Provisional Translation

Convention on Nuclear Safety
National Report of Japanfor the Third Review Meeting

August 2004
Government of JapanTABLE OF CONTENTS
Preface
A. General Provisions
Existing Nuclear Installations……………………………………………………..

6-1

6.1

Existing Nuclear Installations in the Scope of this Convention…………………………

6-1

6.2

Major Events in the Existing Nuclear Installations after the Previous Report…………..

6-2

6.3

Evaluation and Verification of Safety, and Position as to Continued Operation………...

6-3

Article 6

B. Legislation and Regulation
Legislative and Regulatory Framework………………………………………….

7-1

7.1

Basic Legislation Governing the Utilization of Nuclear Energy………………………...

7-1

7.2

Legislations and Regulations Governing the Safety of Nuclear Installations…………...

7-2

7.3

Legislative Regulatory Framework at Each Stage……………………………………….

7-5

7.4

Enforcement of Applicable Regulations and Terms of License………………………….

7-7

Article 7

Article 8

Regulatory Body…………………………………………………………………… 8-1

8.1

Mandate and Duties of Regulatory Body………………………………………………...

8-1

8.2

Organizations for Enforcement of Safety Regulation of Nuclear Installations………….

8-2

8.3

Nuclear and Industrial Safety Agency (NISA)…………………………………………..

8-2

8.4

Organization related to NISA……………………………………………………………

8-5

8.5

The Nuclear Safety Commission (the NSC)……………………………………………..

8-6

8.6

The Atomic Energy Commission (the AEC)……………………………………………..

8-7

8.7

Other Administrative Bodies……………………………………………………………..

8-8

Article 9 Responsibility of the License Holder………………………………………………

9-1

9.1

Regulatory measures for the license holder to take the prime responsibility for the 9-1
safety of nuclear installations…………………………………………………………….

9.2

Supervision of the License Holders by Regulatory Body………………………………..

9-1

C. General Safety Considerations
Basic Policy for Priority to Safety……………………………………………….

10-1

10.1

Basic Policy for Priority to Safety……………………………………………………….

10-1

10.2

Efforts for Improvement in Safety Culture………………………………………………

10-1

Article 10iFinancial and Human Resources………………………………………………...

11-1

11.1

Financial Resources of the License Holder……………………………………………...

11-1

11.2

Human Resources of the License Holder………………………………………………...

11-1

11.3

Efforts for Ensuring Infrastructure of Human Resources in Japan………………………

11-2

Article 11

Human Factors……………………………………………………………………

12-1

12.1

Efforts by Regulatory Body……………………………………………………………...

12-1

12.2

Efforts by License Holders………………………………………………………………

12-2

Article 12

Quality Assurance………………………………………………………………...

13-1

13.1

Regulatory Requirements for QA of Nuclear Installation……………………………….

13-1

13.2

Confirmation of QA by Regulatory Body………………………………………………..

13-2

13.3

Implementation and Assessment of QA Program by License Holders…………………..

13-2

Article 13

Article 14

Assessment and Verification of Safety…………………………………………... 14-1

14.1

Assessment and Verification of Safety Prior to Construction……………………………

14-1

14.2

Assessment and Verification of Safety Prior to the Commissioning…………………….

14-3

14.3

Assessment and Verification of Safety during Operating Life Time…………………….

14-4

14.4

Probabilistic Approach in Regulation……………………………………………………

14-6

14.5

Introduction of Safety Goals……………………………………………………………..

14-7

14.6

Activities for Introduction of the Safety Regulation with Utilization of Risk
Information………………………………………………………………………………

14-9

Radiation Protection……………………………………………………………...

15-1

15.1

Summary of Laws and Requirements on Radiation Protection………………………….

15-1

15.2

Laws and Requirements and Response of License Holders..............................................

15-2

15.3

Regulatory Control Activities……………………………………………………………

15-6

Article 15

Emergency Preparedness………………………………………………………...

16-1

16.1

Development of Laws and Rules for Nuclear Emergency Preparedness………………..

16-1

16.2

Nuclear Emergency Preparedness and the Measures……………………………………

16-2

16.3

Implementation of Nuclear Emergency Drill……………………………………………

16-4

16.4

International Framework and Relationship with Neighboring Countries……………….

16-6

Article 16ii

D. Safety of Installations
Article 17

Siting………………………………………………………………………………. 17-1

17.1

Basic Concept on the Siting of Nuclear Facilities……………………………………….

17-1

17.2

Principal Assessment System Concerning the Siting of Commercial Power Reactors….

17-1

17.3

Evaluation to Events Caused by External Factor………………………………………...

17-2

17.4

Evaluation for the Impacts to the Public of Accidents…………………………………...

17-3

17.5

Environmental Impact Assessment………………………………………………………

17-4

17.6

Re-evaluation of Site Related Factors……………………………………………………

17-5

17.7

Arrangements with Neighboring Countries on Safety Impact of Nuclear Facilities…….

17-5

Design and Construction…………………………………………………………

18-1

18.1

Licensing Process at the Design and Construction Stages of Nuclear Facilities………...

18-1

18.2

Realization of Defense with Multiple Steps and Methods (Defense in Depth) and

Article 18

Confinement of Radioactive Materials at Design and Construction Stages……………..
18.3

18-1

Prevention of Accidents and their Mitigation Systems (Regulatory Guide for
Reviewing Classification of Importance of Safety Functions for Light Water Nuclear
Power Reactor Facilities)………………………………………………………………...

18-3

18.4

Preparation of Accident Management Policy……………………………………………

18-4

18.5

Measures to Ensure the Technical Reliability by Experience, Test and Analysis……….

18-5

18.6

Consideration of Human Factors and the Man-Machine Interface………………………

18-7

Operation………………………………………………………………………….

19-1

19.1

Initial License…………………………………………………………………………….

19-2

19.2

Limiting Conditions for Operation………………………………………………………

19-2

19.3

Regulations for Operation, Maintenance, Inspection and Testing……………………….

19-2

19.4

Response to Accidents and Anticipated Operational Occurrences………………………

19-4

19.5

Engineering and Technical Support: Application of the Results of Research andArticle 19

Development……………………………………………………………………………..

19-4

19.6

Reporting of Incidents……………………………………………………………………

19-5

19.7

Collection, Utilization and Sharing of Operating Experience Information……………...

19-6

19.8

Management of Spent Fuel and Radioactive Waste……………………………………...

19-6

Annexesiii

Acronym and Abbreviation Used in this Report
ABWR

advanced boiling water reactor

ACNRE

Advisory Committee for Natural Resources and Energy

AEC

Atomic Energy Commission

AESJ

Atomic Energy Society of JapanALARA

as low as reasonably achievable

AOT

Allowed Out of Service Times

ABWR

Advanced boiling water reactor

APWR

advanced pressurized water reactor

ASCOT

Assessment of Safety Culture in Organizations TeamBSS

Basic Safety Standards

BTC

BWR Operation Training Center

BWR

boiling water reactor

Dose Limit Notification

Notification for Dose Limits on the basis of the Rules forCommercial Power Reactors

EIS

Environmental Impact Statement

Regulatory Guide forRegulatory Guide for Reviewing Safety Design of Light Water

Safety Design

Nuclear Power Reactor Facilities

Regulatory Guide forRegulatory Guide for Reviewing Safety Assessment of Light

Reviewing Safety

Water Nuclear Power Reactor Facilities

Assessment
Regulatory Guide forRegulatory Guide for Reviewing Seismic Design of Nuclear

Reviewing Seismic

Power Reactor Facilities etc

DesignRegulatory Guide forRegulatory Guide for Reviewing Nuclear Reactor Siting

Reactor Siting

Evaluation and Application Criteria

Fugen

heavy water moderated boiling light water cooled reactor
owned by JNC

FY

Fiscal Year

IAEA

International Atomic Energy Agency

ICRP

International Commission on Radiological Protection

INES

International Nuclear Event Scale

INPO

Institute of Nuclear Power Operations

ISO

International Standards Organization

JAERI

Japan Atomic Energy Research Institute

JAPEICJapan Power Engineering and Inspection Corporationiv

JCO Criticality Accident

Criticality Accident at JCO Co. Uranium Fuel Fabrication
Facility

JEA

Japan Electric Association

JEAC(G)

Japan Electric Association Code (Guideline)

JNC

Japan Nuclear Cycle Development Institute

JPDR

Japan Power Demonstration Reactor

JSME

Japan Society of Mechanical Engineers

LCO

Limiting Conditions for Operation

METI

Ministry of Economy, Trade and Industry

Minister of METI

Minister of Economy, Trade and Industry

MEXT

Ministry of Education, Culture, Sports, Science andTechnology

Minister of MEXT

Minister of Education, Culture, Sports, Science andTechnology

MITI

Ministry of International Trade and Industry(METI at present)

Mj

Japan Meteorological Agency seismic intensity scale

MLIT

Ministry of land , Infrastructure and Transportation

Monju

prototype fast breeder reactor owned by JNC

MOX

Mix Oxide

NISA

Nuclear and Industrial Safety Agency

NPS

nuclear power station

NSC

Nuclear Safety Commission

NS Network

Nuclear Safety Network

NSRR

Nuclear Safety Research Reactor

NTC

Nuclear Power Training Center

NUPEC

Nuclear Power Engineering Corporation

NUSS

Nuclear Safety Standards, IAEA

OECD/NEA

Organization of Economic Co-operation andDevelopment/Nuclear Energy Agency

OSART

Operational Safety Assessment Review Team

PSA

probabilistic safety assessment

PSR

periodic safety review

PWR

pressurized water reactor

QA

quality assurance

Reactor Regulation Law

Law for the Regulation of Nuclear Source Material,
Nuclear Fuel Material and Reactorsv

R & D reactor

Power reactors at the stage of research and development

RHRS

Residual Heat Removal System

RPS

Reactor Protection System

SCL

Steam Condensation Line

SSC

Structures, Systems and Components

STS

Standard Technical Specifications

Special Law for Nuclear

Special Law of Emergency Preparedness for Nuclear

Emergency

DisasterTEPCOTokyo Electric Power Company

TNS

Thermal and Nuclear Power Engineering Society

UK

United Kingdom of Great Britain

USA

United States of America

V&V

verification and validation

WANO

World Association of Nuclear OperatorsviPreface
1.Preparation of the Report
This report was produced in compliance with the Article 5 of the Convention on Nuclear Safety.
This report was prepared by the Nuclear and Industrial Safety Agency (hereinafter referred to as“NISA”) in consultation with the Nuclear and Industrial Safety Subcommittee of the Advisory
Committee for Natural Resources and Energy for the Ministry of Economy, Trade and Industry, withthe support of an incorporated administrative agency Japan Nuclear Energy Safety Organization ,(hereinafter referred to as “JNES”), and the cooperation of Japan Nuclear Cycle Development Instituteand the Federation of Electric Power Companies of Japan. This report was reviewed also by otherrelevant governmental organizations. Views of the Nuclear Safety Commission (hereinafter referred toas “the NSC”) were reflected to this report.
The Summary Report of the Second Review Meeting pointed out some items for which it wasrecommended to provide further information in next review meeting.
In this report, we tried to respond to them and to questions and comments on our previous reportraised by other Contracting Parties during the second review meetings. Description of operating
experience, alteration of nuclear power installation and progress in research and development islimited to the three years since the Second Review Meeting. The special topics in this report, that are aseries of falsification by Tokyo Electric Power Co. (hereinafter referred to as the “TEPCO falsification
issue”) and the far-reaching renovation of the legislative and regulatory framework, are summarized in
sections 4. and 5. of this preface.
The report on each article of the Convention consists of a) the reference of the convention article
encircled in square brackets, b) following the brackets, shown in italic letters are the introduction of
the feature of each article report and major changes after the previous reporting, and c) also in themain text of each article, major changes after the previous reporting are shown in italic letters.
Under the legislative and regulatory framework of Japan, nuclear installations in the scope of thisConvention (land-based civil nuclear power plants) correspond to commercial power reactors andpower reactors at the stage of research and development, and the safety regulation are fundamentallythe same to these two types of nuclear installations. Detailed description in this report is oncommercial power reactors with plenty of experience with siting, design, construction and operation,etc.
2. Current Status of Nuclear Energy Utilization in Japan(1) General
Since the oil crises in 1970s, Japan has actively promoted nuclear power generation in order tointroduce alternative energy resources to petroleum, aiming for stable supply and price of electricity.
In recent years, nuclear power generation has played an important role in order to decrease CO2
discharge to the environment, in the process of its power generation. Nuclear power generation has
been promoted under the premise of safety and nuclear nonproliferation. This has resulted in 52
nuclear power installations that are currently in operation. In the fiscal year of 2002, nuclear power
supply reached about 31.2 percent of total generation of electricity.
The first Energy Master Plan was decided by the Cabinet and reported to the Diet in October 2003 inaccordance with the Basic Law on Energy Policy. The plan states that nuclear power generation should
be promoted as a basic power supply recognizing the excellent characteristics of nuclear power
generation in terms of stable supply of electricity and a measure against global warming, and that
Preface-1

necessary investment should be encouraged under the environment of electricity market liberalization.
In “The long-term energy supply and demand outlook” published in July 2001, the number of new
nuclear power plants to be commissioned by FY 2010 was reduced to 13 units, from 16 to 20 units,reflecting a loss of public confidence on to nuclear power caused by the criticality accident in 1999 at
a uranium fuel processing plant of JCO Co., Ltd (hereinafter referred to as the “JCO criticality
accident”) and other troubles in nuclear facilities.
In June 2002, NISA asked the Nuclear and Industrial Safety Subcommittee of the Advisory Committee
for Natural Resources and Energy to initiate a study on the future approach for an effective andefficient regulatory system on nuclear safety. Expedited by the revelation of the TEPCO falsification
issue in August 2002, NISA, in compliance with the NSC recommendation, amended the Reactor
Regulation Law and the Electricity Utilities Industry Law in December 2002, and renovated safety
regulatory systems and related organizations in October 2003.
The Kanazawa Branch of the Nagoya High Court delivered a judgment, on January 27, 2003, andnullified the license for the breeder reactor "Monju" on an administrative litigation lawsuit. The
government lost the lawsuit, and appealed to the Supreme Court on January 31. The regulatory body,on January 30, 2004, approved alteration of the design and construction method of Monju inaccordance with the Reactor Regulation Law and the Electricity Utilities Industry Law.
(2) Current Status of Nuclear Installations in Japan
As of September 2004, there are 55 units of nuclear installations in Japan; 52 units are in operation, 2units are under construction after achieving criticality and one unit ceased operation in March 2003 forthe preparation of decommissioning. Total licensed capacity of nuclear power generation is about 47.4
GWe.
In FY 2002, the total capacity of 45.7 GWe of nuclear power generation accounted for about 19.6
percent of the nation’s total capacity of electricity generation, and nuclear power generated 294.9
billion kWh of electricity that was about 31.2 percent of 944.7 billion kWh electricity generated inJapan.
While average annual capacity factors of nuclear power plants had exceeded 80 percent from FY 1995
to 2001, that of FY 2003 dropped to 59.7 percent. It was because all of 17 nuclear reactors of TEPCO
were shutdown in April 2003 due to the Periodic Inspections conducted earlier than scheduled and dueto the prolonged outage to cope with various additional checks that were resulted from the TEPCO
falsification issue revealed in August 2002. The reactors of the said company have been reviving
operation one by one after verification of safety. Other nuclear power plants continued stable operation
during this reporting period and the average frequency of unplanned shutdowns over FYs 2001 to
2003 was as small as 0.2 times per reactor-year.
3. International Activities for Ensuring Safety of Nuclear Installations
Recognizing that international cooperation is essential for ensuring safety of nuclear installations,Japan has actively been participating in various activities of IAEA and OECD/NEA for informationexchanges and for discussions on safety related issues.
A news during this reporting period is that Japan acceded to the Joint Convention on the Safety of
Spent Fuel Management and on the Safety of Radioactive Waste Management in August 2003 andparticipated in the first review meeting held in November 2003. Japan had opportunities to receive
peer-reviews of the contracting parties on the safety of radioactive waste management as well as on
the safety of nuclear installations.
Japan has made a positive commitment to a cooperation program for establishing regulatory bodies
Preface-2

and enhancing nuclear safety regulations in Asian countries and also with offering extra-budgetaryfunding to the IAEA.
Japan has been exchanging of regulatory information on nuclear safety with China, France, Korea,
Sweden, U.K. and U.S.A. through bilateral arrangements, and has shared its knowledge andexperiences with them. Japan makes efforts to enhance the safety of nuclear power plants in Japan andin the world.
Also electric power companies are contributing to maintain high level of safety and reliability of
nuclear installations in Asia, through cooperation in managing the WANO Tokyo Center.
Units 3 and 6 of the Kashiwazaki-Kariwa Nuclear Power Station of TEPCO invited the OSART of
IAEA in November 2004.
4. TEPCO Falsification Issue(1) Falsification of Self-Controlled Inspection Records by Tokyo Electric Power Co.
In July 2000, a former employee of an inspection company that contracted self-controlled inspection
with TEPCO made an allegation to the Ministry of International Trade and Industry (present METI)
that TEPCO falsified self-controlled inspection records. This was the first allegation under the
Allegation System established in June 2000 and was transferred to NISA in January 2001. Since thealleged falsification occurred about 10 years ago and since preservation of inspection records was not
sufficient, the investigation met great difficulty. In August 2002, it was made public by NISA thatfalsifications such as tampering with self-controlled inspection records and cover up of cracks in coreshrouds were committed at three nuclear power stations of TEPCO from the latter half of 1980’s to the1990’s. It took two years for NISA to make it public.
In September 2002, NISA conducted on-site inspections in all nuclear power stations of TEPCO andthe headquarters of TEPCO in order to investigate what were the facts. In October 2002, NISA
announced to the public that the alleged falsifications were identified, and that although cracks orindications of crack were found on the re-circulation system piping and core shrouds they do not pose
any immediate risk to the reactor safety.
NISA conducted special Nuclear Safety Inspections and Periodic Inspections strictly on their nuclear
installations, issued a letter of severe warning to TEPCO, and ordered the company to reconstruct its
quality assurance system and renovate organizational climate fostering true safety culture. NISA
requested TEPCO to report the progress of reconstruction/renovation activities by the end of FY 2002.
In response to this, TEPCO submitted to NISA in March 2003 their measures including involvementof the top management with quality assurance of the nuclear power division, clarification of
responsibilities and authorities in nuclear power quality assurance program, preparation of manuals,
etc. associated with quality assurance, establishment of audit division under the direct control of thepresident and reinforcement of judicial affairs department.
(2) Instruction to other license holders to make full review on their plants record
NISA instructed other license holders than TEPCO to make full review on their plants to confirm if
there were any falsifications in past self-controlled inspection records. Some license holders reported
that there had been cracks or indications of crack in re-circulation piping and core shrouds.
NISA confirmed that there were no falsifications in self-controlled inspection records and that theyevaluated that the cracks pose no immediate risk to plant safety. NISA judged that the license holders’evaluation on cracks was appropriate. NISA also requested these license holders to implement similar
measures implemented by TEPCO such as reconstruction of their quality assurance system, etc. Thoselicense holders submitted reports on their progress in reconstruction.
Preface-3

The NSC requested full reporting from NISA immediately after revelation of the above-mentioned
falsification case. In October 2002, the NSC published basic policies and action plans called “The
response to the falsifications in self-controlled inspection records of NPPs“ in order to prevent
recurrence.
Also, in October 2002, recognizing urgent needs to restore general public’s confidence in nuclear
safety, the NSC made a recommendation called “Recommendation on Restoration of Confidence in
Nuclear Safety” to the Minister of METI through the Prime Minister. This recommendation, which
was based on the provision of Article 24 of the Law for Establishment of Atomic Energy Commission
and Nuclear Safety Commission, was for first time since the establishment of the NSC in 1978. The
recommendation was reflected to the renovated nuclear safety regulations that were implemented after
the above falsifications issue in self-controlled inspection records.
The NSC concluded according to their independent investigation and analysis that the results of thesafety evaluation on cracks of re-circulation pipings and core shrouds, conducted by NISA, wereadequate.
(3) Falsifications in Reactor Containment Leakage Rate Test and the Administrative Measure
Taken
Apart from the case mentioned above, it was revealed in October 2002 that, at the periodic inspectionsin 1991 and 1992 of the Unit 1 of the Fukushima Daiichi Nuclear Power Station attended by inspectorsof regulatory body, the results of reactor containment leak rate tests were falsified by Tokyo ElectricPower Co. Inc., in order to show intentionally low leak rate. In that month, NISA considered that thisfalsification violated the law and NISA took an administrative measure of one year suspension ofoperation of the said unit. NISA requested to conduct inspections of leak rate test of all reactor
containments of TEPCO that resulted in shutdown of all 17 units of TEPCO in April 2003.
The NSC monitored independently NISA’s inspection of the reactor containment leak rate test at theUnit 1 of the Fukushima Daiichi Nuclear Power Station and concluded the leakage rate was within thelimit.
(4) Explanation to the Public and Restart of Power Plants
NISA held dozens of explanatory meetings for local governments and the public on the safetyassessment of nuclear power stations of TEPCO and on re-construction of regulatory system. The
reactors have been restarted one by one after completing pre-start safety checks and after restoring
local communities’ confidence in the safety of the nuclear power stations.
The NSC also confirmed the report which showed that the reactor containment leakage rate tests had
been properly conducted.
(5) Background of the TEPCO falsification issue
The TEPCO falsification issue has significantly eroded public confidence in nuclear safety. NISA
analyzed factors that led to these falsification issues as follows.
In this problem there were three kinds of factors; factors on the license holders’ side, on the regulatoryside and common to the both sides. Some of the problems on the license holders’ side were an
accustomed and complacent decision making process by limited persons, ineffective audit by top
management and divisions other than nuclear power division, and the lack of understanding on theimportance of quality assurance system to ensure nuclear safety. Some of the problems on theregulatory side were ambiguity of regulatory procedure on self-controlled inspection by license
holders, lack of formulated acceptance criteria of cracks, and insufficient penalty for organizational
Preface-4

illegal acts. One of the problems common to both sides was a lack of recognition of importance to theaccountability for safety itself as well as the process to achieve safety.

5. Renovation of the Regulatory System of Nuclear Safety
NISA had promoted the study on the future approach for the effective and efficient safety regulatory
system, including and not limited to inspection system, license holders’ activities for safety operation,
quality assurance. Expedited by the revelation of the falsification problem of Tokyo Electric Power
Co., NISA renovated his safety regulation, as described below, in order to prevent recurrence offalsifications and to maintain internationally acceptable safety regulation.

Enhancement
Enhancementof
ofTotal
TotalSafety
SafetyRegulation
RegulationSystem
SystemFrom October, 2003

Up to October, 2003

Nuclear Safety Commission with enhanced functions *from April, 2003

Nuclear Safety
Commission
Minister of
METI(request for quarterly report, enlarged scope of investigation authority)

Fitness-for-Safety
Inspection

Pre-service
Inspection

Minister of
METI

Clear criteria
for trouble reporting

Licensees

Clear scope ofConstruction approval-Safety significant items-Confirmation oflicensee’s inspection

Selfimposed
inspection

NISA

NlSA

-Safety significant items-Confirmation oflicensee’s inspection

Periodic
Inspection

Fitness-for-safety
inspection(QA and maintenancemanagement)

Strict pre-service
inspection*
Except for NISA's
inspection scope

Periodical inspection

Licensees
QA system
ISO9000 series
Clear Definition in
Safety Prev.Rules

Maintenancemanagement
Periodical Licensee’s
Inspection
as a responsibility

Except for NISA's
inspection scope

Revelation of falsified
self-imposed inspection results<Causes>

Evaluation of
inspection results

1. Habitual self-righteousness of a limited
number of site staff
2. Inadequate quality assurance system
3. Negligence of re-assessment andpreservation of inspection records

Establishment of Japan Nuclear
Energy Safety Organization

Licensee side:

Regulator side:
1. Unclear positioning of licensee’s
self-imposed inspection
2. Unclear definition of integrity checkmethods for operating power plants

Obligation
to conduct
integrity
evaluation(with JSME
rule)
Obligation
for records
keeping andreporting

Review of licensee’s inspection
system (Periodical Safety
Management Inspection)[Establishment of information collection/provision system(including minor events)][Active information disclosure by licensees and regulators]* Especially important inspections for direct confirmation of ‘safe ‘shutdown’, ’core
cooling’ and ‘confinement’ functions and ‘total plant performance’(1) Renovation of Quality Assurance System and Maintenance Management System
As the license holders’ quality assurance system was found to be inadequate, the Reactor Regulation
Law was amended to stipulate that quality assurance should be established and should be included in
the Operational Safety Program, and that the compliance with the Program should be confirmed at the
Nuclear Safety Inspection.
The Reactor Regulation Law stipulates the following requirements on quality assurance:
1) Establish a quality assurance program, implement quality assurance in accordance with theprogram, and continually improve the program,2) Define in the quality assurance program, an organization of quality assurance and a PDCA
(Plan-Do-Check-Action) cycle of each item of the activities on safe operation,3) Clarify responsibilities and authorities within the organization, and top management shallbe involved in quality assurance activities, and
4) Clarify relations between each item of the activities on safe operation and the process of
JIS-Q9000 (2000).
Preface-5

The Reactor Regulation Law stipulates that maintenance management should be established andshould be included in the Operational Safety Program and that the compliance with the Program
should be confirmed at the Nuclear Safety Inspection.
The Reactor Regulation Law stipulates following requirements on maintenance management:
1) Establish maintenance management policies and targets,
2) Develop an implementation program and implement maintenance management in accordancewith the program,3) Define, in the implementation program, frequency, time, methods to confirm and to evaluate
the results, the corrective measures, if any, and matters concerning records, and
4) Periodically review and revise policies, targets and the implementation program ofmaintenance management.
NISA has confirmed that the “Rules of Quality Assurance for Safety of Nuclear Power Plants (JEAC
4111-2003)” and the “Rules of Maintenance Management of Nuclear Power Plants (JEAC
4209-2003)”, developed by Japan Electric Association, meet the quality assurance requirements andthe maintenance management requirements defined in the Reactor Regulation Law, respectively.
(2) Introduction of the Licensee’s Periodic Inspection
Before the amendment of the Electricity Utilities Industry Law, the regulatory body requested
inspection only for the equipment especially important to safety, leaving the other equipment toself-controlled inspection by the license holders.
The amended Electricity Utilities Industry Law stipulates that a license holder shall perform the
Licensee’s Periodic Inspection, which replaces the former self-controlled inspection, to theequipment designated by technical standards, at the intervals not exceeding 13 months, shall confirm
the inspection results to comply with the technical standards, and shall record the results.
(3) Introduction of the Fitness-for-Service Assessment
Non-destructive examination on cracks by ultrasonic test is made mandatory, and is included in the
Licensee’s Periodic Inspection. The Fitness-for-Service Assessment requires an estimation of growthof crack, if found, and structural integrity assessment of the component. The Technical Standards
specifies the basic requirements for the Fitness-for-Service Assessment, leaving details of assessment
methods and criteria to Rules of Fitness-for-Service for Nuclear Power Plants (2000 and 2002
editions) developed by a corporate judicial person, the Japan Society of Mechanical Engineers.
It is also stipulated that the results of the Fitness-for-Service Assessment should be recorded and kept
by license holders and that license holders report the results to the regulatory body.
(4) Introduction of the Periodic Safety Management Review
The license holders shall undergo the Periodic Safety Management Review by JNES, either on
documents review or on-site review, that includes review on organization for implementing the
Licensee’s Periodic Inspection, method of inspection, schedule control, management of contractors, ifany, management of inspection records, and education and training on inspection.
To conduct an at-site review more effectively and efficiently, items to be reviewed are randomly
chosen without prior notice to the license holder.
JNES reports the review results to NISA. NISA evaluates the review results and informs theevaluation results to the license holder. The numbers of inspection items for the next Licensee’s
Periodic Inspection is decided depending on the performance of previous review results.
Preface-6

Introduction
IntroductionofofPeriodic
PeriodicLicensee’s
Licensee’sInspection
Inspectionand
andFitness-for-Service
Fitness-for-ServiceAssessment
Assessment
IntroductionofLicensee’s
Periodic
Inspection
Introduction of Licensee’s Periodic InspectionSystem
Systemz Facilities and components formerly subjected to self-imposed inspection are legally positioned
as periodic licensee's inspection, with clear scope of inspection.
z JNES reviews the implementation system for the inspection as part of periodic safety
management review, and the authority evaluates the review results• Clear legal definition of the scope of periodic licensee's inspections.
• Academic and association’s standards are used for subject components and methods of inspection.
BeforeBefore Modification
Modification
Obligation to conformto technical standards

After
After Modification
Modification
Obligation to conformto technical standards

Periodic safety management review
Review of organization and methods for
implementation of periodic licensee’s inspection

Establishment of
implementation
system• Organization• Inspection methods,
etc.

