy Bureau, MEXT; data from FY2013 reports submitted pursuant to theprovisions of Article 67 (1) of the Act on the Regulation of Nuclear Source Material, Nuclear Fuel Material
114

ANNEXES L
and Reactors, and data from the FY2013 Radioactive Waste Management Status Reports, which were
submitted by the licensees pursuant to the provisions of Article 42 (1) of the Act concerning Prevention from
Radiation Hazards due to Radioisotopes, etc.(Radiation Hazards Prevention Act), as well as Article 39 (3) of
the Ordinance for Enforcement of said Act.
Waste stored by licensees of research reactor operations and those of nuclear reactor facilities used forresearch, excluding power reactors used for power generation, and those stored by users of nuclear fuelmaterials related to usage facilities of such materials pursuant to Article 41 of the Ordinance for
Enforcement of the Act on the Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactors
Name of facility

Nuclear Science
Research InstituteLiquidSolid waste

waste(drum*1)

Remarks(m3)
Sum of values for reactor facilities and128,442-those for facilities using nuclear fuelmaterials

Nuclear Fuel Cycle
Engineering

63,316

25.9

Facility using nuclear fuel materials

Laboratories
Oarai Research andDevelopment Center(North Area)
JAEA

Sum of values for reactor facilities and
1,478

-

materials
29,634-

Waste storage facility
For solid wastes, values refer to those for

Oarai Research andDevelopment Center

those for facilities using nuclear fuel

145

0.03

(South Area)

reactor facilities (for temporary storage).
For liquid wastes, values refer to facilities
using nuclear fuel materials.

Ningyo-toge
Environmental

14,91910.5

Facility using nuclear fuel materials

1,070

22.0

Reactor facility

Engineering Center
Mutsu Office, Aomori
Research andDevelopment Center
For solid wastes, values refer to the sum
Nuclear Professional School, Schoolof Engineering, the University ofof those for reactor facilities and those for
33

2.7

Tokyo

facilities using nuclear for temporarystorage. For liquid wastes, values refer tothose for reactor facilities.

115

L

ANNEXES

Research Reactor Institute, Kyoto
University

The values refer to the sum of reactor
73

0.0

facilities and for facilities using nuclear
fuel materials.

National Institute of Radiological
Sciences
Nuclear

Tokai Safeguards

Material

CenterControl

Rokkasho Safeguards

CenterAnalytical Laboratory

Institute for Atomic Energy, Rikkyo
University

1,269

-

Facility using

nuclear fuel materials

468-

Facility using

nuclear fuel materials

324-

Facility using

nuclear fuel materials

15

0

Reactor facility

5-

Reactor facility

3-

Reactor facility

Atomic Energy Research Institute,Tokyo City University (former
Musashi Institute of Technology)
Atomic Energy Research Institute,
Kinki University
Nuclear Fuel Industries, Ltd. Tokai
Works

Facility using
6,378

6.35

(reposting of the values in Table L2.4 as afabricating facility)

Nippon Nuclear Fuel Development
Co., Ltd.
Nuclear Development Corporation
Research Reactor
Center311

10.5

Facility using

nuclear fuel materials

1,887

-

Facility using

nuclear fuel materials

74-

Reactor facility
For solid wastes, the values refer to the

Toshiba
Corporation

nuclear fuel materials

Nuclear EngineeringLab.

sum of reactor facilities and facilities
1,605

0.7

using nuclear fuel materials. For liquid
wastes, the values refer to facilities using
nuclear fuel materials.

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

496-

Reactor facility

251,945

78.68-

Division, Hitachi, Ltd.
Total

Waste stored by licensees who are connected to facilities that use nuclear fuel materials but do not fall underthose stipulated in Article 41 of the Act on the Regulation of Nuclear Source Material, Nuclear Fuel Material andReactors

116

ANNEXES L
Sum of values of solid and liquid waste

76,866 drums *1(195 facilities)

materials

Note: The data in this table includes those of long half-life low heat generating radioactive waste anduranium waste generated in the facilities.
*1: Unit: 200-liter drum, including values equivalent to 200 liters per drum.
Wastes stored by a licensee of waste management pursuant to Article 4 (1) of Radiation Hazards Prevention

Act
Amount of waste

Name of facility(drum*)
Kanto Waste Relay Station
II

Remarks

8,501

Japan Radioisotope
Association

Ichihara Office

66,818Kansai Waste Relay

0

Station
Vesta Co., Ltd.

56,573This data is also reported
Nuclear Science ResearchInstitutepursuant to the Act on the
99,890Regulation of Nuclear
Source Material, Nuclear
Fuel Material and Reactors.

JAEA

This data is also reported
pursuant to the Act on the

Oarai Research and33,598Development Center

Regulation of Nuclear
Source Material, Nuclear
Fuel Material and Reactors.

Tsukuba Laboratory, T.N. Technos Co., Ltd.

317

Total

266,932* Unit: 200-liter drum, including values equivalent to 200 liters per drum; this data includes values forliquid waste.
L3

List of spent fuel storage facilities and radioactive waste storage facilities

L3-1

List of spent fuel management facilities(1)

Facilities related to power reactors

Facilities in which spent fuel management
facilities are locatedMajor purpose

Location

117

Major feature

L

ANNEXES

Tokai No. 2 Power Station, JAPCO

Tsuruga Power Station, JAPCO
Hokkaido Prefecture
Tomari Power Station, Hokkaido ElectricPower Co., Inc.

IbarakiPrefecture
Fukui
Prefecture
Hokkaido
Prefecture

Onagawa Nuclear Power Station, Tohoku

MiyagiElectric Power Co., Inc.

Prefecture

Higashidori Nuclear Power Station, Tohoku

AomoriElectric Power Co., Inc.

Prefecture

Fukushima Daiichi Nuclear Power Plant,

Fukushima

TEPCO

Prefecture

Fukushima Daini Nuclear Power Plant,

Fukushima

TEPCO

Prefecture

Kashiwazaki-Kariwa Nuclear Power Plant,

Niigata

TEPCO

Prefecture

Hamaoka Nuclear Power Station, Chubu

Shizuoka

Electric Power Co., Inc.

Prefecture

Shika Nuclear Power Station, Hokuriku

Ishikawa

Electric Power Co., Inc.

Prefecture

Mihama Power Station, the Kansai Electric

Fukui

Power Co., Inc.

Prefecture

Takahama Power Station, the Kansai Electric

Fukui

Power Co., Inc.

Prefecture

Ohi Power Station, the Kansai Electric

Fukui

Power Co., Inc.

Prefecture

Shimane Nuclear Power Station, theShimane

Chugoku Electric Power Co., Inc.

Prefecture

Ikata Power Station, Shikoku Electric Power

Ehime

Co., Inc.

Prefecture

Genkai Nuclear Power Station, Kyushu

Saga

Electric Power Co., Inc.

Prefecture

Sendai Nuclear Power Station, Kyushu

Kagoshima

Electric Power Co., Inc.

Prefecture

Advanced Thermal Reactor Fugen, Fugen

Fukui

Reactor Decommissioning R&D Center,

Prefecture

Storing spent fueldry cask storage)

Storing spent fuelWet storage

Storing spent fuelWet storage

Storing spent fuelWet storage

Storing spent fuelWet storage

Storing spent fuel118

Wet storage (partially stored in

Wet storage (partially stored indry cask storage)

Storing spent fuelWet storage

Storing spent fuelWet storage

Storing spent fuelWet storage

Storing spent fuelWet storage

Storing spent fuelWet storage

Storing spent fuelWet storage

Storing spent fuelWet storage

Storing spent fuelWet storage

Storing spent fuelWet storage

Storing spent fuelWet storage

Storing spent fuelWet storage

Storing spent fuelWet storageANNEXES L
JAEA
Reprocessing Facility of the Nuclear FuelIbaraki

Cycle Engineering Laboratories, Tokai

Prefecture

Research and Development Center, JAEA

Aomori

Rokkasho Reprocessing Plant, JNFL

Prefecture

Fast Breeder Reactor Monju, FBR Research andFukui

Development Center, JAEA

Prefecture(2)

Storing spent fuelWet storage

Storing spent fuelWet storage

Storing spent fuelWet storage

List of spent fuel management facilities (related to research and test reactors)

Facilities in which spent fuel management facilities are

Location

locatedMajor purpose

Major feature
Wet storage

Nuclear Science Research Institute of the Tokai Research

Ibarakiand Development Center, JAEA

Prefecture

Storing spent fuel(partially stored
in dry cask
storage)

IbarakiOarai Research and Development Center, JAEA

Prefecture
Osaka

Research Reactor Institute, Kyoto University

Prefecture

L3-2

List of radioactive waste management facilities(1)

Facilities related to power reactors

Facilities in which radioactive waste
management facilities are located

Tokai Power Station, JAPCO

Tokai No. 2 Power Station, JAPCO

Tsuruga Power Station, JAPCO

Location

Storing spent fuelWet storage

Storing spent fuelWet storage

Major purpose

Disposing and storing

Ibaraki

waste from power

Prefecture

reactors

Disposing and storing

Ibaraki

waste from power

Prefecture

reactors

Fukui
Prefecture

119

Major feature
Storing waste after
reducing the volume bycompressing or
incineration
Storing waste after
reducing the volume bycompressing or
incineration

Disposing and storing

Storing waste after

waste from power

reducing the volume byreactors

compressing or

L

ANNEXES
incineration
Disposing and storing

Tomari Power Station, Hokkaido Electric

Hokkaido

Power Co., Inc.

Prefecturewaste from powerreactors

Disposing and storing

Higashidori Nuclear Power Station,

AomoriTohoku Electric Power Co., Inc.

Prefecturewaste from powerreactors

Disposing and storing

Onagawa Nuclear Power Station, Tohoku

MiyagiElectric Power Co., Inc.

Prefecture

Fukushima Daiichi Nuclear Power

Fukushima

Station, TEPCO

Prefecture

Fukushima Daini Nuclear Power Station,

Fukushima

TEPCO

Prefecturewaste from powerreactors

Disposing and storing
waste from powerreactors

Disposing and storing
waste from powerreactors

Disposing and storing

Kashiwazaki-Kariwa Nuclear Power

Niigata

Station, TEPCO

Prefecturewaste from powerreactors

Disposing and storing

Hamaoka Nuclear Power Station, Chubu

Shizuoka

Electric Power Co., Inc.

Prefecturewaste from powerreactors

Disposing and storing

Shika Nuclear Power Station, Hokuriku

Ishikawa

Electric Power Co., Inc.

Prefecturewaste from powerreactors

Disposing and storing

Mihama Power Station, the Kansai

Fukui

Electric Power Co., Inc.

Prefecture120

waste from powerreactors

Storing waste after
reducing the volume bycompressing or
incineration
Storing waste after
reducing the volume bycompressing or
incineration
Storing waste after
reducing the volume bycompressing or
incineration
Storing waste after
reducing the volume bycompressing or
incineration
Storing waste after
reducing the volume bycompressing or
incineration
Storing waste after
reducing the volume bycompressing or
incineration
Storing waste after
reducing the volume bycompressing or
incineration
Storing waste after
reducing the volume bycompressing or
incineration
Storing waste after
reducing the volume bycompressing or
incineration

ANNEXES L

Takahama Power Station, the Kansai

Fukui

Electric Power Co., Inc.

Prefecture

Ohi Power Station, the Kansai Electric

Fukui

Power Co., Inc.

Prefecture

Shimane Nuclear Power Station, theShimane

Chugoku Electric Power Co., Inc.

Prefecture

Ikata Power Station, Shikoku Electric

Ehime

Power Co., Inc.

Prefecture

Disposing and storing
waste from powerreactors

Disposing and storing
waste from powerreactors

Disposing and storing
waste from powerreactors

Disposing and storing
waste from powerreactors

Disposing and storing

Genkai Nuclear Power Station, Kyushu

Saga

Electric Power Co., Inc.,

Prefecturewaste from powerreactors

Sendai Nuclear Power Station, Kyushu

Kagoshima

Electric Power Co., Inc.,

Prefecture

Disposing and storing
waste from powerreactors

Storing waste after
reducing the volume bycompressing or
incineration
Storing waste after
reducing the volume bycompressing or
incineration
Storing waste after
reducing the volume bycompressing or
incineration
Storing waste after
reducing the volume bycompressing or
incineration
Storing waste after
reducing the volume bycompressing or
incineration
Storing waste after
reducing the volume bycompressing or
incineration
Storing waste inAdvanced Thermal Reactor Fugen, Fugen
Reactor Decommissioning R&D Center,
JAEA

Fukui
Prefecture

Disposing and storingstorage after reducing

waste from power

the volume byreactors

compressing or
incineration

Prototype fast-breeder reactor Monju,
FBR Research and Development Center,
JAEA

(2)

Fukui
Prefecture

Disposing and storing

Storing waste after

waste from power

reducing the volume byreactors

compressing

List of radioactive waste management facilities (excluding those related to power reactors)

Facilities in which radioactive waste
management facilities are located*
Global Nuclear

Facility for

Location

Major purpose

Major feature

Kanagawa

Disposing and storing

Storing waste after

121

L

ANNEXES

Fuel-Japan Co., Ltd.

fabricating nuclear

Prefecture

uranium waste

fuel materials

Mitsubishi Nuclear
Fuel Co., Ltd.

Facility for
fabricating nuclear
fuel materials

by compressing
Storing waste after
Ibaraki

Disposing and storing

reducing the volume

Prefecture

uranium waste

by compressing or
incineration

Facility for

Disposing and storing

fabricating nuclear
Nuclear Fuel
Industries, Ltd. Tokai
Works

fuel materials
Facility for

uranium waste
IbarakiPrefecture

fabricating nuclear

Kumatori Works

Facility using

Osaka
Prefecture

nuclear fuel materials
Facility for
Ningyo-toge
Environmental
Engineering Center,
JAEA

Facility using

uranium waste

Prefecture

nuclear fuel materials

Nuclear Science

Research and test

Research Institute ofreactor facility

the Tokai Research and(under operation: 7;

Development Center,

under

JAEA

decommissioning: 1),

Storing waste after
reducing the volume
by incineration
Storing waste after
reducing the volume
by compressing

reducing the volume

nuclear fuel materials

by compressing

Disposing and storing
waste from facilities
nuclear fuelmaterials
Disposing low-level
radioactive waste

facility

by incineration

facilities using

using

Waste disposal

reducing the volume

Storing waste after

uranium waste
Okayama

Storing waste after

Storing waste from

Disposing and storing

fabricating nuclear
fuel materials

nuclear fuelDisposing and storing

fabricating nuclear
fuel materials

waste from facilities

materials

Facility for

Industries, Ltd.

Disposing and storing

using

fuel materials

Nuclear Fuelreducing the volume

materials

Storing waste after
reducing the volume
by incineration
Storing waste after
reducing the volume
by incineration

Trench disposal of
concrete waste

Disposing and storing
Ibaraki

waste from researchPrefecture

and test reactor
facilities using
nuclear fuel materials,

facility using

and facilities using

nuclear fuelradioisotope

materials, and facility

122

Storing waste after
reducing the volume
by compressing or
incineration

ANNEXES L
managed by disposal
service businesses*1
Storing high-level
radioactive waste andwaste containing

Nuclear Fuel Cycle
Engineering

Reprocessing facility

Laboratories, Tokai

IbarakiResearch andPrefecture

Disposing and storingtrans-uranium after

high-level radioactive

reducing volume bywaste and waste

solidifying high-levelcontaining transradioactive waste

uraniumwith glass orincinerating the waste

Development Center,

containing trans

JAEA

uranium
Disposing and storing

Storing waste after

Facility using

waste from facilities

reducing the volume

nuclear fuel materials

using

by compressing or

nuclear fuelmaterials

incineration

Research and reactor
facilities (under

Disposing and storing

operation: 3; under
Oarai Research andDevelopment Center,
JAEA

waste from researchdecommissioning: 1),
waste storage facility,

Ibarakifacility using nuclear

Prefecture

fuel materials, andand test reactor
facilities, facilities
using nuclear fuelmaterials, and facilities

facility managed by

Storing waste after
reducing the volume
by compressing or
incineration

using radioisotope

disposal service
businesses *1
Mutsu Office, Aomori

Research and test

Disposing and storing

Research andreactor facility

Aomoriwaste from research

Development Center,(underPrefecture

and test reactor

JAEA

decommissioning: 1)

facilities
Disposing and storing

Reprocessing facility,
JNFL

Reprocessing facility

AomoriPrefecturehigh-level radioactive
waste and waste
containing transuranium

123

Storing waste after
reducing the volume
by compressing
Storing waste fromstorage facilities that
accept spent fuelmaterials (areprocessing facility
is now under

L

ANNEXESconstruction)
Facilities for storing
Waste storage facility

Storing vitrified waste

returned vitrified
waste

Waste disposal
Enrichment andDisposal Office, JNFL

facility
Facility for uranium

AomoriPrefecture

enrichment

Disposing low-level

Waste disposal

radioactive waste

facilities Units 1 andmaterials

2

Disposing and storing
uranium waste

Storing waste

Temporarily storing

Commissioned to thewaste from the research

Nuclear Science

Nuclear Professional

Research and test

School, School ofreactor facility,

Ibarakiand test reactor

Research Institute ofEngineering, thefacility using

Prefecture

facilities and facilities

the Tokai Research

University of Tokyo

nuclear fuel materials

using nuclear fueland Development

materials

Center, JAEA

Disposing and storing

Storing waste after

waste from facilities

reducing the volumeusing radioisotope

by incineration

Radioisotope Center,

Facility managed by

the University ofdisposal serviceTokyobusinesses *1

Tokyo

Disposing and storing

Research and test
Research Reactor

reactor facility

Institute, Kyoto(under operation: 2),

University

facility using

waste from researchOsakaand test reactor

Prefecture

facilities and facilities
using nuclear fuelnuclear fuel materials

Institute for Atomic
Energy, Rikkyo
University

Storing wastematerials

Research and test

Disposing and storing

reactor facility

Kanagawa

waste from research(underPrefecture

and test reactor

decommissioning: 1)

Storing waste

facilities

Atomic Energy
Research Institute,

Research and test

Tokyo City University

reactor facility

Kanagawa(former Musashi(underPrefecture

Institute ofdecommissioning: 1)

Storing waste fromresearch and test

Storing waste

reactor facilities

Technology)
Atomic Energy
Research Institute,
Kinki University

Research and test

Osaka

reactor facility

Prefecture

124

Storing waste fromresearch and test
reactor facilities

Storing waste

ANNEXES LRadiotoxicology
Experiment Building,

Facility using

Chiba

National Institute ofnuclear fuel materials

Prefecture

Tsukuba Center No. 2

Facility using

Ibaraki

Office, AIST

nuclear fuel materials

PrefectureRadiological Science

On Site Laboratory,
Rokkasho Safeguards
Analytical Laboratory,
Nuclear Material

Prefectureusing

nuclear fuel materials

Prefecture

CenterFacility managed bydisposal service
businesses*2

Ichihara Office, Japan

Facility managed byRadioisotope

disposal service

Station 2, Japan
Radioisotope
Association
Kansai Waste Relay
Station, Japan
Radioisotope
Association
Research Reactor
Center, Toshiba
Corporation

nuclear fuelStoring wastematerials

Material Control

Kanto Waste Relay

Storing waste

nuclear fuel materials

nuclear fuel materials

Ibaraki

Association

facilities using

waste from facilities

Facility using

Association

Storing waste from

AomoriCenter, Nuclear

Japan Radioisotope

Storing waste

nuclear fuel materials

Facility using

Tokai Safeguards

Takizawa Laboratory,

facilities using

Disposing and storing

Control Center

The Kaya Memorial

Storing waste from2

businesses *Facility managed bydisposal service
businesses *2

Facility managed bydisposal service
2

businesses*

Iwate
Prefecture

Chiba
Prefecture

Chiba
Prefecture

Osaka
Prefecture

Research and test
reactor facility

Kanagawa(underPrefecture

decommissioning: 1)

Storing waste fromfacilities using
nuclear fuel materials

Disposing and storing
waste from facilities
using radioisotope

storage

Storing waste after
reducing the volume
by compressing or
incineration

Storing waste fromfacilities using

Storing waste

radioisotope
Storing waste fromfacilities using

Storing waste

radioisotope

Storing waste fromfacilities using

Storing waste

radioisotope

Storing waste from theresearch and test

Storing waste

reactor facilities

Nuclear Engineering

Facility using

Kanagawa

Storing waste fromLab., Toshiba

nuclear fuelPrefecture

research and test

125

Storing waste in

Storing waste

sto

L

ANNEXES

Corporationmaterials, research

reactor facilities andand test reactor

facilities using

facility

nuclear fuel materials

Ozenji Hitachi
Training Reactor

Research and test

Center, Power &reactor facility

Kanagawa

Industrial Systems(underPrefecture

Nuclear Systemdecommissioning: 1)

Storing waste from theresearch and test

Storing waste

reactor facilities

Division, Hitachi, Ltd.
NFD Hot Laboratory,
Nippon Nuclear Fuel
Development Co., Ltd.

Fuel Hot Laboratory,
Nuclear Development
Corporation

Tsukuba Laboratory,
T.N. Technos Co., Ltd.

Commissioned to

Facility using

Ibaraki

waste from facilities

Oarai Research andnuclear fuel materials

Prefectureusing

Development Center,

nuclear fuelmaterials
Disposing and storing
Facility using

Ibaraki

waste from facility

nuclear fuel materials

Prefectureusing

nuclear fuelmaterials
Facility managed bydisposal service
businesses *1
Facility managed by

Vesta Co., Ltd.

Disposing and storing

disposal service
1businesses *IbarakiPrefecture

Chiba
Prefecture

JAEA
Storing waste after
reducing the volume
by compressing

Disposing and storing

Storing waste after

waste from facilities

reducing the volumeusing radioisotope

by incineration

Disposing and storing

Storing waste after

waste from facilities

reducing the volumeusing radioisotope

by incineration* One licensee operates one facility unless otherwise noted. When one licensee operates more than one
facility or implements decommissioning measures for more than one facility, that situation will beclearly described.
*1: Facilities managed by disposal service businesses refer to those approved pursuant to Radiation
Hazards Prevention Act .
*2: Facilities managed by disposal service businesses refer to those approved pursuant to the Radiation
Hazards Prevention Act and the Medical Care Act.
Amount of disposed radioactive waste
Name of facility

Waste Disposal Facilities, Enrichment
and Disposal Office, JNFL

Major nuclides to be confirmed

Amount (drumｓ)

Unit 1

Co-60, Ni-63, Cs-137, Sr-90, C-14

147,507*2

Unit 2

Co-60, Ni-63, Cs-137, Sr-90, C-14

112,672*2

Total

-

260,179*2

126

ANNEXES L
Nuclear Science Research Institute of
the Tokai Research and Development
1

Center, JAEA *Waste disposal

Co-60, Ni-63, Cs-137, Sr-90, Ca-41,

facilities

C-14, Eu-152, H-3

1,670 tons

*1: Disposing very low-level concrete waste generated by dismantling the JPDR, thedecommissioning of which has been transferred to the phase of preserving the disposal site since
October 1997
*2: Unit: 200-liter drum
L3-3

Nuclear facilities undergoing decommissioning(1)

Facilities related to power reactors

Name of facility

Tokai Power Station, JAPCO

Location

IbarakiPrefecture

Type ofreactor

GCR

Power

Period ofoutputcommercial(10MW)

operation

16.6

Current state ofdecommissioning

Jul. 1966 -Decommissioning measures

Mar. 1998

started in 2001
Finished initial operation in

Advanced Thermal Reactor

March 2003; spent fuelFugen, Fugen Reactor

Fukui

Decommissioning R&D Center,

Prefecture

ATR

16.5

Mar. 1979 -continues to be removed andMar. 2003

decommissioning continues

JAEA

from February 2008 to FY2033
as scheduled
Finished operation in January
2009; received approval for adecommissioning plan inNovember 2009; removing spent
fuel during the first phase of thedecommissioning preparation

Units 1 and 2, Hamaoka Nuclear
Power Station, Chubu ElectricPower Co., Inc.

ShizuokaPrefecture

BWR

Mar. 1976 -period, while starting the

54.0

Jan. 2009;

research and study on

84.0

Nov. 1978 -contamination andJan. 2009decontaminating the systems, aswell as dismantling andremoving facilities andequipment outside the radiation
controlled area;
decommissioning scheduled forcompletion during the 2030s

127

L

ANNEXES(2)

Nuclear facilities under decommissioning measures; Nuclear facilities scheduled to be
decommissioned; Current situation of the decommissioning measures (research reactors
facilities )Name of facility

Location

Type ofreactor

Thermaloutput(kW)

Period ofCurrent situation of theoperation*

decommissioning measures
Removed heavy water;

JRR-2 of the Nuclear
Science Researchsegregated reactor cooling

Heavy-water-

Institute, Tokai

Ibarakimoderated

Research andPrefecture

cooling tank

Development Center,

10,000Oct. 1960 Dec. 1996

reactorsystems; sealed the body of thenuclear reactor; removed thesecondary cooling facilities;
removed experimental facilities;

JAEA

moved the spent fuelNuclear ship Mutsu(the first Japanese
nuclear ship), Mutsu
Office, Aomori
Research andPressurized
AomoriPrefecture

Development Center,

Completed dismantling the ship;

light-watermoderated and36,000cooled reactor;

Aug. 1974- Feb. 1992

PWR

maintaining and managing theaccessory onshore facilities tostore solid waste and dispose of
liquid waste

JAEA
Deuterium Criticality
Assembly (DCA),
Oarai Research andDevelopment Center,

IbarakiPrefecture

Completed shut down of the

Heavy-watermoderated1

reactor

Dec. 1969

reactor functions; removed- Sep. 2001

heavy water; removed thecooling systems

JAEA
Ozenji Hitachi Training

Dismantled and removed theReactor (HTR) Center,
Power & Industrial

Kanagawa

Light-water

Systems Nuclear

Prefecture

moderated andSystem100

Dec. 1961- Feb. 1975

cooled reactor

Kanagawa

moderated

Reactor Center,

Prefecture

unhomogeneous

Toshiba Corporation

reactor vessel with concrete;

Conducted permanent shutdown

Light-water(TTR-1), Researchfollowed by solidifying theremoved the spent fuelDivision, Hitachi, Ltd.
Training Reactor

body of the nuclear reactor,

100

Mar. 1962of operational functions;- Jan. 2001

removed facilities for reactor
cooling systems; removed thereactor128

ANNEXES L
spent fuelResearch and test
reactor (RUR),
Institute for Atomic
Energy, Rikkyo

Zirconium
Kanagawa
Prefecture

University

hydridemoderated

100

light-water

Dec. 1961

Conducted shutdown of the- Dec.

reactor functions; removed the2001

spent fuelcooled reactor

Research and test
reactor, Atomic Energy
Research Institute(MITRR), Tokyo City
University (former

Zirconium
Kanagawa
Prefecture

Musashi Institute of

hydridemoderated

100

light-water

Jan. 1963 Jan. 2004

Conducted shutdown of thereactor functions; removed thespent fuelcooled reactor

Technology)
Nuclear reactor Yayoi

IbarakiAir coolingof the University ofPrefecture

fast reactor

Tokyo

2

Apr. 1971 -Finished reactor operations on

Mar. 2011

March 31, 2011; scheduled tousing uranium

advance the decommissioning

as fuelprocedures* The term period of operation refers to the period from reaching the first critical state to shutting
down the operation.

129

L

ANNEXES

L4

Excerpt of Regulations Relevant to Sections G and H

I．Excerpt of Regulations Relevant to Section G
Table G1-1 Ordinance on Activity of Interim Storage of Spent Fuel (Excerpt)(Application for Permission for Spent Fuel Interim Storage Activity)
Article 2(1) An application form for permission for the interim storage of spent fuel set forth in Article 43-4,
paragraph (2) of the Act on the Regulation of Nuclear Source Material, Nuclear Fuel Material andReactors (hereinafter referred to as the “Act”) shall include the following:(i)with regard to the storage capacity set forth in Article 43-4, paragraph (2), item (iii) of the Act,
entering the maximum storage capacity for each type of spent fuel to be stored;(ii) with regard to the location, structure and equipment of the spent fuel interim storage facilities set
forth in Article 43-4, paragraph (2), item (iv) of the Act, entering data in accordance with thefollowing classification:a. to h. (omitted)(iii) with regard to the storage method set forth in Article 43-4, paragraph (2), item (iv) of the Act,
entering data in accordance with the following classification:a. and b. (omitted)(iv) with regard to the construction plan for the spent fuel interim storage facilities set forth in
Article 43-4, paragraph (2), item (v) of the Act, entering the sequence and schedule of theconstruction work;(v) with regard to the method for shipping spent fuel after the termination of interim storage set
forth in Article 43-4, paragraph (2), item (vi) of the Act, entering the name of the party to which
said spent fuel is to be returned and the method thereof.
(2) A written business plan and other documents specified by the Ordinance of the Nuclear Regulation
Authority (hereinafter referred to as the “Ordinance of the NRA”) as prescribed in Article 22,paragraph (2) of the Order for Enforcement of the Act on the Regulation of Nuclear Source Material,
Nuclear Fuel Material and Reactors (hereinafter referred to as the “Order”) shall be attached to theapplication form set forth in the preceding paragraph and shall be as follows:(i) to (viii) (omitted)(3) One original copy and one duplicate copy of the application form set forth in paragraph (1) shall be
submitted.
(Application for Approval for Design and Construction Methods)
Article 4(1) A person who seeks approval for the design and construction methods of spent fuel interim storage
facilities (excluding a welding method pertaining to spent fuel interim storage facilities as
130

ANNEXES L
prescribed in Article 11 for which welding is to be performed; hereinafter the same applies in this
Article and the following Article) pursuant to the provisions of Article 43-8, paragraph (1) of the
Act shall submit an application form containing the following matters:(i) to (v) (omitted)(2) Documents explaining computationally that the design and construction methods pertaining to said
application conform with the technical standards set forth in Article 43-8, paragraph (3), item (ii) of
the Act (hereinafter referred to as the “technical standards” in this Article and the following
Article), and other documents explaining that quality control methods conform to the technicalstandards set forth in item (iii) of said paragraph.
(3) When it is impossible to file at one time an application for approval under Article 43-8, paragraph (1)of the Act regarding the design and construction methods as a whole, the applicant may file anapplication splitting the design and construction methods and explaining the reason why.
(4) One original copy of the application form set forth in paragraph (1) shall be submitted.
(Application for Pre-service Inspection)
Article 7(1) A person who intends to undergo an inspection with regard to the construction work of the spent fuelinterim storage facilities (excluding a welding method pertaining to spent fuel interim storage
facilities as prescribed in Article 11 for which welding is to be performed) and the performance
thereof pursuant to the provisions of Article 43-9, paragraph (1) of the Act shall submit anapplication form containing the following matters:(i) to (v) (omitted)(2) When the person has changed any application details in the preceding paragraph, he/she shallpromptly notify the appropriate authorities.
(3) One original copy of the application set forth in paragraph (1) and the notification highlighted in thepreceding paragraph shall be submitted.
(Implementation of Pre-service Inspection)
Article 8 A Pre-service Inspection set forth in Article 43-9, paragraph (1) of the Act shall be conducted
covering the following items and at times respectively prescribed therein:(i)matters concerning materials or components relating to the prevention of criticality of spent fuel,radiation shielding, confinement of spent fuel, and heat removal from spent fuel: duringchemical analysis tests, non-destructive tests, mechanical tests, pressure tests, or leakage tests orat any other time that the Nuclear Regulation Authority finds appropriate;(ii) matters concerning the assembly of the main body of the spent fuel interim storage equipment,
facilities for accepting spent fuel, or radioactive waste disposal facilities: when the sizes ofmajor parts of the respective facilities can be measured, or during non-destructive tests,
mechanical tests, pressure tests, or leakage tests, or at any other time that the Nuclear Regulation
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Authority finds appropriate;(iii) matters concerning the assembly of measurement and control facilities, radiation control
facilities or other auxiliary facilities of the spent fuel interim storage equipment: when therelevant facilities are completed;(iv) matters concerning the performance of the spent fuel interim storage facilities: when containers
in which spent fuel is encapsulated are installed, when the spent fuel interim storage facilities
are completed, or at any other time that the Nuclear Regulation Authority finds appropriate.

(Spent Fuel Interim Storage Facilities Subject to Welding Inspection)
Article 11 Spent fuel interim storage facilities specified by the NRA Ordinance set forth in Article 43-10,
paragraph (1) of the Act are as follows:(i)vessels belonging to the main body of the spent fuel interim storage equipment, disposal
facilities, radiation control facilities or other auxiliary facilities of the spent fuel interim storage
equipment; or pipes with an outside diameter exceeding 61mm (for pipes whose maximum
operating pressure is less than 98kPa, with an outside diameter exceeding 100mm) that belong tothese facilities, both of which contain radioactive material with a concentration of 37mBq/cm3
or more (where said radioactive material is in liquid form, 37kBq/cm3 or more);(ii) vessels of the main body of the spent fuel interim storage equipment, disposal facilities,
radiation control facilities or other auxiliary facilities of the spent fuel interim storage
equipment; pipes with an outside diameter of 150mm or more which contain radioactive
material with a concentration of less than 37mBq/cm3 (where said radioactive material is inliquid form, less than 37kBq/cm3) and whose parts to which pressures as specified as follows orlarger are applied (hereinafter referred to as the "pressure parts") need to be welded:(a) for vessels or water pipes whose maximum operating temperature is lower than 100°C, a
maximum operating pressure of 1960kPa;(b) for vessels other than those prescribed in (a) above, a maximum operating pressure of 98kPa
or more;(c) for pipes other than those prescribed in (a) above, a maximum operating pressure of 980kPa(for longitudinal joints, a maximum operating pressure of 490kPa).
(Application for Welding Inspection)
Article 12(1) A person who intends to undergo an inspection with regard to welding of the spent fuel interim
storage facilities pursuant to the provisions of Article 43-10, paragraph (1) of the Act shall submit anapplication form containing the following information to the Nuclear Regulation Authority:(i) to (v) (omitted)(2) The following documents shall be attached to an application form as set forth in the preceding
paragraph:132

ANNEXES L(i) to (iii) (omitted)(3) When any information in the application form set forth in paragraph (1) or in the documents set forthin the preceding paragraph has been changed, the applicant shall promptly notify the appropriate
authority.
(4) One original copy of the application set forth in paragraph (1) and the document from the preceding
paragraph shall be submitted.
(Implementation of Welding Inspection)
Article 13 A welding inspection as set forth in Article 43-10, paragraph (1) of the Act shall be conducted
for each of the following processes:(i)when any welding is performed (excluding situations pertaining to seal welding for vessels or
pipes set forth in Article 11, item (ii) and situations where the NRA approves the use of the
facilities, recognizing that such use will not pose any problem because of the standardization of
welding operation and materials used for welding.);(ii) with regard to welded parts for which a non-destructive test is required to confirm compliancewith the technical standards prescribed in Article 43-10, paragraph (3), item (ii) of the Act(hereinafter referred to as the “technical standards for welding”): when it becomes possible tocarry out such a non-destructive test;(iii) with regard to welded parts for which a mechanical test is required to confirm compliance withthe technical standards for welding: when it has become possible to carry out such a mechanicaltest;(iv) when it has become possible to carry out a pressure test or leakage test to confirm compliancewith the technical standards for welding (excluding the cases pertaining to seal welding forvessels or pipes set forth in Article 11, item (ii)).
(Approval for Welding Method)
Article 15(1) A person who intends to obtain approval as set forth in Article 43-10, paragraph (2) of the Act shallsubmit an application form containing the following information with regard to each welding
situation:(i) to (v) (omitted)(2) Documents explaining the following matters shall be attached to an application form as set forth in
the preceding paragraph:(i) to (iii) (omitted)(3) When the Nuclear Regulation Authority finds that the welding method submitted conforms with allof the following, it shall grant the application approval set forth in said paragraph:(i)the type and capacity of the welding equipment are appropriate for the welding method
contained in the application;
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ANNEXES(ii) the welding method is appropriate for ensuring the strength and corrosion resistance of thewelded parts;(iii) a designated welder has the requiste skills to perform the task at hand.

(4) One original copy of the application form set forth in paragraph (1) shall be submitted.
(Welding Inspection of Imported Goods)
Article 16(1) A person who intends to undergo an inspection with regard to welding of imported equipment for
spent fuel interim storage for which he/she performed the welding pursuant to the provisions ofArticle 43-10, paragraph (4) of the Act shall submit an application form containing the following
information to the NRA:(i) to (iv) (omitted)(2) The following documents shall be attached to an application form as set forth in the preceding
paragraph:(i) to (iv) (omitted)(3) When any information has been changed in the application form set forth in paragraph (1) or the
documents set forth in the preceding paragraph, the appropriate authority will be promptly notified.
(4) One original copy of the application (paragraph (1) and documents in the preceding paragraph shallbe submitted.
(Application for Periodic Facility Inspection)
Article 19(1) A person who intends to undergo an inspection with regard to the performance of the spent fuelinterim storage facilities pursuant to the provisions of Article 43-11, paragraph (1) of the Act shallsubmit an application form containing the following information:(i) to (iii) (omitted)(2) When the person has changed any details in the application form set forth in the preceding paragraph,he/she shall make a notification to that effect promptly.
(3) One original copy of the application (paragraph (1) and documents outlined in the preceding
paragraph shall be submitted.
(Implementation of Periodic Facility Inspection)
Article 20 The interval specified by the NRA Ordinance set forth in Article 43-11, paragraph (1) of the
Act shall be one year.
(Storage Plan)
Article 23(1) A storage plan of the spent fuel interim storage facilities under Article 43-13 of the Act shall be
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drawn up for each item of the spent fuel interim storage equipment in Form 1. A three-year storage
plan (starting from April 1 of the relevant year to March 31 of the following year; the same applies
hereinafter) shall be submitted every fiscal year. It will start from the fiscal year when a facility isscheduled to begin operations and will submitted no later than January 31 of the preceding fiscal
year.
(2) Notwithstanding the provisions of the preceding paragraph, in the case where permission under
Article 43-4, paragraph (1) of the Act or permission for a change under Article 43-7, paragraph (1) of
the Act is obtained during the period between February 1 of the preceding fiscal year and March 31of the relevant fiscal year and storage is to be commenced within said period, a storage plan shall be
submitted promptly after obtaining said permission.
(3) When there are any changes in the storage plan set forth in the preceding two paragraphs, anapplicant will draw up a new storage plan highlighting each change of the spent fuel interim storage
equipment in Form 1 and submit it within 30 days of any said change.
(4) One original copy of the storage plan set forth in the preceding three paragraphs shall be submitted.
(Quality Assurance)
Article 28 Pursuant to the provisions of Article 43-18, paragraph (1) of the Act, a licensee of spent fuelinterim storage activity shall draw up a quality assurance plan based on the Operational
Safety Programs, and shall organize, carry out, evaluate and constantly improve operationalsafety activities (including measures prescribed in Article 29 to Article 35-2).
(Quality Assurance Plan)
Article 28-2 A quality assurance plan shall specify the following issues:(i)the organization for conducting quality assurance;(ii) plans for operational safety activities;(iii) implementation of operational safety activities;(iv) evaluation of operational safety activities;(v) improvements in operational safety activities.
(Organization for Conducting Quality Assurance)
Article 28-3 An organization for conducting quality assurance shall be as follows:(i)the organization is operated by a licensee of spent fuel interim storage activity (in the case of acorporation, its representative);(ii) the responsibility, authority, and duties concerning quality assurance are clarified;(iii) the organization has prepared a mechanism to draw up, implement and evaluate a quality
assurance plan and make improvements to the plan on an on-going basis.
(Plans for Operational Safety Activities)
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Article 28-4 plans for operational safety activities to be specified in a quality assurance plan shall be as
follows:(i)the processes specified in Q9000 of the Japanese Industrial Standards based on the Industrial
Standardization Act (Act No. 185 of 1949) and their correlation are clarified in operationalsafety activities;(ii) quality assurance is conducted based on each stage of organizing, carrying out, evaluating, andimproving operational safety activities on an on-going basis;(iii) when procuring goods or services from third parties, the methods of managing themappropriately are specified;(iv) the details of pending operational safety activities are specified in accordance with

operationalsafety;(v) procedures for document and records management concerning operational safety activities are
specified;(vi) an education and training system for personnel who carry out operational safety activities is
specified.
(Implementation of Operational Safety Activities)
Article 28-5 Operational safety activities in a quality assurance plan shall be as follows:(i)

In individual operational safety activities (hereinafter referred to as "individual duties"), thefollowing procedures are to be followed:(a) drawing up an implementation plan for individual duties (hereinafter referred to as the"implementation plan" in this Article), and clarifying the goals and requirements;(b) performing individual duties based on the implementation plan; in this case, it should be
confirmed at an appropriate stage that said plan complies with the requirements;(c) managing appropriately any amendments to the implementation plan(ii) when procuring goods or services from third parties, the relevant person must specify
appropriate measures including management methods (while also obtaining technicalinformation on operational safety) to effectively maintain and operate said goods or services
after procurement and to share such information with other licensees;(iii) in order to confirm that individual duties comply with the implementation plan, necessary
inspections and testing are to be carried out;(iv) persons carrying out such inspections and testing are to be chosen in accordance with thesignificance for operational safety;(v) In the event of a situation of non compliance (hereinafter referred to as "non-compliance"),appropriate management methods to handle such a situation are to be specified.
(Evaluation of Operational Safety Activities)
Article 28-6 The evaluation of operational safety activities in a quality assurance plan shall be as
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follows:(i)

necessary monitoring and evaluation covering imlementation of operational safety activities will
be conducted systematically;(ii) a systematic audit will be conducted to ensure that the operational safety activities are being
carried out appropriately;(iii) Such an audit will be made by a person whose individual duties are not being evaluated.
(Improvements in Operational Safety Activities)
Article 28-7 Improvements in operational safety activities in a quality assurance plan shall be as follows:(i)

the improvements should include procedures to prevent any recurrence of non-compliance(including analysis for determining root causes of the incidents, such as accidents and failures
set forth in the items of Article 43-13, and others (hereinafter referred to as "root cause
analysis"));(ii) the improvements should include procedures to prevent non-compliance (including procedures
for root cause analysis);(iii) in taking prevention action, operational safety knowledge obtained both at one’s own spent fuelinterim storage facility and other facilities should be included;(iv) The results of the said evaluation should be reflected appropriately.
(Access to Radiation Controlled Areas)
Article 29 Pursuant to the provisions of Article 43-18, paragraph (1) of the Act, a licensee of spent fuelinterim storage activity shall designate radiation controlled areas and peripheral monitoringareas and take the following measures:(i)for radiation controlled areas:(a) establishing clearly marked zoning areas with walls, fences, and other partitions with limitedaccess or ‘lock up’ restrictions in accordance with radiation risks;(b) prohibiting eating, drinking or smoking in areas where there is a risk of inhaling radioactive
material;(c) ensuring that the density of radioactive material on the surface of floors, walls and goods thatpeople may come into contact with does not exceed the surface density limit specified by the
Nuclear Regulation Authority;(d) For persons leaving a controlled area, ensuring that the density of radioactive material on thesurface of clothing, shoes and other items (wrapped or in containers) shall not exceed 10% of
the surface density limit set forth in © above.

(ii) for peripheral monitoring areas, the following measures are to be taken:(a) prohibiting people from living in those areas;(b) installing fenses or boundary signs to limit access by unauthorized personnel (this should not
apply in areas where it is clear people will not trespass).
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ANNEXES(Measures concerning Doses,)

Article 30(1) Pursuant to the provisions of Article 43-18, paragraph (1) of the Act, a licensee of spent fuel interim
storage activity shall take the following measures, with regard to doses of radiation workers:(i)ensuring that the doses of radiation workers do not exceed theNRA specified limits;(ii) ensuring that the concentration of radioactive material in the air does not exceed theconcentration limit specified by the Nuclear Regulation Authority.
(2) Irrespective of the provisions of the preceding paragraph, where it is urgent and unavoidable, such aswhere a disaster has occurred or may occur at a spent fuel interim storage facility, it may bepermissible to employ workers in emergency tasks within a dose range that does not exceed limits
specified by the Nuclear Regulation Authority. (female workers are limited toinfertile women or

those who have already notified the relevant licensee in writing of their intention to avoid
pregnancy).
(Patrol and Checking of Spent Fuel Interim Storage Facilities)
Article 31(1) Pursuant to Article 43-18, paragraph (1) of the Act, a licensee of spent fuel interim storage activity
shall employ personnel to patrol and check the facility at least once a day (excluding those who haveobtained approval as set forth in Article 43-27, paragraph (2) of the Act).
(2) Pursuant to the provisions of Article 43-18, paragraph (1) of the Act, a licensee of spent fuel interim
storage activity who has obtained approval as set forth in Article 43-27, paragraph (2) of the Act
shall employ radiation workers who ordinarily enter radiation controlled areas to patrol the spent fuelinterim storage facilities at least once every week.
(Periodic Self-Inspection of Spent Fuel Interim Storage Facilities)
Article 32(1) Pursuant to the provisions of Article 43-18, paragraph (1) of the Act, a licensee of a spent fuelinterim storage activity shall take inspection measures set forth in the following items (when theapproval set forth in Article 43-27, paragraph (2) of the Act has been obtained, excluding item (i)):(i)

conducting an annual inspection to determine whether the performance of the spent fuel interim
storage facility conforms with the technical standards specified by the NRA Ordinanceprescribed in Article 43-10-2 of the Act;(ii) conducting monthly tests of each part of alarm and other emergency devices and annual
performance tests for each overall device.
(iii) conducting annual calibration tests for instruments and radiation detectors that directly relate tothe operational safety of spent fuel interim storage facilities.
(2) A licensee who has obtained approval as set forth in Article 43-27, paragraph (2) of the Act shallconduct an annual inspection to ensure that operations of a spent fuel interim storage facility is138

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maintained as stated in the application form for said approval or the approval for a change as set forthin Article 12-6, paragraph (3) of the Act as applied mutatis mutandis pursuant to Article 43-27,
paragraph (3) of the Act, or documents attached to such application form.
(Operation of Spent Fuel Interim Storage Equipment)
Article 33 Pursuant to the provisions of Article 43-18, paragraph (1) of the Act, a licensee shall take thefollowing measures for the operation of spent fuel interim storage equipment (this does not
apply where approval in Article 43-27, paragraph (2) of the Act has been obtained):(i)having qualified personnel persons operate the spent fuel interim storage equipment;(ii) ensuring that qualified personnel are on duty during any spent fuel interim storage equipment
operations;(iii) qualified operators oversee pre-commencement, commencement and post-shutdown operations;(iv) specifying actions to be taken in an emergency overseen by qualified personnel;(v) maintaining ventilators, radiation detectors and emergency equipment to allow them to function
at any time;(vi) before starting test operations, checking measures to be taken in the event of an abnormality;(vii) during operational training, trainees under the supervision of operators, are instructed on mattersto be observed;(viii)storing spent fuel in the main body of the spent fuel interim storage equipment;(ix) precautions to be taken when storing spent fuel in a prominent place at an interim storage
facility;(x) Personnel other than those directly engaged in the interim storage of spent fuel follow the
instructions of qualified operators in the facility;(xi) taking necessary measures for spent fuel cooling;(xii) storing spent fuel to prevent it reaching criticality in any situation.
(Transport within the Site)
Article 34(1) Pursuant to the provisions of Article 43-18, paragraph (1) of the Act, a licensee of a spent fuelinterim storage facility shall take the following measures covering the transportation of spent fuelwithin the site:(i)transporting spent fuel in a manner to reduce the risk of it reaching criticality under any
circumstance;(ii) during transportation, encasing spent fuel in a container but with the following exceptions:(a) transporting contaminated material with a radioactive concentration not exceeding NRA limits
and for which prevention measures specified by the NRA have already been taken.
(b) transporting bulky loads such as large machinery that is difficult to encasebut otherwise
employing NRA approved hazard prevention measures;
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ANNEXES(iii) transport containers shall conform with the following standards:(a) the length of each side of the cuboid circumscribed to said container is no shorter than 10 cm;(b) a container can be handled easily and safely and will not suffer from cracks or damage fromchanges in temperature, internal pressures and oscillation during transportation;(iv) ensuring that the dose equivalent rates at the surface and at a distance of one meter from thesurface of a container will not exceed the dose equivalent rates specified by the Nuclear
Regulation Authority and that the density of radioactive material on the surface of the material to
be transported will not exceed 10% of the surface density limit set forth in Article 29, item (i),(c);(when transport is conducted without encapsulating the material contaminated by nuclear fuelmaterial prescribed in item (ii), (a) or (b) in a container, pursuant to the provisions of the proviso to
said item, said material contaminated by spent fuel; hereinafter referred to as "material to be shipped"in this Article), the vehicle loading or containing said material to be transported, or other machineryor components for transporting the spent fuel, etc. (hereinafter referred to as "transport equipment" inthis Article) will not exceed the dose equivalent rates specified by the Nuclear Regulation Authority,
respectively, and that the density of radioactive material on the surface of the material to betransported will not exceed 10% of the surface density limit set forth in Article 29, item (i), (c);(v) ensuring that contamined materials do not move, fall or drop during transportation;(vi) ensuring that spent fuel is not loaded onto the same transport as hazardous materials specified by
the Nuclear Regulation Authority;(vii) deploying guards, signs and other measures at necessary locations along the transportation routeto limit the number of unauthorized personnel or vehicles;(viii)reducing transportation speeds and, over long distances, employing a backup escort security
vehicle;(ix) to ensure security, employing a person qualified in handling spent fuel to accompany andsuervise as necessary;(x) Transport and containers to be clearly marked by NRA-approved labels. (closed type containers
should be designed not to require reshipment enroute, be able to withstand repeated use and beequipped for mechanical loading and offloading).

(2) In the case set forth in the preceding paragraph, when it is difficult to implement the measures set
forth in item (iii) and item (iv) due to special reasons, it is permissible to user other NRA-approved
measures (provided that does equivalent rates at the surface of the material does not exceed NRAlimits).
(3) The provisions of paragraph (1), item (ii) to item (iv) and item (vii) to item (x) do not apply totransportation within radiation controlled areas.
(4) In the case where a licensee has taken necessary security measures with regard to the transport ofspent fuel according to the technical standards for transport prescribed in Article 3 to Article 17 of the
Ministerial Ordinance on Transport of Nuclear Fuel Material,. Outside the Factory or Site (Ministerial
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Ordinance Issued by the Prime Minister's Office No. 57 of 1978) and Article 3 to Article 19 of the
Ministerial Ordinance on Transport of Nuclear Fuel Material,by Vehicle (Ordinance of the Ministry ofTransport No. 72 of 1978), the licensee may transport said spent fuel within the spent fuel interim
storage facility complex, notwithstanding the provisions of paragraph (1).
(Disposal within the Site)
Article 35 Pursuant to the provisions of Article 43-18, paragraph (1) of the Act, a licensee of spent fuelinterim storage activity shall take the following measures to dispose of radioactive waste at
the spent fuel interim storage facility:(i)radioactive waste disposal is conducted by appropriately dressed personnel skilled in disposal
and related radiation protection expertise;(ii) persons entering the disposal facilities and not directly engaged in the activities must follow the
instructions of those engaged in the disposal;(iii) disposing of gaseous radioactive waste with either of the following methods:(a) discharging such waste through the exhaust facilities;(b) storing waste in tanks to prevent radiation hazards;(iv) when adopting the disposal method set forth in (a), reducing as much as possible theconcentration of radioactive material in the exhaust through filtration, radioactivity decay, andair dilution at the exhaust facilities; in such a circumstance, monitoring radioactive material
concentrations at the exhaust vent or exhaust monitoring equipment, to ensure that they do not
exceed NRA limits in the air outside the peripheral monitoring area;(v) disposing of radioactive liquid waste by any of the following methods:(a) discharging waste through the drainage facilities;(b) storing waste for disposal in tanks to prevent radiation hazards;(c) encasing waste in a vessel or solidifying it with a vessel and storing it for disposal at a storage
facility capable of preventing radiation hazards;(d) solidifying waste in solidification equipment capable of preventing radiation hazards;(vi) when adopting the disposal method in (a) of the preceding item, reducing radioactive material
concentrations in the effluent as much as possible through filtration, evaporation, adsorption
using the ion-exchange resin method, radioactivity decay and dilution with a large amount ofwater at the drainage facilities; in this case, monitoring the concentration of radioactive material
in the effluent at the discharge port or effluent monitoring equipment, thereby ensuring thatradioactive concentrations in the water at the boundary outside the peripheral monitoring area do
not exceed NRA-mandated limits.
(vii) when adopting the disposal method set forth in (c) of item (v) and encasing radioactive waste ina vessel, said vessel shall conform to the following standards:(a) the vessel has a less permeable structure, is resistant to corrosion, and prevents leaks ofradioactive waste;
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ANNEXES(b) the vessel is risk free from cracks or other damage;(c) the vessel lid is hard to remove;(viii)when adopting the disposal method in (c) of item (v) solidifying radioactive waste with acontainer, the vessel shall be able to prevent a scatter or leak of radioactive waste;(ix) when adopting the disposal method set forth in (c) of item (v) storing radioactive waste for
disposal at a storage disposal facility able to prevent radiation hazards, the following procedures
are to be followed:(a) when encasing radioactive waste in a vessel and storing it for disposal, taking measures toprevent the spread of contamination should the vessel develop and cracks or otherdamage,including covering said container with materials that can absorb the radioactive waste
in its entirety, or by installing a tray to receiv all of radioactive waste;(b) signposting a container encasing or solidified with radioactive waste, and providing a serial
number for cross checking said radioactive waste with the details recorded based on theprovisions of Article 27;(c) posting precautions for management in a prominent place at said storage facilities;(x) disposing solid radioactive waste by any of the following methods:(a) incinerating waste in an incinerator capable of preventing radiation hazards;(b) encapsulating waste in a vessel or solidifying it with a container and storing said waste before
disposal at an appropriate storage disposal facility;(c) with regard to such radioactive waste such as large machinery which is difficult to dispose of
by method (b) above, or waste that requires radioactivity decay, storing such waste for
disposal at a storage facility that can prevent radiation hazards;(xi) The provisions of item (vii), item (viii) and item (ix) (excluding (a) of said item) shall apply
mutatis mutandis with regard to disposal by the method set forth in (b) of the preceding item;(xii) The provisions of (c) of item (ix) shall apply mutatis mutandis with regard to disposal by themethod set forth in (c) of item (x).