Licensees

Licensees

Self-imposed inspection
by licensees(conducted at licensees'
discretion)

Periodic licensee’s
inspection
The Inspection is obliged
to conduct periodicallyby licensees

Periodic
Inspection

Periodic
Inspection

Obligation to record and keep
inspection results

The
The authority
authority inspects
inspects
components
components especially
especially
importantimportant toto assuring
assuring
publicpublic safety.
safety.

Obligation to conduct fitnessfor-service assessment, and toreport the results

The authority inspects
components especially
important to assuring
public safety.

Nuclear and Industrial
Safety Agency

Incorporated
administrative agency
Japan Nuclear Energy
Safety Organization(JNES)

Evaluation of periodic
safety management review
Evaluation based on review results,
and notification of assessment
results

Nuclear and Industrial Safety Agency(5) Clarification of Reporting Criteria for Accidents and Failures
Reporting criteria of accidents and failures are clarified by the amending the Reactor Regulation Law.
The reporting criteria for minor events, which had been reported only according to an administrative
notification, are now included in the law.
(6) Establishment of a System to Collect and Disseminate Information Including Minor Events
For thorough transparency, appropriate information disclosure of accidents and failures including
minor events is very important. For the purpose, it is important to share information of minor trouble
and usual operational events among license holders, manufacturers, universities, institutes andregulatory body and to analyze the information for the improvement of safety management activities
and safety regulations.
License holders established a public information library “NUCIA” (http://www.nucia.jp) on internet todisseminate collected information on nuclear power station including information of accidents andfailures.
(7) Clarification of the Periodic Safety Review (PSR)
Provisions on the PSR, which had been conducted every 10 years, are clarified by the amendment of
the Reactor Regulation Law. The Periodic Safety Review is integrated into the Operational Safety
Program, and the inspectors of NISA confirm that the PSR is conducted on compliance with the
Operational Safety Program. Items of the PSR are as follows:

Preface-7

Items1) Comprehensive evaluationof operational experience

Before amendment

After amendment

Self-controlled review

Item in the Operational
Safety Program

2) Reflection of the latest
technical knowledge

Self-controlled review

Item in the Operational
Program3) Probabilistic safetyassessment

Self-controlled review

Self-controlled review

The implementation of probabilistic safety assessment (PSA) is asked by NISA, although it remains tobe self-controlled review by license holder.
(8) Clarification of the Aging Management Review
License holders shall take following measures for aging management of a plant from the period notlater than thirty years after the commissioning. Measures for aging management are integrated into the
Operational Safety Program. Measures for aging management include: a) to perform technical review
on aging for the safety related structures, systems and components to evaluate the effectiveness of thecurrent maintenance activities on those structures, systems and components to prevent loss of safetyfunctions; b) to establish a Ten-Year Maintenance Program based on above-mentioned technicalreview on aging; and c) to re-evaluate technical review on aging and the Ten-Year Maintenance
Program at least once in ten years.
(9) Improvement of the Regulatory System on Nuclear Safety
In order to strengthen the supervision and audit functional competence of the NSC, which is
independent organization from the regulatory bodies, such as NISA, MEXT, and the MLIT, regulatory
bodies shall submit quarterly reports to the NSC on their regulatory activities after issuingestablishment license, that are various regulatory activities in construction and operational stages.
The NSC may collect information on regulatory activities from the licence holder and contractor inorder to conduct its audit function.
For these improvements, number of staffs was increased in the NSC.
Concerning the renovation of nuclear safety regulation, the NSC advised NISA on Quality Assurance
System and Licensee’s Periodic Inspection System with regards to its basic requirements and items to
be considered during the system operation.

Preface-8

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

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

Nuclear
Nuclear safety
safety regulation
regulation bybyregulatory
regulatory body
body
Construction
Construction StageStage•• Approval
Approval ofof designdesign andandconstruction
construction methods
methods•• Pre-service
inspection
Pre-service inspection•• Approval
Approval ofof fitness-for-safety
fitness-for-safety
programprogramOperation
Operation StageStage•• Facility
Facility periodic
periodic inspection
inspection•• Inspection
Inspection ofof observanceobservance status
status ofoffitness-for-safety
fitness-for-safety program,
program, etc.
etc.
OthersOthers•• On
On thethe spot
spot entry
entry andand inspection
inspection•• Report
Report ofof accidents
accidents andand failures,
failures,
etc.
etc.

Asking Consultation

Secondary
Secondary review
review
Mandatory Advice
Report of theimplementing
situation, etc.
concerning
nuclear safety
regulation
ReportObservation and
Audit

Objectives:
Promotion ofcontinuous
improvement andenhancement throughobservation and auditof nuclear safety
regulatory activities of
the regulatory body

Emergency
Emergency preparedness
preparedness
Technical
Technical capability
capability

Regulatory
Regulatory investigation
investigation•• Common
Common subjects
subjects andand important
importantsubjects
subjects forfor ensuring
ensuring thethe safety
safety(Examples)(Examples) Licensee's
Licensee's periodic
periodic
inspection,
inspection, Quality
Quality assurance
assurance activities,
activities,
etc.
etc.

•• Important
Important pointed-out
pointed-out subjects
subjects
at
at thethe individual
individual administrative
administrative
disposition
disposition oror atat thethe secondary
secondaryreview
review• Licensee's obligation to cooperate
for the investigation(10) Establishment of Japan Nuclear Energy Safety Organization
A law for establishing an incorporated administrative agency “Japan Nuclear Energy Safety
Organization (JNES)” was enacted in the extraordinary diet session of the autumn of 2002. JNES wasinaugurated integrating of a part of former Nuclear Power Engineering Corporation, and former Japan
Power Engineering and Inspection Corporation. JNES was established in order to enhance regulatory
safety inspection together with NISA.
JNES with about 420 personnel, together with NISA with 300 personnel including 100 site resident
inspectors, and five commissioners of the NSC and its secretariat with 100 personnel constitutes theregulatory system on nuclear safety, and it is making efforts ceaselessly to improve the competency ofstaffs.
(11) Development of Experts Engaged in the Nuclear Safety
NISA prepares training programs for personnel engaged in regulatory activities on nuclear safety.
NISA provides, depending on type of jobs and experiences of personnel, a fundamental course and an
advanced course for specialized knowledge and skills and highly specialized course for latest
technology and expertise. With particular emphasis on quality management of nuclear facilities, “jobtraining program on quality assurance for nuclear facilities” started in the FY 2002.
(12) Enhancement of Public Relations Activities
NISA recognizes it is an important task to play a role of the “representative of the public” in nuclear
safety administration, to ensure safety of the public and to give reassurance on nuclear safety to the
public, especially to the local residents in the vicinity of nuclear facilities. For this purpose, NISA
considers it is necessary to actively disclose information, intensify public dialogue, and to enhance
understanding of the public and the local residents.

Preface-9

For example, NISA held a number of dialogue meetings with local residents on the TEPCO
falsification issue, collected their opinions, answered to their questions and explained measures toprevent recurrence, in order to restore their confidence.
In April 2004, taking new budgetary steps to enhance the public relations activities further, NISA
established the Nuclear Safety Public Relations and Training Division as a responsible division, anddecided to station the Regional Public Relations Officers at major sites.
(13) Intensified Penalties to Prevent Recurrence
In order to deter organizational illegal acts, penalties were intensified so that a corporate penalty
becomes as heavy as 100 times that of personnel and imprisonment against serious violation such as
noncompliance with orders to conform to technical standards, evasion of the regulatory inspection, or
noncompliance with orders for license holders to submit reports including reports of contractors formaintenance.
(14) Improvement of Implementation of Allegation System
NISA established “the Committee on Investigation of Alleged Case”, and improved procedures ofinvestigation, so that alleger’s interest should be strictly protected and so that investigation of thealleged case should be conducted and disclosed in due process. The NSC was also designated as the
responsible organization to receive and to investigate allegation, based on the Reactor Regulation Law.

Preface-10

A. General Provisions

Article 6

Existing Nuclear Installations

Each Contracting Party shall take the appropriate steps to ensure that the safety of nuclear
installations existing at the time the Convention enters into force for that Contracting Party isreviewed as soon as possible. When necessary in the context of this Convention, the Contracting
Party shall ensure that all reasonably practicable improvements are made as a matter ofurgency to upgrade the safety of the nuclear installation. If such upgrading cannot be achieved,plans should be implemented to shut down the nuclear installation as soon as practicallypossible. The timing of the shut-down may take into account the whole energy context andpossible alternatives as well as the social, environmental and economic impact.
There are a total of 55 nuclear installations in Japan in the scope of the Convention as of the end of August 2004,
including 52 reactors in operation, two in the commissioning stage that attained criticality, and one thatterminated operation in March 2003 and is in preparation for decommissioning.
After the previous report, the Unit 5 of the Hamaoka Nuclear Power Station, Chubu Electric Power Co., Inc.
attained criticality and enters the scope of the Convention. Tokai Power Station of the Japan Atomic Power Co.,
which was in preparation of decommissioning, entered decommissioning stage and became out of the scope of
the Convention.
Since the descriptions of how the safety of existing nuclear installations has been ensured are given in thereports for other articles, the repetition is avoided. Instead, major events after the previous report for existing
nuclear installations are described here according to the types of installations, which are BWR, PWR and powerreactors in research and development stage.

6.1 Existing Nuclear Installations in the Scope of this Convention
There are a total of 55 nuclear installations in Japan in the scope of the Convention at the end of
August 2004. The breakdown is shown in the followings:
Breakdown of Nuclear Installations in the scope of the Convention
Type
Commercial
power reactor

Boiling water
reactor (BWR)

Pressurizedwater reactor(PWR)
Power reactor in research anddevelopment stage

Number of
Remarks
Units
in operation
29
under construction*
1 Unit 5 of the
Hamaoka Nuclear
Power Station,in operation
23
Statusunder construction*in preparation fordecommissioning

1
1

Monju
Fugen

* Unit under construction that attained criticality

The existing nuclear installations are listed in Annex 1, and their locations are shown in Fig. 6-1.

6-1

6.2 Major Events in the Existing Nuclear Installations after the Previous Report
Major events in the existing nuclear installations after the previous report are shown in the followings:(1) BWR Plants
1) Falsification of Self-Controlled Inspection Records by Tokyo Electric Power Co., Inc.
In August 2002, it was revealed that Tokyo Electric Power Co., Inc. had covered up the record
for the existence of cracks on core shrouds of reactors and falsified the self-controlled
inspection records. For the fact finding, NISA conducted On-the-Spot Inspection of all the
nuclear power stations and the head office of Tokyo Electric Power Co., Inc. After theinvestigation, NISA announced that the fact of falsification was identified, and that althoughcracks or indications of crack, were found on the re-circulation system piping and shrouds,
they did not pose any immediate risk to the reactor safety. A letter of severe warning was issued
to Tokyo Electric Power Co., Inc. NISA conducted special Nuclear Safety Inspection and strict
Periodic Inspection on those nuclear installations.
2) Instruction to Other 15 Licence holders to Make Comprehensive Checking
NISA also instructed other 15 licence holders, including PWR and fuel cycle facility licenceholders, to make comprehensive checking on their plants to confirm whether there had been no
falsification in the self-controlled inspection records. Some licence holders reported that cracks
were found on shroud of their plants, and that they evaluated that the cracks pose no
immediate risk to plant safety. NISA confirmed that there had been no falsification on the
self-controlled inspection records, and that the licence holders’ evaluation on cracks wasappropriate.
3) Falsification on Inspection of Reactor Containment Leak Rate and the Administrative Measure
Taken
It was revealed in October 2002 that, during the Periodic Inspections of the Unit 1 of the
Fukushima Daiichi Nuclear Power Station in 1991 and 1992 attended by inspectors of
regulatory body, the reactor containment leak rate tests were falsified by Tokyo Electric PowerCo. Inc., to show intentionally low leak rate. In that month, NISA considered this falsification
violated the law and took an administrative measure of one year suspension of operation of theUnit1, and conducted inspections of leak rate of all reactor containments of the company.
4) Prevention of Hydrogen Accumulation in Piping
On November 7, 2001, a part of residual heat removal system piping of the Unit 1 (BWR) of the
Hamaoka Nuclear Power Station, Chubu Electric Power Co., Inc., ruptured by rapid
combustion of the non-condensable gas (i.e., hydrogen) accumulated in the piping.
NISA instructed BWR licence holders to alter steam condensation system piping of the residual
heat removal system by removing a part of piping or installing a shutoff valve in it to prevent
accumulation of hydrogen, and to alter, for example, the inclination of other piping systems
where hydrogen may accumulate.

6-2

(2) PWR Plants
1) Enhancement of Periodic Inspection Relating to Prevention of Recurrence of Primary Coolant
Leak
It was reported in our previous report that NISA instructed licence holders to intensify Periodic
Inspection to prevent recurrence of the primary coolant leak from the regenerative heatexchanger connecting piping which occurred at the Unit 2 (PWR) of the Tsuruga Power Station,
the Japan Atomic Power Co. Since then, licence holders have added ultrasonic inspection, etc.
to the inspection items for class 3 piping (located inside at the reactor containment).
Furthermore, considering damage on the regenerative heat exchanger shell-side exit piping of
the Unit 2 of the Tomari Power Station, Hokkaido Electric Power Co., Inc., NISA instructed
licence holders, in December 2003, to expand their inspection scope over the systems andequipment belonging Class 1 and 2 defined by the Regulatory Guide for Reviewing
Classification of Importance of Safety Functions for Light Water Nuclear Power Reactor.
Licence holders are conducting the inspection in the Licensee’s Periodic Inspection.
2) Improvement of Quality Assurance Activities for Inspection of Imported Fuels
It was reported in our previous report that the regulatory measures were taken against thefalsification of inspection data of mixed oxide fuels (hereinafter called “MOX fuels”) for the
Unit 3 of the Takahama Power Station, the Kansai Electric Power Co., Inc. In October 2003,
the Reactor Regulation Law was revised so that the licence holders’ quality assurance
activities were included in the scope of regulatory inspection. On the basis of new legislation,
the Kansai Electric Power Co., Inc. reported to NISA of the improvement in the quality
assurance program for procurement of MOX fuels from overseas. NISA confirmed that the
program was appropriate, and reported it to the NSC in February 2004.
3) Inspection Concerning Ni-base Alloy Portions in Primary Coolant Boundary
In December 2003, NISA instructed licence holders to implement, bare metal inspections andultrasonic inspections for Ni-base Alloy 600 portion in primary coolant boundary, during thenearest Licensee’s Periodic Inspections, as measures against primary water stress corrosion
cracking, that occurred weld joints of nozzle stubs at pressurizer bypass lines in the Unit 2 of
the Tsuruga Power Station, the Japan Atomic Power Co., in September 2003, and at nozzle
stubs at reactor vessel heads in the Davis-Besse Nuclear Power Station in March 2002.
Moreover, NISA requested licence holders to provide inspection programs including volumetricexaminations of nozzle stubs at reactor vessel heads and bottoms.
4) Secondary Pipe Rupture Accident at Unit 3, Mihama Power Station
On August 9, 2004 at the Mihama Power Station Unit 3 (PWR, 826MWe) of the Kansai ElectricPower Co., Inc.(KEPCO), the main condensate water pipe ruptured and high temperaturesecondary water blew out into the turbine building when the reactor was in full power
operation. In the turbine building, there were many workers preparing for the Periodic
Inspection which was to commence on August 14. Workers who were close to the break wereseriously exposed to the flashed water that killed four and injured seven by scald.
NISA immediately took its action as establishing the Accident Investigation Committee aiming
at identifying the cause and preventing recurrence of the accident. The NSC also established areview subcommittee aiming at reflecting lessons learned from the accident to the futurenuclear safety policy.
The location the rupture took place was in the just downstream of the flow measurement orifice.
6-3

According to KEPCO, they had their own guideline that obliges itself to conduct residual life
evaluation and the planning of the inspection to the portions where the thinning is expected.
KEPCO also reported that the inspection was not implemented to the portion since thebeginning of its operation. The ruptured portion was planned to be inspected in the Periodic
Inspection starting from August 14, 2004.
Since this event was considered to be generic not only to PWRs but to BWRs and thermal
power plants, on August 11,2004, NISA issued instructions to operators of all nuclear power
plants and thermal power plants with more than 1,000kW outputs;− to check whether obliged inspections were implemented to all the pipes inquestion, and− to take adequate corrective actions if such un-inspected portions are identified.
(Note)The descriptions above are based on the information obtained as of August 13, 2004.
(3) Power Reactors in Research and Development StageThe Kanazawa Branch of the Nagoya High Court delivered a judgment, on January 27, 2003, andnullified the license for the breeder reactor "Monju" on an administrative litigation lawsuit. The
government lost the lawsuit, and appealed to the Supreme Court on January 31.
METI, considering the opinion of the NSC, approved in January 2004, the change of design andconstruction method in accordance with the Reactor Regulation Law and the change of construction
plan in accordance with the Electricity Utilities Industry Law.

6.3 Evaluation and Verification of Safety, and Position as to Continued Operation
NISA had implemented the necessary safety assessment and verification for existing nuclear
installations at planning, licensing, construction and operation stages. They are explained in the reports
concerning Article 7 to Article 19.
Through those assessments and verification, principles of this convention have been applied to ensure
the safety of existing nuclear installations for every stage from licensing to operation.
As shown in 6.2, the measures to ensure the safety has been appropriately applied to these eventsoccurred during the period after the previous reporting. On the basis of the results of this report, The
Japanese government concluded that continued operation of the nuclear installations in Japan isappropriate. The plants that are in construction stage and attained criticality are expected to beapproved for commercial operation after pre-service inspection.

6-4

Fig. 6-1 Location of Nuclear Installations(as of the end of August 2004)
Hokkaido Electric Power Co., Inc.
Tomari Power Station
Unit. 1 & 2 <PWR> (operating)
Unit. 3 <PWR> (under construction (sub-critical))Tokyo Electric Power Co., Inc.
Kashiwazaki Kariwa Nuclear Power Station
Unit. 1, 2, 3, 4 & 5 <BWR> (operating)
Unit. 6 & 7 <ABWR> (operating)Hokuriku Electric Power Co., Inc.
Shika Nuclear Power Station
Unit. 1 <BWR> (operating)
Unit. 2 <ABWR> (under construction (sub-critical))

The Japan Atomic Power Co.
Tsuruga Power Station
Unit. 1 <BWR> (operating)
Unit. 2 <PWR> (operating)
Unit. 3 & 4 <APWR> (in preparation of construction)

6-5

Japan Nuclear Cycle Development InstituteMonju <FBR>(under construction (attained criticality))

Japan Nuclear Cycle Development InstituteFugen <ATR>(in preparation of decommissioning)
The Kansai Electric Power Co., Inc.
Mihama Power Station
Unit. 1, 2 & 3 <PWR> (operating)

The Kansai Electric Power Co., Inc.
Ohi Power Station
Unit. 1, 2, 3 & 4 <PWR> (operating)

The Kansai Electric Power Co., Inc.
Takahama Power Station
Unit. 1, 2, 3 & 4 <PWR> (operating)

Chugoku Electric Power Co., Inc.
Shimane Nuclear Power Station
Unit. 1 & 2 <BWR> (operating) andUnit. 3 <ABWR> (in preparation of construction)

Tohoku Electric Power Co., Inc.
Higashidoori Nuclear Power Station,
Unit. 1 <BWR> (under construction (non-critical))Tohoku Electric Power Co., Inc.Onagawa Nuclear Power Station,
Unit. 1, 2 & 3 <BWR> (operating)Tokyo Electric Power Co., Inc.
Fukushima Daiichi Nuclear Power Station,
Unit. 1, 2, 3, 4, 5 & 6 <BWR> (operating)Tokyo Electric Power Co., Inc.
Fukushima Daini Nuclear Power Station,
Unit. 1, 2, 3 & 4 <BWR> (operating)
The Japan Atomic Power Co.
Tokai Power Station <GCR> (under decommissioning)
Tokai Daini Power Station <BWR> (operating)

Chugoku Electric Power Co., Inc.
Kaminoseki Nuclear Power Station
Unit.1 & 2 <ABWR>(in preparation of construction)

Chubu Electric Power Co., Inc.
Hamaoka Nuclear Power Station
Unit. 1, 2, 3 & 4 <BWR> (operating) andUnit. 5 <ABWR> (under construction (attained criticality))

Kyushu Electric Power Co., Inc.
Genkai Nuclear Power Station
Unit. 1, 2, 3 & 4 <PWR> (operating)
Kyushu Electric Power Co., Inc.
Sendai Nuclear Power Station
Unit. 1 & 2 <PWR> (operating)Electric Power Development Co., Ltd.
Oma Power Station,
Unit. 1 <ABWR> (in preparation of construction)

Shikoku Electric Power Co., Inc.
Ikata Power Station
Unit. 1, 2 & 3 <PWR> (operating)B. Legislation and Regulation

Article 7

Legislative and Regulatory Framework

1. Each Contracting Party shall establish and maintain a legislative and regulatory framework
to govern the safety of nuclear installations.
2. The legislative and regulatory framework shall provide for:(i) the establishment of applicable national safety requirements and regulations;(ii) a system of licensing with regard to nuclear installations and the prohibition of theoperation of a nuclear installation without a licence;(iii) a system of regulatory inspection and assessment of nuclear installations to ascertain
compliance with applicable regulations and the terms of licenses;(iv) the enforcement of applicable regulations and of the terms of licences, including
suspension, modification or revocation.
The Atomic Energy Basic Law has been established as the basic law governing the utilization of nuclear energy,
and the Law on the Regulations of Nuclear Source Material, Nuclear Fuel Material and Reactors (Reactor
Regulation Law) and the Electricity Utilities Industry Law have been established as the laws to govern the safetyof nuclear installations.
After the previous report, the Reactor Regulation Law has been revised to accommodate new regulatory
framework, such as adoption of performance-oriented technical standards into regulatory system, clarificationof reporting criteria for accidents/failures and clarification of modification or repair work that necessitate
application of the construction permit, establishment of Licensee’s Periodic Inspection and Periodic Safety
Management Review System, provision of regulatory inspection etc. by JNES, and provision of the Periodic
Assessment of Nuclear Facilities including Periodic Safety Review and Aging Management Program. The
Allegation System was revised so that an alleger can allege violation of safety regulation to the NSC as well as
to the regulatory body. Also, penalties to license holders have been intensified.

7.1 Basic Legislation Governing the Utilization of Nuclear Energy
Japan has enacted the Atomic Energy Basic Law as its basic law on the utilization of nuclear energy.
The objectives of the Atomic Energy Basic Law are quoted as "to secure future energy resources,
achieve progress in science and technology, and promote industry, by encouraging research,development, and the utilization of nuclear energy, and thereby contribute to improvement of thewelfare of human society and the national living standard." The basic policy is prescribed as follows:"The research, development and utilization of nuclear energy shall be limited to peaceful purposes, on
the basis of the highest priority of ensuring safety, and performed on a self-controlled basis underdemocratic administration, and the results obtained shall be made public and actively contribute tointernational cooperation."
In order to achieve these objectives and the basic policy, the law provides for the establishment of a setof laws to govern following areas:− Establishment of the Atomic Energy Commission and the Nuclear Safety Commission, andtheir duties, organization, administration, and authorities.
− Regulations governing nuclear fuel materials.
− Regulations for the construction, etc. of nuclear reactors.
− Prevention of radiation hazards.
The law also provides that those who will utilize nuclear energy shall manage their facilities under thesupervision of the regulatory body in accordance with these laws.

7-1

7.2 Legislations and Regulations Governing the Safety of Nuclear Installations
The major laws related to the safety regulation of nuclear installations have been established as shownin the following (1) through (5). The matters on the organization for the safety regulation of nuclear
installations are provided in the Law for Establishment of the Atomic Energy Commission and the
Nuclear Safety Commission, the Law for Establishment of the Ministry of Economy, Trade andIndustry, etc.
The NSC reviews the quality of nuclear safety administration by observing and auditing not only
regulatory activities but also regulatory system of NISA pursuant to Article 25 of Law for
Establishment of the Atomic Energy Commission and the Nuclear Safety Commission.
The major laws governing safety regulation of nuclear installations are shown in Figure 7-1.
(1) The Reactor Regulation Law and the Electricity Utilities Industry Law
The Reactor Regulation Law and the Electricity Utilities Industry Law are applied to the safety
regulations of commercial power reactors.
1) The Reactor Regulation Law
The Reactor Regulation Law, in order “to ensure that the utilization of nuclear source material,
nuclear fuel material, and reactors are limited to peaceful purposes, and carried out in a planned
manner, and to ensure safety of the public by preventing the hazards due to these utilization andproviding physical protection of nuclear fuel material, in accordance with the spirit of the Atomic
Energy Basic Law”, provides for:− Refining of nuclear source material and nuclear fuel material− Fabrication and enrichment of nuclear fuel− Establishment and operation etc. of reactors.
− Storage or reprocessing of spent nuclear fuel− Management and disposal of radioactive wastes− Use of nuclear source material and nuclear fuel material− Use of internationally regulated substances, etc.
And the following are established for reactor facilities.
− Regulations for the basic design and policy nuclear facility for construction application− Regulations for the detailed design and construction for construction permit− Inspections at the time of facility construction including approval of welding method,
welding inspection, pre-service inspection− Regulations for safe maintenance and operation (approval of Operational Safety Program,and Nuclear Safety Inspection)− Periodic Inspections of facility during operation− Measures for securing safety and physical protection− Regulations on facility transfer, and succession or merger of license holder− Dismantling of facility.
The allegation system, established by the Reactor Regulation Law, was revised so that personnel
can allege violation of safety regulation to the NSC as well as to NISA, without unfavorable
treatment. The rule under the law provides that the personal data of alleger be protected. The rulealso provides for adequate procedures for investigation and disclosure of alleged case.
The Minister of METI is required to report quarterly the status of regulatory activity to the NSC.
When the NSC independently reviews the regulatory activities based on the quarterly report, thelicense holder and the contractor who engaged in the maintenance of nuclear installation, are
7-2

required to cooperate with the NSC.
2) Electricity Utilities Industry Law
The Electricity Utilities Industry Law is established to protect the interests of users of electricity
and to promote sound development of electric utilities industry by appropriate and reasonableadministration of electric utilities industry, and to ensure the safety of public and to prevent
pollution by regulating construction, maintenance and operation of power generating equipments(herein after referred to as “electric structures”), and it provides followings for the purpose:− Electric utilities operation− Electric structures− Use of land etc.
− Registered safety management review agency, designated test agency, and registered survey
agencyThe provisions on Construction Plan, Welding Safety Management Review, Fuel Assembly
Inspection, Pre-Service Inspection, Periodic Inspection, and Periodic Safety Management Reviewof the Electric Utilities Industry Law are applied to commercial power reactors, and thecorresponding provisions of the Reactor Regulation Law are exempted from application.
Some of the technical standards under the Electricity Industry Law, which has been applied todetailed design, are specification code. In order to facilitate quick response to technologicalinnovation and coordination with international standards and to encourage license holders’
activities to promote safety, NISA is replacing specification code with performance code which
are supplemented by academic society and association standards established through due andtransparent process.
In the process of establishing performance code, harmonization of domestic standards withinternational standards are promoted. Namely, the confirmation of harmonization with IAEA
nuclear safety standard NS-R-1is incorporated in the review process.
In addition to technical standards mentioned above, license holders adopt other academic society
and association standards. The system of the technical standards based on the Electricity Utilities
Industry Law is shown in Figure 7-2 and other related standards are shown in Table 7-2.
The Minister of METI is required to report quarterly the status of regulatory activity to the NSC.
When the NSC independently reviews the regulatory activities based on the quarterly report of NISA,
the license holder and the contractor who engaged in the maintenance of nuclear installation are
required to cooperate with the NSC.
(2) The Basic Law for Emergency Preparedness and the Special Law for Nuclear Emergency
The nuclear emergency had been addressed within the legal framework of the Basic Law for
Emergency Preparedness. Taking account of the special characteristics of a nuclear emergency, theSpecial Law for Nuclear Emergency was established in December 1999. The Law stipulates special
measures for nuclear emergency, including license holders’ obligation for preventing nuclear
emergency, the Declaration of Nuclear Emergency, and establishment of the Nuclear Emergency
Headquarters, as well as activation of emergency measures in nuclear emergency. It also stipulates thata Senior Specialists for Nuclear Emergency be stationed in the vicinities of nuclear installations, who
guides and advises license holders in preparing preventive measures for nuclear emergency, andconducts other activities necessary to prevent the occurrence and progression of a nuclear emergency.
The chapter of nuclear emergency in the Basic Plan for Emergency Preparedness based on the Basic
Law for Emergency Preparedness, clarifies the measures to be activated at each step from the
7-3

occurrence of abnormal events, progression into nuclear emergency, to the recovery from emergency.
(3) Law for Radiation Protection
The radiation protection at nuclear installations is regulated by the Reactor Regulation Law, theElectricity Utilities Industry Law and the Industrial Safety and Health Law.
The Reactor Regulation Law stipulates zone control for radiation protection, dose control of personnel
engaged in radiation work, measurement and monitoring of radiation levels, etc. in order to protect
personnel and the public. The Electricity Utilities Industry Law prescribes the radiation instrument
devices to be installed in nuclear power stations. The Industrial Safety and Health Law define the dose
limits of personnel engaged in radiation work, which are equivalent to the Reactor Regulation Law.
The Law for Technical Standards of Radiation Hazards Prevention maintains consistency among
technical standards for radiation hazards prevention by establishing the Radiation Review Council.
In order to prevent hazards due to the use of radioisotopes in nuclear installations the Law for
Prevention of Radiation Hazards due to Radioisotopes, etc. (hereinafter, called as Radioactive Hazard
Prevention Law) stipulates zone control of radiation protection, dose control of personnel engaged inradiation work and radiation measurement in controlled area etc.
The ICRP Recommendation 1990 was incorporated into relevant legislation in April 2001.
(4) The Law for Environmental Impact Assessment
The Environmental Impact Assessment Law was enacted in June 1999, replacing the departmental
decision, July 1977, of the MITI. The law stipulates for the environmental impact assessment of
nuclear installation other than safety assessment.
The objective of the Environmental Impact Assessment Law is for license holders to perform proper
assessment of a large business plan which may pose large impact on the environment, and to prepare
proper plan to preserve the environment. The law provides for a set of procedures for it.
Environmental assessment on commercial power plants, including nuclear power plants, is performedin accordance with the provisions of the Environment Impact Assessment Law and the corresponding
provisions of the Electricity Utilities Industry Law. Environmental impact assessment is obligatory for
nuclear installation regardless of its scale.
(5) The Law on Compensation for Nuclear Damage
The Law on Compensation for Nuclear Damage establishes the basic system on compensation for
nuclear damage caused by a nuclear accident.
The Law adopts the “liability without fault” principle and imposes sole liability of compensation for
nuclear damage on license holders, exempting claimants from proving license holder’s fault inaccordance with the general principle of the Civil Law. Also, infinite liability of compensation is
imposed on the license holder. To secure the fund of and to facilitate the compensation, the license
holder is required to make the Financial Arrangement for Nuclear Damage Liability. The amount of
the Arrangement is sixty billion yen for a nuclear installation.
The Arrangement consists of the Nuclear Damage Liability Insurance Contract with a civil insurer andthe Indemnity Agreement for Compensation with the national government. The latter supplements theformer in the case of large-scale accident such as caused by earthquake or volcanic eruption. And incase the total amount arranged by the license holder is not sufficient for full compensation, thenational government, on the basis of decision by the Diet, would aid to cover the license holder. In thecase of enormous natural disaster or social disturbance, the national government bears thecompensation, exempting license holder from liability for compensation.
7-4

7.3

Legislative and Regulatory Framework at Each StageThe overview of the safety regulations on the basis of the Reactor Regulation Law, the Electricity
Utilities Industry Law, etc. from planning stage through operation stage is shown in Figure 7-3. A
summary of the safety regulations for a commercial power reactor is stated in this section.
(1) Planning Stage
When selecting a site for a nuclear installation, the electric utility, on the basis of the Environmental
Impact Assessment Law and the Electricity Utilities Industry Law, performs environmental impact
assessment, and submits to METI the draft Environmental Impact Statement (draft EIS) explaining
current status of the environment and measures to protect it. The draft EIS is sent to the related local
governments to be disclosed for public comments. The utility prepares their views addressing
residents’ comments. Assessments on air, water, and soil pollution due to radioactive substances are
performed under the Reactor Regulation Law and exempted from application of the Environmental
Impact Assessment Law. METI conducts the evaluation, soliciting experts’ opinion.
METI, also, holds public hearings (primary public hearings) to obtain understanding and cooperationof local residents. The results of public hearings are taken into consideration in the safety examination.
(2) Establishment Stage
The license applicant, having completed the procedure of planning stage, submit application format
for the Establishment License to NISA in accordance with the Reactor Regulation Law. Applicants
attach documents to the application format including description on safety design of the nuclear
installation, radiation control, and accidents and failures.
NISA conducts an examination to determine the adequacy of the site, and the basic design of structureand equipment from the points of prevention of radiological hazards, focusing on the evaluation of thesafety of the reactor core and the radiation exposure due to establishment of the nuclear installation. In
addition, the regulatory body confirms that the nuclear installation should be used for peaceful purpose
and in line with the planned development and utilization of nuclear energy, and the applicant has
sufficient technical capability to ensure safety and sufficient financial basis to execute the plan.
In this examination, the regulatory guides in Table 7-1 and other documents established by the NSC
are used. In the examination, site surveys, and analysis are conducted, when necessary.
The Minister of METI consults with the AEC and the NSC on the results of its examination.
During the process of review of METI’s results, the NSC holds a public hearing (secondary public
hearing) focusing on safety problems characteristic to the installation, and gives its views to the
Minister of METI. The Minister of METI considers these views, asks for the consent of the Minister of
MEXT, and then issues the license.
(3) Construction StageIn accordance with the Electricity Utilities Industry Law, the license holder shall submit theConstruction Plan for establishment of electric structures, and obtain the approval of the Minister of
METI before starting construction work. NISA examines the Construction Plan to confirm that thedetailed design of electric structures is consistent with the basic design and design policies approved at
the stage of establishment license, and is in conformity with the technical standards based on theElectricity Utilities Industry Law. And the license holder shall designate Chief Electrical Engineers
and Chief Engineers of Boiler and Turbine and notify NISA of it.
After obtaining approval of Construction Plan, the license holder shall undergo the Pre-Service
7-5Inspection by NISA at each process of construction and at the completion of all construction work,
which confirms that construction is conducted in accordance with the construction plan and is inconformity with the technical standards. The license holder shall obtain design approval by NISA forfuel assemblies to be loaded in the reactor and undergo the Fuel Assembly Inspection conducted by
NISA. The license holder shall perform Licensee’s Welding Inspection for welding of pressurizedparts and containment vessels and shall undergo review by JNES on the organization conducting theinspection, the inspection method, schedule control, and other items provided by the ordinance of
METI (Welding Safety Management Review).
(4) Operation StageAt the start of operation, the license holder shall notify NISA of the operation plan, obtain approval of
the fitness-for-safety program that prescribes the procedure of operational management, limitation ofoperating conditions and safety education of personnel, designate the Chief Engineers of Reactors, theChief Electrical Engineers, and the Chief Engineers of Boiler and Turbine who supervise the safety ofthe operation, and the Persons Responsible for Operation, and notify NISA of them. The license holder
is required to notify NISA of the operation plan annually.
The 17 items prescribed in the Operational Safety Program are shown in the report of Article 19 (Table
19-1), which includes periodic assessment, quality assurance, and maintenance management etc.
The license holder shall control the radiation exposure of personnel engaged in radiation work so that
their doses do not exceed the dose limit, and shall report the exposure dose of personnel to NISA
periodically.
License holder shall discharge into the environment gaseous and liquid radioactive waste generated
during operation, in compliance with the concentration values provided in the Operational Safety
Program which are lower than the concentration limits stipulated in the Reactor Regulation Law. A
license holder shall make effort to reduce discharge amount as small as possible so that annual public
exposure in the vicinity will be kept below 50 µ Sievert in accordance with the Regulatory Guide for
the Annual Dose Target for the Public in the Vicinity of Light Water Nuclear Power Reactor Facilities(hereinafter referred to, as “Dose Target Guide for Public Dose”).
After starting operation, the license holder, in accordance with the Electricity Utilities Industry Law,
shall perform the Licensee’s Periodic Inspection to confirm that that the installations conforms withthe technical standards, and shall undergo the Periodic Inspection by NISA on the major part ofstructures important to safety. The Periodic Inspection and the Licensee’s Periodic Inspection are
conducted during shutdown of operation within the interval not exceeding 13 months from the date ofstart of operation or the date of completion of the previous inspection. Since October 2003, JNES
conducts part of the Periodic Inspection and notifies NISA of the results on the basis of the revision of
the relevant laws. Also, license holder shall undergo the Periodic Safety Management Review, inwhich JNES reviews the license holder’s organization conducting the Licensee’s Periodic Inspection,
inspection method, schedule control, and other items provided in the ordinance of METI, and report to
NISA for the evaluation.
License holder shall undergo the Nuclear Safety Inspection by the Nuclear Safety Inspectors on theobservance of the Operational Safety Program, including the organization of license holder, quality
assurance, maintenance management, operation, maintenance and repair of component, surveillance,
radiation control, management of radioactive wastes, discharge control of gaseous and liquidradioactive wastes, monitoring, safety education. NISA conducts the entry inspection of nuclear
facilities to confirm compliance with safety regulation, if necessary.
If any failures occur in nuclear installation, license holders shall report failures etc. immediately to
NISA in accordance with the provisions of the Reactor Regulation Law and the Electricity Utilities
Industry Law, and shall report to NISA, without delay, the situation of failures and the measures taken.
7-6In order to improve transparency of information to the public, the reporting criteria for failures etc.
were more clearly defined by amending the Reactor Regulation Law, in October 2003. License holders
have established the system to collect information on events, including minor events that are outside of
the reporting criteria, and disclose them to the public.
Criteria for necessity of approval or notification of the Construction Plan for any modification or
repair work of electric structures after startup of operation was clarified by the amendment of theRules for the Electricity Utilities Industry Law, in October 2003. NISA established “Regulatory Guideon the Construction Plan“ to identify the details of the amendment and notified license holders of it.
MITI (present METI) issued, in 1992, a departmental decision to request license holders to voluntarily
perform Periodic Safety Review at a regular operating interval (approximately every ten years),
including incorporation of operating experiences from commissioning to date and the latest
technological knowledge, and probabilistic safety assessment. On the basis of the amendment of theReactor Regulation Law, in October 2003, the Periodic Safety Review was incorporated into the
Operational Safety Program, the observance of which the Nuclear Safety Inspector inspects at the
Nuclear Safety Inspection. The implementation of probabilistic safety assessment, however, remains to
be a voluntary activity of license holder as yet.
On the basis of the amendment of the Reactor Regulation Law, in October 2003, license holder was
obliged to perform technical evaluation on ageing of nuclear installation before the continuation ofoperation more than thirty years and shall prepare a ten-year maintenance program based on thetechnical evaluation. The subsequent evaluation should follow within ten years.

7.4 The Enforcement of Applicable Regulations and the Terms of License
In accordance with the Reactor Regulation Law, the Minister of METI may revoke the Establishment
License or issue a Shutdown Order of nuclear installation for up to one year, under circumstances suchas operating a nuclear installation without an Establishment License, violating an order legally issued
by NISA, failing to implement measures necessary for safety prescribed by NISA, or failing to obtainapproval for the Fitness-for-Safety Program.
The Reactor Regulation Law also prescribes imprisonment and/or fines under circumstances such as
establishing a nuclear installation without an Establishment License, violating a Shut-Down Order, or
failing to take relevant emergency measures. NISA may order changes in the Fitness-for-Safety
Program whenever it is deemed necessary for preventing potential radiological hazards License
holders failing to abide by such orders would be punished with a fine.
In accordance with the Electricity Utilities Industry Law, if it is judged for an electric structure not to
conform to the technical standards, the Minister of METI may order repair, alteration, relocation,
temporary suspension of usage, or limitation of usage.
The Electricity Utilities Industry Law prescribes fines if the license holder violates a TechnicalStandard Conformance Order, or establishes or alters an electric structure without obtaining necessary
approval for a construction plan, or uses an electric structure without undergoing or passing the
Pre-Service Inspection, the Fuel Assembly Inspection, or the Welding Safety Management Review. It
also prescribes to revoke the business license, if an electric utility violates the law or orders based on
the law causing serious damage to the public benefits.
On the basis of the amendment of the Reactor Regulation Law, October 2003, when an employee
violates a law and is punished by a fine, the legal person who legally employs him or her is also
punished by a fine as heavy as 100 times of the employee’s fine, to prevent organizational illegal acts.

7-7

Table 7-1 Major Safety Regulatory Guides of the NSC for Light Water Nuclear Power
Reactor Facilities
SitingDesignPrevention of Radiological Hazards

Safety Evaluation

Dose Target

Technical
Competence- Regulatory Guide for Reviewing Nuclear Reactor Siting
Evaluation and Application Criteria- Regulatory Guide for Reviewing Safety Design of Light Water
Nuclear Power Reactor Facilities- Regulatory Guide for Reviewing Classification of Importance of
Safety Functions for Light Water Nuclear Power Reactor
Facilities- Regulatory Guide for Reviewing Seismic Design of Nuclear
Power Reactor Facilities- Regulatory Guide for Reviewing Fire Protection of Light Water
Nuclear Power Reactor Facilities- Regulatory Guide for Reviewing Radiation Monitoring in
Accidents of Light Water Nuclear Power Reactor Facilities- Fundamental Policy to be Considered in Reviewing of Liquid
Radioactive Waste Treatment Facilities- Regulatory Guide for Reviewing Safety Assessment of Light
Water Nuclear Power Reactor Facilities- Regulatory Guide for Evaluating Core Thermal Design ofPressurized Water Cooled Nuclear Power Reactors- Regulatory Guide for Evaluating Emergency Core Cooling
System Performance of Light Water Power Reactors- Regulatory Guide for Evaluating Reactivity Insertion Events ofLight Water Nuclear Power Reactor Facilities- Regulatory Guide for Evaluating Dynamic Loads on BWR
MARK-I Containment Pressure Suppression Systems- Regulatory Guide for Dynamic Loads on BWR MARK-II
Containment Pressure Suppression Systems- Regulatory Guide for Meteorological Observation for Safety
Analysis of Nuclear Power Reactor Facilities- Regulatory Guide for the Annual Dose Target for the Public in theVicinity of Light Water Nuclear Power Reactor Facilities- Regulatory Guide for Evaluating the Annual Dose Target for the
Public in the Vicinity of Light Water Nuclear Power Reactor
Facilities- Guide for Radiation Monitoring of Effluent Released from Light
Water Nuclear Power Reactor Facilities-Regulatory Guide for Reviewing Technical Competence of
Nuclear Operator

7-8

Table7-2-1 Academic Society and Association Standards etc.
(Guidelines and Rules of the Japan Electric Association)
Number
Title
JEAC 4111-2003 (*) Rules of Quality Assurance for Safety of Nuclear Power Plants
JEAC 4201-2000
Method of Surveillance Tests for Structural Material of Nuclear Reactors
JEAC 4202-2004
Drop-Test Method for Ferritic SteelJEAC 4203-2004
Primary Reactor Containment Vessel Leakage Testing
JEAC 4205-2000
In-service Inspection of Light Water Cooled Nuclear Power
Plant Components
JEAC 4206-2000
Methods of Verification Tests of the Fracture Toughness for Nuclear Power
Plant Components
JEAC 4206-2003
Methods of Verification Tests of the Fracture Toughness for Nuclear Power
Plant Components (supplement)
JEAC 4209-2003 (*) Rules of Maintenance Management of Nuclear Power Plants
JEAG 4602-1992
Definitions of Nuclear Reactor Coolant Pressure Boundary and Reactor
Containment Boundary
JEAC 4605-1992
Definitions of Engineered Safety Features and Related Systems of Nuclear
Power Plants
JEAG 4101-2000
Guide of Quality Assurance for Nuclear Power Plants
JEAG 4102-1996
Guide of Emergency Measures for Nuclear Power Plants
JEAG 4204-2003
Guide for Quality Control of Nuclear Fuel for Nuclear Power Plants
JEAG 4207-2004 (*) Ultrasonic Examination for In-service Inspection of Light Water Cooled
Nuclear Power Plant Components
JEAG 4208-1996
Eddy Current Test Guide for In-service Inspections of Steam Generator
Heat Transfer Tubes for Light Water Type Nuclear Power Plants
JEAG 4601-1987
Technical Guidelines for A seismic Design of Nuclear Power Plants
JEAG 4601-S-1984
Technical Guidelines for A seismic Design of Nuclear Power Plants:
Classification and Allowable Stress
JEAG 4601-1991
Technical Guidelines for A seismic Design of Nuclear Power Plants:
Supplement
JEAG 4603-1992
Guide for Design of Emergency Electric Power Supply Systems
for Nuclear Power Plants
JEAG 4604-1993
Guide for Design of Plant Protection Systems for Nuclear Power Plants
JEAG 4606-2003
Guide for Radiation Monitoring for Nuclear Power Plants
JEAG 4607-1999
Guide for Fire Protection of Nuclear Power Plants
JEAG 4608-1998
Lightning Protection Guidelines for Nuclear Power Plants
JEAG 4609-1999
Application Criteria for Programmable Digital Computer System
in Safety–Related System of Nuclear Power Plants
JEAG 4610-2003
Personal Dose Monitoring for Nuclear Power Plants
JEAG 4611-1991
Guide for Design of Instrumentation & Control Equipment with Safety
Functions
JEAG 4612-1998
Guide for Safety Grade Classification of Electrical and MechanicalEquipment with Safety Functions
JEAG 4613-1998
Technical Guide Lines for Protection Design against Postulated Piping
Failures in Nuclear Power Plants
JEAG 4614-2000
Technical Guidelines on Seismic Base Isolation System for Structural
Safety and Design of Nuclear Power Plants
JEAG 4615-2003
Guide for Design of Radiation Shielding for Nuclear Power Plants
JEAG 4616-2003
Technical Guide for Design of Base Structures for Dry Cask Storage
Buildings
JEAG 4801-1995
Guide for Operating Manual of Nuclear Power Plants
JEAG 4802-2002
Guide for Education and Training for Nuclear power Plant Operator
JEAG 4803-1999
Guide for Operational Safety Preservation of Light Water Cooled Reactors

7-9Table7-2-2 Academic Society and Association Standards etc.
(Guidelines and Rules of the Japan Society of Mechanical Engineers)
Number
Title
Standards
for
NuclearPower
Generation
Equipment: Maintenance
JSME S NA1-2002 (*)
Standards (revised in 2002)
Standards for Nuclear Power Generation Equipment: Welding
JSME S NB1-2001
Standards
Standards for Nuclear Power Generation Equipment: Design an
JSME S NC1-2001 (*)
Construction Standards
Standards for Nuclear Power Generation Equipment: Design Standards
JSME S ND1-2002
for Prevention of Piping BreakStandards for Nuclear Power Generation Equipment: Concrete
JSME S NE1-2003
Reactor Containment Vessel
Standards for Spent Fuel Storage Facility: Structural Standard
JSME S FA1-2001
for Metallic Cask
Guide for Prevention o f Fluid Induced Vibration of Tube and
JSME S016
U-Tube of Steam Generator
Evaluation Guideline on High Cycle Thermal Fatigue of Piping
JSME S017
Table7-2-3 Academic Society and Association Standards etc.
(Guidelines and Rules of the Atomic Energy Society of Japan)
NumberTitle
AESJ-SC-P001:2002
Procedure of Probabilistic Safety Evaluation on Shutdown Condition of
Nuclear Power Station
AESJ-SC-P002:2003
Evaluation Criteria of Fuel Integrity after Transient Boiling Transition
for BWRAESJ-SC-P003:2003
Performance Criteria of Wind Tunnel Test to obtain the effective heightof Discharge Source
AESJ-SC-F001:2000
Periodic Inspection Criteria of Cask for Spent Fuel, MOX fueland High Level Radioactive Waste
AESJ-SC-F003:2002
Measurement method of Sorption Distribution CoefficientBasic Procedure of Batch Method for Barrier Material of Near Face
Disposal
Table7-2-4 Academic Society and Association Standards etc.
(Guidelines and Rules of the Thermal and Nuclear Power Engineering Society)
NumberTitle
TNS-S3121-2003
Qualification Standards for Industry Product on Weld of Electri
Structures
Note: * Academic Society and Association Standards etc. that NISA has reviewed for technicaladequacy in order to utilize as references of specifications.

7-10

Atomic Energy Basic Law

Major Examination Guides
for Safety Design ofLight Water Nuclear Power
Reactor Facilities(Table 7-1)

Electricity Utilities Industry Law

Law for the Regulation of Nuclear Source
Material, Nuclear Fuel Material andReactors

Special Law of Emergency
Preparedness for Nuclear
DisasterElectricity Utilities
Industry Law,
Ordinance

Ordinance for the Regulation of Nuclear
Source Material, Nuclear Fuel Material
and Reactors

Basic Law for Emergency
Preparedness

Law on Compensation for
Nuclear Damage
Electricity Utilities
Industry Law, Rules

Rules for the Installation,
Operation, etc. of Nuclear Power
Reactors at the Stage of
Research and Development

Notification for Dose
Equivalent Limits on theBasis of the Rules forCommercial Power Reactors

Notification for Dose Limits on thebasis of the Rules for Manufacturing
Business of Nuclear Fuel Material etc.