(Periodic Evaluation of Spent Fuel Interim Storage Facilities)
Article 35-2
(1) Pursuant to the provisions of Article 43-18, paragraph (1) of the Act, a spent fuel interim storage
facility licensee shall undertake the following measures for each of the spent fuel interim storage
facilities at intervals not exceeding ten years:(i)evaluating operational safety activities at the spent fuel interim storage facility;(ii) evaluating the incorporation of the latest technical knowledge into operational safety activities.
(2) A licensee shall undertake the following measures no later than the 20th anniversary of the day that
operations began:(i)conducting a technical evaluation on ageing;(ii) based on the technical evaluation outlined in the preceding item, drawing up a ten-year142

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operational safety plan for the spent fuel interim storage facility.
(3) The evaluation and plan outlined in the preceding paragraph shall be reevaluated at intervals of notexceeding ten years.
(4) The provisions of the preceding three paragraphs do not apply where an approval in Article 43-27,
paragraph (2) of the Act has already been obtained.
(Operational Safety Programs)
Article 37(1) A person seeking approval for Operational Safety Programs under Article 43-20, paragraph (1) of the
Act shall specify the following details for each site for which he/she intends to obtain approval, andshall submit an application form containing said Operational Safety Programs to the Nuclear
Regulation Authority:(i)matters concerning compliance with related laws and regulations, as well as the Operational
Safety Programs (including senior management involvement);(ii) matters concerning the development of a safety culture (including senior management
involvement);(iii) matters concerning quality assurance of the spent fuel interim storage facilities (including themethod and system for conducting root cause analysis and positioning of the procedure manuals
in the Operational Safety Programs);(iv) matters governing the duties of those engaged in the operation and management of the spent fuelinterim storage facilities and their organization (excluding what is set forth in the followingitem);(v) matters covering the duties of chief engineers of spent fuel, the authority necessary for chiefengineers of spent fuel in supervising operational safety, and their positions in the organization;(vi) matters concerning operational safety education for radiation workers at spent fuel interim
storage facilities:(a) matters governing policies to provide operational safety education (including drawing up an
implementation plan);(b) details of education on operational safety in the following areas:
1. compliance with related laws and regulations, as well as Operational Safety Programs;
2. the structure, functions, and operation of spent fuel interim storage facilities;
3. radiation control;
4. the handling of nuclear fuel material and contaminated material;
5. actions to be taken in an emergency;(c) other matters necessary for operational safety education related to spent fuel interim storage
facilities;(vii) the operation of equipment, the management of which is particularly necessary in view ofoperational safety;
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ANNEXES(viii)the specification of radiation controlled areas and peripheral monitoring areas, as well as theaccess control to these areas;(ix) the exhaust and effluent monitoring equipment;(x) the monitoring of doses, dose equivalents, concentration of radioactive material, and density ofradioactive material on the surface of radioactively contaminated materials, as well as thedecontamination;(xi) the management of radiation detectors and measurement methods;(xii) the policing and security of spent fuel interim storage facilities and accompanying actions;(xiii)the periodic self-inspection of spent fuel interim storage facilities;(xiv) the reception, transport, and other handling of spent fuel;(xv) the disposal of radioactive waste;(xvi) actions to be taken in an emergency;(xvii) maintenance of proper records and reports on operational safety pertaining to the spent fuelinterim storage facilities (including the status of compliance with the Operational Safety
Programs). Such reports include ones made to senior management following any incidents suchas accidents and other failures under items of Article 43-13,;(xviii) periodic evaluation of the spent fuel interim storage facilities;(xix) sharing with other licensees technical information on operational safety obtained from thebusiness operators involved in maintenance and checks;(xx) information disclosure on non-compliance if any;(xxi) other matters necessary for operational safety of spent fuel interim storage facilities.

(2) A person seeking approval under Article 43-27, paragraph (2) of the Act shall add the following
details to the Operational Safety Programs approved under Article 43-20, paragraph (1) of the Act orobtain approval for the amended Operational Safety Programs, for the purpose of undertaking
decommissioning measures specified in a decommissioning plan for which he/she intends to obtainapproval, no later than the date of said approval. The same applies when intending to further amend
said amended Operational Safety Programs. Matters include:(i)the system for complying with the related laws and regulations, as well as the Operational Safety
Programs (including senior management involvement);(ii) the system for developing a safety culture (including senior management involvement);(iii) quality assurance of the spent fuel interim storage facilities (including a system for conducting
root cause analysis, and positioning of the procedure manuals in the Operational Safety
Programs);(iv) quality assurance of the decommissioning measures (including the system for conducting root
cause analysis, and positioning of the procedure manuals in the Operational Safety Programs);(v) the duties of those engaged in decommissioning measures and their organization (excluding
what is set forth in the following item);(vi) the duties of chief engineers of spent fuel, the authority necessary for them to supervise
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operational safety and their positions in the organization;(vii) operational safety education for radiation workers engaged in decommissioning measures:(a) policies for providing education on operational safety (including the drawing up of an
implementation plan)(b) the following matters concerning the details of education on operational safety:
1. compliance with related laws and regulations, as well as Operational Safety Programs;
2. the structure and functions of spent fuel interim storage facilities;
3. decommissioning measures for spent fuel interim storage facilities;
4. radiation control;
5. the handling of nuclear fuel material and material contaminated by nuclear fuel material;
6. actions to be taken in an emergency;(c) other matters necessary for education on operational safety pertaining the spent fuel interim
storage facilities;(viii)the operation of equipment, the management of which is crucial to operational safety;(ix) the specification of radiation controlled areas, protection areas, and peripheral monitoring areas,
as well as access control to these areas;(x) the exhaust monitoring equipment and effluent monitoring equipment;(xi) monitoring of doses, dose equivalents, concentration of radioactive material, and density ofradioactive material on the surface of material contaminated by radioactive material, as well as
the removal of contamination;(xii) the management of radiation detectors and measurement methods;(xiii)the periodic self-inspection of the spent fuel interim storage facilities;(xiv) the policing of spent fuel interim storage facilities and accompanying actions;(xv) the disposal of radioactive waste;(xvi) actions to be taken in an emergency;(xvii) establishment of proper records and reports on operational safety pertaining to the spent fuelinterim storage facilities, including the status of compliance with the Operational Safety
Programs. Such reports include ones made to senior management in the event of incidents suchas accidents and failures set forth in the items of Article 43-13;(xviii) matters concerning proper records and reports on operational safety pertaining to thedecommissioning measures including the status of compliance with the Operational Safety
Programs (such reports include ones made to senior management in the event incidents such asaccidents and failures set forth in the items of Article 43-13;(xix) sharing with other licensees of spent fuel interim storage facilities technical information on
operational safety documented by maintenance and checks operators;(xx) information disclosure on non-compliance if any;(xxi) management of decommissioning measures;(xxii) other matters on operational safety of spent fuel interim storage facilities or decommissioning
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(3) The provisions of the main clause of paragraph (1) apply mutatis mutandis in the cases set forth in
the preceding paragraph.
(4) One original copy of the application form set forth in paragraph (1) (including the cases where said
paragraph is applied mutatis mutandis pursuant to the preceding paragraph) shall be submitted.
(Inspection of the Status of Compliance with the Operational Safety Programs)
Article 38(1) An inspection under Article 43-20, paragraph (5) of the Act will be conducted four times every
year; however, the inspection for spent fuel interim storage facilities for which approval as set forthin Article 43-27, paragraph (2) of the Act has been obtained, will be conducted four times or lessevery year, in accordance with the progress of the decommissioning measures.
(2) The matters specified by the Ordinance of the NRA as set forth in Article 12, paragraph (6) of the
Act as applied mutatis mutandis pursuant to Article 43-20, paragraph (6) of the Act shall be as
follows:(i)

entering the office, facility or site;(ii) inspecting books, documents, equipment, components, or any other necessary property;(iii) questioning employees and other people concerned;(iv) requesting the submission of spent fuel or any other necessary samples (limited to the minimum
amount necessary for testing).
(Physical Protection Programs)
Article 41(1) A person seeking approval for Physical Protection Programs under Article 43-25, paragraph (1) of
the Act shall submit an application form for said Physical Protection Programs to the NRA andspecify the following matters for each place of business:(i)a system for complying with related laws and regulations, as well as the Physical Protection
Programs (including senior management involvement);(ii) a system for developing a security culture (including senior management involvement);(iii) the duties of those engaged in the physical protection of specified nuclear fuel material and theirorganization;(iv) specifications of the physical protection areas (for the place of business handling the specified
nuclear fuel material set forth in item (i) to item (vi) of the table of Article 36, paragraph (1), thephysical protection areas and peripheral physical protection areas; the same applies in thefollowing item) and the access control areas, as well as the patrol and monitoring;(v) access control for physical protection areas;(vi) management of specified nuclear fuel material;(vii) measures for the constant maintainence of equipment or devices necessary for the physical146

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protection of specified nuclear fuel material;(viii)an information system security plan;(ix) maintenance and inspection of equipment to physically protect specified nuclear fuel material;(x) emergency responses;(xi) the development of a communication system;(xii) information management on measures necessary for the physical protection of specified nuclear
fuel material;(xiii)the education and training necessary for the physical protection of specified nuclear fuelmaterial;(xiv) an emergency response plan for spent fuel interim storage facilities;(xv) measures to be taken in response to threats such as sabotage (limited to matters falling under
Article 36, paragraph (2), item (xxiv) (including cases where said item is applied mutatis
mutandis pursuant to paragraph (3) of said Article));(xvi) periodic evaluation and improvements necessary for the physical protection of specified nuclear
fuel material;(xvii) records on the physical protection of specified nuclear fuel material pertaining to the spent fuelinterim storage facilities (including the status of compliance with physical protection programs);(xviii) other items necessary for the physical protection of specified nuclear fuel material at spent fuelinterim storage facilities.
(2) One original copy and one duplicate copy of the application form set forth in the preceding paragraphshall be submitted (when filing an application for any of the spent fuel interim storage facilities set
forth in item (iv) of the table of Article 63, paragraph (1) of the Order that is specified by the Nuclear
Regulation Authority in a public notice, one original copy and two duplicate copies of the applicationform).
(Inspection of the Status of Compliance with the Physical Protection Programs)
Article 41-2
(1) The inspection under Article 12-2, paragraph (5) of the Act as applied mutatis mutandis pursuant to
Article 43-25, paragraph (2) of the Act is to be conducted once every year.
(2) Matters specified by the NRA Ordinance as set forth in Article 12-2, paragraph (6) of the Act asapplied mutatis mutandis pursuant to Article 43-25, paragraph (2) of the Act shall be as follows:(i)entering the office, facility or site;(ii) inspecting books, documents, equipment, components, or any other necessary property;(iii) questioning employees and other people concerned;(iv) requesting the submission of specified nuclear fuel material, or any other necessary samples(limited to the minimum amount necessary for testing).
(Application for Approval for Decommissioning Plans)
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Article 43-3-2(1) A person seeking approval for a plan concerning decommissioning measures (hereinafter referred toas a "decommissioning plan"), pursuant to the provisions of Article 43-27, paragraph (2) of the Act,
shall draw up a decommissioning plan concerning the matters set forth in the following items andsubmit an application form containing said plan to the Nuclear Regulation Authority:(i)the name and address of the applicant and, in the case of a corporation, the name of its
representative;(ii) the name and location of the place of business pertaining to the decommissioning measures;(iii) the spent fuel interim storage facilities subject to decommissioning measures pertaining to thedecommissioning plan for which approval as set forth in Article 43-27, paragraph (2) of the Act
is sought (hereinafter referred to as the “facilities under decommissioning measures”) and theirpremises;(iv) facilities to be dismantled and the methods of the dismantlement;(v) removal of contamination caused by spent fuel;(vi) disposal of material contaminated by spent fuel;(vii) decommissioning processing measures.
(2) The documents or drawings set forth in the following items shall be attached to the application form
set forth in the preceding paragraph:(i) to (x) (omitted)(3) One original copy and one duplicate copy of the application form set forth in paragraph (1) shall be
submitted.
(Standards for Approval for Decommissioning Plans)
Article 43-6 The standards specified by the Ordinance of the NRA as prescribed in Article 12-6,
paragraph (4) of the Act as applied mutatis mutandis pursuant to Article 43-27, paragraph (3) of the
Act shall be as follows:(i)

spent fuel has been removed from the spent fuel interim storage facilities;(ii) the management, processing, and disposal of material contaminated by spent fuel has been
conducted in an appropriate manner;(iii) the implementation of the decommissioning measures is appropriate to prevent disasters that
could be caused by material contaminated by spent fuel.
(Application for Confirmation of the Completion of Decommissioning Measures)
Article 43-7
(1) A person who wishes to obtain confirmation of the completion of the decommissioning measures,
pursuant to the provisions of Article 12-6, paragraph (8) of the Act as applied mutatis mutandis
pursuant to Article 43-27, paragraph (3) of the Act, shall submit an application form to the NRA
containing following items:
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ANNEXES L(i) to (v) (omitted)(2) A document containing the following matters shall be attached to the application form set forth in thepreceding paragraph:(i) and (ii) (omitted)(3) One original copy and one duplicate copy of the application form set forth in paragraph (1) shall be
submitted.
(Standards for Confirmation of the Completion of Decommissioning Measures)
Article 43-8 The standards specified by the NRA Ordinance as prescribed in Article 12-6, paragraph (8)of the Act as applied mutatis mutandis pursuant to Article 43-27, paragraph (3) of the Act shall be as
follows:(i)there is no need to take any measures to prevent soil radiation hazards in the premises of the
facilities under decommissioning and facilities remaining on said premises;(ii) the disposal of the material contaminated by spent fuel has been completed;(iii) the handover of the radiation control records prescribed in Article 27, paragraph (1) to anorganization designated by the Nuclear Regulation Authority set forth in paragraph (5) of said
Article has been completed.
(Report of Accidents and Failures)
Article 43-13 When falling under any of the following items, a licensee of a spent fuel interim storage
facility (including former licensees; hereinafter the same applies in the following Article
and Article 48) shall immediately inform the Nuclear Regulation Authority, and make a asituation report and actions to be taken within ten days, pursuant to the provisions ofArticle 62-3 of the Act:(i)when any spent fuel has been stolen or has gone missing;(ii) in the event of a failure of the spent fuel interim storage facilities and when special measures are
required for repair work and this has interrupted the interim storage of spent fuel;(iii) when a failure has interrupted or might possibly interrupt the interim storage of spent fuel in alimited area; has interrupted the function for preventing radiation hazards due to externalradiation, the removal function of the decay heat from the spent fuel, or the function forpreventing a fire or explosion;(iv) when a failure or other unexpected event in the spent fuel interim storage facilities has caused
abnormalities in discharging gaseous radioactive waste through the exhaust facilities ordischarging radioactive liquid waste through the drainage facilities;(v) where gaseous radioactive waste has been discharged through the exhaust facilities, and when
the concentration of radioactive material in the air outside the peripheral monitoring area has
exceeded the concentration limit set forth in Article 35, item (iv);(vi) where radioactive liquid waste has been discharged through the drainage facilities, and when the149

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ANNEXESconcentration of radioactive material in the water at the boundary outside the peripheral
monitoring area has exceeded the concentration limit set forth in Article 35, item (vi);(vii) when any spent fuel has leaked outside the radiation controlled area;(viii)when a failure or other unexpected event has caused a leak of spent fuel leak within a radiation
controlled area; provided, however, that the cases falling under any of the following are
excluded (excluding the cases where measures have been newly taken such as access control orlock up the place where the leak occurred or the case where the leaked material has spread tooutside the radiation controlled area):(a) when leaked liquid spent fuel has not spread outside the weir to prevent the spread of any leakthat had been installed around the equipment where the leak occurred;(b) where spent fuel in the form of gas has leaked but where the ventilators at the leak site
continue to functionin properly;(c) when the radiation leakof spent fuel is minor;(ix) when the spent fuel has reached or may possibly reach criticality;(x) when a failure or other unexpected events have caused persons in the radiation controlled area tobe exposed to doses which exceeded or may possibly exceed 5mSv for radiation workers or
0.5mSv for persons other than radiation workers;(xi) when any radiation worker has been exposed to radiation that exceeds or may possibly exceed
the dose limit set forth in Article 30, paragraph (1), item (i);(xii) any other hazard or potential hazard which may affect people in relation to the spent fuelfacilities, exluding those hazards (except radiation incidents) that do not require hosptal
treatment.

(Emergency Measures)
Article 44 Pursuant to the provisions of Article 64, paragraph (1) of the Act, a licensee of spent fuelinterim storage activity shall take the following emergency measures:(i)

Immediately extinguish an outbreak of fire and preventing it from spreading to the spent fuelinterim storage facilities and at the same time immediately reporting the outbreak to fire
authorities;(ii) moving spent fuel to a safar place if time allows and prohibiting access to everyone except
guards and officials erecting warning signs and roping off threatened areas;(iii) to prevent radiation hazards, warning people within or near spent fuel interim storage facilities
to evacuate;(iv) preventing the spread of spent fuel contamination and removing the contaminant;(v) rescuing and promptly evacuating persons who have received or possibly receiving radiation
hazards;(vi) taking other necessary measures for preventing radiation hazards.

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Table G1-2 Ordinance on Standards for the Location, Structure, and Equipment of Spent Fuel Interim
Storage Facilities (Excerpt)(Prevention of Criticality of Spent Fuel)
Article 3 Spent fuel interim storage facilities shall be designed to prevent any risk that spent fuelmay reach criticality.
(Shielding)
Article 4(1) Spent fuel interim storage facilities shall incorporate measures such as shielding tosignificantly reduce doses around the place of business from direct and sky-shine radiation.
(2) To prevent radiation hazards, spent fuel interim storage facilities shall incorporate measures
such as shielding to reduce doses in radiation controlled areas or other places within thebusiness area where people are present.
(Function to Confine Spent Fuel)
Article 5: Spent fuel interim storage facilities shall be able to effectively confine spent fuel in alimited area.
(Heat Removal)
Article 6: Spent fuel interim storage facilities shall be able to effecively remove the decay heat ofspent fuel without using power.
(Prevention of Fire Damage)
Article 7: Spent fuel interim storage facilities shall use a combination of the following measures toensure so that basic safety functions will not be impaired by fire or explosions;(i)preventing fires or explosions;(ii) detecting early fires or explosions and controlling any outbreak;(iii) reducing the effects of fire and explosions.
(Constructing Spent Fuel Interim Storage Facilities)
Article 8(1) Spent fuel interim storage facilities shall be constructed on terrain that can support saidcomplexes even in the case of seismic shocks calculated under paragraph (2) of the following
Article (with regard to facilities that are capable of ensuring basic safety functions, including
the impact of seismic force set forth in paragraph (3) of said Article).
(2) Spent fuel interim storage facilities shall be constructed in areas where there is a negligible
possibility of loss of basic safety functions even in the event of its deformation.
(3) Facilities to ensure basic safety functions shall be constructed on terrain where there is151

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(Prevention of Damage due to Earthquakes)
Article 9(1) Spent fuel interim storage facilities shall be designed to fully sustain a seismic force.
(2) Such seismic forces shall be calculated in accordance with degrees of radiation impact on the
public resulting from a possible loss of facility safety functions caused by an earthquake.
(3) Spent fuel interim storage facilities shall be designed to protect their basic safety functions,while in service, against a seismic force that acts due to acceleration caused by an earthquakethat may possibly exercise large effects on said spent fuel interim storage facilities.
(4) Spent fuel interim storage facilities shall be designed to retain their basic safety functions evenin the event of slope failure triggered by earthquakes..
(Prevention of Tsunami Damage)
Article 10: Spent fuel interim storage facilities shall be designed to retain their basic safetyfunctions even in the event of a major impact from a tsunami(Prevention of Damage from Other External Events)
Article 11(1) Spent fuel interim storage facilities shall be designed to retain their basic safety functions evenin the event of natural phenomena other than earthquakes and tsunamis.
(2) Spent fuel interim storage facilities shall be designed to retain their basic safety functions in
the wake of human-induced incidents (excluding intentional events) within the business areaor nearby vicinity that could potentially impair the safety of said facility(Prevention of Illegal Entry into Spent Fuel Interim Storage Facilities)
Article 12: The business area will be equipped to prevent illegal entry or the introduction of
explosives, flammable and other items which could cause personal harm, as well as
unauthorized computer access (as prescribed in Article 2, paragraph (4) of the Act on
the Prohibition of Unauthorized Computer Access (Act No. 128 of 1999)).
(Facilities with Safety Functions)
Article 13:(1) When sharing any facilities with safety functions with other nuclear facilities or sharing any
equipment belonging to facilities with safety functions within single spent fuel interim storage
facilities, said facilities with safety functions or equipment shall be such that they do notdamage the safety of the spent fuel interim storage facilities.
(2) Facilities with safety functions shall be subject to an inspection or testing to confirm the152ANNEXES L
integrity of said safety functions and their proper maintenance or repair.
(Prevention of Radiation Hazards in the Event of a Postulated Accident that May Cause theHighest Dose)
Article 14 Spent fuel interim storage facilities shall be designed to prevent public radiation
hazards around the place of business in the event of an assumed accident which could
cause the highest dose.
(Metal Cask)
Article 15(1) Spent fuel interim storage facilities shall be equipped with metal casks.
(2) A metal cask shall be such that it can ensure the integrity of spent fuel in light of the ageing ofsaid metal cask and the spent fuel.
(Facilities for Accepting Spent Fuel)
Article 16: Spent fuel interim storage facilities shall have facilities both to accept spent fuel while
ensuring the basic safety functions during transporting and receipt of the metal casks inwhich spent fuel is encased.
(Instrumentation and Control Facilities)
Article 17:(1) Spent fuel interim storage facilities shall have instrumentation and control facilities toproperly monitor that as part of the basic safety functions, the function for confining spent
fuel and the function for removing heat are secured.
(2) Spent fuel interim storage facilities shall be able to detect and immediately raise the alarm
about the possibility of an accident which could damage the complex’ basic safety functions
where the concentration of radioactive material or radiation doses set forth in Article 19, item(ii) has risen significantly, or where there is a risk that a significant amount of radioactive
waste could leak from disposal facilities.
(Disposal Facilities)
Article 18:(1) Spent fuel interim storage facilities shall have disposal facilities (excluding those for storing
radioactive waste for disposal) able to treat radioactive waste generated in said facilities andsignificantly reduce airborne radioactive concentrations outside the peripheral monitoring area
and in water at the border of the peripheral monitoring area.
(2) Spent fuel interim storage facilities shall be able to store radioactive waste for disposal.
(Radiation Control Facilities)
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Article 19: The business are shall have radiation control facilities, as prescribed as follows:(i)equipment for monitoring and managing doses to help protect radiation workers;(ii) equipment to monitor and measure radioactive material concentrations and radiation
doses within the business place and surrounding area;(iii) equipment to register information at an appropriate place to help protect the public andradiation workers from radiation.
(Standby Power)
Article 20: Spent fuel interim storage facilities shall secure standby power for monitoring andother necessary equipment in the event of loss of electric power supply from theoff-site power grid.
(Communications Equipment)
Article 21(1) The business place shall have a warning device and communications equipment

to deliver

necessary instructions to personnel in the area in the event of an accident.
(2) The place of business shall be able to communicate with necessary places outside theimmediate vicinity with a dedicated communications system in the event of an accident.
(3) Spent fuel interim storage facilities shall have equipment to assist in the evacuation of people
from the place of business.
Table G1-3 Ordinance on Technical Standards for the Design and Construction Methods of Spent FuelInterim Storage Facilities (Excerpt)(Prevention of Criticality of Spent Fuel)
Article 3: Spent fuel interim storage facilities shall have measures such as criticality-safe
geometries to eliminate the possibility that spent fuel may reach criticality.
(Prevention of Damage due to Fire)
Article 4:(1) If there is a risk that spent fuel interim storage facilities may be affected by a fire or explosion
and their basic safety functions damaged, automatic fire extinguishing and alarm equipment
shall be installed..
(2) The fire extinguishing equipment and alarm equipment set forth in the preceding paragraphshall be such that their failure, damage or malfunction would be unlikely to impair the basic
safety functions of the spent fuel interim storage facilities.
(3) With regard to facilities with safety functions that may be damaged by a fire or explosion,
noncombustible or nonflammable materials shall be used wherever possible, while preparing
proper protection measures such as the installation of fire walls.
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ANNEXES L(Ground for Constructing Spent Fuel Interim Storage Facilities)
Article 5: Spent fuel interim storage facilities shall be constructed on terrain capable of supporting
such structures even in the case of seismic tremors described in Article 8, paragraph (1)of the Ordinance on Standards for Permission for Activity.
(Prevention of Earthquake Damage)
Article 5-2: Spent fuel interim storage facilities shall be constructed so that even seismic damage(calculated under Article 9, paragraph (2) of the Ordinance on Standards for
Permission for Activity) will not cause radiation hazards to the public.
(2) Spent fuel interim storage facilities shall be constructed so that their basic safety functions will
not be impaired by a seismic force set forth in Article 9, paragraph (3) of the Ordinance onStandards for Permission for Activity.
(3) In order to ensure that the basic safety functions of spent fuel interim storage facilities will not
be impaired due to slope failure resulting from an earthquake set forth in Article 9, paragraph(3) of the Ordinance on Standards for Permission for Activity, protection and other relevantmeasures shall be taken.
(Prevention of Damage due to Tsunamis)
Article 5-3: To ensure that the basic safety functions of spent fuel interim storage facilities will
not be impaired due to tsunamis set forth in Article 10 of the Ordinance on Standards
for Permission for Activity, protective and other necessary measures shall be taken.
(Prevention of Damage due to Impacts from the Other External Events)
Article 5-4:
(1) Where there is a risk that other natural phenomena (excluding earthquakes and tsunamis) may
impair the basic safety functions of spent fuel interim storage facilities, protective measures
such as strengthening ground foundations shall be taken.
(2) In regions adjacent to a peripheral monitoring area where there are places of business,railways, roads, or other factors that may cause outside impacts, protective and other measures
shall be taken. They will ensure that the basic safety functions of a spent fuel interim storage
facility will not be impaired because of fire, explosions or accidents involving vehicles, ships
or aircraft carrying hazardous materials or any other human-induced events excluding
intentional events.
(Prevention of Illegal Entry into Spent Fuel Interim Storage Facilities)
Article 5-5: The place of business where spent fuel interim storage facilities are installed(hereinafter referred to as the “place of business”) shall prepare measures to prevent
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that could harm personnel or cause physical damage. Other measures will be
introduced to block

unauthorized computer access as prescribed in Article 2,paragraph (4) of the Act on the Prohibition of Unauthorized Computer Access (ActNo. 128 of 1999.
(Materials and Structures)
Article 6:(1) Materials and structures of vessels and pipes belonging to spent fuel interim storage facilities
and structures that support them and which are necessary to ensure their basic safety functions,shall be of sufficient strength and resistant to corrosion to fulfill their function.
(2) Vessels and pipes necessary for ensuring the basic safety functions of the spent fuel interim
storage facilities shall be installed capable of resisting anticipated pressure or leakage tests
without significant leakage.
(Heat Removal)
Article 7: Spent fuel interim storage facilities shall be designed to efficiently remove the decay
heat of spent fuel or materials contaminated by spent fuel.
(Function for Confining Spent Fuel)
Article 8: Spent fuel interim storage facilities shall be designed to maintain the function for
confining spent fuel in a limited area as follows:(i)

appropriate metal cask pose a negligible possibility of external leakages of spent fuel;(ii) when connecting a pipe delivering non-contaminated spent fuel liquid materials toanother pipe or vessel containing a contaminated fluid, the structure shall be so
configured that it will prevent any contaminated spent fuel from flowing into the pipedelivering non-contaminated material;(iii) Where equipment for handling material contaminated by spent liquid fuel is installed(restricted to that part of a facility where there is a risk that leakages of materials
contaminated by spent liquid fuel may expand) will be constructed as follows:(a) interior floor and wall surfaces are structured to make it difficult for material
contaminated by liquid spent fuel to leak;(b) an embankment to prevent an external leak of contaminated materials is installed at theentrance and other potentially vulnerable areas of any complex handling contaminatedmaterials. This will not apply in instances where inside floor surfaces are lower thanthose of neighboring facilities or of the surrounding ground surface and there is
therefore a negligible threat of leakage.
(c) spent fuel interim storage facilities are constructed so that any internal floor surface is156