7-11

Rules for the Installation,
Operation, etc. of Commercial
Power Reactors

Industrial Safety and Health Law

Ordinance Establishing
Technical Standards forElectrical Equipment(Fig. 7-2)

Law for Technical Standards ofRadiation Hazards Prevention

Law for Environmental Impact
Assessment< Academic Society and Association Standards etc.>
Technical Guideline andRules of the Japan Electric
Association

Technical Standards of the
Thermal and Nuclear PowerEngineering Society of Japan

Technical Standards of
the Japan Society of
Mechanical Engineers

Technical Standards of theAtomic Energy Society ofJapan

Fig. 7-1 Major Legislations Governing the Safety Regulation of Nuclear Installations

7-11

Electricity Utilities Industry Law

Ordinance for the
Enforcement the Electricity
Utilities Industry Law

Rules for the Enforcementof the Electricity Utilities
Industry Law

Ordinance ofEstablishing TechnicalStandards for Nuclear
Power Generation
Equipments

Ordinance ofEstablishing TechnicalStandards on Nuclear
Fuel Material forPower Generation

Ordinance ofEstablishing TechnicalStandards for Electric
Equipment

Ordinance ofEstablishing TechnicalStandards on Thermal
Power Generation

Ordinance ofEstablishing TechnicalStandards on the
Welding of Electric

7-12
Technical Standards on
Structures etc., of Nuclear
Power Generation Facilities

Technical Standards on
Structures etc., for Concrete
Reactor Containment

Technical Standards on Dose,etc. due to Radiation from
Nuclear Power Generation
Facilities< Academic Society and Association Standards etc.>
Technical Rules and of the Technical
Guidelines of Japan Electric Association

Technical Standards of the Japan
Society of Mechanical Engineers of Japan(Table7-2-1)(Table 7-2-2)

Standards of Atomic Energy
Society of Japan(Table 7-2-3)

Fig. 7-2 Systems of Technical Standards
7.12

Technical Standards of the Thermal andNuclear Power Engineering Society(Table 7-2-4)

Site Selection
Environmental Impact Assessment
The Public Hearing (1st)Application for Reactor Establishment
Asking Consultation

Asking Consultation(peaceful use, planned
implementation andfinancial foundation)

Atomic Energy
Commission(radiological hazards prevention
and technical competency)
Examination by NISA

Mandatory Advice

Establishment License

Mandatory
AdviceNuclear Safety
Commission

Public Hearing (2nd)Application and ApprovalofConstruction Plan
Pre-Service Inspection
Licensee’s Welding
Inspection,
Welding Safety
Management Review
Approval ofOperational Safety
Program

Periodic Inspection

Construction Work

Commissioning

Operation

Licensee’s Periodic
Inspection,
Periodic Safety
Management Review

Notification of Dismantling
Implementation Order

Collection of Reports
DismantlingOn-the-Spot Entry andInspection
Nuclear Safety
Inspection

Notification of Decommissioning
Implementation Order
Decommissioning

Fig. 7-3 Flow of Safety Regulations in accordance with Legislations, etc.
for Nuclear Installations
7-13

Article 8

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, andprovided with adequate authority, competence and financial and human resources to fulfill its
assigned responsibilities.
2. Each Contracting Party shall take the appropriate steps to ensure an effective separation
between the functions of the regulatory body and those of any other body or organization
concerned with the promotion or utilization of nuclear energy.
As the regulatory body to ensure the safety of nuclear installations in Japan, Nuclear and Industrial Safety
Agency (NISA) has been established as a “special organization into the METI. NISA has clear responsibilities
for safety regulations pursuant to the Atomic Energy Basic Law and the Reactor Regulation Law and thefunctions of NISA are substantially separated, by the law, from those of other bodies or organizations concernedwith the promotion or utilization of nuclear energy.
The Atomic Energy Commission (the AEC) and the Nuclear Safety Commission (the NSC) had been established.
Each Commission is composed of commissioners appointed by the Prime Minister with the consent of the Diet.
The AEC has duties of planning, deliberation, and making decisions concerning research and development forpeaceful use of nuclear energy, and the NSC has duties of those for ensuring of nuclear safety. Both
Commissions, through the Prime Minister, can recommend the heads of relevant administrative organs and canrequest them reports, documents, explanation, their opinions and, other necessary cooperation.
Since the second review meeting in order to implement measures for safety regulations more efficiently, thefollowings were newly established: the Senior Advisory Inspector System in NISA and the Incorporated
Administrative Agency Japan Nuclear Energy Safety Organization (JNES) to support NISA

8.1 Mandate and Duties of Regulatory Body
The mandate of a regulatory body is to ensure safety of nuclear installations, and its duties are to
enforce the legislative and regulatory framework described in the report of Article 7.
One of the important requirements for a regulatory body satisfying his responsibility is, as indicated in
Article 8, Paragraph 2 of this Convention, to ensure effective separation between functions of theregulatory body and those of any other body or organization concerned with promotion or utilizationof nuclear energy.
Another important function of a regulatory body is to keep communicating independently with the
public of its regulatory decisions, its opinions and their basis.
On the basis of the Atomic Energy Basic Law, the regulatory body is responsible to conduct regulatory
activities prescribed in the Reactor Regulation Law, the Electricity Utilities Industry Law, etc.
As for legislations and regulations etc. applied to the examination of the basic design or basic design
policies of nuclear facilities and to the inspection of nuclear facilities in the construction andoperational stages, the NISA and the NSC work toward improvement and enhancement of legislations
and regulations based on operating experiences, trend of the latest knowledge of the technology
advancement, etc., and the international consensus.
In case of a nuclear emergency, the Basic Law on Emergency Preparedness, the Special Law ofEmergency Preparedness for Nuclear Disaster and other related laws are applied. Relevant
administrative bodies in such a case are described in the report of article 16.

8-1

8.2 Organizations for Enforcement of Safety Regulation of Nuclear Installations
In Japan, the Minister of Economy, Trade and Industry serves as the minister in charge of safety
regulation for all facilities and activities concerning utilization of nuclear energy.
Nuclear and Industrial Safety Agency (NISA) has been established in the Ministry of Economy, Tradeand Industry (METI) as an independent "special organization" dedicated to the administration of safety
regulations. NISA has been executing the policies independently from the Agency of Natural
Resources and Energy dedicated to promote the nuclear energy.
The Incorporated Administrative Agency Japan Nuclear Energy Safety Organization (JNES) wasestablished in October 2003.
JNES provides together with NISA infrastructure to assure safety in the use of the nuclear energy.
The NSC and the AEC had been established respectively in the Cabinet Office. The commissioners ofboth of these commissions are appointed by the Prime Minister with the consent of the Diet.
Each of these two commissions plans, deliberates, and decides policies concerning either the nuclear
power application or ensuring the safety, from the standpoint to regulate all over the country
respectively
As described in the report of Article 7, the NISA conducts a safety examination of nuclear installations,and the Minister of METI consults the NSC and the AEC on the results of the examination.
The NSC submits to the Minister of METI a specific report on the safety of the nuclear installation,
after an independent examination and public hearings. The NSC establishes examination guides to be
used for the examination. Fig. 8-1 presents an overview of administrative organizations that are
responsible for the safety regulation of nuclear installations.

8.3 Nuclear and Industrial Safety Agency (NISA)(1) The Role of NISANISA administers the safety regulations for nuclear installations. Specifically, NISA entrusted by the
Minister of METI, conducts clerical works concerning the competence of the Minister of METI as
follows:− The Minister of METI, who is the competent minister stipulated in the Reactor Regulation
Law, has the authority to issue a license for the establishment of a nuclear installation, after
conducting examination of siting, structure, and equipment, so that radiological hazards due tothe establishment of the nuclear installation are prevented. The Minister of METI has theauthority to revoke the license under circumstances such as violation of the Reactor
Regulation Law by the license holder.
− The Minister of METI has the authority to establish ministerial orders on the operation plans,measures on operational safety and on protection of specified nuclear fuel materials,
Operational Safety Program, the Nuclear Installation Dismantling Notifications, the Chief
Engineer of Reactors, emergency preparedness, etc. The Minister of METI has the authority 1)
to approve Operational Safety Program, 2) to accept reports on operation plans, the Nuclear
Installation Dismantling Notifications, and the appointment of Chief Engineer of Reactors, 3)
to collect reports on incidents and failures from license holders, and 4) to order suspension of
the operation of nuclear installations, dismissal of Chief Engineer of Reactors, measuresrelating to Dismantling Notifications and measures needed for emergency preparedness.
− The Minister of METI, and the Minister of MEXT, conducts examinations for Chief Engineer
8-2−of Reactors and issues the licenses. The Minister of METI has the authority also to order toreturn such licenses in a case of violation of the law by the Chief Engineers.
The Minister of METI, who is the competent minister stipulated in the Electricity Utilities
Industry Law, has the authority to establish ministerial ordinances relating to technicalstandards, Pre-Service Inspections, fuel assembly inspections, Welding Safety Management
Reviews, Periodic Inspections, and Periodic Safety Management Reviews. The Minister of
METI has the authority 1) to approve construction plans, 2) to conduct Pre-Service Inspections
including confirmation of the safety performance of the power plant, Fuel Assembly
Inspections, and Periodic Inspections, and 3) to issue an Order for Conformity with TechnicalStandards in the case of nonconformity to the technical standards. The Minister of METI has
the authority also to hold examinations for Chief Electrical Engineers, to issue licenses for
Chief Electrical Engineer and Chief Engineer of Boiler and Turbine, and to order the return ofsuch licenses in case of violation of the law by the Chief Engineers.

NISA evaluates results of the Periodic Safety Management Review
performed by JNES. JNES
reviews the organization, inspection method, process control, and other items provided by Ministerial
Order of the METI, concerning the Licensee’s Periodic Inspection, and report the results to NISA.
NISA evaluates also the results of Welding Safety Management Review performed by JNES.
(2) Organization of NISANISA was established as a "Special Organization" in METI, and has 11 divisions dedicated toadministration of the safety regulation of nuclear installations. Table 8-1 shows the assigned duties ofthe divisions.
Nuclear Safety Inspectors are assigned to the resident position at each nuclear installation. Fig.8-2
shows the locations of the Nuclear Safety Inspectors Offices.
NISA has a total of approximately 300 staff engaged in nuclear safety regulation, out of which 100 are
Nuclear Safety Inspectors and the Senior Specialists for Nuclear Emergency stationed at nuclear
installations.
(3) Improvement of Quality of NISA’s Regulation
NISA provides a strong commitment to its mission, scientific and reasonable judgments, transparency,
neutrality and fairness as the code of conduct for their activities. In this context, the Policy Planningand Coordination Division watches and assesses the performance of other NISA’s divisions indischarging their duties, and take timely remedial actions after consulting with the senior
managements.
NSC, independent from NISA, audits the quality of safety administration by observing and auditing
NISA’s activities aiming to stimulate ceaseless improvement and enhancement .
NISA makes continuous effort to maintain high quality of regulation through education and training of
the personnel as stated in the report concerning Article 11, international activities and hearing to theadvice from experts e.g. members of the Nuclear and Industrial Safety Subcommittee.
"The Law for Evaluation of the Policies Executed by Administrative Organizations" has been enforcedsince April 2002, and in accordance with this law, a framework, with which each administrative
organization of the government evaluates and improves his own policies systematically, has been
provided. METI has developed plans to evaluate the regulatory systems within its jurisdiction in fiscal
year of 2004, and the NISA, according to these plans, evaluates the nuclear safety regulation systemon the basis of the Reactor Regulation Law and the Electricity Utilities Industry Law.

8-3

(4) Further Approach to Information Disclosure
1) NISA’s Activity for Communication with Public
NISA, at a web site (http://www.nisa.meti.go.jp/), has been disclosing information on incidents andaccidents, radiation control, capacity factor and results of the periodic inspection of nuclear
installations and activities of nuclear energy related to advisory committees, and is keeping
communication with the public through questions and answers.
In order to recover the trust of the public which was lost due to the TEPCO falsification issue, NISA
recognized that ensuring the transparency of the safety assurance of the nuclear plant, as well as
explanation of the nuclear safety to the public and the residents in the vicinity of sites, wasimportant.
NISA, held a numbers of explanatory meetings for the residents in the vicinity of sites to exchange
opinions concerning the measures to prevent recurrence, the measures for safety assurance of thenuclear power station and the new safety regulation system enacted in October 2003. Thus, NISA
has been making efforts to address the comprehensible explanation of nuclear safety, enhancementof the activities to hear from public and distribution of a periodic magazine to inform the activities
of NISA, etc.
Also, the NISA opens Nuclear Energy Library in the JNES, where the public can access to license
application documents of nuclear installations, reports of incidents and accidents of nuclear
installations and, books and booklets on energy and nuclear power generation.
2) Public Information Law and Enhancement of NISA Public Information Organization
The Law concerning Access to Information Held by Administrative Organization enacted in April
2001, which prescribes disclosure of information on request, promotes the transparency ofadministration on safety regulation.
NISA developed in April 2004 a new budget to enhance activities to hear from and to speak to the
public further, and has newly established the Nuclear Safety Public Relations and Training Division
and assigned the Regional Public Relations Officer for Nuclear Safety.
The roles of the Nuclear Safety Public Relations and Training Division are a) to deepen
communications with the public as a window to hear from and speak to public on NISA’s activities,b) to conduct the activity to hear from and to speak to the public in various ways, corresponding to
the various needs of the public, c) to provide the personnel of the NISA with education and training
for development of risk communication skills so that the personnel may conduct activities for public
hearing and public relations in a comprehensible manner, and d) to cooperate closely with Nuclear
Safety Inspectors at the site area, in order to support of activities in the site area to hear from andto speak to the public, conducted by the Manager of the Nuclear Safety Inspectors Office as aleader.
The role of the Regional Public Relations Officer for Nuclear Safety is to promote communication
activities with the public more actively upon request of local governments where many nuclear
power facilities are located.

8-4

8.4 Organizations related to NISA
(1) Council
On the basis of the METI Establishment Law, the Advisory Committee for Natural Resources andEnergy (ACNRE) was established, a subcommittee of which is the Nuclear and Industrial Safety
Subcommittee (the NISS) that proposes policies on nuclear safety and safety of electric power as theterms of reference. The organization of the NISS is given in Table 8-2.
The Minister of METI appoints members of the ACNRE from persons of knowledge and experience,and these members select a chairperson of the ACNRE mutually. Subcommittees are established by
the resolution of the ACNRE, and the chairperson designates members of the subcommittees including
the NISS. The members of the subcommittees are assigned based on their expertise and experiencefrom the fields of nuclear and thermal-hydraulic design, nuclear fuel design, system design, equipment
design, seismic design, material strength, radiation control, meteorology, geology, soil etc.
Subjects to be discussed such as "How the safety assurance of nuclear power and operational safety ofelectric power system in the future should be under the changing social and economical
circumstances" were submitted to the Nuclear and Industrial Safety Subcommittee. The NISS andother subcommittees have deliberated on what nuclear safety regulation system should be, and theresults were reported to the NISA.
NISA solicits views of experts and members of the NISS.
(2) Incorporated Administrative Agency, Japan Nuclear Energy Safety Organization (JNES)JNES, consisted of about 420 officers and staffs, was established in October 2003 as an organizationthat establishes the infrastructures in corporation with the NISA to ensure the safety in utilization of
nuclear energy.
The mission of JNES is to implement their duties effectively and efficiently based on scientificjudgments to contribute to the improvement of nuclear safety regulation and, to deliver and transmit
actively the safety information to the public in order to gain the public confidence to the safety of
nuclear energy.
JNES implements the following activities:− Inspection of nuclear fuel cycle facilities including nuclear power reactor facilities, and otherinspections similar to those;− Safety analysis and evaluation of designs of nuclear fuel cycle facilities including nuclear
power reactor facilities;− Activities to minimize probability of occurrence of nuclear emergencies, to prepare for anuclear emergency, to prevent propagation of a nuclear emergency and, to recover from thenuclear emergency;− Investigation, testing, research, and training concerning safety assurance for utilization of
nuclear energy.; and− Collection, analysis and transmission of information to assure nuclear safety.
The procedure for JNES to implement activities and the relation of JNES with NISA of METI are asshown in the followings:− NISA develops a plan on each activity based on the regulatory needs, and defines themedium-term objective in accordance with the Law of the General Rules for Incorporated
Administrative Agency, and the Minister of METI assign it to JNES.
− JNES prepares a scheme (medium-term scheme) to accomplish the medium-term objective,
apply the scheme to the Minister of METI, and obtain the approval, then JNES prepares
8-5

a-FY plan in accordance with the medium-term scheme, notify the plan to the said ministerand implement it.

Allocation of Responsibilities Between NISA and JNESNISA: Nuclear and Industrial Safety Agency
JNES: Japan Nuclear Energy Safety Organization
Activities for Inspection etc., Analysis and Evaluation,
Support for Disaster Prevention., International Cooperation

Activities for Information Investigation

NISA

Planning Organization
Implementing Organization

Activities for Test and Research

NISA• Planning of inspections• Planning of review• Planning of disaster prevention• Planning of international
cooperation• Prepare goals of the medium term

NISA
• Planning of guides, standards, criteriaetc.
• Prepare goals of the medium term

Instructions of
the goals in themedium term

Close
cooperation

Proposalon theinspection• Inspection, verification,
Periodic safety management
review, etc.
• Safety analysis, cross check• Support for disasterprevention
Analysis and Review • Collection and dispatch of
Support for Disaster
information for international
Prevention
cooperation
Inspection Results
Supply of Information • Provide the implementation
plan of the medium term

Application

Application

Adequatecoordinationof opinion

Support of
Activities
Information
service
Proposal

Instructions of
the goals in themedium term

Supply of
information

JNES• Inspections• Safety review• Preparedness of
disaster prevention• International cooperation

Inspection
review

Instructions of
the goals in themedium term

• Planning on collection,compilation, and supply of
information to ensure the safety• Prepare goals of the medium
term

JNES

Cooperation
on general invitationof proposals(standards,
criteria. etc)

Inspection andverification
Periodic safety
management
review, etc.

Nuclear Business Operator

JNES• Implementation of investigation, test,
and research to collect data andinformation for planning of guides,
standards, criteria etc.
• Provide the implementation plan of
the medium term

University, Society, Association• Collection, compilation,and supply of information
to ensure the safety• Provide theimplementation plan of themedium term

Public relations
Public hearing

Supply of
informationeasy tounderstandPeople in Japan

8.5 The Nuclear Safety Commission (the NSC)
The Atomic Energy Basic Law was partially revised on October 4, 1978 to establish the NSC under
the Prime Minister’s Office. The NSC administers the function of safety regulation, belonged to the
AEC till then, in order to strengthen the system of ensuring the nuclear safety. (The NSC wastransferred from the Prime Minister’s Office to the Cabinet Office due to central government reform in
January 6, 2001.)
The NSC is responsible for planning, deliberation and decisions on matters that are related to ensuringsafety of the research, development, and utilization of nuclear energy.
The NSC conducts its own review on the results of NISA’s examination on a application, andsupervises and audits the regulatory activities of the agency to check the appropriateness of his
regulatory administration as the safety regulation in construction and operation stages after issuance ofthe license, as investigation activities to stimulate a ceaseless improvement and enhancement.
Therefore, the framework that ensures the quality of safety administration is kept.
If the NSC deems it necessary as part of its assigned duties, the NSC may recommend and may
request reports and cooperation concerning the submission of materials, statement of views, andexplanation to the heads of relevant administrative organizations, by way of the Prime Minister.
Since April 2003 (partially, from October 2003), the above functions have legally been enacted. The
8-6

NSC receives from NISA the following reports on the quarterly bases after the approval of the license
for establishment of nuclear installation: reports concerning conducts of the regulatory activities suchas approval of construction plan, Pre-Service Inspection, Periodic Inspection, Periodic Safety
Management Review, Welding Safety Management Review, approval of Operational Safety Programand Nuclear Safety Inspection, and reports concerning accidents and failures of nuclear installations.
NSC has also the authority to inquire directly operators and contractors in order to supervise and toaudit the safety regulation implemented by regulatory body.
In the case that there is violation of safety regulations in any of nuclear faciliies, one can directly
allege the fact to the NSC, and the NSC has also the authority to investigate the allegation.
The Minister of METI, before issuing an establishment license for nuclear installations, shall receive
views of the NSC on the following matters: (1) the applicant for the license of the nuclear installation
has adequate technical capability to establish and reliably operate a nuclear reactor, and (2) the site,
structures and equipment of the nuclear installation may not cause any hindrance to the prevention ofradiological hazards.
The NSC is composed of five commissioners appointed by the Prime Minister with the consent of theDiet, and these commissioners elect a chairman among them. General affairs of the NSC are
performed by the NSC Secretariat of Cabinet Office. The NSC Secretariat is composed of theSecretary-General, the General Affairs Division, the Regulatory Guides and Review Division, theRadiation Protection and Accident Management Division and the Subsequent Regulation Review
Division and has about 100 personnel.
Under the NSC, two special safety examination committees, eight special committees and five others
are organized as shown in Table 8-3. The Special Committees may organize working groups underthem, if necessary.
The members of the Committee on Examination of Reactor Safety and the Committee on Examinationof Nuclear Fuels Safety are appointed from persons of knowledge and experiences by the Prime
Minister in accordance with the Law for Establishment of the AEC and the NSC. The Emergency
Technical Advisory Body is composed of the commissioners of the NSC and the Emergency Response
Measures Investigators who are also appointed by the Prime Minister from persons of knowledge andexperiences. The members of other Special Committees are selected from commissioners of the NSC
and persons of knowledge and experiences.
The results of investigation and evaluation of each committee are reported to the NSC and aredeliberated by the NSC. The results of the discussion in the Emergency Technical Advisory Body arereported to the NSC together with their advice and determined by the NSC as recommendation items.
Deliberations of all committees, including the special committees and working groups under the NSC
are open to the public. The contents of the deliberations are provided for the public at a homepage(http://www.nsc.go.jp/) and the Nuclear Energy Library of the NSC.

8.6 The Atomic Energy Commission (the AEC)
The AEC was established, on January 1, 1956, under the Prime Minister's Office, on the basis of theAtomic Energy Basic Law and the Law for Establishment of the AEC and the NSC, to conductnational policy concerning research, development, and utilization of nuclear energy in a planned
manner and to ensure the democratic administration of nuclear energy policy. (The AEC wastransferred to the Cabinet Office in January 2001.)
The AEC has duties of planning, deliberation, and decisions concerning the research, development andutilization of nuclear energy (excluding matters relating to regulations on ensuring safety).
8-7

If the AEC deems it necessary as a part of its assigned duties, it may advise by way of the Prime
Minister, and request reports and cooperation including
the submission of materials, statement ofviews, and explanation from the heads of relevant administrative organizations.
The Minister of METI, before issuing an establishment license for nuclear installations, shall receive
views of the AEC with regard to the following items: (1) the nuclear installations will not be used forany purposes other than peaceful purposes, (2) the license will cause no hindrance to the planneddevelopment or utilization of nuclear energy, and (3) the applicant has an adequate financial basis toconstruct and maintain the nuclear installations.
The AEC is composed of the chairman and four other commissioners appointed by the Prime Ministerwith the consent of the Diet.

8.7 Other Administrative Bodies
Establishment of nuclear installations necessitates the compliance with the other laws such as the Fire
Protection Law and the Port Regulation Law therefore the relevant safety regulations are conducted by
the relevant government offices e.g. the Fire Protection Agency and the Ministry of National Land andTransportation.

8-8

Table 8-1 Assigned Duties of the Divisions Related to Safety Regulation of Nuclear Installations(including nuclear fuel cycle facilities), NISA, METI
Policy Planning and
Coordination Division- Planning and coordination concerning the general policyof the NISA

- Activities for public hearing and public relations
concerning the nuclear safety
Nuclear Safety Public- Administration of the Nuclear Safety Inspectors and Senior
Relations and Training
Specialists for Nuclear Emergency Preparedness
Division- Training and education of personnel to gain and to improvetheir competency- Planning and coordination concerning technology andNuclear Safety Regulatory system to ensure the nuclear safety
Standard Division- Regulation of nuclear power reactors in the stage of
research and development, etc.
Nuclear Safety Special
Investigation Division- Management of allegation and litigation concerning
nuclear safety

Nuclear Power
Licensing Division- Regulation of commercial power reactors in the design andconstruction stage

Nuclear PowerInspection Division- Regulation of commercial power reactors in the operation
stage

Nuclear Fuel Transportand Storage Regulation
Division- Regulation of spent nuclear fuel storage business- Regulation concerning transportation of nuclear fuelmaterials from sites

Nuclear Fuel Cycle
Regulation Division- Regulation concerning businesses of refining, processing,fabrication, spent-fuel storage, and reprocessing.

Radioactive Waste
Regulation Division- Regulation of radioactive waste business, and dismantlingand decommissioning of nuclear installations including
nuclear fuel cycle facilities

Nuclear Emergency
Preparedness Division- Planning of nuclear emergency preparedness- Prevention and investigation of incidents andaccidents in nuclear businesses- Administration of activities in nuclear emergency- Matters concerning physical protection

Electric Power Safety
Division- Regulation of turbine etc.
- Environmental impact assessment

8-9

Table 8-2 Organization of the Nuclear and Industrial Safety Subcommittee, ACNRE
Basic Safety Policy
Subcommittee
Nuclear Reactor Safety
Subcommittee
Nuclear Fuel Cycle Safety
Subcommittee
Decommissioning Safety
Subcommittee
Radioactive Wastes Safety
Subcommittee
Seismic and Structural Design
Subcommittee
Nuclear Emergency
Preparedness Subcommittee
INES Evaluation Subcommittee
Subcommittee for the Convention
on Nuclear Safety
Electrical Power Safety
Subcommittee
Study Group on the Way ofInspection
Subcommittee for the Joint
Convention on Radioactive Wasteand Spent Fuel Safety
Subcommittee for the Institution of
Nuclear Safety Regulation- General matters securing safety- Technical matters on commercial power reactors andpower reactors at the stage of research anddevelopment- Fabrication and reprocessing of nuclear fuel, storage ofspent fuel, transportation of nuclear fuel material, andthe technical standards- Decommissioning of nuclear installations*- Securing safety of disposal and storage of radioactive
wastes- Technical matters on seismic safety and structural
integrity of nuclear installations*- Measures for incidents and failure, and general crisis
managementforemergencies
of
nuclearinstallations*and physical protection of nuclear
material- INES Evaluation on incidents and accidents of nuclear
installations*- Matters related to the Convention on Nuclear Safety andinternational standards on nuclear safety- Securing safety of electrical power- Matters concerning inspection system of nuclear power
generation facilities and nuclear fuel cycle facilities- Matters related to the Convention on Joint Convention
Radioactive Waste and Spent Fuel Safety- Study of the legal system for the prevention offalsification of the self-controlled inspection record
based on the investigation of the background of thefalsification

Study of the followings, in the case where a plant has
cracks in a core shroud or reactor coolant re-circulation
system piping:
Subcommittee for(1) Verification of validity in the check methods for core
fitness-for-service assessment etc.
shroud etc.
of nuclear power system(2) Technical fitness-for-service assessment· judgment
method(3) Fitness-for-service verification etc. of individual plant
based on check result specifically*: Including nuclear fuel cycle facilities

8-10

Table 8-3 Committees, etc. under the NSC
Committee on Examinationof Reactor Safety
Committee on Examinationof Nuclear Fuel Safety
Emergency TechnicalAdvisory Body

- Matters concerning the safety of nuclear reactor facilities- Matters concerning the safety of nuclear fuel material- Technical advice in emergency measures in case of occurrence ofan accident or a failure that meet the given standard level innuclear installation etc.

Emergency TechnicalAdvisory Body for Disaster- Technical advices etc. for the emergency measures required in a
Prevention of Nuclear
case of actual or potential nuclear ship emergency
Carriers and Submarines
Special Committee for- Matters concerning safety standards and guides of reactors,
Nuclear Safety Standards andnuclear fuel facilities, and other nuclear installations
GuidesSpecial Committee onRadioactive Wastes andDecommissioning- Matters concerning the safety assurance in radioactive waste
disposal- Matters concerning the safety assurance in decommissioning of
nuclear installations

Special Committee on Safety- Establishment of safety goals
Goal
Special Committee on
Radiation Protection- Matters concerning the radiation protection considering domestic
and foreign trends.