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not higher than external drainage canals discharging effluent outside the place ofbusiness (excluding sealed ground water drainage canals which have no openings
within the radiation controlled area and are thus not subject to contamination threat).
This does not apply where said drainage canals are equipped with a system that safely
disposes of the contaminated effluent and equipment for measuring the matters set forthin Article 15, paragraph (1), item (iii).
(Shielding)
Article 9:(1) Spent fuel interim storage facilities shall be designed so that dose levels from direct andsky-shine radiation are far below NRA-specified dose limits.
(2) Shielding equipment will be installed to prevent external radiation hazards within the placeof businesss. Measures will be taken to prevent potential radiation leaks where said
shielding equipment has vulnerable openings, pipes, or other penetration points.
(Ventilation)
Article 9-2: Where there is a need to prevent radiation hazards due to air contaminated by spent
fuel within the spent fuel interim storage facilities, ventilators shall be installed as prescribedas follows:(i)

ventilators have the capacity required to prevent radiation hazards;(ii) ventilator construction ensures that air contaminated by spent fuel cannot flow back into
the main system;(iii) filters can be properly maintained, quickly replaced and their design ensures the easy
removal of contaminated materials;(iv) air inlets will not easily take in air contaminated by spent fuel.
(Prevention of Contamination by Spent-Fuel-Contaminated Material)
Article 10: In buildings heavily frequeneted by personnel, walls, floors and other areas subject topossible contamination can be easily cleaned and ‘de-contaminated.’(Facilities with Safety Functions)
Article 11:(1) When sharing any facilities with safety functions with other nuclear facilities or sharing any
equipment within single spent fuel interim storage facilities, said facilities with safetyfunctions or equipment shall be designed to not damage the safety of the spent fuel interim
storage facilities.
(2) Facilities with safety functions shall be designed to ensure that safety inspections or testing
and the maintenance or repair of said safety functions can be effectively conducted.
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Article 12 Equipment for transporting and accepting metal casks in which spent fuel is encased
shall be installed as follows:(i)the equipment for transporting and accepting metal casks in which spent fuel is encased
can handle said casks safely;(ii) such equipment can safely retain metal casks containing spent fuel should local power
supplies be suspended.
(Instrumentation and Control Facilities)
Article 13: (1) Spent fuel storage facilities shall have equipment for measuring either directly or
indirectly the following situations:(i)surface temperature of metal casks in which spent fuel is encapsulated;(ii) pressure at the closure head of metal casks in which spent fuel is encapsulated formonitoring seal performance of the head (excluding the instance where the closure heads
are welded);(iii) temperatures of air supply and exhaust of buildings where spent fuel is stored.
(2) Spent fuel interim storage facilities shall be equipped to detect and immediately raise the alarm
to any risks posed to the basic safety functions of said facilities because of damage to or
malfunctioning of equipment. Other factors may include high concentrations of radioactive
material as outlined in Article 15, paragraph (1), item (ii) or where the dose equivalent of
external radiation set forth in item (iv) of said paragraph has risen significantly, or where there
arises a risk that a significant amount of radioactive liquid material leaks from the disposal
facilities of radioactive liquid waste.
(Disposal Facilities)
Article 14: Equipment for disposing radioactive waste (excluding equipment for storing
radioactive waste for disposal) shall be installed as follows:(i)such equipment has the capability to dispose of radioactive waste generated in the spent
fuel interim storage facilities so that the concentration of radioactive material in the air
outside the peripheral monitoring area and in water at the border of the peripheral
monitoring area will be lower than their respective concentration limits specified by the
Nuclear Regulation Authority;(ii) the equipment is installed separately from that for disposing of non-radioactive waste.
This does not apply when non-radioactive fluid waste is fed into the equipment handling
fluid radioactive waste but there is negligible possibility that this radioactive waste could
flow back into the equipment handling non-radioactive fluid waste;(iii) the equipment for disposing gaseous radioactive waste does not discharge waste at points
other than the exhaust vent;158

ANNEXES L(iv) a filter in the equipment for disposing of gaseous radioactive waste must beproperly
maintained, easily replaced and it ensures the easy removal of contamination by spent
fuel;(v) the equipment for disposing of radioactive liquid waste discharges said waste only at thedischarge port.
(Radiation Control Facilities)
Article 15:(1) The place of business shall have radiation control facilities to either directly or indirectly
measure the following:(i)

NRA-specified dose equivalent rates at the side wall of the radiation shielding structure;(ii) concentration of radioactive material in exhaust gases at or near the exhaust vent of thegaseous radioactive waste;(iii) concentration of radioactive material in effluent at or near the discharge port ofradioactive liquid waste:(iv) dose equivalent and concentration of airborne radioactive material, as well as density ofradioactive material on the surface of materials contaminated by radioactive material
specified by the Nuclear Regulation Authority, all of which pertain to external radiation in
the radiation controlled area;(v) dose equivalent specified by the NRA of external radiation in the peripheral monitoringarea.
(2) Radiation control facilities shall be designed to indicate at an appropriate place any necessary
information contained in the preceding paragraph.
(Standby Power)
Article 16 Spent fuel interim storage facilities shall secure standby power to ensure the continued
functioning of monitoring and other necessary equipment in the event of loss ofelectric power supply from the off-site power grid.
(Communications Equipment)
Article 16-2:(1) The place of business shall have a warning device and communications equipment to alert andinstruct personnel in the event of an accident.
(2) The place of business shall have the necessary equipment to communicate with other areas in
the event of an accident.
(3) Spent fuel interim storage facilities shall have equipment to assist in the evacuation of
personnel from the place of business.

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Table G6-1 Matters to be specified in the Operational Safety Programs(Article 37, paragraph (1) of the Ordinance on Activity of Interim Storage of Spent Fuel
1. The system for complying with related laws and regulations, as well as the Operational Safety
Programs (including senior management involvement)
2. The system for developing a safety culture (including senior management involvement)
3. Quality assurance of the spent fuel interim storage facilities (including the method and systemfor conducting root cause analysis and positioning of the procedural manuals in the
Operational Safety Programs)
4. The duties and organization of operational and management personnel of spent fuel interim
storage facilities excluding the situation highlighted in the following paragraph
5. The duties and authority of spent fuel chief engineers in supervising operational safety, andtheir positions in the organization
6. Operational safety education for radiation worker at the spent fuel interim storage facilities:
a. Policies to provide education on operational safety (including the development of an
implementation plan)b. The following matters concerning the details of education on operational safety:(1) Compliance with related laws and regulations and Operational Safety Programs(2) The structure, functions, and operation of spent fuel interim storage facilities(3) Radiation control(4) Handling of nuclear fuel material and material contaminated by nuclear fuel material(5) Actions to be taken in an emergency
c. Education on operational safety at spent fuel interim storage facilities:
7.The operation and management of equipment which is particularly important in view ofoperational safety
8. The specification of radiation controlled areas and peripheral monitoring areas, as well as
access control to these areas
9. The exhaust monitoring and effluent monitoring equipment
10. The monitoring of doses, dose equivalents, concentration of radioactive material, anddensity of radioactive material on the surface of material contaminated by radioactive
material, as well as decontamination
11. The management of radiation detectors and measurement methods
12. The policing of spent fuel interim storage facilities and accompanying actions
13. The periodic self-inspection of spent fuel interim storage facilities
14. The reception, transport and other handling of spent fuel15. The disposal of radioactive waste
16. Actions to be taken in an emergency
17. Maintaining proper records and reports on operational safety at spent fuel interim storage
facilities (including the status of compliance with the operational safety programs and160

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reports, including those two senior management, detailing incidents and accidents)
18. Periodic evaluation of the spent fuel interim storage facilities
19. Sharing with other similar licensees technical information on operational safety obtained
from business operators conducting maintenance checks
20. Information disclosure on non-compliance if any
21. Other matters necessary for operational safety

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ANNEXESII．Excerpt of Regulations Relevant to Section H
Table H1-1 Ordinance on Activity of Category 2 Waste Disposal of Nuclear Fuel Material and Materials
Contaminated by Nuclear Fuel Material (Excerpt)(Application for Permission for Category 2 Waste Disposal Activity)
Article 2: Details contained in an application form (limited to one pertaining to Category 2 waste disposal
activity) as set forth in Article 51-2, paragraph (2) of the Act on the Regulation of Nuclear
Source Material, Nuclear Fuel Material and Reactors (hereinafter referred to as the “Act”) shallbe as follows:(i)with regard to the property and quantity of the nuclear fuel material set forth in Article 51-2,
paragraph (2), item (iii) of the Act, entering the type and quantity of radioactive waste subject toCategory 2 waste disposal, and the maximum radioactivity concentration and total amount ofradioactivity for each type of radioactive material contained in said radioactive waste;(ii) the location, structure and equipment of waste disposal facilities set forth in Article 51-2,
paragraph (2), item (iv) of the Act, entering data in accordance with the following classification:a. to g. (omitted)(iii) the disposal method set forth in Article 51-2, paragraph (2), item (iv) of the Act, entering data inaccordance with the following classification:a. and b. (omitted)(iv) the timing for amendment set forth in Article 51-2, paragraph (2), item (v) of the Act, entering thetiming for each amendment or the abolition of the peripheral monitoring areas or measuresprescribed in Article 17, which is to be made in accordance with the attenuation of radioactivity;(v) the construction plan for waste disposal facilities set forth in Article 51-2, paragraph (2), item (vi)of the Act, entering the sequence and schedule of the construction work.
(2) A written business plan and other documents specified by the Ordinance of the Nuclear Regulation
Authority (hereinafter referred to as the “Ordinance of the NRA”) as prescribed in Article 30,
paragraph (2) of the Order for Enforcement of the Act on the Regulation of Nuclear Source Material,
Nuclear Fuel Material and Reactors (hereinafter referred to as the “Order”) that shall be attached tothe application form set forth in the preceding paragraph shall be as follows:(i) to (ix) (omitted)(3) One original copy and one duplicate copy of the application form set forth in paragraph (1) shall be
submitted.
(Application for Permission for Changes)
Article 3 Statements in an application form (limited to an application form pertaining to Category 2 waste
disposal activity) set forth in Article 33 of the Order shall be as follows:(i) and (ii) (omitted)(2) Documents set forth in the following items shall be attached to the application form set forth in the162ANNEXES L
preceding paragraph:(i) to (vii) (omitted)(3) One original copy and one duplicate copy of the application form set forth in paragraph (1) shall be
submitted.
(Application for Confirmation Related to Category 2 Waste Disposal Pertaining to Waste Disposal
Facilities)
Article 4(1) A person who intends to seek confirmation related to Category 2 waste disposal pursuant to theprovisions of Article 51-6, paragraph (1) of the Act shall submit an application form prepared inAppended Form 1 to the Nuclear Regulation Authority, together with the following documents:(i) to (iv) (omitted)(2) One original copy of the application form set forth in paragraph (1)(Confirmation Related to Category 2 Waste Disposal Pertaining to Waste Disposal Facilities)
Article 5 Confirmation related to Category 2 waste disposal under Article 51-6, paragraph (1) of the Act
shall be made for the matters set forth in the following items at the times respectively prescribed
therein:(i)the matters concerning the assembly of waste disposal facilities other than radiation control
facilities: when the size of major parts of the respective facilities can be measured;(ii) the assembly of radiation control facilities when said facilities are completed;(iii) the closure of tunnels (those pertaining to Category 2 waste disposal activity): at the time when
conducting the backfilling or blocking of the tunnel and its opening;(iv) the matters other than those set forth in the preceding items: at the time when covering the waste
disposal site with earth and sand or at any other time that the NRA finds appropriate.
(Technical Standards for Waste Disposal Facilities)
Article 6:(1) The technical standards for Category 2 waste disposal activity prescribed in Article 51-6, paragraph (1)of the Act (hereinafter referred to as the “technical standards for waste disposal facilities, etc.”) are as
follows:(i)the amount of radioactivity for each type of radioactive material contained in a waste landfill at
the place of business shall not exceed the total amount of radioactivity for each type of material
stated in the application form for permission. These are set forth in Article 51-2, paragraph (1) of
the Act or Article 51-5, paragraph (1) of the Act and in the document containing the conditions
attached when permission was granted under Article 62-2, paragraph (1) of the Act (hereinafterreferred to as the “application form, etc.” in this Article, Article 6-3, and Article 8);(ii) before starting landfilling, standing water shall be removed and measures taken to prevent the163

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ANNEXESfuture infiltration of rainwater (when the waste disposal site is demarcated with internal partition
equipment as set forth in item (iii) of the following paragraph, the demarcated area for landfilling;hereinafter the same applies in this item);(iii) when landfilling solidified concrete waste and where there is a risk that radioactive material may
spread outside the waste disposal site measures to prevent such an occurrence shall be taken;(iv) the waste disposal site shall be filled with earth and sandso that there will no hole left after

completing landfilling;(v) explosive, corrosive and other hazardous substances shall not be landfilled;(vi) when landfilling is completed the surface of the waste disposal site shall be covered so that buriedmaterials and equipment installed at the waste disposal site are not easily exposed;(vii) the waste disposal facilities shall contain the structures and equipment stated in the application
form, in addition to satisfying the preceding items.
(2) The technical standards for pit disposal ( by the method set forth in Article 1-2, paragraph (2), item(iv), (a)) are, in addition to items outlined in the preceding paragraph, as follows:(i)the facilities shall be constructed by the method specified by the Nuclear Regulation Authority forthe prevention of radiation hazards;(ii) the engineered barrier structure shall satisfy the following requirements:(a) it is structurally safe against self-weight, earth pressure and seismic force;(b) measures are taken to prevent corrosion, taking into account the quality of the surface andunderground water and the soil;(iii) a waste disposal site that has an opening exceeding 50 square meters or a capacity exceeding 250
cubic meters must satisfy the requirements set forth in the preceding item. It will be demarcatedby internal partition equipment, which is installed according to NRA specifications for theprevention of radiation hazards, into areas whose respective areas do not exceed around 50 square
meters or into areas whose respective capacities does not exceed around 250 cubic meters;(iv) while conducting landfill, the barrier and the internal partition equipment set forth in item (iii)shall be inspected as necessary. Where a risk of damage to such equipment or a radioactive leakis found, counter measures shall be taken;(v) when landfilling is completed or where the waste disposal site is demarcated by the internal
partition equipment set forth in item (iii), a cover that satisfies requirements set forth in item (ii)shall be installed promptly by an NRA authorized method to prevent radiation hazards, before thesite or area is covered with earth and sand.
(3) The technical standards for pit disposal ( by the method set forth in Article 1-2, paragraph (2), item(iv), (b)) are in addition to provisions provided for in paragraph (1), are as follows:(i)the facilities shall be constructed by the NRA approved method method for the prevention ofradiation hazards;(ii) the facilities solidifying radioactive waste integrally shall satisfy the requirements set forth in item(ii) of the preceding paragraph and its volume shall not exceed around 500 cubic meters.
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ANNEXES L(Application for Confirmation Related to Category 2 Waste Disposal Pertaining to Radioactive Waste to
be Disposed of)Article 7(1) A person seeking confirmation related to Category 2 waste disposal pertaining to radioactive waste,pursuant to the provisions of Article 51-6, paragraph (2) of the Act, shall submit an application to the
Nuclear Regulation Authority, in accordance with the classification of radioactive waste set forth in
the following items:(i)a waste package: an application form in Appended Form 2;(ii) solidified concrete waste: an application form in Appended Form 3.
(2) An application form as set forth in the items of the preceding paragraph shall be attached with thefollowing documents when landfilling waste packages and the documents set forth in item (i) and item(iv) when landfilling solidified concrete waste:(i) to (v) (omitted)(3) One original copy of the application form set forth in paragraph (1) shall be submitted.
(Technical Standards for Radioactive Waste to be Disposed of)Article 8(1) The technical standards (limited to those pertaining to Category 2 waste disposal activity) prescribed in
Article 51-6, paragraph (2) of the Act are to be as follows:(i)in the case of Intermediate Depth Disposal(a) radioactive waste to be disposed of shall be generated at the factory or place of business where afuel facility (limited to a facility solely conducting the fabrication of fuel assemblies that containmixed uranium and plutonium oxide), research reactor facility, power reactor facility or
reprocessing facility is installed;(b) radioactive waste to be disposed of shall be a waste package;(c) said waste package shall be as specified in the following paragraph:(ii) in the case of pit disposal:(a) radioactive waste to be disposed of shall be generated at the facility or place of business where a
research reactor facility or power reactor facility is installed;(b) radioactive waste to be disposed of shall be solidified concrete waste or a waste package;(c) said waste package or solidified concrete waste shall be as specified in the following paragraph orparagraph (3);(iii) in the case of trench disposal:(a) radioactive waste to be disposed of shall be generated at the facility or place of business where a
research reactor facility or power reactor facility is installed;(b) radioactive waste to be disposed of shall be solidified concrete waste;(c) said solidified concrete waste shall be as specified in paragraph (3).
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ANNEXES(2) The technical standards for a waste package are as follows:(i)to prevent radiation hazards, radioactive waste shall be encased in a container or solidified with acontainer by the method specified by the Nuclear Regulation Authority;(ii) the radioactivity concentration shall not exceed the maximum radioactivity concentration stated in
the application form.;(iii) the surface density of radioactive material shall not exceed 10% of the surface density limit as set
forth in Article 14, item (i), (c);(iv) any material that may damage the integrity of the waste package shall not be included;(v) it shall have enough strength to bear the potential load that may be applied when landfilled;(vi) there shall be no significant damage;(vii) a sign of radioactive waste shall be indicated prominently and permanently on the surface of thewaste package, and a serial number for cross checking said waste package with the matters statedin the application form set forth in the preceding Article shall also be included.
(3) The technical standards for solidified concrete waste are as follows, with the provisions of paragraph(2), item (ii) applied mutatis mutandis:(i)

explosive materials shall not be contained;(ii) measures for cross checking said solidified concrete waste with the provisions in the application
form set forth in the preceding Article shall have been taken;(Quality Assurance)
Article 13-3 Pursuant to the provisions of Article 51-16, paragraph (2) of the Act, a licensee of Category 2
waste disposal activity shall draw up a quality assurance plan based on the Operational Safety
Programs, and shall organize, carry out, evaluate and improve operational safety activities(including the measures prescribed in Article 14 to Article 19-2) based on the quality
assurance plan, and make improvements to the quality assurance plan on an on-going basis.
(Quality Assurance Plan)
Article 13-4: A quality assurance plan shall specify the following matters:(i)the organization for conducting quality assurance;(ii) plans for operational safety activities;(iii) implementation of operational safety activities;(iv) evaluation of operational safety activities;(v) improvements in operational safety activities.
(Organization for Conducting Quality Assurance)
Article 13-5: An organization for conducting quality assurance shall be as follows:(i)the organization is operated by a licensee of Category 2 waste disposal activity (in the case of acorporation, its representative);
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ANNEXES L(ii) the responsibility, authority, and duties concerning quality assurance are clarified;(iii) the organization has prepared a mechanism to draw up, implement and evaluate a quality
assurance plan and improve the plan on an on-going basis.
(Plans for Operational Safety Activities)
Article 13-6: The matters concerning plans for operational safety activities to be specified in a quality
assurance plan shall be as follows:(i)the processes specified in Q9000 of the Japanese Industrial Standards based on the Industrial
Standardization Act (Act No. 185 of 1949) and their correlation are clarified in operational safety
activities;(ii) the mechanism is to be such that quality assurance is conducted based on each stage of organizing,
carrying out, evaluating, and improving operational safety activities, and operational safety
activities are improved on an on-going basis;(iii) when procuring goods or services from third parties, the methods of managing them appropriately
are to be specified;(iv) the details of operational safety activities are to be specified in accordance with the significancefor operational safety;(v) procedures for appropriate management of documents and records concerning operational safety
activities are to be specified;(vi) an education and training system for personnel carrying out operational safety activities is to be
specified.
(Implementation of Operational Safety Activities)
Article 13-7 The implementation of operational safety activities to be specified in a quality assurance plan
shall be as follows:(i)

for individual operational safety activities (hereinafter referred to as "individual duties"), thefollowing procedures are to be followed:(a) drawing up an implementation plan for individual duties (hereinafter referred to as the"implementation plan"), and clarifying their requirements and goals;(b) performing individual duties based on the implementation plan; in this case, it should be
confirmed at an appropriate stage that said plan complies with requirements;(c) managing any amendments to the implementation plan appropriately;(ii) when procuring goods or services from third parties, the relevant person in charge must ensure
they are appropriate for the implementation plan (including obtaining technical information on
operational safety required for the maintenance and operation of said goods orservices),appropriate management methods are adopted and all information is shared, withlicensees of Category 1 waste disposal activity and other licensees of Category 2 waste disposal
activity);
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ANNEXES(iii) to confirm that individual duties comply with the implementation plan requirements, necessary
inspections and testing are to be carried out;(iv) officials carrying out inspections and testing set forth in the preceding item are to be selected inaccordance with the significance for operational safety;(v) When requirements are not complied with (hereinafter referred to as "non-compliance"), themethods of appropriately managing such situation are to be specified.

(Evaluation of Operational Safety Activities)
Article 13-8: The matters concerning the evaluation of operational safety activities in a quality assurance
plan shall be as follows:(i)

necessary monitoring and measurement of operational safety activities will be conductedsystematically;(ii) a systematic audit will be conducted to make it clear that operational safety activities are being
carried out appropriately;(iii) the evaluation set forth in the preceding item will be made by someone other than those whose
individual duties are to be evaluated.
(Improvements in Operational Safety Activities)
Article 13-9: The matters covering improvements in operational safety activities to be specified in aquality assurance plan shall be as follows:(i)

improvements are to be made by specifying correctional procedures to prevent recurrences of
non-compliance (including procedures for conducting analysis to determine root causes ofincidents such as accidents and failures set forth in Article 22-17