Special Committee on Safe
Transport of Radioactive
Materials- Matters concerning the safety assurance in transportation ofradioactive materials considering domestic and foreign trends.

Special Committee on
Analysis and Evaluation of
Nuclear Accidents andFailures- Analysis and evaluation of domestic and foreign nuclear accidents
and failures

Special Committee on
Nuclear Safety Research- Planning of nuclear safety research program- Investigation of implementation status of the nuclear safety
research program- Evaluation of the nuclear safety research program

Special Committee on
Nuclear Disaster- The emergency preparedness in the vicinity of nuclear
installations, etc.

Task Force for introductionof Safety Regulations Using
Risk Information- Review and analysis of the issue in introduction of safety
regulations using risk information

Project Team on Safety
Survey of Reprocessing
Facilities
Safety Investigation on
Disposal of Specified
Radioactive Wastes- The survey and analysis on the matters considered in the safety
regulation activities during the stage of test operation of the
Rokkasho reprocessing facility- Technical matters concerning the safety assurance in the final
disposal of high-level radioactive wastes

8-11Administrative Organization for Supervision and Auditing of Regulatory Activities
ChairmanAtomic Energy
Commission*
Prime Minister

Cabinet Office

Chairman
Nuclear Safety
Commission*

General Affairs Division
Regulatory Guides andReview Division

Secretary-General* Established in accordance with the Law for
Establishment of the Atomic Energy
Commission and the Nuclear Safety Commission

Administrative Organization for Regulatory Activities

Radiation Protection and
Accident Management
Division
Subsequent Regulation
Review Division

Policy Planning and
Coordination Division
Nuclear Safety Public Relations
and Training Division
Nuclear Safety Regulatory
Standard Division

Minister
Ministry of Economy,
Trade and Industry

Nuclear Safety Special
Investigation Division

Director-General
Nuclear and Industrial
Safety Agency- Director-General for Nuclear
and Industrial Safety Policy,- Deputy Directors-General,- Deputy Director-General for
Safety Examination(Established in accordance with the
Ministry of Economy, Trade andIndustry Establishment Law.)

Nuclear Power Inspection
Division
Nuclear Fuel Cycle
Regulation Division
Nuclear Fuel transport andStorage Regulation Division
Radioactive Waste Regulation
Division
Nuclear Emergency
Preparedness Division

Incorporated Administrative Agency, Japan

Electric Power Safety
Division

Nuclear Energy Safety Organization

Nuclear Safety Inspectors(Established in accordance with the General Rules for
Incorporated Administrative Agency and the Law for
Incorporated Administrative Agency, Japan Nuclear Energy
Safety Organization.)Fig. 8-1

Nuclear Power Licensing
Division(Located in 17sities of the Nuclear
Power Plants)

The Outline of the Safety Administrative Organization for Nuclear
Installations (including Nuclear Fuel Cycle)

8-12Tomari Nuclear Safety Inspectors Office
Unit 1 & 2 <PWR> (In operation), & Unit 3 <PWR> (Under construction)
Tomari NPS, Hokkaido Electric Power Co., Inc
Kashiwazaki-kariwa Nuclear Safety Inspectors Office
Unit 1, 2, 3, 4 & 5 <BWR>), & Unit 6 & 7 <ABWR> (In operation)
Kashiwazaki-kariwa NPS, Tokyo Electric Power Co., Inc
Sapporo-city

Shika Nuclear Safety Inspectors Office
Unit 1 <BWR> (In operation), & Unit 2 <BWR> (Under construction)
Shika NPS, Hokuriku Electric Power Co., Inc

Higashidoori Nuclear Safety Inspectors Office

Tsuruga Nuclear Safety Inspectors Office
Unit 1 <BWR> (In operation) & Unit 2 <PWR> (In operation)
Tsuruga NPS, The Japan Atomic Power, Inc.
Fugen <ATR> (Under decommissioning setup) & Monju <FBR>(Under construction, First Criticality Attained)
Japan Nuclear Cycle Development Institute

Unit 1, <BWR> (Under construction),
Higashidoori NPS, Tohoku Electric Power Co., Inc.

Mihama Nuclear Safety Inspectors
Unit 1, 2 & 3 <PWR> (In operation),
Mihma PS, The Kansai Electric Power Co., Inc

8-13

Sendai- city
Ohi Nuclear Safety Inspectors Office
Unit 1, 2, 3, & 4 <PWR> (In operation),
Ohi PS, The Kansai Electric Power Co., Inc

Niigata- city
Fukushima- city

Takahama Nuclear Safety Inspectors Office
Unit 1, 2, 3, & 4 <PWR> (In operation),
Takahama PS, The Kansai Electric Power Co., Inc
Shimane Nuclear Safety Inspectors Office
Unit 1 & 2 <BWR> (In operation),
Shimane NPS, Chugoku Electric Power Co., Inc

Kanazawa- city
Mito-city
Fukui- city
Matsue- city
Shizuoka-city

Genkai Nuclear Safety Inspectors Office
Unit 1, 2, 3, & 4 <PWR> (In operation),
Genkai NPS, Kyushu Electric Power Co., Inc

Fukushima Daiichi Nuclear Safety Inspectors Office
Unit 1, 2, 3, 4, 5, & 6 <BWR> (In operation),
Fukushima Daiichi NPS, Tokyo Electric Power Co., Inc.
Fukushima Daini Nuclear Safety Inspectors Office
Unit 1, 2, 3, & 4 <BWR> (In operation),
Fukushima Daini NPS, The Japan Atomic Power, Inc.
Tokai & Oharai Nuclear Safety Inspectors Office<GCR> (Under decommissioning), Tokai PS &<BWR> (In operation), Tokai Daini PS
The Japan Atomic Power, Co.

Hamaoka Nuclear Safety Inspectors Office
Unit 1, 2, 3 & 4 <BWR> (In operation),& Unit 5 (Under construction, First Criticality Attained)
Hamaoka NPS, Chubu Electric Power Co., Inc

Matsuyama-city
Saga-city

Sendai Nuclear Safety Inspectors Office
Unit 1 & 2 <PWR> (In operation),
Sendai NPS, Kyushu Electric Power Co., Inc

Onagawa Nuclear Safety Inspectors Office
Unit 1, 2 & 3 <BWR> (In operation),
Onagawa NPS, Tohoku Electric Power Co., Inc.

Ikata Nuclear Safety Inspectors Office
Unit 1, 2 & 3 <PWR> (In operation),
Ikata NPS, Shikoku Electric Power Co., Inc
Kagoshima-city

Fig. 8-2 Establishment of Nuclear Safety Inspectors
Offices
As of August 31, 2004
8-13

Article 9

Responsibility of the Licensee

Each Contracting Party shall ensure that prime responsibility for the safety of a nuclear
installation rests with the holder of the relevant licence and shall take the appropriate steps toensure that each such licence holder meets its responsibility.
The prime responsibility for the safety of a nuclear installation rests with the licence holder, and the regulatory
body establishes relevant regulation to ensure the public safety, and supervises that the licence holder complies
with the regulation.
After the previous report, the amendment of the Rules for the Reactor Regulation Law clarified the licenceholder’s responsibility on quality assurance and maintenance management, and established the Licensee’s
Periodic Inspection and the Periodic Safety Management Review.

9.1 Regulatory measures for the licence holder to take the prime responsibility for the safety of
nuclear installations.
The prime responsibility for the safety of a nuclear installation rests with the licence holder, and thelicence holder shall comply with the regulatory requirements in each stage from planning throughoperation, which are stipulated in the Reactor Regulation Law, the Electricity Utilities Industry Law,etc. Those regulatory requirements are described in the report of Article 7.
The Licence holders activities concerning Education and Training of Operational Personnel etc.
(Article 11), Performance of quality assurance activities (Article 13), Periodic Safety Review (Article
14), Aging Management Review (Article 14), Emergency Preparedness (Article 16), Design andConstruction (Article 18), and Operation (Article 19) are described in the report of the respective
article. The licence holder is continuously making efforts for improving the safety and reliability of its
nuclear installations, as well as meeting with regulatory requirements, through training the personnel,
preparing operation manuals, collecting, studying and sharing information on operating experiences
and applying it to design, operation and maintenance, adopting the latest progress in technologies,
performing the safety research, promoting quality assurance activities, and preparing accident
management.

9.2 Supervision of Licence Holders by Regulatory Body
The basic mechanism to ensure the safety of nuclear installations is that NISA issues license, orders
the licensee to bear the prime responsibility for safety, and supervises it within the legislative andadministrative framework.
The following is an overview of the above mentioned mechanism.
(1) Licensing
The Minister of METI issues a license for the establishment of a nuclear installation after examiningthat the nuclear installation will not be used except for the peaceful purposes, that there is no potential
obstacle for accomplishing the planned development of atomic energy, that technical capability andfinancial foundations of licence holders are sufficient, and that the site, the structure and the equipmentof the nuclear installation may not cause any hindrance to the prevention of nuclear disaster. The
regulation under the Reactor Regulation Law and the Electricity Utilities Industry Law in each stage
from planning through operation is described in section 7.3.

9-1

(2) Licensee’s Periodic Inspection and Periodic Safety Management Review
The Electricity Utilities Industry Law, as amended, stipulates that the licence holder shall perform the
Licensee’s Periodic Inspection replacing former self-controlled inspection, confirm the results tocomply with the technical standards, and record the results. JNES conducts the Periodic Safety
Management Review including review on the organization for implementing the Licensee’s Periodic
Inspection, etc., and reports the review results to NISA. NISA evaluates the review results and informthe licence holder of its conclusion.
(3) Nuclear Safety Inspection and Nuclear Safety Inspector
In accordance with the Reactor Regulation Law, NISA stations the Nuclear Safety Inspectors at eachnuclear installation, who conducts the Nuclear Safety Inspection four times a year to confirm thelicence holder’s compliance with the Operational Safety Program, and addresses incidents if theyoccur.
(4) Quality Assurance Activities and Maintenance Management Activities
In accordance with the ordinance based on the Reactor Regulation Law, the licence holder shallestablish quality assurance system and maintenance management system, and include them in the
Operational Safety Program. NISA confirms the compliance with the Operational Safety Program
through the Nuclear Safety Inspection.
(5) The Senior Specialist for Nuclear Emergency
In accordance with the Special Law for Nuclear Emergency, NISA stations Senior Specialist for
Nuclear Emergency at each site of nuclear installations, who guides and advises the licence holder in
preparing the Licensee’s Plan for Emergency Preparedness, and conducts duties necessary to prevent
nuclear emergency and mitigate the consequence should it occur.
(6) Periodic Safety Review
By the amendment of the ordinance based on the Reactor Regulation Law, the Periodic Safety Review
is integrated into the Operational Safety Program.
(7) Aging Management Review
By the amendment of the ordinance based on the Reactor Regulation Law, the licence holder shall takemeasures for aging management, not later than thirty years after the commencement, to perform
technical review on aging for the safety-related equipment and structures, and to establish the
Ten-Year Maintenance Program. Measures for aging management are integrated into the Operational
Safety Program, the compliance with which should be inspected by inspectors of NISA. Ten years
Program must be revised every ten years.
(8) Accident Management
The licence holder prepares accident management program according to “Accident Management as a
Measure for Severe Accident at Light Water Nuclear Power Reactor Facilities”, a decision by the NSC,
1992, (partly revised by the NSC, 1997) and submits it to NISA for review. NISA reviews andevaluates the technical adequacy of it.
(9) Report
In accordance with the Reactor Regulation Law and the Electricity Utilities Industry Law, the licenceholder shall report to NISA on their business.
9-2

(10) On-the-Spot Inspection
NISA conducts on-the-spot inspection, if necessary, at the plants, offices, etc. of licence holder or its
contractor, in accordance with the Reactor Regulation Law or the Electricity Utilities Industry Law(11) Revocation of License, etc.
Judging that the licence holder violated regulation, the Minister of METI may take measures ofenforcement such as revocation of the license, suspension of operation, fine, etc., in accordance with
the Reactor Regulation Law or the Electricity Utilities Industry Law

9-3

C. General Safety Considerations

Article 10 Priority to Safety
Each Contracting Party shall take the appropriate steps to ensure that all organizations engagedin activities directly related to nuclear facilities shall establish policies that give due priority tonuclear safety.
The development and utilization of the nuclear energy have been promoted giving due priority to safety inaccordance with the Atomic Energy Basic Law.
The JCO criticality accident in 1999, etc. showed importance of moral and safety culture in the organization,and resulted in the introduction of the Nuclear Safety Inspection and the Allegation System.
However, the TEPCO falsification issue showed, again, that negligence of priority to safety among personnel
gave rise to organizational falsification, and led to the renovation of the safety regulation by the NSC and NISA.
In the renovated regulation, they clarify requirements for the license holder’s quality assurance activities
including organization, management, etc., urging the license holder to establish robust safety culture. The
license holder is intensifying efforts to respond to it.

10.1 Basic Policy for Priority to Safety
Priority to safety is a basic policy in all nuclear energy development and utilization in Japan. The
Article 2 of the Atomic Energy Basic Law states that priority should be given to ensure safety in all
related activities (Annex 3.1). Also, The Article 1 of the Nuclear Regulation Law states that “this law,in accordance with the Atomic Energy Basic Law, is enacted for the purposes of providing necessary
regulations on the establishment and operation of reactors, and uses of atomic energy are limited topeaceful purposes and carried out in a planned manner, and at the same time, to ensure the public
safety by preventing the hazards due to these materials and reactors.”
10.2 Efforts for Improvement in Safety Culture
Safety culture in organization is so vital to ensure safety of the nuclear installation, that the lack ofsafety culture there may result in serious consequence. Each of the regulatory body and the license
holder takes various efforts to enhance safety culture.
(1) Efforts by the Regulatory Bodies
The regulatory body requests the license holder to comply strictly with the regulatory requirements forthe quality assurance, urging, at the same time, license holder’s top management to implement quality
management and to take appropriate steps for robust safety culture to prevail among its personnel.
For this purpose, NISA established the regulatory requirements on the quality assurance. Details ofthem are given in the report of Article 13.
Some of regulatory activities to enhance safety culture are shown below.
1) The NSC and NISA have attended, and contributed to, various international meetings orcommittees on safety culture of the IAEA, the OECD/NEA, etc., and collected and studied foreign
examples of good practice on safety culture.
2) The NSC has promoted interdisciplinary and comprehensive study on safety culture, by collecting
operating personnel’s opinion on it, publishing booklets on it, analyzing mechanism to enhance it,colleting good practices on it in other industry, and analyzing characteristics of Japanese safety
culture. Since July 2001, the NSC held 21 dialogue meetings on good practices and existing tasks
on safety culture with operating personnel of nuclear power plants and other nuclear facilities, thereport of which was published in January 2004.

10-1

3) NISA held advisory meetings on safety culture attended by experts including experts from otherindustries, and clarified tasks of the nuclear business operator, tasks of the regulatory body andtasks to be discussed with the public.
4) As an attempt for the regulatory body to monitor and quantify level of safety culture of license
holder, JNES prepared review items on safety culture referring to ASCOT Guidelines of the IAEA,
ISO9001, etc. on April 2004, and has been examining adequacy of them by applying them to foreignand domestic incidents.
(2) Efforts by Nuclear Industry
1) Efforts by Nuclear Industry
The Japan Atomic Industrial Forum Inc., consisting of about 800 business operators (electricity
utilities, reactor manufacturers, etc.) who are engaged in the nuclear business, published astatement entitled "Toward Reform of Japan’s Private Nuclear Industry" on October 8, 1999,
being triggered by the JCO Criticality Accident. That says;− Top management should establish policies that give due priority to safety, andmake safety culture prevail over whole company.
− Top management of each division in a company should clarify scope of duty andresponsibility of each staff, ensure compliance with rules and standards, andperform comprehensive review including preparedness for abnormal situation.
− Top management of each division should strengthen audit function by inviting
managers of other divisions or experts out of the company.
---The rest is omitted--In December 1999, 36 nuclear business operators such as utilities, fuel fabricators, plant
manufacturers, and research organizations united and founded the "Nuclear Safety Network (NSnetwork)" for sharing and improving the nuclear safety culture. Activities of the Network wereintensified by the revelation of the TEPCO falsification issue, and are shown in the followings.
a. Activities to Disseminate Safety Culture−−−

Holding several levels of seminars on nuclear safety for top management andsenior management.
Holding lecture meetings for member companies on corporate ethics by outside
experts.
Continuation of public relations campaigns on nuclear safety and safety culture
with cooperation of other related organizations.

b. Peer Review Activities−−

Peer review guide was revised to integrate lessons learned from the TEPCO
falsification issue.
Improvement of peer review process by inviting experts from outside.

c. Collecting, Sharing and Dispatching Information−−−

Information on nuclear safety and safety culture is extensively collected frommember companies using questionnaire, and shared among them. Items on
corporate ethics are recently added to the questionnaire reflecting the TEPCO
falsification issue,
Information is supplied to the public through Internet.
Information is dispatched overseas positively.
10-2

The Federation of Electric Power Companies, to restore public confidence lost by the TEPCO
falsification issue, established the Confidence Recovery Committee consisting of presidents of all
utility companies in October 2002, and revised the "Action Guideline of Federation of ElectricPower Companies" in December 2002, stressing compliance with regulation and corporate
ethics.
Recognizing importance of transparency in disclosing accidents and failures including minor
events, license holders established public information library “NUCIA” on the Internet to collectand disseminate information on nuclear power station including information on accidents andfailures, and started the operation in October 2003. Fig. 10-1 shows the practical use ofoperation and maintenance information by license holders.
2) Efforts by Each License Holder
Tokyo Electric Power Co., taking a series of falsification issue seriously, is now implementing
various preventive measures against recurrence in three areas, that is, quality assurance,
corporate ethics and safety culture. Measures in the area of safety culture include followings;− Requests personnel to comply with the corporate charter and the president’s
message calling for priority to safety.
− Establishes an organization that promotes safety culture.
− Establishes a forum where management of nuclear power plant discloses
information on plant operation to the local residents, ensuring transparency.
Other license holders, also, have publicly declared, in its annual management plan, a policy togive priority to safety in operation of nuclear power stations, and are implementing the similar
measure to that of TEPCO.
Every license holder has established a nuclear safety planning committee at its head officereporting directly to the director of the nuclear power generation department, and a nuclear safety
steering committee at each site chaired by the head of the power station. The former reviews
license application documents and alteration of the Operational Safety Program, etc., and thelatter reviews the operation management procedure, educational plan on safety, etc. In thesecommittees, information on incidents of domestic and foreign plants are shared and transferred,and implementation plan on the periodic inspection, preventive maintenance, education andtraining programs for employees, and QA activities are discussed and promoted.
The Federation of Electric Power Companies provides a forum for exchange and study of
information on domestic and foreign operational experiences and of measures for improvement,in addition to direct information exchange among persons in charge. Also, the electric powercompanies are engaged in international information exchange on operating experience throughthe Institute of Nuclear Power Operations (INPO), the World Association of Nuclear Operators(WANO), etc.
Nuclear manufacturers propose to utilities application of new technologies, and items for
improvement on safety and work procedures, while utilities propose items for improvement basedon operating experiences to manufacturers.
Some utilities have established institutes for research on safety culture and human factors. For
example, the Kansai Electric Power Co., has established Institute of Nuclear Safety System, Inc.
in 1992, and the research activities on the safety culture, etc. in nuclear power stations arecarried on.
Central Research Institute of Electric Power Industry is carrying on research on human factors
and safety culture.

10-3

Fig. 10-1 Use of Operation and Maintenance Information
by License Holders
D Company
C Company
B Company
A Company• Faults discovered
during the periodic
inspection

Measuresbased on the feedbackof information fromother companies• Measures forpreventive
maintenance

SafetySignificant(Regulatory Req.)
Safety Related(Quality Information)
Others(Non safety)

Implement necessary measures

10-4

Maintenancebased on the normal
maintenance program

Evaluation

Report to theGovernment

Operation and maintenance information
Abnormal events
during operation
Patrol and check(power surge, steam
during normal operation
leak, water leak, etc.)

Each company announces
officially through presses orhomepages.

Official
announcement
Official
announcement

Each company
determines
the scope of official
announcement(with considerations
for the local public)A
A
Measures required

Analysis and
Evaluation

Obtain information of other companies(share among license holders)

NUCIA database

Domestic Information
Foreign Information(WANO, INPO, NRC, Venders etc.)

WANO: World Association of Nuclear Operators
INPO: Institute of Nuclear Power Operations
NRC: Nuclear Regulatory Commission, USA

10-4

Sharing and public presentation of
the registered information on
troubles subject to the regulatoryand quality information

Article 11 Financial and Human Resources
1. Each Contracting Party shall take the appropriate steps to ensure that adequate financial
resources are available to support the safety of each nuclear facility throughout its life.
2. Each Contracting Party shall take the appropriate steps to ensure that sufficient numbers ofqualified staff with appropriate education, training and retraining are available for all
safety-related activities in or for each nuclear facility, throughout its life.
The financial basis of nuclear industry rests on the understanding and recognition that nuclear energy is theenvironmentally clean energy and reliable source for base load power, against the backdrop of deregulation ofelectricity utilities industry including that of power rates.
Although license holders have worked hard to comply with regulatory requirements on the appointment of Chief
Engineers of Reactors, Persons Responsible for Operation, Chief Electrical Engineers, etc., they now face tasksof succession of technology, recruitment and training of personnel in various fields, etc.

11.1 Financial Resources of the License Holder(1) Confirmation at Issuing License
Before issuing license of a nuclear facility, the Minister of METI, in accordance with Article 24(Criteria for the license) of the Reactor Regulation Law, confirms that the applicant for the license
possesses necessary financial basis by requiring the applicant to submit “Amount of Funds Required
for Construction and Finance Procurement Plan”, and also consults with the AEC. (Refer to the section
7.3(2) and Fig. 7-3)
(2) Applicant for the License of Nuclear Facilities
Applicants for license of commercial power reactors are the General Electric Utilities, that is, 9
electric power companies and 2 wholesale electric power companies. The Minister of METI issues
license for electricity utility business only to those meeting certain criteria of financial basis, technicalcompetence, etc. The licensing system of electricity utilities business and the recognition that nuclear
energy is a clean and reliable source ensures license holders sound financial basis.
METI enacted the Ministerial Order of Reserve Fund for Dismantling Nuclear Power Facilities, inaccordance with the provisions of Article 35 of the Electricity Utilities Industry Law. Electric utilities
deposit reserves for decommissioning on the basis of this order. They also deposit reserves covering
final disposal of vitrified wastes and other wastes resulting from reprocessing of spent fuels. The
deposit is reserved in financial accounts of the Nuclear Waste Management Organization of Japan, an
implementing organization for disposal, founded by the Law for Final Disposal of Specified
Radioactive Waste enacted in June 2000.
The JNC, who owns R&D reactors of Monju and Fugen, is established by a law, and financial basis
necessary for its business operation is provided by the national budget.
11.2 Human Resources of the License Holder(1) Confirmation of Technical Competence
Before issuing license of a nuclear facility, the Minister of METI confirms that the applicant possesses
technical competence necessary to establish a nuclear facility and operate it adequately, and consultswith the NSC. The NSC had established the “Regulatory Guide for Reviewing Technical Competenceof a Nuclear Operator” on May, 2004 in order to improve objectiveness and rationality of reviewing.
In this regulatory guide, the follows are provided as fundamental requirements for licensing related tohuman resources that should be satisfied by an applicant;11-1

-Securing engineers,-Education and training for engineers,-Designation and arrangement of qualified personnel.
The license holders are responsible for safety of the decommissioning and for preparing personnel forit. They implement technical development programs on decommissioning in cooperation with national
research institutes, manufacturers and construction companies, and have trained and secured humanresources through studying decommissioning activities abroad and participating in the project ofdecommissioning the Tokai Power Station of the Japan Atomic Power Company.
(2) Qualification, Training and Retraining of Personnel Engaged in Safety Activities
1) Staff Qualification
The license holder shall appoint a Chief Engineer of Reactors to supervise safety operation of
nuclear facility, a Chief Electrical Engineer and a Chief Engineer of Boiler and Turbine tosupervise safety during construction, operation and maintenance of electric structures. The license
holder assign the Persons Responsible for Operation from those who have knowledge, skills, andexperience required for nuclear reactor operation, and who satisfy the standards provided by the
Minister of METI. The Persons Responsible for Operation supervise operators in the control
room of a power plant.
Table 11-1 shows numbers of qualified personnel in nuclear facilities in Japan.
NISA is considering to establish a qualifying system of specialist for ultrasonic flaw detection,
which is necessary for the application of the Rules on Fitness-for-Service for Nuclear Power
Plant Components.
2) Staff Training and Retraining, and Resources for Training
License holders shall integrate safety education programs of personnel in charge of operation andmanagement of a nuclear facility into the Operational Safety Program, and prepare and carry out
long-term and short-term staff training programs to maintain and improve their capabilities.
License holders, in addition to in-house operator training course using simulators (Table 11-2),
periodically send their operators to external operation training centers for retraining. There are
two centers: the BWR Operation Training Center (BTC) for BWRs and the Nuclear Power
Training Center (NTC) for PWRs. A curriculum suitable for the ability/skill of each operator isprepared in these training centers.
Each license holders has established maintenance training centers (Table 11-3) for education andtraining of maintenance personnel. Various mock-up devices, inspection devices and training
devices, etc, simulating plant facilities for training purposes, have been used to maintain andimprove the knowledge, skills and work management capabilities of personnel involved inmaintenance and inspection.
11.3 Efforts for Ensuring Infrastructure of Human Resources in Japan
Nuclear regulatory bodies and nuclear power industry are making efforts for ensuring nuclear experts
now and in the future. Status after the previous reporting is as follows:(1) Training of Experts in NISA
Staff members, who are in charge of nuclear regulation in NISA, are the Senior Specialist for Nuclear
Emergency, the Nuclear Safety Inspector, the Nuclear Facility Inspector, the Electric Structure
Inspector, and the Safety Examiner. These are called "Nuclear Regulatory Staff" as shown below.
11-2

A Senior Specialist for Nuclear Emergency is stationed at each nuclear installation, guides andadvises the license holder in preparing its Plan for Emergency Preparedness, and conducts duties
necessary to prevent progression of nuclear emergency should it occur.
A Nuclear Safety Inspector is stationed at each nuclear installation, conducts the Nuclear Safety
Inspection to confirm license holder’s compliance with the Operational Safety Program, addressincidents if they occur, and supervises operation management of a nuclear installation.
A Nuclear Facility Inspector and /or an Electric Structure Inspector is dispatched from NISA head
office, and conducts inspection activities, such as the Pre-Service Inspection and the Periodic
Inspection of a nuclear installation, and the Fuel Assembly Inspection, on the basis of the Reactor
Regulation Law or the Electricity Utilities Industry Law, respectively.
Safety Examiners conduct the Safety Examination of a nuclear installation.
A Nuclear Regulatory Staff is required to have expertise in nuclear technology. The system of longterm and multistage education and training programs necessary for improvement of his/her expertise isdeveloped, taking account of his/her experience and of the nature of the facility to which he/she isassigned. Moreover, NISA started a Special Training Course on Quality Assurance of Nuclear
Installation in 2002. Summary of training for nuclear safety regulation is shown in Fig. 11-1.
NISA has appointed six Special Inspection Instructors in December 2003. They advise inspectors for
the Nuclear Safety Inspection, the Periodic Inspection, etc. in each power station, instruct them toequalize the levels of inspections, and collect opinions and proposals from inspectors and license
holders at the same time.
Furthermore, NISA maintains and develops its regulatory competence, as well as contributes tointernational safety regulation, through exchange of technical experts and information on safety
regulation and safety technology, under bilateral arrangements with foreign regulatory bodies and in
the framework of multilateral cooperation (the IAEA and the OECD/NEA).
(2) Training of Experts in JNESJNES, as well as NISA, develops training courses for its personnel, putting emphasis on inspection
activities.
JNES’s inspection activities include the Electric Structure Inspection, the Nuclear Facility Inspection,
the Welding Inspection, the Periodic Safety Management Review, the Welding Safety Management
Review, the Safety Verification of Disposal Facility, the Safety Verification of Radioactive Waste
Package, the Verification of Transportation Packaging, and the Verification of Transportation Method.
The Electricity Utilities Industry Law or the Reactor Regulation Law stipulates that each of these
activities be conducted by qualified personnel. JNES prepares various training courses for staff
members to get appropriate qualification in their respective activities. President of JNES assigns
inspectors from those qualified persons.
Moreover, JNES encourages inspectors and examiners to participate in the school of external bodies,scientific seminars, etc. to enhance their expertise.
(3) Efforts by Nuclear Industry
Confronting shrinking and aging population of Japan, the nuclear industry has grave concerns in the
succession of technology, expertise and experiences, and the generational gap. The first generation
experts are in the age of retirement. Each organization in the industry has made various efforts
including revitalization of research and development activity, practical use of IT technology, etc. The
11-3

Japan Atomic Industrial Forum, Inc. established the "Subcommittee for Human Resources" consistingof senior managers in the industry and experts from outside, and studied on human resources in the
future.
The subcommittee has made the following proposals in June 2003:
Training and career development of experts,− Establishment of an industry’s qualification system of nuclear maintenance and repair
technicians− Simplification of organizations of maintenance work
− Establishment of an engineering center to share resources of maintenance and repair
technicians, and to share common training facilities
Recruitment of expert in the future,− Establishment of a nuclear educational system, sharing common educational
infrastructure(4) Efforts by University and Research Institutes
Tokyo University is due to establish a graduate school, in 2005, consisting of three courses of the“Nuclear Engineering Specialist Course”, the “International Engineering Course”, and the“Innovation of Nuclear Energy Course”.
Since 1958, JAERI has been operating training courses for engineers and technicians in radioisotope,
radiation and nuclear technologies. Recently, JAERI started a course for nuclear emergency
preparedness in close cooperation with national and local governments.
(5) Establishment of Professional Engineers System for Nuclear and Radiation Technologies
The Ministry of Education, Culture, Sports, Science and Technology decided to expand the existing
Professional Engineers System, and established the nuclear and radiation technology department.
Qualification test for the department will start in 2004 fiscal year.
The Nuclear and Industrial Safety Subcommittee of the Advisory Committee for Energy andResources published, in July, 2001, a report titled "To Ensure Infrastructure of Nuclear Safety", whichsuggests directions to strengthen the institutional infrastructure, the knowledge-based infrastructure
and the infrastructure of human resources.

11-4

Table 11-1 Numbers of Qualified Persons in License Holders(As of the end of June 2004)
Type of Qualification

Numbers of Qualified Persons

Chief Engineer of Reactors

581

Class I Electrical Chief Engineer

181

Class I Boiler and Turbine Chief

334

EngineerClass

I

Supervisorof

Radiation

1375

ResponsibleforOperation

372

Protection

Person(Note)(Note)
System of the Person Responsible for Operation was changed into the assignment by thelicense holders based on the standards of a Ministry of METI from the qualification by theconventional designated agency in August, 2001.

11-5

Table 11-2

Organization

Operator Training Facilities of Nuclear Facilities

Location

Simulator

BWR Operator Training Okuma-machi, Futaba-gun, Fukushima Prefecture
Center Corp.
Kariwa Village, Kariwa-gun, Niigata Prefecture

Full scale;
Full scale;

3units2unitsNuclear Power Training Tsuruga, Fukui Prefecture
Center Ltd

Full scale;

3unitsThe Japan Atomic Power The Japan Atomic Power Company Training Compact; 1unit
Co., Inc.
Center (Tokai Village)
On site of Tsuruga Power Station
Compact
2unitsThe Hokkaido Electric On site of Tomari Power Station
Full scale; 1unit
Power Co., Inc.
Tohoku Electric Power Nuclear Power Engineering Training Center (on Full scale; 1unit
Co., Inc.
site of Onagawa Nuclear Power Station)
Nuclear Power Engineering Training Center (on Full scale; 1unit
site of Higashidori Nuclear Power Station)
Tokyo Electric Power On site of Fukushima Daiichi Nuclear Power Full scale; 1unit
Co., Inc.
StationFull scale; 1unit
On site of Fukushima Daini Nuclear Power Station Full scale; 1unit
On site of Kashiwazaki Kariwa Nuclear Power
StationChubu Electric Power Nuclear Power Training Center (on site of Full scale; 2units
Co., Inc.
Hamaoka Nuclear Power Station)
Hokuriku Electric Power Nuclear Power Engineering Training Center
Full scale; 1unit
Co., Inc.
(on site of Shika Nuclear Power Station)
The
KansaiElectric On site of Mihama Power Station
Compact; 1unit
Power Co., Inc.
On site of Takahama Power Station
Compact; 1unit
On site of Ohi Power Station
Compact; 1unit
The Chugoku Electric Ohno Training Center (Ohno-machi)
Power Co., Inc.
Shikoku Electric Power Nuclear Engineering Training Center (Matsuyama)Co., Inc.
On site of Ikata Power Station

Full scale;

1unit

Full scale;

1unit

Kyushu Electric Power Nuclear Power Training Center (on site of Genkai
Co., Inc.
Nuclear Power Station)
Nuclear Power Training Center (on site of Sendai
Nuclear Power Station)
Japan Nuclear Cycle
On site of Fugen Power station
Development InstituteOn site of Monju Construction Office

Full scale;

1unit

Full scale;

1unit

Compact; 1unit
Full scale; 1unit(As of the end of June, 2004)

11-6

Table 11-3 Maintenance and Repair Training Centers of License Holders

Reactor Establisher
The
Japan
Power Co.

Name

Location

Atomic The
Japan
AtomicPower Tokai Village, Naka-gun, Ibaraki
Company Training Center
Prefecture

Hokkaido
Electric Nuclear Power Training Center
Power Co., Inc.

On site of Tomari Power Station

Tohoku Electric Power Nuclear
Power
Engineering On site of Onagawa Nuclear
Co., Inc.
Training Center
Power Station
Fukushima Nuclear Power Plant On site of Fukushima Daiichi
Tokyo Electric Power Training Center
Nuclear Power Station
Co., Inc.
Kashiwazaki kariwa Nuclear On site of Kashiwazaki Kariwa
Power plant Training Center
Nuclear Power Station
Chubu Electric Power Nuclear Power Training CenterOn site of Hamaoka Nuclear
Co., Inc.
Power Station
Hokuriku Electric Power Nuclear
Power
Engineering On site of Shika Nuclear Power
Co., Inc.
Training Center
StationThe Kansai Electric Nuclear
Power
Maintenance Takahama-cho, Ohi-gun, Fukui
Power Co., Inc.
Training Center
Prefecture
The Chugoku Electric Shimane Nuclear Power Station
On site of Shimane Nuclear PowerPower Co., Inc.
Engineering Training Center
StationShikoku Electric Power Nuclear Engineering Training Matsuyama City, Ehime PrefectureCo., Inc.
CenterGenkai Nuclear Power Station On site of Genkai Nuclear Power
Kyushu Electric Power Nuclear Power Training Center
StationCo., Inc.
Sendai Nuclear Power Station On site of Sendai Nuclear Power
Nuclear Power Training Center
StationGeneral Training Facility for FBR On
Nuclear fuel cycle
siteofInternational
Development
Cycle
Engineering center
Organization

11-7

Fig. 11-1 Training on Nuclear-Safety Regulation
Training on nuclear safety regulation
Nuclear fuel cycle facility

R&D stage reactor

Commercial power reactor-Risk communication training for managers

Cross-cutting training- Public-relations training for Nuclear Safety Inspectors

Nuclear emergency preparedness,
Crisis management- Quality Assurance training for managers

Meister
Senior expert

11-8- Nuclear emergency preparedness,
Advanced- Nuclear emergency preparedness,on-site training- Off-site center desk-top drill- Emergency preparedness and- Nuclear power generation (BWR,- Nuclear power generation (FBR)
responseforexperts
PWR) for experts- Off-site center management- Inspection technique for inspectors - FBR sodium technical training- Off-site center functional groupt i i
Nuclearemergency preparedness,- Special training course on QA of nuclear installation- Special training course on QA of nuclear installation,
Basic
Follow up- Nuclear officers training

Expert- Nuclear Safety Inspector basic training-Electric Structure Inspector(nuclear power) training- Nuclear Facility Inspector basic training-Nuclear power station risk assessment technology-Nuclear reactor safety design, basic- Overseas training
Entry- Radiation safety- Basic Safety Regulation-Participation to the various basic lectures by the Japan Atomic Energy Research Institute11-8

Article 12 Human Factors
Each Contracting Party shall take the appropriate steps to ensure that the capabilities andlimitations of human performance are taken into account throughout the life of a nuclear
installation.
The license holder takes human factors into consideration at the design stage of nuclear installation, and, at theoperation stage, prepares operational procedures, education and training course for its personnel and the
management system for operation and maintenance. The regulatory body also takes various steps for prevention
and remediation of human errors at design and operation stage.

12.1 Efforts by Regulatory Body
(1) Design Stage1) The Regulatory Guide for Reviewing Safety Design requires that "reactor facilities be designed
to reflect appropriate preventive considerations against operators’ miss-operation", and its
explanatory document requires that “In designing, attention should be given in consideration ofergonomics-oriented factors, to panel layout, operability of operating devices, valves, etc.,
instrument and alarm indication for accurate and quick recognition of reactor status and preventionof errors during maintenance and inspection.” and that “In designing, measures should be taken sothat necessary safety function is maintained without operator’s actions for a certain length after theoccurrence of an abnormal condition.”
The guide also requires that “Control room be designed that the situation of operations andprincipal parameters of reactor and principal related facilities can be monitored and that prompt
manual control can be performed, whenever required, to maintain safety.” In conformity to theserequirements, the Regulatory Guide for Reviewing Safety Assessment requires that “safety
analysis be performed in consideration of the following: In case that operator actions are expected
at the occurrence of abnormal situations, sufficient time and adequate information be available sothat operator may be able to properly judge the situations and take necessary acts with a highdegree of confidence.”
JNES prepared a manual for evaluation of human factors in the main control room, to confirm thatthese requirements are reflected in the design.
2) At the Approval of Construction Plan, the Technical Standards under the Electric Utilities
Industry Law request that the main equipment necessary for safe operation of nuclear installation
can be monitored at a glance and necessary actions can be taken in the control room.
(2) Operation Stage1) The Reactor Regulation Law provides that the license holder prepare the Operational Safety
Program, obtain approval of NISA on it and comply with it. The program includes preparation ofoperation management system, education program on safety, operational procedures etc. NISA
confirms and approves the Operational Safety Program, and the resident Nuclear Safety Inspectors
confirm the compliance with it by the license holder in the Nuclear Safety Inspection.
2) The license holder reports failures of the installation to NISA in accordance with the laws.
Especially, in the case that the failures are identified to be caused by human errors, the license
holder reports to NISA measures addressing failures including improvement of equipment. NISA
consults on the failure with experts when necessary and urges license holders to apply lessons
learned to other installations. JNES analyses human error-related cases in detail, and selects items
to be reflected in the safety regulations. JNES prepares a summary report on lessons learned, andaccumulates them in the database.
12-1

12.2 Efforts by License Holders(1) Considerations in Design
License holders take following considerations on human factors in designing central control room.
1) Considerations for operator actions
Central control room is designed so that operating conditions of the reactor and other importantequipment and principal plant parameters can be monitored at a glance and necessary actions canbe taken in the room during normal operation and abnormal transients, and in accidents.
For example, the control panel adopted in the advanced BWR, ABWR, has fully digitalized
instrument and control system and safety protection system (see Fig. 12-1). The advanced control
panel makes it easy for operator to recognize operating conditions at a glance and to share
information among operators by adopting a large-size display panel. The scope of automation is
expanded, reducing routine operation by operator following a reactor scram. These measures have
improved the reliability of monitoring and operator actions. The fully digitalized main control
panel is also adopted for PWR (see Fig.12-2)
Remodeling control panel in the central control room of an existing nuclear installation, extensive
use of CRT improves monitoring capability and operability of control panel.
2) Considerations on the control room
Following measures are taken to prevent operator’s human errors.
− Control panels allow monitoring of the whole of main systems of the installation, andthe layout provides easy access for operation.
− Operating devices are easily discernible by colors, shapes, name plate, etc., and are laidout in proximity of related indicators, avoiding human errors in operation, maintenanceand checks.
− The alarm labels clearly indicate content of alarm, and important alarms are discernible
from others by color, layout, etc.
− Instruments are laid out so that related plant parameters may be monitored easily.
− Monitoring capacity can be improved by CRT display and clearly discernible alarmindicators.
− Information sharing among operators is improved by adopting large display panels.

Fig. 12-1 Main Control Panel of ABWR

Fig. 12-2 Main Control Panel of theLatest PWR -proto type-

12-2

A design guide for digitalized main control panels is in preparation as one of the academic
society and association standards named “Guide for Human Machine Interface of ComputerizedCentral Control Rooms for Nuclear Power Plants” by the Japan Electric Association.
(2) Considerations in Operation Management
License holders perform appropriate operation management during normal operation and in accidents.
1) Operational management
a. Organizations for operation
The manager of power generation division, responsible for the operation of a nuclear
installation, controls operating shifts in charge of the operation and their supporting groups.
The shift supervisors have authority and responsibilities to take measures required in an
accident, and are selected from those who conform to the criterion specified by the Minister of
METI.
b. Shift of operators
Operators work in shifts. There are shifts devoted to education and training, in addition tooperating shifts, to maintain and improve operator’s capability. The education and training ofoperators is one of the important elements of human factors. Details are described in Section
11.2.
When turning over shift duties, the shift supervisor makes sure to pass on the logbook, thesupervisor logbook, keys, and precise description of operations to the succeeding supervisor.
Each operating staff also transfers information of plant operation to the succeeding operating
staff.
2) Preparation and amendment of operation procedures
Operation procedures are prepared for normal operation, failures and accidents and are constantly
amended by lessons learned from incidents and accidents or by alteration of facilities.
Symptom-based procedures for multiple failures are prepared in addition to scenario-based
procedures for design basis events. The symptom-based procedures enable prevention of accident
progression without identifying the cause of an accident. Also prepared are the procedures
addressing severe accidents exceeding design basis events, and accident management guidelines
for the staff group supporting shift operators. The effectiveness of these procedures is verified bycomparison with the results of the analysis of plant transient by the analysis code used in theapplication for establishment license, and probabilistic safety assessment. Training course using
simulator, based on a symptom-based procedure, is conducted at the operator training facility.
Preparation of the procedures for emergency situation is expected to be effective for mitigation ofoperators’ stress in an emergency.
3) Maintenance Management System
The maintenance department of a license holder controls the work of periodic inspection,
modification works, etc. of a nuclear installation carried out by the plant manufacturer and many
affiliated companies. A majority of human errors in the past occurred in the works associated withmaintenance and repair, which means that the maintenance management by the license holder isvery important.
The plant manager of a nuclear installation manages modification works, clarifying scope of work,
scope of responsibility and authority. Maintenance of important equipment is carried out with a
12-3

prior mock-up test.
Chief engineers (Chief Engineer of Reactors, Chief Electrical Engineer, Chief Engineer of Boiler
and Turbine) perform verification and assessment of regulatory inspections by attending theregulatory inspections or confirming inspection records. They also perform verification andassessment, as appropriate, of the plans and results of regular checks or modification works toprevent human errors in maintenance and management works.

12-4

Article 13 Quality Assurance
Each Contracting Party shall take the appropriate steps to ensure that quality assurance
program are established and implemented with a view to providing confidence that specified
requirements for all activities important to nuclear safety are satisfied throughout the operating
life of a nuclear installation.
The regulatory body (NISA), license holders, plant manufacturers and equipment suppliers (hereinafter referred
to as “manufacturers”), conduct quality assurance (hereinafter referred to as “QA”) activities for nuclear
installations in a coordinated way at each stage from design through operation and maintenance.
The basic concept of regulatory inspection has been continually renovated, seeking for more effective andefficient inspection activities, and in line with international trend in regulatory inspection. It has moved from a
concept of system and component inspection to a concept where NISA encourages license holders to improvetheir QA activities and confirms the adequacy of them. A series of wrongdoings by license holders andmanufacturers, such as the TEPCO falsification issue, falsification of fuel assembly inspection results, improper
construction work at a spent fuel reprocessing facility, revealed the importance of transparency of license
holder’s QA activities and of regulatory supervision on them. In view of the circumstances, NISA accelerated its
regulatory renovation and the NSC reviewed the regulation concerning QA activities for safe operation andpresented its views and opinions to NISA.
After the previous reporting, NISA clarified regulatory requirement for QA. NISA encouraged establishment of
academic society and association standards in conformity to international standards and reviewed theirtechnical adequacy and license holders apply newly established academic society and association standards totheir QA activities.

13.1 Regulatory Requirements for QA of Nuclear Installation
NISA conducts regulatory activities from design stage to operation stage, such as issuance of license,
approval of construction plan, inspection of equipment, etc., on the basis of the Reactor Regulation
Law and the Electricity Utility Industry Law.
The Reactor Regulation Law stipulates that quality assurance system should be established and be
included in the Operational Safety Program, the compliance with which should be confirmed in the
Nuclear Safety Inspection.
The aim of the mechanism mentioned above is for license holders to establish comprehensive andsystematic QA programs, to implement them and to carry out their accountability to the public torestore confidence of the public.
The key points of QA activities are; a) to involve top management, b) to be based on international
standards on QA (ISO9001:2000), c) to improve them by Plan-Do-Check-Act cycle, and d) to establish
an independent audit organization.
The Reactor Regulation Law stipulates that license holder’s QA program should include a)organization governing the performance of QA, b) plan of activities for safe operation, c)
implementation of activities for safe operation, d) evaluation of activities for safe operation, and e)
improvement of activities for safe operation.
Note) The term, activities for safe operation, means activities necessary to maintain safety, inmaintenance work of facilities, operation of reactors, and transportation, storage and management of
nuclear fuel materials or materials contaminated by nuclear fuel materials.
License holders prepare their QA program of the nuclear facilities and implement them, according to
JEAC 4111-2003, “Rules of Quality Assurance for Safety of Nuclear Power Plants” established by
JEA in autumn of 2003 based on the ISO9001:2000. NISA evaluated the rules and accepted them as
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the standards to meet the regulatory requirements.
The contents of JEAC4111-2003 are shown in Table 13-1.
13.2 Confirmation of QA by Regulatory Body
NISA requires applicant for license, or license holder, of a nuclear installation to submit appropriate
QA program, and confirms implementation of QA program as follows:(1) Examination of Basic Policy for QA activities at Reactor Establishment
NISA requires the applicant to submit the “Policy for Quality Assurance” attached to the application
document at safety examination for establishment license of a nuclear installation,(2) Examination of QA Program in Construction StageAt examining the construction plan, NISA requires the license holder to submit the “Description on
QA Program” which the license holder would carry out through design, manufacturing, installationand functional tests. NISA confirms that the license holder has prepared appropriate procedure to audit
subcontractor’s quality control, material control, etc. as well as those of the primary contractor.
(3) Confirmation of QA of Fuel Assembly
NISA requests license holders of fuel assembly fabrication to submit application document for fuelassembly design approval, which describes performance, strength, and flow sheet of fabrication
process, etc. of fuel assemblies, and to submit an explanatory document on QA attached to it. When
conducting the Fuel Assembly Inspection, the inspector of NISA confirms not only the license holder’s
test results but also license holder’s test procedure.
For imported fuel assembly, NISA requests the license holder of reactor to submit the description of
QA program.
(4) Confirmation of QA Activities throughout Operating LifeNISA confirms QA activities of license holders throughout the operating life of nuclear installations asfollows:− Description of QA activities in the Operational Safety Program− Confirmation of compliance of the Operational Safety Program in the Nuclear Safety
Inspection
During outage of nuclear facilities, NISA and JNES, in the Periodic Safety Management Review,
confirms that the Licensee’s Periodic Inspection is performed appropriately.
13.3 Implementation and Assessment of QA Program by License Holders
Outline of QA activities by license holders is as follows;(1) Establishment of QA Program
License holder prepares QA program in accordance with JEAC4111-2003, and implement QA
activities based on it. These programs cover document control, design control, procurement control,
management of inspection and testing, nonconformity management, and audit, etc. The license holder
submits the “Policy for QA” and “Description on QA Program” to NISA as described in section 13.2
(1) through (4).

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(2) QA Activities in Design, Construction, Commissioning, Operation and Maintenance
QA activities are carried out by many organizations. The license holder clarifies the scope andresponsibility of the manufacturer in QA activities, and entrust it with QA activities in its scope. In thesame way, the manufacturer entrust its subcontractors with QA activities in their scope.
(3) QA Audit
JEAC 4111-2003 defines that QA system of manufacturers undergoes prior review and inspection bylicense holder.
The license holder audits manufacturer’s QA activities. The license holder performs an independent
in-house QA audit by departments other than nuclear department reporting directly to top
management. The independent internal QA audit started, learning lessons from the steam generator
tube rupture accident at Mihama Power Station, Unit 2 in 1991.
The manufacturer audits subcontractors’ QA activities in addition to its own internal audit of QA
activities.

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Table 13-1 Contents of JEAC4111-2003, “Rules of Quality Assurance for Safety of Nuclear Power
Plants”

0. Introduction
1. Objective
2. Scope of Application
3. Definition
4. Quality Management System
5. Responsibility of Management
6. Management of Resources
7. Planning and Implementation of Job
8. Evaluation and Improvement

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Article 14

Assessment and Verification of Safety

Each Contracting Party shall take the appropriate steps to ensure that:(i)comprehensive and systematic safety assessments are carried out before theconstruction and commissioning of a nuclear installation and throughout its life. Suchassessments shall be well documented, subsequently updated in the light of operating
experience and significant new safety information, and reviewed under the authority of
the regulatory body;(ii) verification by analysis, surveillance, testing and inspection is carried out to ensure thatthe physical state and the operation of a nuclear installation continue to be inaccordance with its design, applicable national safety requirements, and operational
limits and conditions.
Regulatory body (NISA) and licence holders perform and record the assessment and verification of the safety of
nuclear installations in accordance with the legislative framework, at each stage of planning, establishment,
construction, and operation of nuclear facilities. Necessary regulatory guides are enacted and utilized forassessment and verification of each stage. The audit type inspection is introduced to review the implementing
system for the inspection conducted by licence holders at the operation stage.
In recent years, the probabilistic safety assessment methodology has been developed as a supplement to theconventional deterministic safety evaluation, and the resulted risk information are used in regulatory activities
such as the development of accident management, and the Periodic Safety Review (PSR) in Japan. Also
introduction of the safety goals that define the acceptable risk levels are under development.
The legislative framework required for assessment and verification of the safety is described in the Article 7th .

14.1 Assessment and Verification of Safety prior to Construction
The applicant for a license to establish a commercial power reactor submits a license application
document to NISA pursuant to the Reactor Regulation Law.
NISA examines whether the application conform to the licensing criteria prescribed in the Reactor
Regulation Law.
The outlines of the safety assessment submitted for Establishment Licence and regulatory criteria aredescribed below.
(1) Documents for Establishment License
An application for establishing a commercial power reactor consists of a main text and attacheddocuments detailing safety design, safety analysis, siting assessment, etc. in accordance with theprovisions of the Reactor Regulation Law and the related legislation. The application document
describes basic design with sufficient information for examining the safety.
(2) Safety Assessment and Acceptance Criteria
1) Siting Assessment
The siting assessment of a commercial power reactor is conducted pursuant to the Regulatory
Guide for Reviewing Nuclear Reactor Siting Evaluation and Application Criteria. The Guideline
requires that a) there have as yet been no event (natural disaster) in the past liable to induce large
accident and no such event is expected to occur in the future, b) in relation to its engineered14-1

safety features, nuclear reactors shall be located at a sufficient distance from the public, and c)
the environment of the nuclear reactor site including its immediate proximity shall be such thatappropriate measures for the public can be implemented as required.
2) Safety Assessment
In the safety examination conducted by NISA, it is verified that basic design or design concept of
the commercial power reactor applied conforms to Regulatory Guide for Reviewing Safety
Design of Light Water Nuclear Power Reactor Facilities (hereinafter called, the Regulatory
Guide for Safety Design), and the safety is discussed and evaluated as a whole in accordancewith the provisions of Regulatory Guide for Reviewing Safety Assessment of Light Water
Nuclear Power Reactor Facilities (hereinafter called, the Regulatory Guide for Safety
Assessment.).
The Regulatory Guide for Safety Design requires that the basic policy of the safety design forcommercial power reactors should be established, and structures, systems and components ofnuclear reactor facilities should perform the required functions not only in the normal operation
condition but also in the assumed abnormal situation to ensure the safety. Specifically, twopostulated event categories of "anticipated transients during operation" and "accidents" aredefined and the safety during these events is evaluated based on the Regulatory Guide for Safety
Assessment. The definition of event categories is almost the same as that of the nuclear safety
standards (NUSS) of the IAEA.
Applicants to install nuclear reactors perform safety analysis on these postulated events andproves the adequacy of the safety design of the plant referring the results to the acceptancecriteria.
And, NISA examines the results of analysis performed by applicants to install nuclear reactors
and if necessary confirms the adequacy receiving the report concerning independent analysis
results performed by JNES. Selections of postulated events and their evaluations are as follows.
Single failures and erroneous operation for each system and component are identified as events
to be postulated in the safety evaluation, and the representatives of events leading to similarconsequences in transients but with the severest results are selected. These postulated events areclassified into anticipated transients during operation or accidents through their probability andconsequence as described in the Regulatory Guide for Safety Assessment, and the safety isevaluated in accordance with the defined acceptance criteria according to the classification.
a)

Anticipated Transients During Operation.
Anticipated transients during operation are those events that may be caused by a single
failure or malfunction of component or a single erroneous operation by the operator during
the life of commercial power reactors, or events that result in abnormal conditions causedby external disturbances expected to generate in the same degree of frequency of those.
Fourteen events for Pressurized Water Reactors (PWRs) and twelve events for Boiling
Water Reactors (BWRs) are specified as events to be evaluated. In the analysis of these
events, the adequacy of the safety design of such important safety systems as reactor
protection system, reactor shutdown system, etc. are confirmed through verifying the
integrity of reactor core and reactor coolant pressure boundaries based on the acceptancecriteria provided in the Regulatory Guide for Safety Assessment.

b) Accidents
Accidents are events more serious and less frequent than anticipated transients during
operation, which have to be postulated for the potential of releasing radioactive substances
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from a commercial power reactor that should be evaluated. Ten events for PWR and nine
events for BWR are selected as events to be evaluated. In the analysis of these events, theadequacy of the safety design of engineering safety features is confirmed by verifying that
there would be no significant damage to the core, that reactor containment boundaries
would remain sound, and that there would be no significant risk of radiation exposure to the
public in the vicinity based on the acceptance criteria provided in the Regulatory Guide for
Safety Assessment.
Among the accidents, loss of coolant accident is analyzed and evaluated according to theRegulatory Guide for Safety Assessment and the Regulatory Guide for Evaluating
Emergency Core Cooling System Performance of Light Water Power Reactors, andreactivity insertion accident is analyzed and evaluated according to the Regulatory Guide
for Safety Assessment and the Regulatory Guide for Evaluationg Reactivity Insertion
Events of Light Water Nuclear Power Reactor Facilities.
The Minister of Economy Trade and Industry consults the Nuclear Safety Commission in order to hear
the opinion about the results of examination, and the Nuclear Safety Commission deliberates whether
there is some problems for preventing radiological hazards or not, etc., and implements the public
hearing to evaluate the public opinion.