and hereinafter referred to as"root cause analysis");(ii) improvements are to be made by specifying prevention procedures to avoid possible
non-compliance (hereinafter referred to as “preventive action”) including procedures for root
cause analysis;(iii) in taking preventive action, both information obtained from operational safety activities at one's
own waste disposal facilities but alss from other facilities will be included;(iv) evaluation results from activities outlined in the preceding Article will be reflected appropriately.
(Access to Radiation Controlled Areas)
Article 14: Pursuant to the provisions of Article 51-16, paragraph (2) of the Act, a licensee of Category 2
waste disposal activity shall designate radiation controlled areas and peripheral monitoringareas and will take a series of measures: (they will not apply when such areas are notdesignated in the operational safety programs for which approval for amendments as set forthin Article 51-18, paragraph (1) of the Act has been obtained).
(i)for radiation controlled areas, the following measures will be taken:
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ANNEXES L(a) zoning areas will be marked with signs, walls, fences, and other partitions, clearly distinguishingthem from surrounding areas, and will include access control or lockup in accordance withradiation risks.;(b) prohibiting eating, drinking or smoking at locations where there is a risk of oral intake ofradioactive material;(c) ensuring that the surface density of radioactive material on floors, walls and other surfaces withwhich people come into contact with, does not exceed the surface density limit specified by the
Nuclear Regulation Authority;(d) ensuring that when people leave a radiation controlled area the density of radioactive material on
clothing, shoes or on the surface of containers and wrapping of items he/she intends to take out
does not exceed 10% of the surface density limit set forth in (c) above;(ii) for peripheral monitoring areas, the following measures should be taken:(a) prohibiting people from living in those areas;(b) limiting the access by people other than those on business by installing fences or boundary signs(this will not apply when it is clear there is no obvious hazard to people)..
(Measures concerning Doses)
Article 15:(1) Pursuant to the provisions of Article 51-16, paragraph (2) of the Act, a licensee of Category 2 waste
disposal activity shall take measures with regard to doses,affecting radiation workers:(i)ensuring that radiation doses affecting workers do not exceed limits specified by the NRA;(ii) ensuring that airborne radioactive concentrations in the workplace do not exceed NRA limits.
(2) Irrespective of the provisions of the preceding paragraph, in an unavoidable situation such as a disasteror potential disaster at a waste disposal facility, it may be necessary for personnel to undertake
emergency work, providing doses do not exceed limits specified by the NRA (female workers will be
restricted to those who are infertile or those who have notified, in writing, the relevant licensee thatthey have no intention of becoming pregnant).
(Patrol and Checking of Waste Disposal Facilities)
Article 16: Pursuant to the provisions of Article 51-16, paragraph (2) of the Act, a licensee of Category 2
waste disposal activity shall engage personnel to patrol and check the facilities at least once aweek under the Operational Safety Programs for which he/she has obtained approval orapproval for amendments as set forth in Article 51-18, paragraph (1) of the Act.
(Maintenance of Waste Disposal Sites)
Article 17:(1) Pursuant to the provisions of Article 51-16, paragraph (2) of the Act, a licensee of Category 2 waste
disposal activity shall undertake the following measures for the maintenance of the waste disposal site:
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ANNEXES(i)monitoring any leak of radioactive material outside the waste disposal site.When an abnormal leakis found, promptly repairing any relevant equipment at the waste disposal site and taking any
needed measures to prevent an abnormal radioactive leak;(ii) designating a protected area for disposal, clearly distinguishing it from surrounding areas withsigns and maintaining the site in good order (excluding measures in the preceding item);(iii) installing an easily viewable signboard and other indicators at the waste disposal site and updatingthem when there are any changes in the following areas:(a) type of radioactive waste;(b) the dates of starting and completing landfilling;(c) matters concerning operational safety;(2) The provisions of the preceding paragraph do not apply to waste disposal facilities for which theapproval set forth in Article 51-25, paragraph (2) of the Act has been obtained.
(Transport within the Place of Business)
Article 18:(1) Pursuant to the provisions of Article 51-16, paragraph (2) of the Act, a licensee of Category 2 waste
disposal activity shall take the following measures covering the transport of nuclear fuel material
within the place of business of the waste disposal complex:(i)encasing nuclear fuel material in a container during transportation with the following exceptions:(a) transporting contaminated materials with a radioactive concentration below NTA-specified limits
and for which measures to prevent a radioactive leak have been taken;(b) when transporting contaminated materials such as large machinery which is difficult to fit into a
container, but taking hazard prevention measures approved by the NRA;(ii) containers described in the preceding item shall conform with the following standards:(a) the length of each side of the cuboid circumscribed to said container is no shorter than 10 cm;(b) a container can be handled easily and safely and is not subject to cracks or other damage fromtemperature changes, internal pressure, or oscillation;(iii) ensuring that the dose equivalent rates at the surface and at a distance of one meter from thesurface of the vessel in which nuclear fuel material is encased..Ensuring the transportation
vehicle . (hereinafter referred to as "transporting equipment") will not exceed the dose equivalent
rates specified by the NRA ,and the density of radioactive material on the surface of the material
to be transported will not exceed 10% of the surface density limit set forth in Article 14, item (i),(c) (when transportation is conducted without encapsulating the contaminated material prescribedin item (i), (a) or (b) in a container, pursuant to the provisions of the proviso to said item, said
material contaminated by nuclear fuel material; hereinafter referred to as "material to betransported" in this Article),(iv) ensuring that the material will not move, fall or drop during loading, transportation and unloading;(v) ensuring that nuclear fuel material is not loaded onto the same transportation as hazardous
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materials specified by the Nuclear Regulation Authority;(vi) displaying signs, deploying guards at key locations and taking other appropriate measures along
the transport route to limit access by people other than those official involved in the movement.;(vii) reducing the speed of the transportation vehicle and providing a security escort vehicle over long
distances;(viii)Providing an expert in handling nuclear fuel material to accompany and supervise the movement
if necessary(ix) Utilizing NRA-specified labels and signs at critical positions on the materials to be transported
and the transporter itself. Containers should be designed to not require reshipment on the way, arestrong enough to withstand repeated use and are equipped with devices for easy loading andunloading(2) As noted in the preceding paragraph, when it is difficult to implement all of the measures set forth initem (ii) and item (iii), it is acceptable to adopt other NRA approved measures, though this would not
apply when the dose equivalent rate at the surface of the transported material exceeds NRA specified
limits.
(3) The provisions of paragraph (1), item (i) to item (iii) and item (vi) to item (ix) do not apply to transport
within the radiation controlled areas.
(4) In the case where a licensee of Category 2 waste disposal activity has taken measures necessary forensuring security with regard to the transport of nuclear fuel material, according to the technicalstandards for transport prescribed in Article 3 to Article 17 of the Ministerial Ordinance on Transportof Nuclear Fuel Material. Outside the facility or place of business (Ministerial Ordinance Issued by thePrime Minister’s Office No. 57 of 1978) and Article 3 to Article 19 of the Ministerial Ordinance on
Transport of Nuclear Fuel Material by Vehicle (Ordinance of the Ministry of Transport No. 72 of
1978), the licensee may conduct the transport of said nuclear fuel material, etc. within the place ofbusiness where the waste disposal facilities have been installed, notwithstanding the provisions ofparagraph (1).
(Disposal within the Place of Business)
Article 19: Pursuant to the provisions of Article 51-16, paragraph (2) of the Act, a licensee of Category 2
waste disposal activity shall take the following measures with regard to the disposal ofradioactive waste within the place of business where the waste disposal facilities have been
installed:(i)ensuring radioactive waste disposal is conducted under the supervision of disposal and radiation
protection experts. Appropriate clothese should be worn by workers and officials;(ii) persons other than those directly engaged in the disposal must follow their instructions at the site;(iii) disposing of gaseous radioactive waste with either of the following methods:(a) discharging through the exhaust facilities;(b) storing disposal waste in tanks that can prevent radiation hazards;
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ANNEXES(iv) when adopting the disposal method set forth in (a) of the preceding item, reducing theconcentration of radioactive material in the exhaust to the extent possible through filtration,
radioactivity decay, dilution with a large amount of air at the exhaust facilities; in this case,monitoring radioactive concentrations in the exhaust system, thereby ensuring that radioactive
concentrations in the air outside the peripheral monitoring area will not exceed limits specified by
the Nuclear Regulation Authority;(v) disposing of radioactive liquid waste with any of the following methods:(a) discharging through the drainage facilities;(b) storing for disposal in tanks that can prevent radiation hazards;(c) encasing such waste in a vessel or solidifying it with a vessel and storing said waste for disposal
at the storage disposal facilities that can prevent radiation hazards;(d) incinerating waste to prevent radiation hazards;(e) solidifying waste in the available solidification equipment;(f) landfilling waste in accordance with the technical standards prescribed in Article 6 and Article 8;(vi) when adopting the disposal method set forth in (a) of the preceding item, reducing theconcentration of radioactive material in the effluent to the extent possible by way of filtration,
evaporation, adsorption using the ion-exchange resin method, radioactivity decay, dilution with alarge amount of water at the drainage facilities; in this case, monitoring the concentration ofradioactive material in the effluent at the discharge port or effluent monitoring equipment, thereby
ensuring that the concentration of radioactive material in the water at the boundary outside theperipheral monitoring area will not exceed the concentration limit specified by the Nuclear
Regulation Authority;(vii) when adopting the disposal method set forth in (c) of item (v) and encapsulating the radioactive
waste in a container, said vessel shall conform with the following standards:(a) the container is resistant to corrosion, less permeable and ablve to prevent leaks of radioactive
waste;(b) the container is free from any cracks or damage;(c) the container lid is hard to remove;(viii)when adopting the disposal method set forth in (c) of item (v) and solidifying radioactive wastewith a container, the vessel integrally solidified with the radioactive waste will be able to preventa scatter or leak of radioactive waste;(ix) when adopting the disposal method set forth in (c) of item (v) and storing disposable radioactive
waste at the storage facilities to prevent radiation hazards, the following procedures will befollowed:(a) when encapsulating the waste in a container and storing it for disposal, taking measures necessary
to prevent the spread of contamination in the event of any cracks or damage to said container,such as covering said container with materials that can absorb the waste or installing a tray thatcan receive the encapsulated radioactive waste;
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ANNEXES L(b) attaching a radioactive waste sign to a container in which the radioactive waste is encapsulated or
which has solidified with the radioactive waste, and indicating a serial number for cross checking
said radioactive waste with the details recorded based on the provisions of Article 13;(c) posting precautions for management in a prominent place at said storage facilities;(x) when adopting the disposal method in item (v), monitoring the concentration of radioactive
material in underground water to ensure that at the boundary outside the peripheral monitoringarea it does not exceed the concentration limit in item (vi);(xi) disposing of solid radioactive waste by any of the following methods:(a) incinerating waste to prevent radiation hazards;(b) encapsulating waste in a container or solidifying it with a container and storing said waste for
disposal at the storage disposal facilities;(c) with regard to large machinery for which it is extremely difficult to adopt the disposal method in(b) above, or radioactive waste that requires radioactivity decay, storing such waste for disposal at
the storage facilities;(d) landfilling waste in accordance with the technical standards prescribed in Articles 6 and 8;(xii) The provisions of item (vii), item (viii) and item (ix) (excluding (a) of said item) shall apply
mutatis mutandis with regard to disposal by the method set forth in (b) of the preceding item;(xiii)The provisions of (c) of item (ix) shall apply mutatis mutandis with regard to disposal by themethod set forth in (c) of item (xi);(xiv) The provisions of item (x) shall apply mutatis mutandis with regard to disposal by the method set
forth in (d) of item (xi).
(Periodic Evaluation of Waste Disposal Facilities)
Article 19-2:(1) Pursuant to the provisions of Article 51-16, paragraph (2) of the Act, a licensee of Category 2 waste
disposal activity shall use the measures set forth in the following items for each waste disposal site atintervals of not exceeding ten years:(i)evaluating the management of radiation exposure due to nuclear fuel material based on the latest
technical knowledge;(ii) taking measures to protect waste disposal facilities based on the results of the evaluation outlinedin the preceding item.
(2) In addition to measures prescribed in the preceding paragraph, a licensee of Category 2 waste disposal
activity shall utilize measures outlined in the preceding paragraph for the waste disposal site when
he/she intends to change the measures to be taken for the operational safety of Category 2 waste
disposal in accordance with the attenuation of radioactivity.
(3) The provisions of the preceding two paragraphs do not apply to waste disposal facilities for whichapproval in Article 51-25, paragraph (2) of the Act has been obtained.

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ANNEXES(Operational Safety Programs)
Article 20:(1) A person (limited to a licensee of Category 2 waste disposal activity) who seeks approval for
Operational Safety Programs under Article 51-18, paragraph (1) of the Act shall specify the
Operational Safety Programs concerning the following matters for each place of business for which
he/she intends to obtain the approval, and shall submit an application form containing said Operational
Safety Programs to the Nuclear Regulation Authority:(i)the matters concerning the system for complying with relevant laws and regulations, as well as the
Operational Safety Programs (including senior management involvement);(ii) the system for developing a culture of safety (including senior management involvement);(iii) quality assurance of the waste disposal facilities (including the method and system for conducting
root cause analysis and positioning of the procedural manuals in the Operational Safety
Programs);(iv) the duties of those engaged in the operation and management of the waste disposal facilities andtheir organization (excluding what is set forth in the following item);(v) the duties and authority of chief engineers of radioactive waste, necessary for supervising
operational safety, and their positions in the organization;(vi) education on operational safety for radiation worker at the waste disposal facilities:(a) policies to provide education on operational safety (including the drawing up of an
implementation plan);(b) the following matters concerning the details of education on operational safety:
1.compliance with appropriate laws and regulations, as well as Operational Safety Programs;
2. the structure, functions, and operation of the waste disposal facilities;
3. radiation control;
4. handling of nuclear fuel material and material contaminated by nuclear fuel;5. actions to be taken in an emergency;(c) other matters necessary for education on operational safety pertaining the waste disposal
facilities;(vii) measures to be taken for the operational safety of Category 2 waste disposal in accordance withthe attenuation of radioactivity;(viii)the specification of the radiation controlled areas, peripheral monitoring areas and protection areas
for disposal, as well as the access control to these areas;(ix) the exhaust monitoring equipment and effluent monitoring equipment;(x) monitoring of doses, dose equivalents, concentration of radioactive material, and density ofradioactive material on the surface of material contaminated by radioactive material, as well as theremoval of contamination;(xi) monitoring the waste disposal site and the nearby vicinity (excluding the monitoring described initem (x)) to obtain information necessary for the periodic evaluation of the waste disposal
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facilities under Article 19-2;(xii) the management of radiation detectors and measurement methods;(xiii)the policing of waste disposal facilities and accompanying actions;(xiv) the reception, transportation, disposal and other handling of radioactive waste;(xv) actions to be taken in an emergency;(xvi) handing of records and reports on operational safety pertaining to the waste disposal facilities(including the status of compliance with the Operational Safety Programs). Such reports include
ones submitted to senior management following incidents such as accidents and failures set forthin the items of Article 22-17;(xvii) periodic evaluation of waste disposal facilities;(xviii) sharing with other Category 1 licensees of waste disposal activity and licensees of Category 2
waste disposal activity technical information on operational safety obtained by operator during
maintenance checks;(xix) information disclosure on non-compliance if any;(xx) other matters necessary for operational safety pertaining to waste disposal facilities.
(2) A person (limited to a licensee of Category 2 waste disposal activity) who intends to seek approval as
set forth in Article 51-25, paragraph (2) of the Act shall add the following matters to the Operational
Safety Programs approved under Article 51-18, paragraph (1) of the Act or obtain approval for theamended Operational Safety Programs, for the purpose of taking the decommissioning measures
specified in the decommissioning plan for which he/she intends to obtain said approval, no later thanthe date of said approval. The same applies when intending to further amend said amended Operational
Safety Programs:(i)the matters concerning the system for complying with the relevant laws and regulations, as well as
the Operational Safety Programs (including senior management involvement);(ii) the system for developing a safety culture (including senior management involvement);(iii) quality assurance of the waste disposal facilities (including issues concerning the method andsystem for conducting root cause analysis, and positioning of the procedure manuals, in the
Operational Safety Programs);(iv) quality assurance of the decommissioning measures (including matters concerning the method andsystem for conducting root cause analysis, and positioning of the procedure manuals in the
Operational Safety Programs);(v) the duties of those engaged in the decommissioning measures and their organization (excluding
the situation set forth in the following item);(vi) the duties and authority of chief engineers of radioactive waste, necessary to supervise operationalsafety, and their positions in the organization;(vii) education on operational safety for radiation workers engaged in decommissioning:(a) matters concerning policies for providing education on operational safety including the drawing
up of an implementation plan
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ANNEXES(b) the following matters concerning the details of education on operational safety:
1. compliance with relevant laws and regulations, as well as Operational Safety Programs;
2. the structure and functions of the spent fuel interim storage facilities;
3. decommissioning measures for auxiliary facilities of the waste disposal site;
4. radiation control;
5. handling of nuclear fuel material and material contaminated by nuclear fuel material;
6. actions to be taken in an emergency;(c) other matters necessary for education on operational safety pertaining the waste disposal facilities;(viii)measures to be taken for the operational safety of Category 2 waste disposal in accordance withthe attenuation of radioactivity;(ix) the specification of radiation controlled areas, peripheral monitoring areas and protection areas for
disposal, as well as the access control to these areas;(x) exhaust monitoring and effluent monitoring equipment;(xi) monitoring of doses, dose equivalents, concentration of radioactive material, and density ofradioactive material on the surface of material contaminated by radioactive material, as well as thedecontamination;(xii) management of radiation detectors and measurement methods;(xiii)the policing of waste disposal facilities and related actions;(xiv) the transport, disposal and other handling of radioactive waste;(xv) actions to be taken in an emergency;(xvi) maintaining proper records and reports on operational safety at waste disposal facilities (including
the status of compliance with the Operational Safety Programs). Such reports include ones madeto senior management on accidents, failures and other incidentsset forth in the items of Article
22-17,;(xvii) maintenance of proper records and reports on operational safety covering decommissioning
measures (including the status of compliance with the Operational Safety Programs). Such reports
include ones made to senior management for accidents, failures and other incidents set forth in theitems of Article 22-17;(xviii) sharing with other Category 1 licensees of waste disposal activity and licensees of Category 2
waste disposal activity technical information on operational safety obtained by operators during
maintenance and checks;(xix) the matters concerning the information disclosure on non-compliance if any;(xx) management of decommissioning measures;(xxi) other matters necessary for operational safety of waste disposal facilities or decommissioning
measures.

(3) A person who intends to obtain approval for amendments to the matters set forth in paragraph (1), item(vii) with regard to the Operational Safety Programs for which he/she has obtained approval or approval
for amendments as set forth in Article 51-18, paragraph (1) of the Act, shall submit an application form
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as set forth in paragraph (1) or paragraph (2), together with a document explaining the results of theperiodic evaluation of the waste disposal facilities under Article 19-2.
(4) The provisions of the main clause of paragraph (1) apply mutatis mutandis in the cases set forth inparagraph (2).
(5) One original copy of the application form set forth in paragraph (1) (including the cases where said
paragraph is applied mutatis mutandis pursuant to the preceding paragraph) shall be submitted.
(Inspection of the Status of Compliance with the Operational Safety Programs)
Article 20-2:(1) An inspection (limited to the inspection pertaining to Category 2 waste disposal activity) under Article
51-18, paragraph (5) of the Act is to be conducted four times every year; provided, however, that theinspection for the waste disposal facilities for which approval as set forth in Article 51-25, paragraph(2) of the Act has been obtained, it is to be conducted four times or less every year, in accordance withthe progress of the decommissioning measures.
(2) The matters concerning the inspection set forth in the preceding paragraph which are specified by theOrdinance of the NRA as set forth in Article 12, paragraph (6) of the Act as applied mutatis mutandis
pursuant to Article 51-18, paragraph (6) of the Act shall be as follows:(i)entering the office, facility or place of business;(ii) inspecting books, documents, equipment, components, or any other necessary property;(iii) questioning employees and other people concerned;(iv) requesting the submission of nuclear source material, nuclear fuel material, material contaminatedby nuclear fuel material, or any other necessary samples (limited to the minimum amountnecessary for testing).
(Physical Protection Programs)
Article 22-2:(1) A person (limited to a licensee of Category 2 waste disposal activity) who intends to seek approval for
Physical Protection Programs under Article 51-23, paragraph (1) of the Act shall specify the PhysicalProtection Programs concerning the following matters for each place of business for which he/she
intends to seek the approval, and shall submit an application form containing said Physical Protection
Programs to the Nuclear Regulation Authority:(i)the matters concerning the system for complying with relevant laws and regulations, as well as the
Physical Protection Programs (including senior management involvement);(ii) the system for developing a security culture (including senior management involvement);(iii) the duties of those engaged in the physical protection of specified nuclear fuel material and theirorganization;(iv) the specifications of the physical protection areas, access to controlled areas and patrolling andmonitoring. (for the place of business handling the specified nuclear fuel material set forth in item
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ANNEXES(i) or item (ii) of the table of Article 19-3, paragraph (1), the physical protection areas andperipheral physical protection areas; the same applies in the following item) ;(v) access control to the physical protection areas;(vi) management of specified nuclear fuel material;(vii) measures for maintaining equipment or devices necessary for the physical protection of specified
nuclear fuel material;(viii)an information system security plan;(ix) maintenance and inspection of equipment and devices necessary for the physical protection of
specified nuclear fuel material;(x) responses in an emergency;(xi) the development of a communication system;(xii) management of information on measures to physically protect specified nuclear fuel material;(xiii)education and training to ensure the physical protection of specified nuclear fuel material;(xiv) an emergency response plan for waste disposal facilities;(xv) measures to be taken in response to the threats such as sabotage (limited to the matters fallingunder Article 19-3, paragraph (2), item (xxiii) (including the cases where said item is appliedmutatis mutandis pursuant to paragraph (3) and paragraph (4) of said Article));(xvi) periodic evaluation and improvements necessary for the physical protection of specified nuclear
fuel material;(xvii) records on the physical protection of specified nuclear fuel material at waste disposal facilities(including the status of compliance with the Physical Protection Programs);(xviii) other matters necessary for the physical protection of specified nuclear fuel material at waste
disposal facilities.

(2) One original copy and one duplicate copy of the application form set forth in the preceding paragraphshall be submitted (when filing an application for any of the waste disposal facilities set forth in item(iv) of the table of Article 63, paragraph (1) of the Order that is specified by the Nuclear Regulation
Authority in a public notice, one original copy and two duplicate copies of the application form).
(Inspection of the Status of Compliance with Physical Protection Programs)
Article 22-3:(1) An inspection (limited to the inspection pertaining to Category 2 waste disposal activity) under Article
12-2, paragraph (5) of the Act as applied mutatis mutandis pursuant to Article 51-23, paragraph (2) ofthe Act is to be conducted once every year.
(2) The matters concerning the inspection set forth in the preceding paragraph which are specified by the
NRA Ordinance as set forth in Article 12-2, paragraph (6) of the Act as applied mutatis mutandis
pursuant to Article 51-23, paragraph (2) of the Act shall be as follows:(i)entering the office, facility or place of business;(ii) inspecting books, documents, equipment, components, or any other necessary property;
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ANNEXES L(iii) questioning employees and other people concerned;(iv) requesting the submission of specified nuclear fuel material or any other necessary samples(limited to the minimum amount necessary for testing).
(Application for Approval of Decommissioning Plans)
Article 22-7
(1) A person (limited to a licensee of Category 2 waste disposal activity) who intends to seek approval fora plan concerning decommissioning measures (hereinafter referred to as a "decommissioning plan"),pursuant to the provisions of Article 51-25, paragraph.
(2) of the Act, shall draw up a decommissioning plan based on the following items and submit anapplication form containing said plan to the Nuclear Regulation Authority:(i) to (vii) (omitted)(2) The following documents or drawings shall be attached to the application form described in thepreceding paragraph:(i) to (x) (omitted)(3) One original and one duplicate copy of the application form set forth in paragraph (1) shall be
submitted.
(Standards for Approval of Decommissioning Plans)
Article 22-10: The standards (limited to Category 2 waste disposal activity) specified by the NRA
Ordinance as prescribed in Article 12-6, paragraph (4) of the Act as applied mutatis
mutandis pursuant to Article 51-25, paragraph (3) of the Act shall be as follows:(i)the period for implementing the measures prescribed in Article 51-2, paragraph (2), item (v) of the
Act has elapsed;(ii) there is no need to take the measures prescribed in Article 17, paragraph (1):(iii) the management, processing, and disposal of nuclear fuel material has been conducted in an
appropriate manner;(iv) the implementation of the decommissioning measures is appropriate to prevent disasters that may
be caused by nuclear fuel material.
(Application for Confirmation of the Completion of Decommissioning Measures)
Article 22-11:(1) A person (limited to a licensee of Category 2 waste disposal activity) who intends to apply for
confirmation of the completion of the decommissioning measures, pursuant to the provisions of Article
12-6, paragraph (8) of the Act as applied mutatis mutandis pursuant to Article 51-25, paragraph (3) ofthe Act, shall submit an application form containing the matters set forth in the following items to the
Nuclear Regulation Authority:(i) to (v) (omitted)
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ANNEXES(2) A document containing the following issues shall be attached to the application form set forth in thepreceding paragraph:(i) and (ii) (omitted)(3) One original copy and one duplicate copy of the application form set forth in paragraph (1) shall be
submitted.
(Standards for Confirmation of the Completion of Decommissioning Measures)
Article 22-12: The standards (limited to those pertaining to Category 2 waste disposal activity) specified
by the NRA Ordinance in Article 12-6, paragraph (8) of the Act as applied mutatis
mutandis pursuant to Article 51-25, paragraph (3) of the Act shall be as follows:(i)there is no need to take any measures to prevent radiation hazards with regard to the soil in thepremises of the auxiliary facilities under decommissioning measures and facilities remaining insaid premises;(ii) the disposal of the nuclear fuel material has been completed;(iii) the handover of the radiation control records prescribed in Article 13, paragraph (1) to anorganization designated by the Nuclear Regulation Authority set forth in paragraph (5) of said
Article has been completed.
(Report of Accidents and Failures)
Article 22-17: When experiencing any of the following situations, a licensee of Category 2 waste disposal
activity (including former licensees of Category 2 waste disposal activity; hereinafter thesame applies in the following Article and Article 27) shall immediately inform the Nuclear
Regulation Authority of such fact, and make a report on the situation thereof and actions to
be taken, within ten days, pursuant to the provisions of Article 62-3 of the Act:(i)when any nuclear fuel material has been stolen or has gone missing;(ii) in the event of a failure of the waste disposal facilities and when special measures are required for
repair work for said failure, and this has interrupted the Category 2 waste disposal;(iii) when a failure of the waste disposal facilities has interrupted or might interrupt Category 2 waste
disposal by losing the ability to confine nuclear fuel material in a limited area, losing the ability toprevent radiation hazards due to external radiation, and the function for preventing a fire or
explosion at the waste disposal facilities;(iv) when a failure or other unexpected event in the waste disposal facilities has caused any
abnormalities in discharging gaseous radioactive waste through the exhaust facilities ordischarging radioactive liquid waste through the drainage facilities;(v) where gaseous radioactive waste has been discharged through the exhaust facilities, and when theconcentration of radioactive material in the air outside the peripheral monitoring area has
exceeded the limit in Article 19, item (iv);(vi) when the concentration of radioactive material in the water at the boundary outside the peripheral
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monitoring area has exceeded the concentration limit in Article 19, item (vi);(vii) when any nuclear fuel material has leaked outside the radiation controlled area;(viii)when a failure or other unexpected event in the waste disposal facilities has caused a leak of
nuclear fuel material within the radiation controlled area. Situations falling under any of thefollowing are excluded from the above (excluding the cases where measures have been newly
taken to limit access or secure the place where the leak occurred or where the leaked material has
spread to outside the radiation controlled area):(a) when leaked liquid nuclear fuel material, has not spread to outside the weir and measures havebeen taken to contain the spread of any leak;(b) where gaseous nuclear fuel material has leaked, but where ventilators keep functioning properly;(c) when the amount of radiation of the leaked nuclear fuel material. is small or when the leak isotherwise minor;(ix) when a failure or other unexpected event in the waste disposal facilities has exposed nearby
personnel to doses which have exceeded, or may possibly exceed, 5mSv for radiation workers or
0.5mSv for other people;(x) when any worker has been exposed to radiation that exceeds or may possibly exceed the dose
limit set forth in Article 15, paragraph (1), item (i);(xi) in addition to the preceding items, when any hazard (excluding hazards other than radiation
hazards that do not require hospital treatment) has occurred or may possibly occur to people inrelation to the waste disposal facilities.
(Emergency Measures)
Article 23: Pursuant to the provisions of Article 64, paragraph (1) of the Act, a licensee of Category 2
waste disposal activity shall take the following emergency measures:(i)where a fire has occurred at a waste disposal facility or there is a risk of fire spreading to the waste
disposal facilities, extinguishing or preventing the spread of a fire and immediately reporting thesituation to fire authorities;(ii) where there is enough time, moving nuclear fuel material to asafe place if necessary and barring
access to people other than those workers and guards enganged in roping off the area andestablishing warning signs.
(iii) warning nearby people to evacuate if necessary to avoid radiation hazards;(iv) preventing the spread of a contamination outbreak caused by nuclear fuel material and andremoving the contaminant;(v) where a person has received or may have possibly received radiation exposure, promptly rescuingand evacuating said person;(vi) taking other necessary measures to prevent radiation hazards.