14.2 Assessment and Verification of Safety Prior to the Commissioning
The licence holder of reactor establishment shall develop a construction plan for establishment ofelectric structures, and shall obtain the approval of NISA before starting construction inaccordance with the Electricity Utilities Industry Law. After obtaining the approval of
construction plan, he shall undergo the pre-service inspection by NISA at the every process and at
the completion of construction. For fuel assemblies to be loaded into the nuclear reactor, he shallobtain the design approval and undergo the fuel assembly inspection by NISA. For the welding ofpressurized parts, containments, etc., the licence holder of reactor establishment shall conduct the
Licensee's Welding Inspection, and shall undergo review of the implementation system
concerning Licensee's Welding Inspection (Welding Safety Management Review) performed by
JNES.
Verification of the safety for the approval of construction plan, of fuel assembly design and
Welding Safety Management Review are described in the followings.
(1) Verification of Safety at Approval of Construction Plan, and Pre-service Inspection
The licence holder shall develop a construction plan for establishment of electric structures, and shallobtain the approval of NISA after obtaining the establishment license and before starting constructionin accordance with the Electricity Utilities Industry Law. NISA will review to confirm that thedetailed design of electric structures is not contradictory in the basic design or fundamental design
policies of the establishment licensing stage, and is not nonconforming with the technical standards inaccordance with the Electricity Utilities Industry Law for the approval of construction plan concerned.
Licence holders, after receiving the Approval of Construction Plan, undergoes Pre-Service Inspection
by NISA at each construction stage and at the completion of all construction works, to verify that theconstruction is completed in accordance with the Approval of Construction Plan and is notnonconforming with the technical standards. The Pre-Service Inspections includes those inspections
on structure, strength or leak-tightness of each component and these inspections on function andperformance of overall system of commercial power reactor. Details are shown in Table 14-1. The
inspection at the time of the criticality and the completion of construction works in the table areso-called commissioning tests. From October 2003, JNES conduct a part of the above mentioned
Pre-Service Inspection.
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(2) Verification of safety through the Approval of Fuel Assembly Design and the Fuel Assembly
Inspection
A person who intends to use fuel assembly undergoes the Fuel Assembly Inspection, pursuant to theElectricity Utilities Industry Law, after receiving the Approval of Fuel Assembly Design. NISA, in
issuing the approval, verifies that the proposed fuel design takes into consideration of thermal
conditions, radiation conditions, corrosion resistance, corresponding to operating conditions, and thatit maintains sufficient strength through the years in service. NISA confirms in inspection thatfabrication of fuel assemblies is performed in accordance to the approved design and technicalstandards. The Fuel Assembly Inspection is also required for the replacement fuel, regardless ofwhether or not there have been design changes From October 2003, JNES conduct a part of the above
mentioned Fuel Assembly Inspection.
Imported fuel assemblies are also required to undergo and pass the Fuel Assembly Inspection by
NISA.
(3) Verification of Safety through Welding Safety Management Review
The licence holder performs Licensee's Welding Inspection on welded pressurized parts and weldedcontainment, and the management system of Licensee's Welding Inspection undergoes the review by
JNES.

14.3 Assessment and Verification of Safety during Operating Life TimeThe licence holder obtains the approval of Operational Safety Program before commissioning, andperform the periodical safety assessment, and investigation of an accident or a failure and measures
to prevent the recurrence, and undergoes the spot entry inspection conducted by NISA/JNES at any
time in addition to the Nuclear Safety Inspection, the Periodic Inspection, and the Periodic Safety
Management Review during the operating lifetime, so that the comprehensive confirmation of thesafety of commercial power reactors is performed.
Confirmation of the safety by inspection and periodical evaluation of the safety are described in thefollowings:(1) Verification of the Safety by Inspection
NISA has set-up resident Nuclear Safety Inspectors at nuclear reactor facilities and performs four
inspections per year (Nuclear Safety Inspection) on the observance of Operational Safety Program inaccordance with the Reactor Regulation Law to recognize the status of compliance to various
regulations for the safety and the status of the activities for safe operation performed by the licenceholder. In accordance with the Electricity Utilities Industry Law, NISA and JNES perform the Periodic
Inspection of structures and components important to the safety in the time interval that does notexceed 13 months after the day of commissioning or the day of last Periodic Inspection ended,
The inspections which was conducted by the licence holder as self-controlled inspection previously
was redefined by the amendment in the Electricity Utilities Industry Law as a Licensee’s Periodic
Inspection, and JNES performs the audit type inspection (Periodic Safety Management Review) toreview the implementing system, planning and management of Licensee’s Periodic Inspection.
(2) Periodic Safety Assessment
In accordance with the Reactor Regulation Law, NISA decided in October 2003 to request
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the

licence holder for the implementation of "Periodic Safety Review (PSR)" in every 10 years interval
after the first review at the time not exceeding ten years after commissioning, and for the
implementation of "Aging Management Review" by the day passing 30 years after commissioning.
1) Periodic Safety Review (PSR)
PSR is the effort by the licence holder to evaluate his activities for-safe operation that has been
carried out since the commissioning of the plant. PSR is performed in every about ten years andfor the purpose to acquire the prospect for the plant concerned be able to continue the safe
operation in the next decade with maintaining the high level of performance equivalent to thenewest nuclear power plant.
PSR had been carried out since 1992 by the licence holder in accordance with the request of the
Ministry of International Trade and Industry (old Ministry of Economy, Trade and Industry), but
NISA decided that it is necessary to clarify the position of the Periodic Safety Review as a part ofrenovation of nuclear safety regulations.
For this purpose, the provisions of "Periodic Assessment of Nuclear Reactor Facilities" wasadded in October 2003 to the Ordinance of the MITI, No. 77, 1978, the Rules for the Installation,
Operation, etc. of Commercial Power Reactors (hereinafter called, the Rules for Commercial
Power Reactors), and the implementation of PSR was defined as one of the requirement in the
Operation Safety Program
Since compliance to Operational Safety Program is confirmed by Nuclear Safety Inspection, it ispossible for NISA to confirm that the licence holder is properly implementing the activities forsafe operation in every about ten years through PSR in "the Periodic Assessment of Nuclear
Reactor Facilities", and to make request of improvement, if needed.
As items to be implemented at the PSR, a) evaluation of the situation of the activities for safe
operation of nuclear reactor facilities (comprehensive evaluation of operating experiences), b)
evaluation of the situation of reflection of the state of the art technical knowledge to activities forsafe operation (reflection of the newest technical knowledge) are defined. The probabilistic safetyassessment is not requested as obligation based on regulation, but required to the licence holder
as a self imposed activities to be implemented as used to be.
PSR was implemented for 40 times as to 34 units out of 52 units in operation as of June, 2004
PSR was implemented for second times to six units. (Refer to Table 14-2)2) Aging Management Review
The Ministry of International Trade and Industry (old Ministry of Economy, Trade and Industry)evaluated the Measures for Aging Management implemented by the licence holder in February
1999 for the nuclear reactors with 30 years after commissioning, and documented in the report,"Evaluation of the Measures for Aging Management for Nuclear Power Stations, and Future
Activities on the Aging Management"
In October 2003, NISA added the Aging Management Review in the provisions of "Periodic
Evaluation of Nuclear Reactor Facilities" to "the Rules for the Commercial Power Reactors" andprovided as one of the requirement in the Operational Safety Program to implement Measures
for Aging Management.
Aging Management Review to be implemented at the time within 30 years after commissioning,are:a) analyze the impacts of technically conceivable aging phenomena on structures andcomponents of nuclear power stations with safety functions, and technically evaluate the
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possibility for prevention of the loss of function of the components and structures due toaging phenomena under the present maintenance activities provided to them,b) extract new maintenance measures from the technical evaluation results to make a planof ten-year maintenance program.
c) re-evaluate this ten-year maintenance program with ten-year interval
NISA requested licence holders to report the newly extracted maintenance measures in theten-year maintenance program of "Measures for Aging Management" to reflect the results on
inspections, such as the Periodic Inspection, as necessary. Licence holders should materialize
methods of maintenance management, frequency and time, etc. of the maintenance measures into
ten-year maintenance program. Licence holders should implement those in accordance withOperational Safety Program.
Since the "Measures for Aging Management" was defined as a requirement of the regulation,
more rational and standardized Measures for Aging Management will be investigated and will be
provided as academic and association standards etc. in the future based on recipe to aging inabroad and on the latest knowledge.
NISA evaluates the technical evaluation and ten-year maintenance program conducted by licenceholders with the incorporation of the of specialists’ opinion, as well as the lessens learned fromoperating experiences in and outside Japan and the latest knowledge, and experimental results.
Technical evaluation and planning of the ten-year maintenance program in relation with theaging were implemented for nine out of fifty-two units as of June 2004. (See to Table 14-3)

14.4 Probabilistic Approach in Regulation(1) Prior to Construction
1) Acceptance Criteria in Safety Examination−−

Consideration of Fall of an Airplane
In the safety examination of reactor establishment licensing, the necessity to consider thefall of an airplane to the reactor facility design as "a human induced external event"should be determined. The probability of an airplane fall to the reactor facility isevaluated as the determining criteria. NISA enacted "on the Assessment Standard on the
Airplane Fall Probability to a Nuclear Power Reactor Facility" as a regulatory guide in
July 2002.
Impact Assessment of the Turbine Missile
In the safety examination of reactor establishment licensing, the necessity to consider theturbine missile to the reactor facility design as "a missile generated inside the reactor
facility to be assumed" should be determined. The probability of damage to the reactor
facility (the coolant pressure boundary in the containment and the spent fuel pool) is
evaluated as the determining criteria.

(2) Prior to Commissioning
1) Assessment of the Effectiveness of Accident Management Measures
The licence holders implemented PSA for nuclear power reactors under operation or construction
to evaluate the integrity of the core and the containment in a case of the severe accident, andutilized it for assessment of the effectiveness of their accident management measures. Internal
events during operation were subject to their analysis, and the results were utilized to extract
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accident management measures and to evaluate their effectiveness.
(3) During the Operating Lifetime
1) Safety Assessment through the Periodic Safety Review(PSR)
As one of the activities of PSR the licence holders implemented PSA for internal events during
power operation using the newest data, and the results were utilized for the assessment of safety
features of the nuclear reactor facilities and verification of the effectiveness of the accident
management measures. PSA for internal events during the shutdown conditions was additionallyimplemented through the PSR in 2001 and afterwards.
2) Assessment of Allowed Out of Service Times (AOT) defined in Operational Safety Program
The operational restriction of the engineered safety system and the permissible time of recovery
at the time of the standby exceptions (Allowed Out of Service Times (AOT)) are to be set up in
the Operational Safety Program. On this matter, the Nuclear Power Engineering Corporation(predecessor of JNES) had developed and proposed standard techniques as evaluation methods
on the adequacy of AOT, referring mainly to the U.S Standard Technical Specifications (STS)and taking account of the components failure rates in Japan also.
3) The Impact Assessment and Evaluation of the Measures Taken to Pipe Rupture Accident in the
Unit-1 of Hamaoka NPS
In the study on the measures to prevent recurrence of the pipe rupture accident occurred in
November 2001 on the steam condensing line (SCL) of the residual heat removal system (RHRS)of the Unit 1 of Hamaoka NPS, the PSA with considerations of the pipe break accident
specifically to SCL of RHRS, was implemented on core integrity and it was evaluated that thepipe rupture of the accident concerned does not significantly increase the risk. It was also
evaluated that several proposed measures were effective in reducing the risk.

14.5 Introduction of Safety Goals
The NSC has issued regulatory guides and standards required for the examination in administrative
steps to ensure the prevention of radiation hazards and the public safety. These standards andregulatory guides provided the basis of design, construction, and operation of the facility necessary to
restrict the risk on the public, to a sufficiently low level. However, except the Regulatory Guide for the
Annual Dose Target for the Public in the Vicinity of Light Water Nuclear Power Reactor Facilities,
there were no guidelines that define quantitative objectives for acceptable to the public.
As development on PSA methodology to quantify the risk levels of nuclear power plants has
progressed, the NSC started discussions on safety goals and issued a report on Interim Safety Goals in
December 2003. The report discusses the objectives, scope and draft of the interim safety goals andissues to be investigated further.
The outline of the draft safety goals are as follows.
(1) Concerned Activities for Utilization of Nuclear Energy
The safety goal should be established for all activities in the utilization of nuclear energy that may
have the adverse influence of radiation exposure on the public. Application of the established safety
goal should be with considerations of the maturity of risk assessment models and the characteristics ofeach risk in each activity area. And the established safety goal should not be uniformly applied to all
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activities.
(2) Structure of Safety Goal
The safety goal consists of two fold. One is the qualitative goal, which is a acceptable level of danger(risk) of an accident that nuclear operators (licence holders) must observe under the nuclear safety
regulations. The other is the quantitative goal that specifies the numerical value corresponding to theacceptable level of the risk. In this context, the risk during normal operation of nuclear power reactor
facilities, for which the numerical guideline of dose limits is specified, is excluded.
Since indicators of the qualitative goal is important to show the safety level, it is desirable to be
objective and common to all risks accompanied to various activities, in which the possibility of healthdamage is not fully excluded.
Therefore, the individual mortality of the pubic should be used as the indicator to meet theserequirements. And the events to be concerned that may have effects on the quantitative goal are bothinternal events such as failure of components and human error, and external events such as
earthquakes, tsunamis, and fall of an airplane. But, intentional and artificial events such as
destructive activity against an industry are excluded.
The mean values that could be obtained by evaluating the magnitude of the uncertainty will be used asa general rule for the comparison of quantitative goal or the performance goal of nuclear installations
to be developed in the future to the results of risk-assessment.
(3) Contents of the Draft of the Safety Goal
The draft of the safety goal is as follows:
1) the Qualitative Goal
The possibility of health damage to the public by emission of radiation or release of radioactive
materials accompanied with activities for utilization of nuclear energy should not meaningfullyincrease the risk of damage to the health of the public in daily life.
2) the Quantitative Goal
The mean value of acute fatality risk by radiation exposure resulting from an accident of a
nuclear installation to individuals of the public, who habit in the vicinity of the site boundary of a
nuclear installation, should not exceed the probability of about 1x10-6per year. And, the meanvalue of fatality risk by cancer caused by the radiation exposure resulting from an accident of a
nuclear installation of individuals of the public, who habit in the area in some distance from thenuclear installation, should not exceed the probability of approximately 1x10-6per year.
3) the Performance Goal for Each Area of Activities for Utilization of nuclear energy
It is reasonable to review and indicate the level that will be understood as the performance goal
to conform with the safety goal, according to the characteristics of each accident that could
occur at nuclear installations. As an example for nuclear reactor facilities, it is appropriate toreview the probability of occurrence of the severe core damage and the probability of occurrenceof a release event of significant amount of radioactive materials in a specific time period during
normal operation of nuclear reactor facilities.

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14.6 Activities for Introduction of the Safety Regulation with Utilization of Risk Information
In order to establish more effective and efficient regulatory system, utilization of risk information forsafety regulations has been progressing in each country, though the extent is different.
Also in Japan, the Nuclear Safety Commission decided in November 2003, “the Basic Policy on
Introduction of Nuclear Safety Regulation with Utilization of Risk Information”. This policy describesthat nuclear safety regulations with utilization of risk information will be as follows:− It is useful for enhancement of the rationality, consistency and transparency of the safety
regulation and for proper allocation of resources for activities of the safety regulation.
− It will evolve and advance the regulation, which has been based on the conventional
engineering judgment and deterministic evaluation, by utilizing risk information obtained fromquantitative and probabilistic assessment, while basically maintaining the concept ofdefense-in-depth.
− At this stage, it is appropriate to focus on a study on its introduction at the operation stage,and in the future, it will be aimed at to systematically study its introduction into the wholesafety assurance system that includes design and construction stage, taking into considerationsof the safety goals currently under study.
− For its introduction, it is important to ensure the reliability and transparency of the risk
assessment and to win its broad understanding of the general public.
And the NSC expects regulatory bodies and licence holders to perform the positive study on its
introduction into their concrete safety assurance and regulatory activities, and academic andindustrial societies and research organizations, etc. to prepare the voluntary consensus standards forrisk assessment and conduct the safety research on the risk assessment.
In response to the above-mentioned decision of the NSC, NISA announced in December 2003, “theStudy of the Nuclear Safety Regulation with Utilization of Risk Information”, and clarified theapproach, as the administrative authority of the regulation, to show how risk information will beutilized for the safety regulation from now on. The contents are as follows:(1) Fundamental Concept
The fundamental concept for the study of NISA on the concrete method for utilization of risk
information for the safety regulation is as follows. The study will be conducted with due deference tothe basic policy of the NSC and close exchange of opinions with the NSC.
−
−
−

−

The utilization of risk information will be studied, in principle for all stages such as siting,design, construction, operation, inspection and decommissioning, etc. of all nuclear facilities
under the regulatory responsibility of NISA.
By utilizing risk information, the subjects to be improved from now on will be found out fromall the systems and activities responsible for the safety regulation of NISA, and more effective
and efficient safety regulation will be realized.
However, since the significance and urgency of utilization of the risk information and thematurity of the methodology for risk assessment vary in each area and stage of utilization of
nuclear energy, the study will be initiated first from the area where the enhancement of theeffectiveness of safety regulation and the efficiency improvement with the regulatory resources
can be expected by utilization of risk information, as well as the area where the risk assessment
methodology has matured.
With these considerations, the immediate major subjects of the study will be nuclear power
plants among nuclear facilities, which have the utilization experience of the risk information.
The buildup of research results on PSA methodology, and operating experiences, and the area
where the risk information (such as frequency of core damage, its contributing factors and theuncertainty) obtained as a result of Level 1 PSA can be used.
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−

−
−

Taking into account the fact that the importance of inspection system has been pointed out fromthe falsification issues of licence holders, utilization of risk information in the inspection
system such as Periodic Inspection and Licensee’s Periodic Inspection shall be the first andforemost immediate subject.
Utilization of risk information shall be promoted conducting the adequate study and building
up sufficient experiences through a trial run (for example, pilot projects) etc. to find issues andresolve them, prior to its full-scale application.
It is required to normalize the standard PSA methodologies by academic and industrial
societies and perform PSA with those methodologies in advance of utilization of risk
information. While NISA cooperates with academic and industrial societies for review of PSA
methodologies, NISA will recommend licence holders to perform PSA with such standardized
methodologies.

(2) PSA Methodology and Preparation of Database
In order to use the methodology of probabilistic safety assessment (PSA) for the safety regulation, it isrequired to ensure the reliability and transparency of the methodology.
The maturity of the PSA methodologies varies depending on the subjects to be assessed. In the case of
nuclear power stations, the assessment of core damage frequency (level 1PSA) and the assessment ofreactor containment failure frequency and source term (level 2PSA), caused by components failure
due to internal events, have been almost established technically, and the standard methodology has
been already developed by the Nuclear Safety Research Association (foundational juridical person).
And currently the Atomic Energy Society of Japan (corporate juridical person) has been conducting
its review and standardization. The assessment methodologies for risk to the public health (level
3PSA) and external events such as earthquake have been developed, but not yet standardized byacademic and industrial societies. For facilities other than nuclear power stations, the methodologies
of PSA have been under developmental stage in many cases. For this reason, much more efforts todevelop and improve those methodologies are desirable.
From the standpoint of ensuring the reliability and the transparency of assessment methodologies, it isimportant that review of assessment methodologies are conducted by organizations such as academic
and industrial societies, and they are standardized under fair procedures. Currently, the Atomic
Energy Society of Japan has been performing the standardization of assessment methodologies underfair and neutral procedures including public review. While NISA participates in those activities ofacademic and industrial societies, it will further confirm the technical adequacy of the standardized
methodologies as the regulatory body and then apply them for the safety regulation. While doing that,
it is also necessary to clarify the applicable scope and limits of assessment methodologies, anduncertainties of analytical results, etc. and make the conditions clear to use those methodologies
properly.
Also for data of components failure rates to be used for PSA, it is necessary to ensure their adequacy
and reliability. Licence holders have been preparing database in the Central Research Institute ofElectric Power Industry, but the adequacy and reinforcement of domestic actual data concerningcommon cause failures and human factors, etc. are required, while the reliability of data is to bereviewed in fair and neutral channels such as academic and industrial societies.
In the study on utilization of risk information for the safety regulation, it is necessary to take into
consideration the preparation status of PSA methodologies and data.
(3) How to Proceed with the Study
From now on, NISA is going to steadily perform the study on the concrete methods for utilization ofrisk information for the safety regulation, and the study on the concrete methods for utilization of risk
information for inspections at nuclear power stations, which is the immediate top-priority subject, is to
14-10

be conducted by “Study Group on the Way of Inspection” set up under the Nuclear and Industrial
Safety Subcommittee.
It is necessary in conducting the study on utilization of risk information for safety regulation to makeefforts to get understanding of the general public at all levels, asking for public comments at theappropriate study stage and reflecting their opinions on the study, along with ensuring thetransparency of study process.

14-11

Table 14 - 1 Outline of Pre-Service Inspections
Time ofInspection(1) At the time of
installation ofeach structuresand components

Contents of Inspection
Test of structure, strength and/or leak tightness of reactor, reactor coolingsystem, instrumentation and control system, fuel handling system, radiation
management system, waste processing system or reactor containment structure is
performed, when each item has been installed and be ready to such testing.
Specifically, material inspection, structure inspection, pressurized leak test,
inspection on foundation and inspection on support structure are performed(2) At the time of
installation of
steam turbine andauxiliary boilers

Test of structures of steam turbine is performed when installation of bottom halfpart of turbine casing is completed.

(3) At the time offuel loading

When the reactor is ready for fuels to be loaded, inspections of systems aroundreactor, items required ensuring safety before fuel loading, and items for whichinspection would be difficult after fuel loading are performed.

Test of structure, strength and/or leakage on auxiliary boiler is performed when
its main part completed to assembly.

In the case of BWR, inspection of main steam bypass valves, inspection offunction and performance of those systems as control rod drive system, corespray system, residual heat removal system, etc. and functional inspections ofsafety protection system, etc. are performed.
(4) At the time ofcriticality

When the reactor reaches criticality, inspections are performed on nuclear
characteristics of reactor core, and function and performance of overall
commercial power reactor which can be performed only after fuel loading
In the case of BWR, an inspection to confirm shutdown margin at full fuelloading, inspections of control rod full stroke test, effective multiplication factor
at first criticality and moderator temperature coefficient tests are performed.

(5) At the time ofcompletion of
construction

When all construction work under the Construction Plan has been completed,inspections are performed on performance of systems around reactor, functions
and performances of overall commercial power reactor that can be confirmed
after fuel loading, and functions and performance of systems other than thosearound reactor.
In the case of BWR, inspections are performed on one control rod scram test,
loss of external power-supply test, generator load interception inspection, plant
trip inspections, load inspections.