Table H1-2 Ordinance on Activity of Waste Interim Storage/Treatment of Nuclear Fuel Material and
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Materials Contaminated by Nuclear Fuel Material (Excerpt)(Application for Permission for Radioactive Waste Storage Activity)
Article 2: Statements in an application form (limited to an application form pertaining to radioactive waste
storage activity) set forth in Article 51-2, paragraph (2) of the Act on the Regulation of Nuclear
Source Material, Nuclear Fuel Material and Reactors (hereinafter referred to as the “Act”) shallbe as follows:(i)with regard to the property and quantity of the nuclear fuel material. set forth in Article 51-2,
paragraph (2), item (iii) of the Act, entering the type and quantity of radioactive waste subject
storage, and the maximum radioactivity concentration and total amount of radioactivity for eachtype of radioactive material contained in said radioactive waste;(ii) with regard to the location, structure and equipment of waste storage facilities set forth in Article
51-2, paragraph (2), item (iv) of the Act, entering data in accordance with the followingclassification:a. to g. (omitted)(iii) with regard to the disposal method set forth in Article 51-2, paragraph (2), item (iv) of the Act,
entering data in accordance with the following classification:a. and b. (omitted)(iv) with regard to the construction plan for waste storage facilities set forth in Article 51-2, paragraph(2), item (vi) of the Act, entering the sequence and schedule of the construction work.
(2) A written business plan and other documents specified by the Ordinance of the Nuclear Regulation
Authority (hereinafter referred to as the “Ordinance of the NRA”) as prescribed in Article 30,
paragraph (2) of the Order for Enforcement of the Act on the Regulation of Nuclear Source Material,
Nuclear Fuel Material and Reactors (hereinafter referred to as the “Order”) that shall be attached tothe application form set forth in the preceding paragraph shall be as follows:(i) to (ix) (omitted)(3) One original copy and one duplicate copy of the application form set forth in paragraph (1) are to besubmitted.
(Application for Approval for the Design and Construction Methods)
Article 4(1) A person who intends to seek approval for the design and construction methods concerning thespecified waste storage facilities (excluding a welding method pertaining to specified waste storage
facilities prescribed in Article 11 for which welding is to be performed; hereinafter the same applies inthis Article and the following Article) pursuant to the provisions of Article 51-7, paragraph (1) of the
Act shall submit an application form containing the matters set forth in the following items:(i) to (v) (omitted)(2) An application form set forth in the preceding paragraph shall be attached with documents explaining
why the design and construction methods in said application conform with the technical standards set
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forth in Article 51-7, paragraph (3), item (ii) of the Act (hereinafter referred to as the “technicalstandards for the design and construction methods” in this Article and the following Article), otherdocuments explaining the design and construction methods pertaining to said application and why they
conform with the technical standards for the design and construction methods, and documents
explaining that the quality control method for the design and construction pertaining to said application
conforms with the technical standards set forth in item (iii) of said paragraph.
(3) When it is impossible to file an application for approval under Article 51-7, paragraph (1) of the Act at
one time with regard to the design and construction methods as a whole, the applicant may file anapplication by splitting the design and construction methods, while attaching the reason therefor.
(4) One original copy of the application form set forth in paragraph (1) shall be submitted.
(Application for Pre-service Inspection)
Article 7(1) A person who intends to undergo an inspection with regard to the construction work of the specified
waste storage facilities (excluding a welding method pertaining to specified waste storage facilitiesprescribed in Article 11 for which welding is to be performed) and the performance thereof pursuant to
the provisions of Article 51-8, paragraph (1) of the Act shall submit an application form containing thematters set forth in the following items::(i) to (v) (omitted)(2) When the applicant has changed any of the information stated in the application form set forth in thepreceding paragraph, he/she shall make a notification to that effect promptly.
(3) One original copy shall be submitted with regard to the application form set forth in paragraph (1) andthe document pertaining to the notification set forth in the preceding paragraph.
(Implementation of Pre-service Inspection)
Article 8: A pre-service inspection as set forth in Article 51-8, paragraph (1) of the Act (limited to theinspection pertaining to specified waste storage facilities; the same applies hereinafter) shall be
conducted for the following items at the times prescribed therein:(i)matters

concerning

radiation

shieldingmaterial,materials

requiringairtightnessorwater-tightness: at the time when conducting chemical analysis tests, non-destructive tests,
mechanical tests, pressure tests, or leakage tests or at any other time that the Nuclear Regulation
Authority finds appropriate;(ii) the assembly of the main body of the waste storage equipment, facilities for accepting radioactive
waste, or other auxiliary facilities of the waste storage equipment (limited to disposal facilities):when the size of major parts of the respective facilities can be measured, or at the time when
conducting non-destructive tests, mechanical tests, pressure tests, or leakage tests;(iii) the assembly of measurement and control facilities, radiation control facilities or other auxiliary
facilities of the waste storage equipment (excluding disposal facilities): when the relevant
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ANNEXESfacilities are completed;(iv) the performance of the waste storage facilities: when the waste storage facilities are completed, orat any other time that the Nuclear Regulation Authority finds appropriate.

(Specified Waste Storage Facilities Subject to Welding Inspection)
Article 11: Waste storage facilities specified by the Ordinance of the NRA set forth in Article 51-9,
paragraph (1) of the Act are as follows:(i)vessels or pipes that contain liquid or gaseous material including plutonium or plutonium
compound and fall under either of the following:(a) vessels that contain plutonium with a concentration of 37μBq/cm3 or more (when containing
liquid material, 37Bq/cm3 or more) and whose maximum operating pressure is 98kPa or more or
whose internal volume exceeds 0.04m3;(b) pipes that contain plutonium with a concentration of 37μBq/cm3 or more (when containing liquidmaterial, 37Bq/cm3 or more) and whose outside diameter exceeds 61mm (for pipes whose
maximum operating pressure is less than 98kPa, whose outside diameter exceeds 100mm)(excluding ducts installed within the area confining radioactive material and whose internalpressure is maintained at a lower level than the external pressure);(ii) vessels or pipes that contain liquid or gaseous material including radioactive material (excluding
those prescribed in the preceding item) and fall under either of the following:(a) vessels that contain radioactive material with a concentration of 37mBq/cm3 or more (whencontaining liquid material, 37kBq/cm3 or more) and whose maximum operating pressure is 98kPa
or more or whose internal volume exceeds 0.04m3;(b) pipes that contain radioactive material with a concentration of 37mBq/cm3 or more (whencontaining liquid material, 37kBq/cm3 or more) and whose outside diameter exceeds 61mm (forpipes whose maximum operating pressure is less than 98kPa, whose outside diameter exceeds
100mm) (excluding ducts installed within the area confining radioactive material and whose
internal pressure is maintained at a lower level than the external pressure);(iii) vessels with a maximum diameter exceeding 150mm or pipes with a diameter exceeding 150mm(excluding the vessels or pipes prescribed in the preceding items) that contain liquid or gaseous
material including radioactive material or belong to emergency facilities, and whose parts towhich pressures as specified as follows or larger are applied (hereinafter referred to as the"pressure parts") are to be welded:(a) for vessels or pipes for liquid whose maximum operating temperature is lower than the boilingpoint of said liquid, a maximum operating pressure of 1960kPa;(b) for vessels other than those prescribed in (a) above, a maximum operating pressure of 98kPa;(c) for pipes other than those prescribed in (a) above, a maximum operating pressure of 980kPa (forlongitudinal joints, a maximum operating pressure of 490kPa).

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Article 12:(1) A licensee who intends to undergo an inspection with regard to welding the specified waste storage
facilities pursuant to the provisions of Article 51-9, paragraph (1) of the Act shall submit anapplication containing the following information to the Nuclear Regulation Authority:(i) to (v) (omitted)(2) The following documents shall be attached to an application form set forth in the preceding paragraph:(i) to (iii) (omitted)(3) When the person has changed any of the information contained in the original application set forth inparagraph (1) or the documents set forth in the preceding paragraph, he/she shall make a prompt
notification to that effect.
(4) One original copy shall be submitted with regard to the application form set forth in paragraph (1) andthe document pertaining to the notification set forth in the preceding paragraph.
(Implementation of Welding Inspection)
Article 13 A welding inspection as set forth in Article 51-9, paragraph (1) of the Act (limited to an
inspection pertaining to specified waste storage facilities) shall be conducted in line with thetiming set forth in the following items:(i)when a welding is performed (excluding cases pertaining to seal welding for vessels or pipes set
forth in Article 11, item (iii) and the cases where the Nuclear Regulation Authority approves,recognizing that there is no problem in light of the conditions of the standardization of welding
operation and materials used for welding);(ii) with regard to welded parts for which a non-destructive test is required based on the technicalstandards prescribed in Article 51-9, paragraph (3), item (ii) of the Act (hereinafter referred to as
the “technical standards for welding”), when it has become possible to carry out a non-destructive
test;(iii) with regard to butt-welded parts for which a mechanical test is required based on the technicalstandards for welding, when it has become possible to carry out a mechanical test;(iv) when it has become possible to carry out a pressure test or leakage test (excluding the cases
pertaining to seal welding for vessels or pipes set forth in Article 11, item (iii)).
(Cases where Welding Inspection is not Required)
Article 14 The cases (limited to those pertaining to specified waste storage facilities) specified by theOrdinance of the NRA set forth in the proviso to Article 51-9, paragraph (1) of the Act shall be
as follows:(i)with regard to vessels or pipes belonging to major experimental equipment, auxiliary facilities of
the waste storage equipment prescribed in Article 2, paragraph (1), item (ii), (h), which areinstalled inside a cell, glove box or other airtight equipment, the case where the Nuclear
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Regulation Authority approved, in advance, the use thereof without undergoing a welding
inspection, recognizing that the use of such vessels or pipes will not pose any problem;(ii) the case of using vessels or pipes as prescribed in Article 11, item (iii) for which only seal welding
was performed (including such vessels or pipes for which welding is newly performed for theirpressure parts).

(Approval for Welding Method)
Article 15:(1) An applicant (limited to a licensee of radioactive waste storage activity) who intends to seek approval
set forth in Article 51-9, paragraph (2) of the Act shall submit an application containing the matters set
forth in the following items with regard to each welding work:(i) to (v) (omitted)(2) Documents explaining the matters set forth in the following items shall be attached to the application
form:(i) to (iii) (omitted)(3) When the Nuclear Regulation Authority finds that the welding method, for which an application for
approval set forth in paragraph (1) has been filed and conforms with all of the following, it shall grant
the approval set forth:(i)the type and capacity of the welding equipment are appropriate for the welding method containedin the application;(ii) the welding method is appropriate for ensuring the strength of the welded parts;(iii) a person who performs any welding is an expert in the welding method that he/she intends toperform.
(4) One original copy of the application form set forth in paragraph (1) is to be submitted.
(Welding Inspection of Imported Goods)
Article 16:(1) A person who intends to undergo an inspection of welding of imported specified waste storage
facilities for which he/she performed the welding pursuant to the provisions of Article 51-9, paragraph(4) of the Act, shall submit an application form with the following items to the Nuclear Regulation
Authority:(i) to (iv) (omitted)(2) The following documents shall be attached to said application form:(i) to (iv) (omitted)(3) When the person has altered any of the information in the application set forth in paragraph (1) or the
documents set forth in the preceding paragraph, he/she shall make a notification to that effectpromptly.
(4) One original copy is to be submitted with regard to the application form set forth in paragraph (1) and
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the document pertaining to the notification set forth in the preceding paragraph.
(Specified Waste Storage Facilities Subject to Periodic Facility Inspection)
Article 18 Auxiliary facilities of the waste storage equipment specified by the Ordinance of the NRA set
forth in Article 35, item (ii) of the Order shall be as follows:(i)

disposal facilities;(ii) emergency power systems.
(Application for Periodic Facility Inspection)
Article 19:(1) A person who intends to undergo an inspection of waste storage facilities set forth in Article 35, item(ii) of the Order pursuant to the provisions of Article 51-10, paragraph (1) of the Act shall submit anapplication form containing the matters set forth in the following items:(i) to (iii) (omitted)(2) When the person has changed any of the information in the application form set forth in the preceding
paragraph, he/she shall make a prompt notification to that effect.
(3) One original copy of the application set forth in paragraph (1) will be submitted together with the
document pertaining to the notification set forth in the preceding paragraph.
(Implementation of Periodic Facility Inspection)
Article 20: The interval (limited to the interval pertaining to radioactive waste storage activity) specified
by the Ordinance of the NRA set forth in Article 51-10, paragraph (1) of the Act shall be one
year.
(Quality Assurance)
Article 26-3: Pursuant to the provisions of Article 51-16, paragraph (3) of the Act, a licensee of a waste
storage activity shall draw up a quality assurance plan based on the Operational Safety
Programs, and shall organize, carry out, evaluate and improve operational safety activities(including the measures prescribed in Article 27 to Article 33-2) based on the quality
assurance plan, and make improvements to said quality assurance plan on an on-going basis.
(Quality Assurance Plan)
Article 26-4: A quality assurance plan shall specify the following matters:(i)the organization for conducting quality assurance;(ii) plans for operational safety activities;(iii) implementation of operational safety activities;(iv) evaluation of operational safety activities;(v) improvements in operational safety activities.
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Article 26-5: An organization for conducting quality assurance shall be as follows:(i)the organization is operated by a licensee of waste storage activity (in the case of a corporation, its
representative);(ii) the responsibility, authority, and duties concerning quality assurance are clarified;(iii) the organization has prepared a mechanism to draw up, implement and evaluate a quality
assurance plan and make improvements to the plan on an on-going basis.
(Plans for Operational Safety Activities)
Article 26-6: The matters concerning plans for operational safety activities to be specified in a quality
assurance plan shall be as follows:(i)the processes specified in Q9000 of the Japanese Industrial Standards based on the Industrial
Standardization Act (Act No. 185 of 1949) and their correlation are clarified in operational safety
activities;(ii) the mechanism is to be such that quality assurance is conducted based on each stage of organizing,
carrying out, evaluating, and improving operational safety activities, and operational safety
activities are improved on an on-going basis;(iii) when procuring goods or services from third parties, the methods to appropriately manage themwill be specified;(iv) the details of operational safety activities are to be specified in accordance with operationalsafety;(v) procedures for appropriate management of documents and records concerning operational safety
activities will be specified;(vi) an education and training system for persons carrying out operational safety activities will be
specified.
(Implementation of Operational Safety Activities)
Article 26-7: The matters concerning the implementation of operational safety activities in a quality
assurance plan shall be as follows:(i)

for individual duties in operational safety activities (hereinafter referred to as "individual duties"),the following procedures will be followed:(a) drawing up an implementation plan for individual duties (hereinafter referred to as the"implementation plan" in this Article), while clarifying the individual’s goals and requirements;(b) performing individual duties based on the implementation plan; in this case, it should be
confirmed at an appropriate stage that said plan complies with the requirements;(c) managing the details of any amendment to the implementation plan;(ii) when procuring goods or services from third parties, the person in charge will oversee a
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procurement appropriate for the implementation plan (including obtaining technical information
on operational safety),for the maintenance and operation of said goods or services,,for sharing
such information with other licensees of waste storage activities and applying appropriate
management methods;(iii) to confirm that individual duties comply with the requirements of the implementation plan,inspections and testing will be spelled out and implemented;(iv) persons carrying out inspections and testing will be chosen in accordance with the needs ofoperational safety;(v) In the event of non compliance (hereinafter referred to as "non-compliance"), the methods ofappropriately handling such situation will be specified.
(Evaluation of Operational Safety Activities)
Article 26-8: The evaluation of operational safety activities will be specified in a quality assurance plan as
follows:(i)monitoring and measurement will be conducted systematically in line with the implementation ofoperational safety activities;(ii) an audit will be conducted to make it clear that operational safety activities are being carried out
appropriately;(iii) the evaluation set forth in the preceding item will be made by someone other than persons whose
performance is being evaluated.
(Improvements in Operational Safety Activities)
Article 26-9: Improvements in operational safety activities in a quality assurance plan shall be as follows:(i)

improvements will be made by specifying correction procedures to prevent the recurrence of
non-compliance (including conducting analysis to determine root causes of incidents such asaccidents and failures set forth in the items of Article 35-16, and others (hereinafter referred to as"root cause analysis"));(ii) improvements are to be made by specifying procedures to avoid possible non-compliance(hereinafter referred to as “preventive action”) including procedures for root cause analysis);(iii) in taking preventive action, knowledge obtained through operational safety activities at one's own
waste storage facilities but also the experience of other facilities will be reflected;(iv) The results of the evaluation from the preceding Article will be reflected.
(Access Control to Radiation Controlled Areas)
Article 27; Pursuant to the provisions of Article 51-16, paragraph (3) of the Act, a licensee of waste
storage activity shall designate radiation controlled areas and peripheral monitoring areas andtake the following measures in these areas:(i)for radiation controlled areas, the following measures are to be taken:
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ANNEXES(a) zoning areas with walls, fences and other partitions, signs, access control and lock-up facilities inaccordance with radiation risks clearly distinguish these areas from others;(b) prohibiting eating, drinking and smoking at locations where there is a risk of oral intake ofradioactive material;(c) ensuring that the surface density of radioactive material on floors, walls, or other surfaces whichpeople may come into contact with do not exceed limits specified by the NRA;(d) ensuring that the density of radioactive material on the clothing, shoes and other items of a person
leaving a controlled area does not exceed 10% of the surface density limit set forth in © above(when said articles are in a container or wrapped their surface area will be measured);(ii) for peripheral monitoring areas, the following measures are to be taken:(a) prohibiting people from living in said areas;(b) limiting public access to a peripheral monitoring area by means of fences and signs except for
personnel on business. This does not apply where there is little danger that people will trespass in
said areas.

(Measures concerning Dose.)
Article 28:(1) Pursuant to the provisions of Article 51-16, paragraph (3) of the Act, a licensee of waste storage
activity shall take the following measures with regard to doses, of radiation workers:(i)ensuring that the doses of radiation workers will not exceed limit specified by the NRA;(ii) ensuring that airborne radioactive material that workers inhale will not exceed limits specified by
the Nuclear Regulation Authority.
(2) Irrespective of the provisions in the preceding paragraph, where it is urgent and unavoidable, such as adisaster or the possibility of one at a waste storage facilities, radiation workers may engage inemergency operations, but only within a range of doses not exceeding the limits specified by the NRA(female workers will be limited to those who are infertile or those who have notified the licensee, in
writing, that they do not intend to become pregnant).
(Patrol and Checking of Waste Storage Facilities)
Article 29:(1) Pursuant to the provisions of Article 51-16, paragraph (3) of the Act, a licensee of waste storage
activity (excluding those who have obtained approval via Article 51-25, paragraph (2) of the Act) shall
employ security personnel to patrol and check waste storage facilities at least once a day..
(2) Pursuant to the provisions of Article 51-16, paragraph (3) of the Act, a licensee of a waste storage
activity who has obtained the approval as set forth in Article 51-25, paragraph (2) of the Act shallengage security personnel to patrol the facilities at least once every week.
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Article 30:(1) Pursuant to the provisions of Article 51-16, paragraph (3) of the Act, a licensee of a waste storage
facility shall institute inspection measures set forth in the following items (when the approval set forthin Article 51-25, paragraph (2) of the Act has been obtained, excluding item (i)):(i)

for specified waste storage facilities as prescribed in Article 35, item (ii) of the Order (excluding
those prescribed in the following item), conducting an inspection every year to determine whether
the performance of said facilities conforms with the technical standards specified by theOrdinance of the NRA as prescribed in Article 51-9-2 of the Act;(ii) with regard to alarm and other emergency devices, conducting performance tests for the operationof each part of said devices every month and an integrated test for the operation of said devices asa whole every year;(iii) with regard to instruments and radiation detectors that directly relate to operational safety of thewaste storage facilities, conducting a calibration every year.
(2) A licensee of waste storage activity who has obtained the approval as set forth in Article 51-25,
paragraph (2) of the Act shall conduct an inspection every year to determine whether the facility’s
performance meets the targets stated in the application form for said approval or the approval for achange as set forth in Article 12-6, paragraph (3) of the Act as applied mutatis mutandis pursuant to
Article 51-25, paragraph (3) of the Act, or documents attached to such application form.
(Operation of Waste Storage Equipment)
Article 31: Pursuant to the provisions of Article 51-16, paragraph (3) of the Act, a licensee of waste
storage activity shall take the following measures for the operation of the waste storage
equipment; this will not apply where the approval set forth in Article 51-25, paragraph (2) ofthe Act has been obtained:(i)

specifying issues to be confirmed prior to the start of operations, those necessary for operational
procedures, matters to be confirmed after shutdown, and ensuring that operators observe them;(ii) specifying actions to be taken in an emergency and having the operators undertake them;(iii) maintaining the status of the ventilators, radiation detectors and emergency equipment to ensure
their continuous functioningso;(iv) before operators begin a trial operation, checking the purpose and methods, to be taken when anabnormality occurs;(v) when operating the waste storage equipment for operational training, specifying the matters to beobserved by trainees under the supervision of operators;(Transport within the Place of Business)
Article 32(1) Pursuant to the provisions of Article 51-16, paragraph (3) of the Act, a licensee of waste storage
activity shall take the measures set forth in the following items with regard to the transport of nuclear
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fuel material within the facilities place of business:(i)encasing nuclear fuel material in a container during transportation though this will not apply in thefollowing cases:(a) when transporting material contaminated by nuclear fuel material (limited to materials with aradioactivity concentration not exceeding limits specified by the Nuclear Regulation Authority),
for which measures to prevent a scatter or leak of radioactive material or other hazard prevention
measures specified by the NRA have already been taken;(b) when transporting material such as large machinery contaminated by nuclear fuel material but
which is extremely difficult to encase in a container, while taking hazard prevention measures asapproved by the NRA;(ii) said containers shall conform with the following standards:(a) the length of each side of the cuboid circumscribed to said container will be no shorter than 10cm;(b) the container can be handled easily and safely and is resistant to cracks or damage,because of
temperature change, internal pressure, and oscillation;(iii) ensuring that the dose equivalent rates at the surface and at a distance of one meter from thesurface of the container does not exceed the dose equivalent rates specified by the NRA and thatthe surface density of the radioactive material does not exceed 10% of the surface density limit set
forth in Article 27, item (i), (c); (when transport is conducted without encapsulating the material
contaminated by nuclear fuel material prescribed in item (i), (a) or (b) in a container, pursuant to
the provisions of the proviso to said item, said material contaminated by nuclear fuel material;
hereinafter referred to as "material to be transported" in this Article), the vehicle loading or
containing said material to be transported, or other machinery or components for transport thenuclear fuel material, etc. (hereinafter referred to as " transporting equipment" in this Article)(iv) loading said contaminated material in such a way as to prevent any movement or fall duringtransportation;(v) ensuring that nuclear fuel material is not loaded onto the same transportation as hazardous
materials as specified by the Nuclear Regulation Authority;(vi) deploying guards at key locations, displaying signs and taking other measures to limit accessalong the route both to other vehicles and people not directly involved in the movement;(vii) reducing the speed of the transporting vehicle and, over a long distance, providing a second
vehicle for security escort;(viii)providing an expert in the handling of nuclear fuel material to accompany and supervise themovement as necessary and ensure security;(ix) labels specified by the Nuclear Regulation Authority to be placed at appropriate positions on theransportation vehicle and materials in a container designed not to require reshipment, is strong
enough for repeated use and is equipped for mechanical loading and unloading and for anchoring
to the transport.
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ANNEXES L(2) When it is difficult to implement all or only part of the measures set forth in item (ii) and item (iii) of
said paragraph, other measures approved by the Nuclear Regulation Authority can be implemented.
This will not apply when the dose equivalent rate at the surface of the contaminated exceeds the dose
equivalent rate specified by the Nuclear Regulation Authority.
(3) The provisions of paragraph (1), item (i) to item (iii) and item (vi) to item (ix) do not apply totransportation within the radiation controlled areas.
(4) In the case where a licensee has taken measures necessary for ensuring transportation security
according to the technical standards for transport prescribed in Article 3 to Article 17 of the Ministerial
Ordinance on Transport of Nuclear Fuel Material. Outside the Factory or Place of Business(Ministerial Ordinance Issued by the Prime Minister's Office No. 57 of 1978) and Article 3 to Article
19 of the Ministerial Ordinance on Transport of Nuclear Fuel Material,. by Vehicle (Ordinance of the
Ministry of Transport No. 72 of 1978), the licensee may conduct the shipment of said nuclear fuelmaterial, etc. within the place of business where the waste storage facilities have been installed,
notwithstanding the provisions of paragraph (1).
(Disposal within the Place of Business)
Article 33 Pursuant to the provisions of Article 51-16, paragraph (3) of the Act, a licensee of waste storage
activity shall take the measures set forth in the following items with regard to the disposal ofradioactive waste at the place of business:(i)having the disposal of the radioactive waste conducted under the supervision of disposal andprotection experts dressed in appropriate work clothes;(ii) where any person other than those engaged in the disposal of the radioactive waste enters thedisposal facilities, having said person follow the instructions of those engaged in the disposal;(iii) disposing of gaseous radioactive waste with either of the following methods:(a) discharging waste through the exhaust facilities;(b) storing waste for disposal in tanks that can prevent radiation hazards;(iv) when adopting the disposal method in (a) of the preceding item, reducing the concentration ofradioactive material in the exhaust to the extent possible through filtration, radioactivity decay
over time, dilution with a large amount of air at the exhaust facilities; in this case monitoring theconcentration of radioactive material lat the exhaust vent or exhaust monitoring equipment toensure that radioactive concentrations in the air outside the peripheral monitoring area will not
exceed the limits specified by the NRA;(v) disposing of radioactive liquid waste by any of the following methods:(a) discharging waste through the drainage facilities;(b) storing waste for disposal in the drain tanks to prevent radiation hazards;(c) encapsulating waste in a container or solidifying such waste in a vessel and storing it at a storage
disposal facility to prevent radiation hazards;(d) incinerating waste to prevent radiation hazards;
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ANNEXES(e) solidifying waste;(vi) when adopting the disposal method in (a) of the preceding item, reducing radioactive
concentrations in the effluent to the extent possible through filtration, evaporation, adsorption
using the ion-exchange resin method, radioactivity decay over time, dilution with a large amountof water at the drainage facilities. In this case, monitoring the concentration of radioactive
material in the effluent at the discharge port or effluent monitoring equipment, ensuring that theconcentration of radioactive material in the water at the boundary outside the peripheral
monitoring area will not exceed the concentration limit specified by the Nuclear Regulation
Authority;(vii) when adopting the disposal method in (c) of item (v) and encasing the radioactive waste in acontainer, said container shall conform with the following standards:(a) the container will be resistant to corrosion, non permeable and built to prevent radioactive waste
leaks;(b) said container is free from any cracks or damage;(c) the container lid is hard to remove;(viii)when adopting the disposal method in (c) of item (v) and solidifying radioactive waste with avessel, said vessel can prevent a scatter or leak of radioactive waste;(ix) when adopting the disposal method in (c) of item (v) and storing radioactive waste at the storage
disposal facilities capable of preventing radiation hazards, the following procedures will befollowed:(a) when encapsulating the waste in a container and storing it for disposal, taking measures toprevent contamination threat in the event of any cracks or damage to said vessel, such as
covering it with materials that can absorb radioactive waste, or installing a tray that can receive
the waste;(b) attaching a radioactive waste sign to said and indicating a serial number for cross checking thewaste with the details based on the provisions of Article 26;(c) posting precautions for management in a prominent place at said storage disposal facilities;(x) disposing of solid radioactive waste with any of the following methods:(a) incinerating waste in equipment that can prevent radiation hazards;(b) encapsulating waste in a container or solidifying it with a container and storing said waste at astorage disposal facility able to prevent radiation hazards;(c) Regarding such radioactive waste as large machinery which is extremely difficult to dispose ofusing the method set forth in (b) above, or radioactive waste that requires radioactivity decay,storing such waste at a storage facility that can prevent radiation hazards;(xi) when adopting the disposal method set forth in (b) or (c) of the preceding item, and when decay
heat of said waste may possibly cause significant overheating, taking necessary cooling measures;(xii) The provisions of item (vii), item (viii) and item (ix) (excluding (a) of said item) shall apply
mutatis mutandis with regard to disposal by the method set forth in (b) of item (x);194

ANNEXES L(xiii)The provisions of (c) of item (ix) shall apply mutatis mutandis with regard to disposal by themethod set forth in (c) of item (x).
(Periodic Evaluation of Waste Storage Facilities)
Article 33-2:(1) Pursuant to the provisions of Article 51-16, paragraph (3) of the Act, a licensee of a waste storage
activity shall take the following measures for each facility at intervals not exceeding ten years:(i)evaluating the implementation of operational safety activities at the waste storage facility;(ii) evaluating how the latest technical knowledge is reflected in operational safety activities.
(2) A licensee shall take the following measures no later than the day on which 20 years have elapsed fromthe commencement of operations:(i)conducting a technical evaluation examining time-related changes;(ii) drawing up a ten-year plan for updated operational safety measures to be taken based on thetechnical evaluation set forth in the preceding item.
(3) The evaluation and plan set forth in the preceding paragraph shall be reevaluated at intervals of not
more than ten years.
(4) The provisions of the preceding three paragraphs do not apply where the approval set forth in Article
51-25, paragraph (2) of the Act has been obtained.
(Operational Safety Programs)
Article 34(1) A person (limited to a licensee of waste storage activity) who intends to seek approval for Operational
Safety Programs under Article 51-18, paragraph (1) of the Act shall specify the Operational Safety
Programs concerning the matters set forth in the following items for each place of business for which
he/she intends to obtain the approval, and shall submit an application form containing said Operational
Safety Programs to the NRA. Matters include:(i)a system for complying with relevant laws and regulations, as well as the Operational Safety
Programs (including senior management involvement);(ii) a system for developing a safety culture (including senior management involvement);(iii) quality assurance of waste storage facilities (including matters concerning the method and systemfor conducting root cause analysis and positioning of procedure manuals, in the Operational
Safety Programs);(iv) the duties of those engaged in the operation and management of the waste storage facilities andtheir organization (excluding the following item);(v) the duties and authority of chief engineers of radioactive waste in supervising operational safety,
and their positions in the organization;(vi) education and training for radiation workers on operational safety:(a) policies to provide education on operational safety (including drawing up an implementation
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ANNEXESplan);(b) the following matters concerning education policies on operational safety:
1. compliance with the relevant laws and regulations, as well as the Operational Safety Programs;
2. the structure, functions, and operation of waste storage facilities;
3. radiation control;
4. handling of nuclear fuel and other materials contaminated by nuclear fuel material;
5. actions to be taken in an emergency;(c) other matters necessary for education policies on operational safety at waste storage facilities;(vii) the operation of sensitive operational safety equipment;(viii)specifications of radiation controlled and peripheral monitoring areas, as well as the access control
to these areas;(ix) exhaust monitoring and effluent monitoring equipment;(x) monitoring of doses, dose equivalents, concentration of radioactive material, and density ofradioactive material on the surface of materials contaminated by radioactive material, as well as
decontamination;(xi) the management of radiation detectors and measurement methods;(xii) policing and checking of the waste storage facilities and accompanying actions;(xiii)the periodic self-inspection of the waste storage facilities;(xiv) the reception, transport, disposal and other handling of radioactive waste;(xv) actions to be taken in an emergency;(xvi) maintenance of operational safety records and reports for waste storage facilities (including thestatus of compliance with the Operational Safety Programs). Reports include ones made to senior
management covering accidents, failures and other incidents contained in the items of Article
35-16;(xvii) periodic evaluation of waste storage facilities;(xviii) sharing with other waste storage facility licensees technical information on operational safetyobtained from business operators conducting maintenance checks;(xix) information disclosure on non-compliance if any;(xx) other matters necessary for operational safety at waste storage facilities.

(2) Licensees of waste storage facilities seeking approval for a decommissioning plan as set forth in
Article 51-25, paragraph (2) of the Act shall add the following matters to the Operational Safety
Programs approved under Article 51-18, paragraph (1) of the Act or obtain approval for the amended
Operational Safety Programs.no later than the date of said approval. The same applies when intending
to further amend said amended Operational Safety Programs. Matters include:(i)a system for complying with relevant laws and regulations, as well as Operational Safety
Programs (including senior management involvement);(ii) a system for developing a safety culture (including senior management involvement);(iii) quality assurance of waste storage facilities (including a system for conducting root cause analysis
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and positioning of the procedural manuals in the Operational Safety Programs);(iv) quality assurance of decommissioning measures (including a system for conducting root cause
analysis, and positioning of procedure manuals in the Operational Safety Programs);(v) duties of personnel engaged in decommissioning measures and their organization (excluding thefollowing);(vi) the duties and authority of chief engineers of radioactive waste in supervising operational safety,
and their positions in the organization;(vii) education on operational safety for radiation workers engaged in the decommissioning measures:(a) policies to provide operational safety education (including drawing up an implementation plan)(b) the details of education on operational safety:
1. compliance with relevant laws and regulations, as well as Operational Safety Programs;
2. the structure and functions of the waste storage facilities;
3. the decommissioning measures for the waste storage facilities;
4. radiation control;
5 the handling of nuclear fuel material and material contaminated by nuclear fuel material;
6. actions to be taken in an emergency;(c) other matters necessary for operational safety education for waste storage facilities;(viii)the operation of sensitive operational safety equipment;(ix) the specification of radiation controlled areas, protection areas and peripheral monitoring areas, aswell as the access controlto these areas;(x) the exhaust monitoring equipment and effluent monitoring equipment;(xi) monitoring of doses, dose equivalents, concentration of radioactive material, and density ofradioactive material on the surface of material contaminated by radioactive material, as well as thedecontamination;(xii) tmatters concerning the management of radiation detectors and measurement methods;(xiii)the policing of waste storage facilities and other accompanying actions;(xiv) the periodic self-inspection of waste storage facilities;(xv) transport, disposal and other handling of radioactive waste;(xvi) actions to be taken in an emergency;(xvii) maintenance of operational safety records and reports for waste storage facilities (including thestatus of compliance with Operational Safety Programs). Such reports include ones made to senior
management covering accidents, failures and other incidents as set forth in the items of Article
35-16;(xviii) maintainin operational safety records and reports covering decommissioning measures(including the status of compliance with the Operational Safety Programs). Such reports include
ones made to senior management covering accidents, failures and other incidents in the items of
Article 35-16;(xix) sharing with licensees of other waste storage facilities operational safety information obtained197

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ANNEXESfrom business operators conducting maintenance checks;(xx) information dissemination on non-compliance if any;(xxi) the management of decommissioning measures;(xxii) other matters necessary for operational safety pertaining to waste storage facilities ordecommissioning measures.

(3) The provisions of the main clause of paragraph (1) apply mutatis mutandis in the cases set forth in thepreceding paragraph.
(4) One original copy of the application form set forth in paragraph (1) (including the cases where said
paragraph is applied mutatis mutandis pursuant to the preceding paragraph) is to be submitted.
(Inspection of the Status of Compliance with the Operational Safety Programs)
Article 34-2:(1) Inspections limited to to radioactive waste storage activity under Article 51-18, paragraph (5) of the
Act will be conducted four times annuallyevery year. However, inspections for waste storage facilities
for which approval as set forth in Article 51-25, paragraph (2) of the Act has already been obtained
will be conducted four times or less every year, in accordance with the progress of thedecommissioning measures.
(2) Inspection procuedres set forth in the preceding paragraph which are specified by the Ordinance of the
NRA as set forth in Article 12, paragraph (6) of the Act as applied mutatis mutandis pursuant to
Article 51-18, paragraph (6) of the Act shall be as follows:(i)entering the office, facility or place of business;(ii) inspecting books, documents, equipment, components, or any other necessary property;(iii) questioning employees and other people concerned;(iv) requesting nuclear source material, nuclear fuel material, material contaminated by nuclear fuelmaterial, or any other necessary samples limited to the minimum amount necessary for testing.
(Physical Protection Programs)
Article 35-2:(1) A licensee of a waste storage facility who intends to obtain approval for Physical Protection Programs
under Article 51-23, paragraph (1) of the Act shall specify the Physical Protection Programs
concerning the matters set forth in the following items for each place of business for which he/she
intends to obtain the approval, and shall submit an application form containing said PhysicalProtection Programs to the Nuclear Regulation Authority. Matters include:(i)

The system for complying with relevant laws and regulations, as well as Physical Protection
Programs (including senior management involvement);(ii) a system for developing a security culture (including senior management involvement);(iii) the duties of those engaged in the physical protection of specified nuclear fuel material and theirorganization;
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ANNEXES L(iv) the specification of the physical protection areas and limited access areas as well as policing andmonitoring (for the place of business handling the specified nuclear fuel material set forth in item(i) or item (ii) of the table of Article 33-3, paragraph (1), the physical protection areas andperipheral physical protection areas). Matters include:(v) access control for the physical protection areas;(vi) the management of specified nuclear fuel material;(vii) measures forcontinuously maintaining equipment or devices necessary for the physicalprotection of specified nuclear fuel material;(viii)an information system security plan;(ix) the maintenance and inspection of equipment and devices for the physical protection of specified
nuclear fuel material;(x) responses in an emergency;(xi) development of a communications system;(xii) the management of information on measures for the physical protection of specified nuclear fuelmaterial;(xiii)the education and training necessary for the physical protection of specified nuclear fuel material;(xiv) an emergency response plan for waste storage facilities;(xv) measures to be taken in response to threat such as sabotage, (limited to matters falling under
Article 33-3, paragraph (2), item (xxiii including cases where said item is applied mutatis
mutandis pursuant to paragraph (3) and paragraph (4) of said Article));(xvi) periodic evaluation and improvements necessary for the physical protection of specified nuclear
fuel material;(xvii) maintaining records on the physical protection of specified nuclear fuel material at waste storage
facilities (including the status of compliance with Physical Protection Programs);(xviii) other matters necessary for the physical protection of specified nuclear fuel material at waste
storage facilities.
(2) One original copy and one duplicate copy of the application form set forth in the preceding paragraphshall be submitted (when filing an application for any of the waste storage facilities set forth in item(iv) of the table of Article 63, paragraph (1) of the Order that is specified by the Nuclear Regulation
Authority in a public notice, one original copy and two duplicate copies of the application form).
(Inspection of the Status of Compliance with Physical Protection Programs)
Article 35-2-2:(1) Inspections, limited to radioactive waste storage activity, under Article 12-2, paragraph (5) of the Act
as applied mutatis mutandis pursuant to Article 51-23, paragraph (2) of the Act is to be conducted once
every year.
(2) The matters concerning the inspection set forth in the preceding paragraph which are specified by theOrdinance of the NRA as set forth in Article 12-2, paragraph (6) of the Act as applied mutatis
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ANNEXESmutandis pursuant to Article 51-23, paragraph (2) of the Act shall be as follows:(i)entering the office, facility or place of business;(ii) inspecting books, documents, equipment, components, or any other necessary property;(iii) questioning employees and other people concerned;(iv) requesting the submission of specified nuclear fuel material or any other necessary samples
limited to the minimum amount necessary for testing.
(Application for Approval for Decommissioning Plans)
Article 35-6:(1) A licensee of a waste storage activity who seeks approval for a decommissioning plan (hereinafterreferred to as a "decommissioning plan"), pursuant to the provisions of Article 51-25, paragraph (2) ofthe Act, shall draw up said plan covering the matters set forth in the following items and submit anapplication form containing said plan to the Nuclear Regulation Authority:(i)the name and address of the applicant and, in the case of a corporation, the name of its
representative;(ii) the name and location of the place of business pertaining to the decommissioning measures;(iii) the waste storage facilities subject to decommissioning measures pertaining to thedecommissioning plan for which approval set forth in Article 51-25, paragraph (2) of the Act issought (hereinafter referred to as the “facilities under decommissioning measures”);(iv) facilities to be dismantled and methods of dismantlement, out of the facilities set forth in thepreceding item;(v) removal of contamination caused by nuclear fuel material;(vi) disposal of nuclear fuel material;(vii) decommissioning measures.
(2) The documents or drawings set forth in the following items shall be attached to the application form:(i) to (x) (omitted)(3) One original copy and one duplicate copy of the application form set forth in paragraph (1) shall be
submitted.
(Standards for Approval for Decommissioning Plans)
Article 35-9: The standards, limited to those pertaining to radioactive waste storage activity, specified by
the Ordinance of the NRA as prescribed in Article 12-6, paragraph (4) of the Act as appliedmutatis mutandis pursuant to Article 51-25, paragraph (3) of the Act shall be as follows:(i)

solid nuclear fuel material that had been managed or liquid or solid nuclear fuel material, that had
been processed have been transported out of the waste storage facilities;(ii) the management, processing, and disposal of nuclear fuel material has been conducted in an
appropriate manner;(iii) the implementation of decommissioning measures isafeguards against disasters that may be
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caused by nuclear fuel material.
(Application for Confirmation of the Completion of Decommissioning Measures)
Article 35-10:(1) A licensee of waste storage activity who seeks confirmation of the completion of decommissioning
measures, pursuant to the provisions of Article 12-6, paragraph (8) of the Act as applied mutatis
mutandis pursuant to Article 51-25, paragraph (3) of the Act, shall submit an application to the NRA
containing the matters set forth in the following items:(i) to (v) (omitted)(2) A document containing the following matters shall be attached to the application set forth in thepreceding paragraph:(i)the distribution of contamination caused by nuclear fuel material;(ii) other matters in addition to the preceding paragraph that the Nuclear Regulation Authority finds
necessary.
(3) One original copy and one duplicate copy of the application form set forth in paragraph (1) shall be
submitted.
(Standards for Confirmation of the Completion of Decommissioning Measures)
Article 35-11: The standards, limited to those pertaining to radioactive waste storage activities, specified
by the Ordinance of the NRA as prescribed in Article 12-6, paragraph (8) of the Act asapplied mutatis mutandis pursuant to Article 51-25, paragraph (3) of the Act shall be as
follows:(i)there is no need to take radiation prevention measures with regard to remaining facilities and soilon the premises under decommissioning measures;(ii) the disposal of the nuclear fuel material has been completed;(iii) the handover of radiation control records prescribed in Article 26, paragraph (1) to an organization
designated by the Nuclear Regulation Authority set forth in paragraph (5) of said Article has been
completed.
(Report of Accidents and Failures)
Article 35-16: When falling under any of the following items, a waste storage activity licensee, including
former licensees, (hereinafter the same applies in the following Article and Article 40) shallimmediately inform the Nuclear Regulation Authority within 10 days, and make a report on
the situation and actions to be taken pursuant to the provisions of Article 62-3 of the Act:(i)when any nuclear fuel material has been stolen or has gone missing;(ii) in the event of a failure of the waste storage facilities and when special measures are required for
repair work for said failure, and this has interrupted the processing or management of radioactive
waste;201

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ANNEXES(iii) when a failure of the waste storage facilities has interrupted or might interrupt the processing or
management of radioactive waste by losing the ability to confine nuclear fuel materials in alimited area, to prevent radiation hazards from external sources or prevent a fire or explosion at
the facility;(iv) when a failure or other unexpected event has caused an abnormality in discharging

gaseousradioactive waste through the exhaust facilities or discharging radioactive liquid waste through thedrainage facilities;(v) where gaseous radioactive waste has been discharged through the exhaust facilities, and when theconcentration of radioactive material in the air outside the peripheral monitoring area has
exceeded the concentration limit set forth in Article 33, item (iv);(vi) where radioactive liquid waste has been discharged through the drainage facilities, and when theconcentration of radioactive material in the water at the boundary outside the peripheral
monitoring area has exceeded the concentration limit set forth in Article 33, item (vi);(vii) when any nuclear fuel material has leaked outside the radiation controlled area;(viii)when a failure or other unexpected event in the waste storage facilities has caused a leak of
nuclear fuel material within the radiation controlled area. However, cases falling under any of thefollowing are excluded--with the exception where new measures have been taken to limit accessor secure the location where the leak occurred or the case where the leaked material has spread tooutside the radiation controlled area:(a) when leaked liquid nuclear fuel material, has not spread outside the weir to prevent the spread ofany leak that had been installed around the equipment where the leak occurred;(b) where gaseous nuclear fuel material has leaked, but when the ventilators at the leak location
continue functioning properly;(c) when the amount of leaked nuclear radiation material, is small or when the leak is otherwise
minor;(ix) when the nuclear fuel material has reached or may possibly reach criticality;(x) when a failure or other unexpected event in the waste storage facilities has caused persons in theradiation controlled area to be exposed, and when effective doses due to said exposure haveexceeded or may possibly exceed 5mSv with regard to radiation workers or 0.5mSv with regard to
non-radiation personnel;(xi) when any radiation worker has been exposed to radiation that exceeds or may possibly exceed thedose limit set forth in Article 28, paragraph (1), item (i);(xii) in addition to what are set forth in the preceding items, when any hazard (excluding those that do
not require hospital treatment) has occurred or may possibly occur to people in relation to thewaste storage facilities.
(Emergency Measures)
Article 36 Pursuant to the provisions of Article 64, paragraph (1) of the Act, a licensee of a waste storage202

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facility shall take the following emergency measures:(i)where a fire has occurred or there is a risk of a fire spreading, extinguishing said fire or preventing
its spread and at the same time reporting the situation to fire authorities;(ii) moving nuclear fuel material whenever possible to a safer place and prohibiting access with ropes
and signs and the employment of guards to unauthorized personnel;(iii) warning people within or near a waste storage facility to evacuate when appropriate;(iv) preventing the spread of contaminated nuclear fuel material and removing said contamination:(v) taking emergency precautions including possible evacuation where persons have been or may be
exposed to radiation hazards;(vi) taking other measures necessary to prevent radiation hazards.
Table H3-1 Ordinance on Standards for the Location, Structure, and Equipment of Waste Interim
Storage/treatment Facilities (Excerpt)(Shielding)
Article 2:(1) Waste storage facilities shall be designed to include such measures as shielding to significantly reduce
doses around the place of business due to direct and sky-shine radiation from said waste storage
facilities.
(2) The design should include shielding measures to reduce doses in the radiation controlled area or otherplaces within the place of business where personnel are present.
(Function for Confining Radioactive Waste)
Article 3: Waste storage facilities shall be able to confine radioactive waste in a limited area.
(Prevention of Fire Damage)
Article 4: Waste storage facilities shall be designed to include the following safety measures to prevent or
limit damage due to fire or explosion:(i)

preventing the occurrence of a fire and explosion;(ii) detecting a fire and explosion at an early stage and extinguishing the fallout;(iii) reducing the impact of a fire and explosion.
(Ground for Constructing Waste Storage Facilities)
Article 5:(1) Waste storage facilities shall be constructed on ground solid enough to support

said facilities evenin the event of a seismic incident calculated under paragraph (2) of the following Article (with regard
to significant facilities for maintaining safety, including the seismic force set forth in paragraph (3) of
said Article).
(2) Major facilities with a high degree of built-in safety measures shall be constructed on solid where there203

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ANNEXESis unlikely to be any major impact on the facilities even in the event of ground where there is
negligible possibility of a loss of their safety functions even in the event of earth problems.

(3) Major facilities with a high degree of built-in safety measures shall be constructed on ground where
there is negligible possibility of displacement.
(Prevention of Damage due to Earthquakes)
Article 6(1) Waste storage facilities shall be designed to fully sustain a major seismic force.
(2) The seismic force set forth in the preceding paragraph shall be calculated in accordance with degrees ofradiation effects to the public resulting from a loss of safety functions of the waste storage facilities
that may possibly be caused by an earthquake.
(3) Major facilities shall be designed to maintain their operational safety functions even against the impactof a major seismic force possibly triggered by an earthquake.,(4) Major facilities shall be designed to protect their safety functions against a potential slope failurecaused by earthquake activity.
(Prevention of Tsunami Damage)
Article 7: Waste storage facilities shall be designed to protect their safety while in operation against theeffects of even major tsunami activity..
(Prevention of Damage due to Impacts from the Other External Events)
Article 8:(1) Waste storage facilities shall be designed to maintain their safety measures even in the event of acatastrophic natural event other than earthquakes and tsunamis.
(2) Waste storage facilities shall be designed to maintain their safety measures against human-induced
events (excluding intentional events) within the place of business vicinity..
(Prevention of Illegal Entry into Waste Storage Facilities)
Article 9: The place of business shall institute measures to prevent illegal entry into the waste storage
facilities or the introduction of explosives, flammable or other items which may harm personnel
or the facilities themselves. Other measures will prevent unauthorized computer access (asprescribed in Article 2, paragraph (4) of the Act on the Prohibition of Unauthorized Computer
Access (Act No. 128 of 1999)).
(Prevention of Criticality of Nuclear Fuel Material)
Article 10: Where there is a risk that nuclear fuel material may possibly reach criticality, waste storage
facilities shall take measures to prevent such an occurrence.

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ANNEXES L(Facilities with Safety Functions)
Article 11:(1) Facilities with safety functions shall secure such functions.
(2) When sharing safety functions with other nuclear facilities or sharing the equipment of facilities withsafety functions measures will be taken to ensure that said safety functions at all facilities are notdamanged.
(3) An inspection can be conducted at facilities with safety functions to ensure the safety of theiroperations and the maintenance and repair of such functions.
(4) Major safety facilities shall have automatic redundancy if it is necessary to maintain their function andensure the safety of waste storage facilities.
(Prevention of Radiation Hazards in the Event of a Postulated Accident that May Cause the Highest Dose)
Article 12: Waste storage facilities shall be designed to prevent public radiation hazards around the placeof business in the event of a postulated accident that may cause the highest dose.
(Waste Treatment Facilities)
Article 13: Waste storage facilities shall have facilities to perform the functions prescribed in Article 32,
item (ii) of the Order for Enforcement of the Act on the Regulation of Nuclear Source
Material, Nuclear Fuel Material and Reactors (Cabinet Order No. 324 of 1957),

prescribedas follows:(i)a facility can treat the radioactive waste it accepts;(ii) when discharging radioactive waste generated by such treatment, installing an exhaust ventconnected to disposal facilities or taking other necessary measures so that the concentration of
airborne radioactive material outside the peripheral monitoring area or material in the water at theboundary of the peripheral monitoring area can be significantly reduced.
(Management Facilities)
Article 14: Waste storage facilities shall manage radioactive waste as follows:(i)the facilities shall have the capacity to manage radioactive waste;(ii) facilities will use an appropriate method to store radioactive waste, taking into consideration theproperties of said waste.
(iii) for facilities that could overheat by decay heat and radiations from radioactive waste, necessary
cooling measures will be put in place.
(Instrumentation and Control Facilities)
Article 15:(1) Waste storage facilities shall have instrumentation and control facilities to properly monitor andconfirm the restriction of radioactive waste to a limited area and other similar functions.
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may threaten the safety of a facilitywhere the concentration of radioactive material or radiation doses
as set forth in item (ii) of the following Article have risen significantly, or where there is a risk that asignificant amount of radioactive waste leaks from the disposal facilities.
(Radiation Control Facilities)
Article 16: The place of business shall have radiation control facilities, as prescribed as follows:(i)equipment for monitoring and managing doses in order to protect radiation workers;(ii) equipment to monitor and measure radioactive material concentrations and radiation doses within
the place of business and surrounding area;(iii) equipment to indicate necessary information at an appropriate place to protect the public andradiation workers from radiation.
(Disposal Facilities)
Article 17:(1) Waste storage facilities shall have disposal facilities able to treat locally generated radioactive waste
and significantly reduce the concentration of radioactive material in the air outside the peripheral
monitoring area and in water at the border of the peripheral monitoring area.
(2) Waste storage facilities shall have the capacity to store radioactive waste for disposal.
(Standby Power)
Article 18: Waste storage facilities shall secure standby power to ensure the continued operation ofmonitoring and other necessary equipment in the event of loss of electric power supply froman off-site power grid.
(Communications Equipment)
Article 19:(1) The place of business shall have a warning device and communications equipment to issue instructions
to local personnel in the event of an accident..
(2) The place of business shall have equipment to communicate with exterior locations in the event of an
accident.
(3) Waste storage facilities shall have the ability to evacuate personnel from within the place of business.
Table H3-2 Ordinance on Standards for the Location, Structure, and Equipment of Category 2 Waste
Disposal Facilities (Excerpt)(Ground for Constructing Waste Disposal Facilities)
Article 3:(1) Waste disposal facilities shall be constructed on terrain firm enough to support said facilities even in206

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the event of a seismic force calculated under paragraph (2) of the following Article.
(2) A waste disposal site shall be constructed on terrain where there is negligible threat to its safety even in
the event of ground movement.
(3) A waste disposal site shall be constructed on ground where there is negligible possibility ofdisplacement.
(Prevention of Earthquake Damage)
Article 4:(1) Waste disposal facilities shall be designed to fully sustain a seismic force.
(2) A seismic force as set forth in the preceding paragraph shall be calculated in accordance with degrees
of radiation effects on the public should the safety functions of a facility be lost because of the effects ofan earthquake.
(Prevention of Tsunami Damage)
Article 5: Waste disposal facilities shall be designed to protect their safety functions despite a large-scale
impact by a tsunami.
(Prevention of Damage due to Impacts from the Other External Events)
Article 6:(1) Waste disposal facilities shall be designed to retain their safety features even following a natural
phenomena excluding earthquakes and tsunamis.
(2) Waste disposal facilities shall be designed to retain their safety features against postulated
human-induced events (excluding intentional events) within the place of business or the neighboring
area.
(Prevention of Fire Damage)
Article 7: Waste disposal facilities shall be designed with a combination of measures to protect its safety
in the event of fire and explosion:(i)

preventing a fire and explosion;(ii) early detection of a fire and explosion and extinguishing said fire.
(iii) reducing the impact of a fire and explosion(Shielding)
Article 8:(1) Waste disposal facilities shall incorporate measures such as shielding to significantly reduce doses
around the place of business from direct and sky-shine radiation.
(2) Where there is a need to prevent radiation hazards, waste disposal facilities shall incorporate
measures such as shielding to reduce doses in the radiation controlled area or other populated places207

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within the place of business.

(3) Waste disposal facilities shall incorporate measures to prevent the scattering of radioactive material.
(Prevention of Radiation Hazards at Abnormal Times)
Article 9: Waste disposal facilities shall satisfy the following requirements:(i)the facilities do not cause radiation hazards to the public in the vicinity of the place of businesseven when an abnormality occurs in the waste disposal facilities during the entirety of the
facility’s operational life;(ii) during the above mentioned period, the facilities are expected to shift to a situation where there isno need to take any measures for the maintenance of the waste disposal site.
(Waste Disposal Site)
Article 10:(1) A waste disposal site shall be able to prevent any abnormal leak of radioactive material outside thewaste disposal site.
(2) During a pit disposal, a waste site will be able to confine radioactive material in a limited area at least
during the period up to the completion of the operation by installing an engineered barrier structure
or by another method.
(3) The safety of a waste disposal site will not be damaged by any chemical material contained in thedisposed radioactive waste or any other chemical material.
(Radiation Control Facilities)
Article 11: The place of business shall have the following radiation control facilities:(i)equipment for monitoring and managing doses in order to protect radiation workers fromradiation;(ii) equipment for monitoring and measuring the concentration of radioactive material and radiation
doses within the place of business and the nearby area;(iii) equipment to relay necessary information at an appropriate place to inform and protect the public
and workers from radiation.
(Disposal Facilities)
Article 12:(1) Waste disposal facilities shall have the capability to treat radioactive waste generated in said facilities
and thereby significantly reduce radioactive material concentrations in the air outside the peripheral
monitoring area and in water at the border of the peripheral monitoring area.
(2) Waste disposal facilities shall have sufficient capacity to store radioactive waste for disposal.
(Monitoring Equipment for Groundwater Levels)
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Article 13: Waste disposal facilities shall have equipment (excluding equipment prescribed in Article 11,
item (i) and item (ii)) for monitoring and measuring groundwater levels and other situations
on the waste disposal site and in the nearby vicinity.
(Standby Power)
Article 14: Waste disposal facilities shall secure standby power for monitoring and other necessary
equipment in the event of loss of electric power supply from an off-site power grid.
(Communications Equipment)
Article 15:(1) The place of business shall have a warning device and communications equipment to provide
instructions to personnel when any abnormality occurs in the waste disposal facilities.
(2) The place of business shall have equipment to communicate with external locations when any
abnormality occurs in the waste disposal facilities.
(3) Waste disposal facilities shall have facilities for the evacuation of people within the place of business.
Table H4-1 Ordinance on Technical Standards for the Design and Construction Methods for Specified
Waste Disposal Facilities or Specified Waste Interim Storage/Treatment Facilities (Excerpt)(Prevention of Fire Damage)
Article 3:(1) If there is a significant risk from fire or explosion to the safety of specified waste disposal facilities orwaste storage facility fire extinguishing and alarm equipment (limited to equipment that automaticallydetects a fire and set off an alarm, such as automatic fire-alarm box and electric fire alarm system)
shall be installed as necessary.
(2) The fire extinguishing and alarm equipment described in the preceding paragraph shall be such that
their failure, damage or malfunction is unlikely to significantly impair the safety of the specified waste
disposal fand storage facilities.
(3) With regard to facilities with safety functions that may be damaged by a fire or explosion,
noncombustible or nonflammable materials shall be used to the extent possible, while preparing proper
protection measures such as the installation of fire walls, as necessary.
(4) Equipment for handling or managing radioactive waste that may generate hydrogen shall be structured
to prevent the retention of generated hydrogen.
(5) Cells and rooms containing equipment for handling or managing radioactive waste that may generatehydrogen (excluding equipment free from any risk of explosion) shall be built to prevent the retentionof hydrogen even in the case where hydrogen leaks from said equipment and other appropriate
measures for preventing an explosion shall be taken therefor.
(Ground for Constructing Specified Waste Disposal Facilities or Specified Waste Storage Facilities)209

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Article 4: Specified waste disposal or waste storage facilities shall be constructed terrain that can support
such structures even if they are subject to seismic forces described in paragraph (1) of thefollowing Article has acted.
(Prevention of Earthquake Damage)
Article 4-2: Specified waste disposal or waste storage facilities shall be designed to prevent radiation
hazards to the public even if damaged by a seismic force. Such force is calculated by theradiation impact on the public resulting from a loss of a facility’s safety functions possibly
caused by an earthquake(2) Major safety facilities shall be designed to protect operating safety functions despite any major impact
from a seismic fore caused by an earthquake.
(3) Protective measures will be taken to ensure that the safety functions of key facilities will not bethreatened because of slope failure resulting from an earthquake.
(Prevention of Tsunami Damage)
Article 4-3: In order to ensure that the safety of specified operating waste disposal and waste storage
facilities will not be impaired by a major tsunami protective and other key measures shall betaken.
(Prevention of Damage due to Impacts from the Other External Forces)
Article 4-4:(1) In the case where there is a risk that postulated natural phenomena other than earthquakes or tsunamis
may threaten the safety of specified waste disposal or waste storage facilities, protection measures,
measures to strengthen ground foundations and other measures shall be taken.
(2) If there are places of business, railways, roads, or human concentrations adjacent to waste disposal or
waste storage facilities, protection and other relevant measures will be taken to ensure said facilities
will not suffer from ‘spillover’ effects from those adjacent areas because of fires, eplosions, accidents
involving vehicles, ships or aircraft carrying hazardous materials or other human-induced events.
(Prevention of Illegal Entry into Specified Waste Disposal and Waste Storage Facilities)
Article 4-5: The place of business where specified waste disposal or waste storagefacilities or are installed(shall prepare security measures to prevent illegal entry or the introduction of explosive,
flammable or other items that may harm personnel and the failities themselves. Other
measures will prevent unauthorized computer access as prescribed in Article 2, paragraph (4)of the Act on the Prohibition of Unauthorized Computer Access (Act No. 128 of 1999))(Prevention of Criticality of Nuclear Fuel Material)
Article 4-6: Where there is a risk that nuclear fuel material may reach criticality, specified waste disposal
facilities and waste storage facilities shall take the necessary preventive measures.
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ANNEXES L(Materials and Structures)
Article 5:(1) Materials and structures of vessels and pipes at specified waste disposal and waste storage andsupporting structures, which are necessary for ensuring the safety of the facilities, should be of
sufficient strength and corrosion resistance to meet the stated design standards of such vessels.
(2) Vessels and pipes of specified waste disposal and waste storage facilities which are necessary to ensure
the safety of the facilities should be able to withstand any appropriate pressure test or leakage test
without significant leakage.
(Function for Confining Radioactive Waste)
Article 6: Specified waste disposal or waste storage facilities shall be designed to maintain the function for
confining radioactive waste in a limited area as prescribed as follows:(i)when connecting a pipe delivering non-radioactive fluid waste to a vessel or pipe containing fluid
radioactive waste, the system shall be such that there is no risk that the radioactive waste will‘flow back’ into the pipes delivering non-contaminated waste.

(ii) the hood handling non-sealed radioactive waste shall be such that it can properly maintaintheair flow speed at the opening;(iii) a room where contamination by radioactive waste may occur shall be such that it can maintain anegative inner pressure, if necessary;(iv) facilities where equipment handling radioactive liquid waste is installed (limited to the part of a
facility where there is a risk that a leak of radioactive liquid waste may expand) are to beconstructed as follows:(a) the composition of the floor and wall surfaces inside a structure hinders the leakage of radioactive
liquid waste;(b) an embankment to prevent a leak of radioactive liquid waste outside the facilities is installed in
the vicinity of equipment handling the waste, at the entrance to the facility and the surroundingarea; This will not apply where the floor surface inside the facility is lower than the floor surfaceof neighboring buildings or the ground surface and there is negligible possibility of a leak outside
the facilities;(c) the facilities are constructed so that inside floor surfaces are not above drainage canals
discharging effluent outside the place of business (excluding drainage canals for spring water
which have no openings within radiation controlled area and are not subject to radioactive waste
contamination ). This does not apply where said drainage canals have a system that safely
disposes of the effluent contaminated by radioactive waste and equipment for measuring thematters set forth in Article 15, paragraph (1), item (iii).
(Shielding)
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Article 7:(1) Specified waste disposal and waste storage facilities shall be designed to maintain doses around theplace of business due to direct and sky-shine radiation from said facilities far below the dose limits
specified by the Nuclear Regulation Authority.
(2) Shielding equipment with the capability to prevent radiation hazards shall be installed in sensitive
araeas the place of business. In this case, measures to prevent a radiation leak shall be taken
where shielding equipment has openings, pipes, or other potentially vulnerablepenetration points.

(Ventilation)
Article 8: At places where there is a need to prevent radiation hazards due to air contaminated byradioactive waste within the specified waste disposal or waste storage facilities, ventilators shall be
installed as follows:(i)

ventilators with the capacity to prevent radiation hazards;(ii) ventilators are designed to prevent air contaminated by radioactive waste from flowing back;(iii) newly installed filters can be properly maintained, easily replaced and has a structure to the easy
removal of contamination by radioactive waste;(iv) the air inlet is installed in such a way it will not easily take in air contaminated by radioactive
waste.
(Prevention of Contamination by Radioactive Waste)
Article 9: Within buildings in specified waste disposal or waste storage facilities frequented by many
people,,radioactive waste contamination can be easily removed from the surface of walls, floors
and other areas with which people may come into contact with.
(Facilities for Accepting or Managing Radioactive Waste)
Article 10:(1) Specified waste disposal facilities for accepting waste that could be overheated by decay heat andradiations from radioactive waste shall be constructed so that necessary cooling measures can be taken.
(2) Specified waste storage facilities shall be constructed as prescribed as follows:(i)have the required capacity to manage radioactive waste;(ii) facilities use an appropriate method for storing radioactive waste based on its particularproperties;(iii) for facilities that could by affected by decay heat and radiations from radioactive waste, necessary
measures are to be put in place for cooling.
(Waste Treatment and Disposal Facilities)
Article 11: Equipment for disposing of radioactive waste shall be installed as prescribed as follows:(i)

said equipment can dispose of radioactive waste generated in the specified waste disposal or waste212

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storage facilities so that the concentration of radioactive material in the air outside the peripheral
monitoring area and in water at the border of the peripheral monitoring area will be reduced below
their respective concentration limits specified by the Nuclear Regulation Authority;(ii) the equipment is installed separately from equipment for disposing of waste other than radioactive
waste; this does not apply where non radioactive fluid waste is fed into equipment handling fluid
radioactive waste, but where there is little possibility that that radioactive waste will flow backinto the system handling non radioactive waste.
(iii) the equipment for disposing gaseous radioactive waste does not discharge this waste at points
other than the exhaust vent;(iv) filters for equipment for disposing of gaseous radioactive waste must be easy to maintain andreplace and be so structured as to ensure the easy removal of contamination by radioactive waste;(v) the equipment for disposing of radioactive liquid waste discharges said waste only at the discharge
port.
(2) Equipment for treating radioactive waste shall have the capability of treating all the radioactive waste it
accepts.
(Facilities with Safety Functions)
Article 12:(1) When sharing of equipment or other items between facilities with safety functions, specified waste
disposal and waste storage facilities will be designed to prevent any damage to their safety functions.
(2) Facilities with safety functions shall be designed to ensure that an inspection or testing of the safetyfunctions of said facilities and the integrity of their maintenance or repair can be conducted.
(3) In addition to what are prescribed in the preceding paragraph, facilities with safety functions or
systems to which said facilities belong shall have automatic redundancy if it is necessary to maintaintheir safety functions.
(Equipment for Transporting)
Article 13: Equipment to transport radioactive waste (excluding equipment free from any risk ofsignificantly impairing human safety) shall be installed as follows:(i)

said equipment has the capability to move radioactive waste that ordinarily needs to betransported;(ii) such equipment can safely retain radioactive waste in the event of the suspension of the power
supply for transporting said radioactive waste.
(Instrumentation and Control Facilities)
Article 14:(1) Specified waste disposal or waste storage facilities shall have equipment to detect and raise an
immediate alarm to any safety risks endangering said facilities through damage or malfunction of213

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ANNEXESequipment. Other include where a concentration of radioactive material set forth in paragraph (1), item(ii) of the following Article or the dose equivalent prescribed in item (iv) of said paragraph has risen
significantly, or where there arises a risk that a significant amount of radioactive material in a liquidstate leaks from the disposal facilities of radioactive liquid waste,.

(2) Specified waste disposal or storage facilities shall have circuits to ensure that radioactive waste cancontinue to confined in a limited area even in the event of equipment damanage or malfunction. There
will also be equipment to promptly and automatically respond to a fire or explosion.
(Radiation Control Facilities)
Article 15:(1) The place of business shall have radiation control facilities for measuring, both directly and indirectly,(i)dose equivalent rates specified by the Nuclear Regulation Authority displayed prominently at theside wall of a radiation shielding structure of the body of the waste management equipment andfacilities for accepting radioactive waste;(ii) concentration of radioactive material in exhaust gases at or near the appropriate exhaust vent;(iii) concentration of effluent radioactive material at or near the discharge port of radioactive liquid
waste:(iv) dose equivalent and concentration of airborne radioactive material, as well as the density ofradioactive material on a contaminatedsurface as specified by the Nuclear Regulation

Authority;(v) dose equivalent specified by the NRA of external radiation in the peripheral monitoring area.
(2) Radiation control facilities shall indicate necessary information at an appropriate place from of thematters set forth in the preceding paragraph.
(Standby Power)
Article 16: Specified waste disposal or waste storage facilities shall secure standby power to be used formonitoring and other necessary equipment in the event of loss of electric power supply from
off-site power grid.
(Communications Equipment)
Article 17:(1) The place of business shall have a warning device and communications equipment so that necessary
instructions can be issued to people within the place of business in the event of an accident.
(2) The place of business shall have equipment to communicate with external sources in the event of an
accident.
(3) Specified waste disposal or waste storage facilities shall have equipment to help the evacuation ofpeople from within the place of business.
F
Table H6-1 Technical Standards
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1. Technical Standards for Waste Disposal Facilities(Technical Standards under Article 6 of the Ordinance on Activity of Category 2 Waste Disposal of
Nuclear Fuel Material or Material Contaminated by Nuclear Fuel Material)(i)the total amount of radioactivity for each type of radioactive material contained in a radioactive
waste landfill shall not exceed the total amount of radioactivity for each type of radioactive
material stated in the application form for permission set forth in Article 51-2, paragraph (1) of the
Act or Article 51-5, paragraph (1) of the Act and in the document that contains the conditions
attached when the permission was granted under Article 62-2, paragraph (1) of the Act(hereinafter referred to as the “application form, etc.” in this Article, Article 6-3, and Article 8);(ii) before starting landfilling, standing water shall be removed and measures taken to prevent the
infiltration of fresh rainwater at the waste disposal site. (when the site is demarcated with internal
partition equipment as set forth in item (iii) of the following paragraph, the demarcated area for
landfilling; hereinafter the same applies in this item(iii) when landfilling solidified concrete waste and where there is a risk that radioactive material may
scatter outside the waste disposal site, measures to prevent scattering shall be taken);(iv) the waste disposal site shall be filled with earth and sand after completing the landfill so that there
will nohole will be left;(v) explosive, corrosive and other hazardous materials shall not be landfilled at the waste disposal
site;(vi) after landfill completion the surface of the waste disposal site shall be covered with earth and sandso that landfilled material and equipment are not easily exposed;(vii) the waste disposal facilities shall have the structure and equipment stated in the application formin addition to satisfying the preceding items.
In the case of conducting a pit disposal with an engineered barrier structure installed
In addition details in the preceding paragraph, technical standards for waste disposal facilities are as
follows:(i)the facilities shall be constructed by the method specified by the Nuclear Regulation Authority forthe prevention of radiation hazards;(ii) the engineered barrier structure shall satisfy the following requirements:(a) structurally it is resistant to its own weight,, earth pressure or seismic force;(b) measures are taken to prevent corrosion from surface or underground water and the soil;(iii) a waste disposal site with an opening whose area exceeds 50 square meters or has a capacity
exceeding 250 cubic meters shall satisfy the requirements set forth in the preceding item and shallbe demarcated by internal partition equipment, which is installed by the method specified by the
Nuclear Regulation Authority for the prevention of radiation hazards, into areas whose respective
areas do not exceed around 50 square meters or into areas whose respective capacities does notexceed around 250 cubic meters;
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ANNEXES(iv) while landfill is ongoing, the barrier structure and internal partition equipment detailed in item(iii) shall be inspected as necessary, and where a risk of damage to such equipment or a leak ofradioactive material is found, required measures shall be taken;(v) at the waste disposal site where landfilling is completed, or where the site is demarcated byinternal partition equipment set forth in item (iii), at the demarcated area where landfilling iscompleted, a cover that satisfies the requirements set forth in item (ii) shall be installed promptly
by the method specified by the Nuclear Regulation Authority for the prevention of radiation
hazards, before covering the site or the area with earth and sand.

In the case of conducting a pit disposal without installing an engineered barrier structure
In addition to what are provided for paragraph (1), technical standards for waste disposal facilities are to
be as follows:(i)the facilities shall be constructed by the method specified by the Nuclear Regulation Authority forthe prevention of radiation hazards;(ii) the facilities solidifying radioactive waste integrally shall satisfy the requirements set forth in item(iii) of the preceding paragraph and its volume shall not exceed around 500 cubic meters.
2. Technical Standards for Radioactive Waste to be Disposed of(Technical Standards under Article 8 of the Ordinance on Activity of Category 2 Waste Disposal of
Nuclear Fuel Material or Material Contaminated by Nuclear Fuel Material)(i)in the case of Intermediate Depth Disposal(a) radioactive waste to be disposed of shall be generated at the factory or place of business where afuel facility (limited to a facility solely conducting the fabrication and enrichment of fuelassemblies that contain mixed uranium and plutonium oxide), research and test reactor facility,
power reactor facility or reprocessing facility is installed;(b) radioactive waste to be disposed of shall be a waste package;(c) said waste package shall be as specified in the following paragraph:(ii) in the case of pit disposal:(a) radioactive waste to be disposed of shall be generated at the factory or place of business where a
research and test reactor facility or power reactor facility is installed;(b) radioactive waste to be disposed of shall be solidified concrete waste or a waste package;(c) said waste package or solidified concrete waste shall be as specified in the following paragraph orparagraph (3);(iii) in the case of trench disposal:(a) radioactive waste to be disposed of shall be generated at the factory or place of business where a
research and test reactor facility or power reactor facility is installed;(b) radioactive waste to be disposed of shall be solidified concrete waste;(c) said solidified concrete waste shall be as specified in paragraph (3).
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Technical standards for a waste package are as follows:(i)for the prevention of radiation hazards, radioactive waste shall be encapsulated in a vessel orsolidified with a vessel by the method specified by the Nuclear Regulation Authority;(ii) the radioactivity concentration shall not exceed the maximum radioactivity concentration stated in
the application for.;(iii) the surface density of radioactive material shall not exceed 10% of the surface density limit as set
forth in Article 14, item (i), (c);(iv) any material that may damage the integrity of the waste package shall not be included;(v) ithe waste package shall have enough strength to bear the potential load that may be applied whenlandfilled;(vi) there shall be no significant damage;(vii) a radioactive waste sign shall be attached in a prominent place on the surface of the waste package
so that it cannot be easily dislodged, and a serial number for cross checking said waste packagewith the details stated in the application form set forth in the preceding Article shall also be
indicated.
Technical standards for solidified concrete waste are to be as follows:(i)

explosive materials shall not be included;(ii) measures for cross checking said solidified concrete waste with the matters stated in theapplication form set forth in the preceding Article shall be taken.
Table H6-2 Matters to be specified in the Operational Safety Programs(Article 34, Paragraph (1) of the Ordinance on Activity of Waste Storage of Nuclear Fuel Material orMaterial Contaminated by Nuclear Fuel Material)(i)

MATTERS concerning the system for complying with relevant laws and regulations, as well as
the operational safety programs (including senior management involvement);(ii) the system for developing a culture of safety (including senior management involvement);(iii) quality assurance of the waste storage facilities (including matters concerning the method andsystem for conducting root cause analysis and positioning of the procedural manuals in theoperational safety programs);(iv) the duties of personnel engaged in the operation and management of waste storage facilities andtheir organization (excluding what is set forth in the following item);(v) the duties and authority of chief engineers of radioactive waste,in supervising operational safety,
and their positions in the organization;(vi) education on operational safety for radiation workers at waste storage facilities:(a) policies for providing education on operational safety (including the drawing up of an
implementation plan);
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1. compliance with the related laws and regulations, as well as operational safety programs;
2. the structure, functions, and operation of the waste storage facilities;
3. radiation control;
4. the handling of nuclear fuel material and material contaminated by nuclear fuel material;
5. actions to be taken in an emergency;(c) education on operational safety pertaining the waste storage facilities;(vii) the operation of sensitive equipment for operational safety;(viii)the specification of radiation controlled areas and peripheral monitoring areas, as well as theaccess control to these areas;(ix) exhaust monitoring equipment and effluent monitoring equipment;(x) monitoring of doses, dose equivalents, concentration of radioactive material, and density ofradioactive material on the surface of material contaminated by radioactive material, as well as
the removal of contamination;(xi) the management of radiation detectors and measurement methods;(xii) the policing and checking of the waste storage facilities and accompanying actions;(xiii)the periodic self-inspection of waste storage facilities;(xiv) the reception, shipment, disposal and other handling of radioactive waste;(xv) actions to be taken in an emergency;(xvi) maintaining proper records and reports on operational safety at waste storage facilities(including the status of compliance with the operational safety programs). Such reports include
ones made to senior management covering accidents and failures set forth in Article 35-16, orother incident equivalent thereto);(xvii) periodic evaluation of the waste storage facilities;(xviii) the sharing with other licensees of waste storage activity technical information on operationalsafety from the business operators conducting a maintenance checks;(xix) information disclosure on non-compliance if any;(xx) other matters necessary for operational safety pertaining to the waste storage facilities.

(Article 20, Paragraph (1) of the Ordinance on Activity of Category 2 Waste Disposal of Nuclear Fuel
Material or Material Contaminated by Nuclear Fuel Material)(i)

MATTERS concerning the system for complying with relevant laws and regulations, as well as
operational safety programs (including senior management involvement);(ii) the system for developing a culture of safety (including senior management involvement);(iii) quality assurance of the waste disposal facilities (including matters concerning the method andsystem for conducting root cause analysis and positioning of the procedural manuals in theoperational safety programs);(iv) the duties of those engaged in the operation and management of the waste disposal facilities and218

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their organization (excluding details set forth in the following item);(v) the duties and authority of chief engineers of radioactive waste in supervising operational safety,
and their positions in the organization;(vi) education on operational safety for radiation workers working at waste disposal facilities:(a) policies for providing education on operational safety (including the drawing up of an
implementation plan);(b) the details of education policies on operational safety:
1 compliance with relevant laws and regulations, as well as the Operational Safety Programs;
2. the structure, functions, and operation of the waste disposal facilities;
3. radiation control;
4. handling nuclear fuel material and material contaminated by nuclear fuel material;
5. actions to be taken in an emergency;(c) education on operational safety at waste disposal facilities;(vii) measures to be taken for the operational safety of Category 2 waste disposal in accordance withthe attenuation of radioactivity;(viii)the specification of the radiation controlled areas, peripheral monitoring areas and protection
areas for disposal, as well as the access control to these areas;(ix) exhaust monitoring equipment and effluent monitoring equipment;(x) monitoring of doses, dose equivalents, concentration of radioactive material, and density ofradioactive material on the surface of material contaminated by radioactive material, as well as
the removal of contamination;(xi) the monitoring of of the waste disposal sites and their immediate vicinity (excluding themonitoring set forth in item (x)) for the purpose of obtaining information necessary for theperiodic evaluation of the waste disposal facilities under Article 19-2;(xii) the management of radiation detectors and measurement methods;(xiii)policing of waste disposal facilities and accompanying actions;(xiv) the matters concerning the reception, transport, disposal and other handling of radioactive waste;(xv) actions to be taken in an emergency;(xvi) maintaining proper records and reports on operational safety at waste disposal facilities(including the status of compliance with the operational safety programs). Such reports include
ones made to senior management in the event of accidents and failures, set forth in Article
22-17;(xvii) periodic evaluation of waste disposal facilities;(xviii) sharing with licensees of Category 1 waste disposal activity and licensees of Category 2 waste
disposal activity of technical information on operational safety obtained from operators
performing maintenance checks;(xix) information disclosure on non-compliance if any;(xx) other matters necessary for operational safety pertaining to the waste disposal facilities.
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Table H6-3 Examples of Methods of Disposing of Radioactive Waste in the Place of Business where
Nuclear Facilities are Installed
1. Gaseous radioactive waste(1) Discharging such waste through exhaust facilities
The concentration of radioactive material in the exhaust should be reduced to the extent possible byfiltration, radioactivity decay over time, dilution with a large amount of air, at the exhaust facilities.
In this case, the concentration of radioactive material at the exhaust vent or exhaust monitoring
equipment should be monitored to ensure that the concentration of radioactive material in the air
outside the peripheral monitoring area will not exceed limit specified by the Nuclear Regulation
Authority.
(2) Storing such waste for disposal in tanks that can prevent radiation hazards
2. Radioactive liquid waste(1) Discharging such waste through the drainage facilities
The concentration of radioactive material in the effluent should be reduced at the drainage facilities
by filtration, evaporation, adsorption using the ion-exchange resin method, radioactivity decay overtime, and dilution with a large amount of water. The concentration of radioactive material in theeffluent at the discharge port or effluent monitoring equipment should be monitored to ensure that theconcentration of radioactive material in the water at the boundary outside the peripheral monitoringarea will not exceed limits specified by the NRA.
(2) Storing such waste for disposal in drain tanks that can prevent radiation hazards(3) Encasingwaste in a vessel or solidifying such waste with a vessel and storing said waste for disposal
at storage disposal facilities that can prevent radiation hazards
a. When encasing radioactive waste in a container, said vessel shall conform to the following
standards:
・The container has a structure that is resistant to corrosion,less permeable and prevents leaks ofradioactive waste;
・The container is not subject to cracks or damage;・The container lid is difficult to remove;b. When solidifying radioactive waste with a container such a structure, can prevent a scatter or leak ofradioactive waste.
c. When storing radioactive waste for disposal at a storage disposal facility the following proceduresshould be followed:
・When encapsulating the radioactive waste in a container and storing it for disposal, taking measuresnecessary to prevent the spread of contamination in the event of any cracks or damage to said
container, such as by covering it with materials that can absorb radioactive waste or by installing a
tray that can receive said radioactive waste;
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・Attaching a radioactive waste sign to a container in which the radioactive waste is encapsulated or
which is solidified with the radioactive waste, and indicating a serial number for cross checking
said radioactive waste with recorded details based on the provisions of Article 44;
・Posting precautions for management in a prominent place at said storage disposal facilities;(4) Incinerating waste in the incinerator to prevent radiation hazards(5) Solidifying waste in solidification equipment that can prevent radiation hazards(6) Landfilling waste in a disposal site in accordance with the technical standards for waste disposal
facilities and the radioactive waste to be disposed of
The concentration of radioactive material in underground water in the peripheral monitoring area
should be monitored the requiste underground equipment to ensure that the concentration ofradioactive material at the boundary outside the peripheral monitoring area does not exceed limits
specified by the Nuclear Regulation Authority.
3. Solid radioactive waste(1) Incinerating waste to prevent radiation hazards(2) Encasing waste in a container or solidifying such waste with a vessel and storing said waste for
disposal at the storage disposal facilities:
a. When encapsulating radioactive waste in a vessel, said vessel shall conform to the following
standards:
・The container is less permeable, resistant to corrosion and prevents radioactive leaks;
・The container is resistant to cracks or damage;・The container lid is hard to remove;b. When solidifying radioactive waste with a container such container integrally solidified with shallbe capable of preventing a scatter or leak of radioactive waste.
c. When storing radioactive waste for disposal at a storage disposal facility to prevent radiation
hazards, the following procedures are to be followed:
・Attaching a radioactive waste sign to a container in which the waste is encapsulated or which issolidified with the radioactive waste, and indicating a serial number for cross checking said
radioactive waste with details recorded under the provisions of Article 44;
・Posting precautions for management in a prominent place at said storage facilities;(3) With regard to cumbersme radioactive waste such as large machinery which is extremely difficult todispose of under the method set forth in 2) above, or radioactive waste that requires radioactivity
decay, storing such waste for disposal at storage facilities that can prevent radiation hazards
Precautions for wastemanagement should be posted in a prominent place at said storage disposal
facilities.
(4) Landfilling such waste in a disposal site in accordance with the technical standards for the waste
disposal facilities and radioactive waste to be disposed of
The concentration of radioactive material in underground water in the peripheral monitoring area
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ANNEXESshould be monitored by underground equipment, to ensure the concentration of radioactive material
in the water at the boundary outside the peripheral monitoring area will not exceed limits specified by
the Nuclear Regulation Authority.

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