14-12

Table 14-2 Periodic Safety Reviews Performed During the Reporting Period

The 8th Review (announced in August 2002)
Unit 3 of the Fukushima Daini NPS (Tokyo Electric Power Co., Inc.: BWR)
Unit 4 of the Fukushima Daini NPS (Tokyo Electric Power Co., Inc.: BWR)
Unit 1 of the Kashiwazaki-kariwa NPS (Tokyo Electric Power Co., Inc.: BWR)
Unit 3 of the Hamaoka NPS (The Chubu Electric Power Co., Inc.: BWR)
Unit 2 of the Shimane NPS (The Chugoku Electric Power Co., Inc.: BWR)
Unit 1 of the Sendai NPS (Kyushu Electric Power Co., Inc.: PWR)
Unit 2 of the Sendai NPS (Kyushu Electric Power Co., Inc.: PWR)
The 9th Review (announced in December 2003)
Unit 1 of the Takahama PS (The Kansai Electric Power Co., Inc.: PWR)
(the second time)
Unit 2 of the Takahama PS (The Kansai Electric Power Co., Inc.: PWR)
(the second time)
Unit 1 of the Shimane NPS (The Chugoku Electric Power Co., Inc.: BWR) (the second time)
Unit 1 of the Genkai NPS (Kyushu Electric Power Co., Inc.: PWR) (the second time)

Table 14-3 Implementation Status of Measures for Aging Management

The 1st Time (announced in February 1999)
Unit 1 of the Tsuruga PS (The Japan Atomic Power Co., Inc.: BWR)
Unit 1 of the Fukushima Daiichi NPS (Tokyo Electric Power Co., Inc.: BWR)
Unit 1 of the Mihama PS (The Kansai Electric Power Co., Inc.: PWR)
The 2nd Time (announced in June 2001)
Unit 2 of the Fukushima Daiichi NPS (Tokyo Electric Power Co., Inc.: BWR)
Unit 2 of the Mihama PS (The Kansai Electric Power Co., Inc.: PWR)
The 3rd Time (announced in March 2004)
Unit 1 of the Takahama PS (The Kansai Electric Power Co., Inc.: PWR)
Unit 2 of the Takahama PS (The Kansai Electric Power Co., Inc.: PWR)
Unit 1 of the Shimne NPS (The Chugoku Electric Power Co., Inc.: BWR)
Unit 1 of the Genkai NPS (Kyushu Electric Power Co., Inc.: PWR)

14-13

Article 15 Radiation Protection
Each Contracting Party shall take the appropriate steps to ensure that in all operational
states the radiation exposure to the workers and the public caused by a nuclear installation shallbe kept as low as reasonably achievable and that no individual shall be exposed to radiation
doses which exceed prescribed national dose limits.
The standards of radiation protection for the general public and personnel engaged in radiation work in Japanare prescribed in the laws and legislations, such as the Reactor Regulation Law, the Electricity Utilities Industry
Law and the Industrial Safety and Health Law, etc. The recommendations of the ICRP 1990 are incorporated
into their provisions of radiation protection with due considerations. Consequently, licence holders have kept theradiation exposure doses of personnel engaged in radiation work below the dose limit, as a matter of course,
and have attempted to reduce the exposure based on the ALARA policy.

15.1 Summary of Laws and Requirements on Radiation Protection
The national standards of radiation protection for a nuclear installation are provided in the Reactor
Regulation Law, the Electricity Utilities Industry Law and the Industrial Safety and Health Law, etc.
and related government ordinances, ministerial orders and notifications based on these laws, andguidelines. The recommendations of the ICRP 1990 are given due consideration and are incorporated
into legislation and regulation. Japan will consider the incorporation of future recommendations if
necessary.
A ministerial ordinance, the Rules for Commercial Power Reactors, established close on radiation
protection, on the basis of the Reactor Regulation Law, prescribes area control for radiation protection,
radiation control of personnel engaged in the radiation controlled areas, measurement and surveillanceof radiation levels, monitoring of discharged radioactive materials, and maintenance of radiation
control equipment. The Dose Limit Notification are enacted, which prescribes dose limits andconcentration limits of radioactive materials both inside controlled area and outside peripheral
monitoring area, and dose limits and concentration limits of radioactive materials for personnel
engaged in radiation work, and dose limits for personnel engaged in emergency activities.
In order to ensure those rules are complied with, each licence holder, it is required to prescribe in thefitness-for-safety program, 1) radiation control area, access controlled areas, and peripheral monitoringarea and access control to these areas, 2) monitoring equipment at air ventilation and water discharge,3) monitoring of the dose, the dose equivalent, the concentration of radioactive materials and thedensity of the surface radioactive materials of objects contaminated by radioactive materials, and thedecontamination, 4) maintenance of radiation monitoring equipment.
Ministerial order “Ordinance of Establishing Technical Standards for Nuclear Power Generation
Equipment” based on the Electricity Utilities Industry Law, provides the technical standards forradiation control equipment (biological shielding walls, ventilation facilities, instrumentation devices,alarm devices, and waste processing equipment, etc.) at nuclear installations. NISA confirms that suchradiation control equipment conforms to the ministerial order at issuing approval of the construction
plan and conducting inspection of the equipment.
The Industrial Safety and Health Law provides that licensees (employers of laborers) take measures toprevent damage to health of personnel engaged in radiation works, including radiation exposure,throughout the period of employment, and requires them to take actions for safety and healtheducation, work environment monitoring and medical examination of workers. On the basis of the law,
the Ministry of Health, Welfare and Labor has enacted a ministerial order, the Rules for Prevention of
Damage from Ionizing Radiation, which prescribes controlled areas, dose limits and measurement,
protection from external radiation, and prevention of radioactive contamination.
15-1

Radioisotopes etc. used in commercial power reactors are also regulated in accordance with the Law
for Prevention of Radiation Hazards due to Radioisotopes, etc. in the same manner as regulated by the
Reactor Regulation Law.
In examining the license to establish a nuclear installation, it is confirmed that the application
conforms to the Regulatory Guides established by the NSC as well as the legislation and technicalstandards. Regulatory Guide for the Annual Dose Target for the Public in the Vicinity of Light Water
Nuclear Power Reactor Facilities, one of these Regulatory Guides, gives dose target guide to reducethe discharge of radioactive materials from a nuclear installation into environment and the dose rate of
the public as low as reasonably achievable (ALARA).
Each licence holder has defined the release control target of liquid wastes and gaseous wastes in thefitness-for-safety program based on this Regulatory Guide for the Annual Dose Target for the Publicin the Vicinity of LWR.
The ICRP 1990 Recommendation (Publication 60) was, after examination by the Radiation Review
Council, incorporated into national legislations and regulations on radiation protection, by revision ofrelated ministerial orders and notifications in April 2001 with following additional considerations.
First, radiation controlled area is defined where dose may exceed 1.3 mSv/ 3months, corresponding to
5 mSv/year which is the special allowable dose limit to the public. Second, the occupational dose limit
for female personnel is set at 5mSv/3months, allocated value for the shorter period, reducing possible
dose for a potential embryo. The allowable dose limits in emergency remain twice of the annual dose
limits as before, considering the IAEA BSS.
The Radiation Review Council is an organization established under MEXT for the purpose ofcoordinating technical standards on prevention of radiation hazards. It submits reports to inquiries
from related administrative organizations, or gives its views to them if necessary.
15.2

Laws and Requirements and Response of Licence Holders(1) Allowable Dose Limits
1) Allowable Dose Limits for Controlled Areas
The Rules for Commercial Power Reactors and the Dose Limits Notification requires licenceholders to establish radiation controlled area including reactor room, and spent fuel storage
facilities and radioactive waste disposal facilities, where the dose of external radiation may
exceed 1.3mSv for three months, or where the concentration of radioactive materials in the air or
the surface density of radioactive materials may exceed the values specified in the Notification,
respectively, and to establish necessary measures to be taken in these areas.
2) Allowable Dose Limits for Occupational Exposure
The allowable dose limits for personnel engaged in radiation works are specified in the Dose
Limits Notification as listed in Table 15-1

15-2

Table 15-1 Dose limits for personnel engaged in radiation work
Items
1. Effective dose limitsa) Personnel engaged in radiation
worksb) Female personnelc) Pregnant Female personnel

Limit

100 mSv / 5 year, but do not exceed 50 mSv forany year
100 mSv / 5 year, but do not exceed 5 mSv for any
3 months
100 mSv / 5 year, but do not exceed 1 mSv frominternal exposure during pregnancy

2. Equivalent dose limitsa) Eye lensb) Skinc) Female abdominal region

150 mSv/ year
500 mSv/ year
2 mSv from notification of pregnancy to delivery

3. Dose limits for the personnel engaged
in emergency radiation worksa) Effective doseb) Equivalent dose for eye lensc) Equivalent dose for skin

100 mSv/ incident
300mSv/ incident
1Sv/ incident

Licence holders have paid much effort not only to comply with the allowable dose limits but also
to reduce doses in line with ALARA concept by taking following activities:− reducing radiation source in systems and components of a nuclear installation,− keeping distances from or setting shields against radiation sources,− reducing working time in radiation environment.
Consequently, the exposure doses of personnel engaged in radiation work, etc. have beensuccessfully reduced to the level as shown in Annex 2.
Exposure doses of personnel engaged in radiation work in commercial NPPs during the reporting
period are summarized as below;
a. Dose per Persons at Commercial NPPs
Average of dose per persons at commercial NPPs for the reporting period were1.2 to 1.4
mSv/year, and it shows slight increase for recent several years. However, the doses are wellwithin the dose limit prescribed in the notification.
In fiscal 2003, average personnel dose was 1.4mSv/year, maximum personnel doseexperienced at a NPP was 19.8mSv, this number was within the dose limit of the notification,
still they were slightly higher than these numbers of 1.3mSv/year and 19.7mSv for the previous
year. One worker who had worked in plural NPPs exceeded 20mSv, but it was well below thedose limits. The number of workers who had been exposed of 15 to 20 mSv/year was 577, andthis number showed slight increase of 559 for the previous year.

15-3

Table Collective Dose ,Average Dose per Persons and Numbers of Workers at Commercial
NPPs
2000 Fy
2001 Fy
2002 Fy
2003 Fy
Collective Dose(man-Sv)
Average dose perperson (mSv/year)
Total
numberofWorkers

78.83

78.05

84.03

96.41

1.2

1.2

1.3

1.4

65,90067,80063,80066,600b. Performance of Collective Dose at Commercial NPPs
In Japan at the end of March, 2004, total of 53 units, namely 30 BWRs and 23 PWRs wereoperating.
The average collective dose per reactor year was slightly increasing for recent several years. The
data for operating BWRs were 2.10 man-Sv for 2002 Fy and 2.20 man-Sv for 2003 Fy
respectively. The reasons for these increase were due to many modernization works in primaryloop recirculation pipings and CRDMs and many inspections/repairs works in core shroud andprimary loop recirculation pipings under the high radiation environments.
Table Collective Dose per Unit/Reactor-Year
2000 Fy
2001 Fy
2002 Fy
BWR
Plants(man-Sv/Ry)
PWR
Plants(man-Sv/Ry)

2003 Fy

1.96

1.68

2.10

2.40

1.03

1.27

1.00

1.07

Licence holders has been making efforts to reduce collective dose associated with large scale
modernization like replacement of core shroud and primary loop recirculation pipings, and thecollective doses are reducing year by year as shown in the case of reactor units of Fukushima
Daiichi NPPs as shown below

15-4

14

Collective Dose (man-Sv)

12

10

8

6

4

2

0
Fukushima Daiichi #3(97/05/2698/07/22)

Fukushima Daiichi #2

Fukushima Daiichi #5

Fukushima Daiichi #1(98/08/1299/7/9)(99/12/800/10/1)(00/12/2101/12/11)

Reduction of Man-Sv in the Core Shroud Replacement at Fukushima Daiichi NPPs

3) Dose Limits for the Public
The dose limits for the public are also given in the Dose Limit Notification as listed in Table
15-2.
Table 15-2 Dose limits for the public
Items
Dose limits outside the peripheral monitoring area
Effective dose
Equivalent dose for eye lensEquivalent dose for skin

Limit
1 mSv/ year
15 mSv/year
50 mSv/ year

(2) Conditions for Discharge of Radioactive Materials
1) Dose Target Guide to Reduce Dose of the Public in Vicinity and Discharge Control (ALARA)In the Dose Target Guide for the Public in the Site Vicinity, the NSC has prescribed thenumerical guide of 0.05 mSv, one twentieth of the dose limit to the public, in order to reducedose for the public due to discharge of radioactive material to the environment during normal
operation of a nuclear installation as low as reasonably achievable.
The licence holder establishes an annual numerical discharge control guide, which corresponds tothe dose target guide at the site vicinity, and makes efforts to keep the discharges of radioactive
effluents below the numerical discharge control guide. NISA acknowledges the numericaldischarge control guide and receives report on it from the licence holder.

2) The Discharge Data and the Measures Taken to Reduce the Amount of the Discharge
The discharge records of radioactive gaseous and liquid waste from the nuclear installations(BWR and PWR) over the past seven years are shown in Tables 15-3 to 15-5. The tables clearly
15-5

show that the discharge quantities are substantially below the numerical discharge control guide,gas discharge from the PWR being only one thousandth of the dose target. This is due to the factthat the licence holders have carried out the radiation management of the nuclear installation inline with the ALARA principle, including following measures.
Gaseous waste is discharged from ventilation port, while being measured and monitored, afterparticles are removed by high efficiency filter, and noble gas and iodine are decayed in a holdup
tank or charcoal bed noble gas holdup equipment.
All liquid waste are collected in a disposal facility, and equipment drain is recovered after being
processed in a filter equipment or demineralizer. Floor drain is recovered after being processed ina concentrator and demineralizer. Floor drain is reused in general, though a part of it may bedischarged through the discharge outlet after the concentration is measured. Recovered liquid
waste from resin is reused after treated in a concentrator and demineralizer. Concentrated liquid
waste generated in this process is treated as a solid waste. Low-level laundry wastewater, etc. areusually drained to the environment after being treated through filter and monitored.
Substantive reduction of fuel leak by improvement of fuels, (consequently, only three cases withfour fuel assemblies) of fuel leak arose during the period of reporting), filtering ventilation
during periodic inspections through local high efficiency filter, and other efforts to minimize
generation of liquid waste resulted in very low level of discharge of gaseous and liquidradioactive wastes.
(3) Environmental Radiation Monitoring
The licence holder is required to install environmental radiation monitoring equipment during normal
operation of a nuclear installation. These equipments include monitoring devices of the dose inside theradiation control area and outside the peripheral monitoring area and automatic devices to alarm any
abnormal increase of concentration of radioactive materials or dose rates.
The licence holder conducts radiation monitoring at the site vicinity during normal operation, assesses
the impact upon the environment of the discharge of radioactive materials from the nuclear installation,and feedbacks the results in improving discharge control and facility management. Local governments(prefectures where nuclear installations are located) also monitor radiation level independently at thesite vicinity to protect public health and safety.
The NSC decided fundamentals of planning and implementation of monitoring and the evaluation ofradiation dose in the Guide for Environmental Radiation Monitoring, in order to improve and to
standardize monitoring technology. Local governments and licence holders implement monitoring inaccordance with this guide.

15.3

Regulatory Control Activities(1) Discharge Control of Radioactive Materials
By the Rules for Commercial Power Reactors, the licence holder is required to report immediately to
the NISA when concentration of radioactive materials in the air outside the peripheral monitoring area
exceeds the allowable limit in discharging gaseous radioactive waste, or when the concentration ofradioactive materials in the water at the outer boundary of the peripheral monitoring area exceeds theallowable limit in discharging liquid radioactive waste, and report the status of the event and measurestaken against it within ten days.
(2) Control of Personal Exposure

15-6

The Rules for Prevention of Damage from Ionizing Radiation require licence holder to measure dose
due to external and internal exposure of workers who are engaged in radiation work or in emergency
work, or enter temporal access into radiation control area. The rules require that the licence holder
monitor and check daily dose due to external exposure, if it is expected to exceed the specified valueof 1mSv at 1cm dose equivalent, and calculate, without delay, the dose of the personnel engaged inradiation works using the method prescribed by the Minister of Health and Labor, and keeps thoserecords for a period of thirty years.
The Radiation Workers’ Registration Center of the Association of Radiation Impact was established in
November 1977, to address the difficulty of controlling the personal dose of workers who work inmore than one radiation environment. The Center unitarily collects and controls such personalradiation control data of the workers who work under the Reactor Regulation Law, as personal
identification control, personal radiation control booklet, periodical dose registration and transfer andcustody of personal radiation dose record.
(3) Control of Collective Dose
Collective dose per rector unit is increasing in recent years as described in 15.2 (1) b. As one of theapproach to scientific and rational regulation, feasibility of optimizing the collective dose by effective
and efficient inspection/repair work introducing Rules on Fitness-for-Service for Nuclear Power
Plants.
It is necessary to analyze the factors in detail that leads to the increase in collective dose, fact finding
survey is planned in 2004Fy, and it is planned to abstract the items to be studied for optimization. It isplanned to derive practical measures for optimization in future, based on the survey.

15-7Table 15-3 Annual discharge of radioactive noble gas in gaseous wasteYear(unit: Bq / year)
Dose Target
2003
Guides

1997

1998

1999

2000

2001

2002

Station - A

N.D.*

N.D.

N.D.

N.D.

N.D.

N.D.

Station - B

4.3×1011 6.1×1011 1.2×1011 5.7×1010 1.5×1010 2.8×1010 1.8×1010

Station

N.D.

6.7×1015
3.7×1015*: N.D. indicates a value below the detection limit concentration of 2 x 10-2 Bq/cm3.
Table 15-4 Annual discharge of radioactive iodine (I-131) in gaseous wasteYear(unit: Bq / year)
Dose Target
2003
Guides

1997

1998

1999

2000

2001

2002

Station - A

N.D.*

N.D.

N.D.

N.D.

N.D.

N.D.

N.D.

2.3×1011

Station - B

8.6×105 1.2×105 1.6×105 1.1×106 2.7×105

N.D.

N.D.

1.0×1011

Station*: N.D. indicates a value below the detection limit concentration of 7 x 10-9 Bq/cm3.
Table 15-5 Annual discharge of radioactive materials (excluding 3H) in liquid waste(unit: Bq / year)
Year
Dose Target
1997
1998
1999
2000
2001
2002
2003
StationGuidesStation - A

N.D.*

N.D.

N.D.

N.D.

N.D.

N.D.

N.D.

2.5×1011

Station - B

N.D.

N.D.

N.D

N.D.

N.D.

N.D.

N.D.

1.4×1011*: N.D. indicates a value below the detection limit concentration of 2 x 10-2 Bq/cm3.
(Represented by 60Co.)(Note)

Station - A : Kashiwazaki-Kariwa NPS (BWR)
Station - B : Ohi NPS (PWR)

15-8

Article 16

Emergency Preparedness

1. Each Contracting Party shall take the appropriate steps to ensure that there are on-site andoff-site emergency plans that are routinely tested for nuclear installations and cover the activities
to be carried out in the event of an emergency. For any new nuclear installation, such plans shallbe prepared and tested before it commences operation above a low power level agreed by theregulatory body.
2. Each Contracting Party shall take the appropriate steps to ensure that, insofar as they arelikely to be affected by a radiological emergency, its own population and the competentauthorities of the States in the vicinity of the nuclear installation are provided with appropriate
information for emergency planning and response.
3. Contracting Parties which do not have a nuclear installation on their territory, insofar as they
are likely to be affected in the event of a radiological emergency at a nuclear installation in thevicinity, shall take the appropriate steps for the preparation and testing of emergency plans fortheir territory that cover the activities to be carried out in the event of such an emergency.
On emergency preparedness, the Special Law of Emergency Preparedness for Nuclear Disaster (hereinafter
called as “Special Law for Nuclear Emergency”) was enacted in December 1999, taking the lessons learned
from the JCO criticality accident.
Considering the special characteristics of nuclear emergency, measures for nuclear emergency preparedness
have been defined to cope with the existing legal framework established by the Basic Law on Emergency
Preparedness, which had defined preparedness for disasters such as earthquakes, typhoons, and conflagrations.
After the previous reporting, the NSC reviewed “Emergency Measures for Nuclear Installations Guideline”(hereinafter called as “Emergency Preparedness Guidelines”), which decides technical aspects of nuclear
emergency measures, harmonizing with the Special Law for Nuclear Emergency and including the lessons
learned from the JCO criticality accident, and revised the guidelines concerning the preventive intake of stableiodine tablets, measures for mental health at a nuclear emergency, the designation of regional medical treatment
system for exposed patients in emergency, etc.

16.1. Development of Laws and Rules for Nuclear Emergency Preparedness
For Japan who was promoting the utilization of nuclear energy under the basic premise of securingsafety, the JCO criticality accident occurred in September 1999 was for the first time, and such a very
serious accident as local residents were instructed for sheltering or evacuation.
Lessons learned from the accident clarified the special characteristics of nuclear emergency, which
would require quick initial responses, close coordinated cooperation between national government andlocal governments, strengthening of the national emergency preparedness and the clarification oflicence holder's responsibilities. The Special Law for Nuclear Emergency was enacted in December
1999 and enforced in June 2000, addressing the special characteristics of nuclear emergency
mentioned above. The Special Law for Nuclear Emergency was enacted so as to harmonize withexisting legal framework established by the Basic Law on Emergency Preparedness, which had
defined roles of the national government, local governments, etc. in emergencies such as earthquakes,
typhoons, and conflagrations.
The “Nuclear Emergency Preparedness” in the Basic Plan for Emergency Preparedness based on the
Basic Law on Emergency Preparedness, was extensively revised in accordance with the Special Law
for Nuclear Emergency, clarifying roles and responsibilities of the national government, local
governments, and licence holders etc.
16-1

The NSC, in May 2000, also taking into consideration of the Special Law for Nuclear Emergency andthe lessons learned from the JCO criticality accident, revised the "Emergency Preparedness
Guidelines" on technical and special matters of a nuclear emergency measures, to include:− Research reactors and nuclear fuel cycle facilities in addition to commercial powerreactors, and,− Accidental release of nuclear fuel material etc. in addition to release of rare gas andiodine from NPS etc.
After that, the Emergency Preparedness Guidelines have been enhanced through the following several
revisions by the NSC:
− In March 2001, the dose coefficient (Sv/Bq) for internal exposure was changed alongwith the term, in response to amendment of the relevant legislations such as the Reactor
Regulation Law etc. based on adoption of the 1990 Recommendation of ICRP;− In June 2001, provisions of the medical treatment for exposed patients in emergency
was revised to be more effective and responsibilities of the national and local
governments and nuclear licence holders were clarified based on the experience of thecriticality accident;− In April 2002, protective measures concerning preventive taking of stable iodine tablets
were established based on the scientific knowledge acquired from the long-term
follow-up survey to atomic bomb sufferers and the investigation results of theChernobyl Power Station accident, etc;
− In November 2002, measures for mental health care in a nuclear emergency were
established based on the experience of JCO criticality accident, experiences of natural
disasters such as seismic disasters, etc; and,− In July 2003, the designation of regional medical treatment system for exposed patientsin emergency was established.

16.2. Nuclear Emergency Preparedness and the Measures
The Special Law for Nuclear Emergency has prescribed measures in nuclear emergency at powerreactors, research reactors, nuclear fuel cycle facilities, etc. Emergency preparedness of a commercial
power reactor is given below.
(1) Nuclear Emergency Preparedness concerning Nuclear Installations (Fig. 16-1)
Quick response and closely coordinated cooperation among relevant organizations are important in a
nuclear emergency.
− The Special Law for Nuclear Emergency defines specific initial events in NPS (seeTable 16-1), the occurrence of which the licence holder shall immediately notify the
Minister of METI and the heads of related local governments.
− The Minister of METI, receiving the notification, triggers activities according to theprocedure stipulated by the law. Staff with expertise in emergency measures will besent to local governments on request. The Senior Specialist for Nuclear Emergency
collects information and coordinates activities preventing expansion of the events.
− When the Minister of METI recognizes that the specific initial event exceeds thepredetermined level and has developed into an emergency, the Minister immediately
reports it to the Prime Minister.
− The Prime Minister have powerful authority to declare “Nuclear Emergency”, and toadvise or direct relevant local governments on necessary measures such as sheltering or
evacuation to be taken by them, as well as to request for dispatch of the Self-Defense
Forces concerning implementation of emergency measures.
− The Prime Minister establishes the "Nuclear Emergency Response Headquarters" inTokyo, which he will head, and the "Local Nuclear Emergency Response
16-2

−
−
−

Headquarters" at the site.
In a nuclear emergency, the NSC establishes “Technical Advisory Organization in an
Emergency” that is composed of commissioners and the Advisors for Emergency
Response. The Organization gives technical advises to the Prime Minister..
Local governments establish their own emergency response headquarters.
In order to share information between the national government and relatedorganizations such as local governments, nuclear licence holders, etc., and, if necessary,to coordinate emergency measures to be implemented by the respective organizations,the "Joint Council for Nuclear Emergency Response" is to be established at the Off-SiteCenter mentioned later.

(2) Measures for On-site and Off-site Nuclear Emergency Preparedness of Nuclear Installations
In order to prepare the “Nuclear Emergency Preparedness” described in paragraph (1), organizations
relevant to nuclear emergency preparedness keep themselves ready to collect and send information andstart quick response against an emergency, and conduct emergency drills, disseminate knowledge andpromote research on emergency preparedness. Outline of roles and responsibilities of relatedorganization are as follows.
1) On-Site Emergency Preparedness of Nuclear Installations
When the licence holder detects abnormal release of radioactive material or abnormal level ofradiation at a nuclear installation, it takes necessary measures to prevent progression of the event
into an emergency.
The licence holder, to cope with emergency properly, prepares a licence holder’s emergency
action plan after consulting with related local governments, which provides for prevention of,
emergency measures against, and post-emergency restoration of a nuclear emergency, including
on-site and off-site cooperation with other organizations. Especially, quick and accurate
notification of occurrence of specific initial events to related organizations is a very important
obligation of the licence holder.
The licence holder is required to take part in comprehensive drills with related organizations, andkeep close contact with them.
2) Emergency Preparedness in the Vicinity of Nuclear Installations
Roles and responsibilities of the national government and local governments in emergency
preparedness in the vicinity of nuclear installations are defined in the Special Law for Nuclear
Emergency and the Basic Plan for Emergency Preparedness. Each local government develops its
own regional emergency prevention plan. They carry out emergency environmental radiation
monitoring, and implement evacuation or sheltering of residents receiving advice or direction
from the Prime Minister based on the report of the Minister of METI. Taking of stable iodine
tablets, as well as sheltering or evacuation, is defined as one of the protective measures.
(3) Responsibilities of Related Organizations Concerning Nuclear Emergency Preparedness
1) Responsibility of the National Government
The national government establishes following preparation to prevent occurrence of nuclear
emergency and to take measures in emergency.
− METI stations a Senior Specialist for Nuclear Emergency in the vicinity of eachnuclear installation, who guides and advises a licence holder in preparing his
emergency action plan and, in emergency, takes necessary measures preventing
expansion of the emergency.
16-3

−

−

−

−
−

The NSC organizes “Technical Advisory Organization in an Emergency” thatcomposed of the commissioners and Advisors for Emergency Response. The mandatesof the organization is to give technical advices to the Prime Minister on a) dissolutionof nuclear emergency, b) the designation or alteration of the regional area thatnecessitates emergency measures to be taken, and c) technical matters on
implementation of emergency response measures.
The Minister of METI designates a facility in the vicinity of a nuclear installation as
Off-Site Center to be used in an emergency. In the case of an emergency, the national
government, the local governments and the licence holder establish at the Off-SiteCenter the "Joint Council for Nuclear Emergency Response", in order to share
information and to coordinate their activities. Off-Site Centers are built on the point
shown in Fig. 16-2, and have necessary facilities and equipments capable tocommunicate with the Prime Minister’s Official Residence, the Cabinet Office, theEmergency Response Center of NISA, the Emergency and Disaster Countermeasures
Center of MEXT and related local governments.
Each Off-Site Center is equipped with means by which the relevant organizations
monitor environmental radiation levels and the plant status. The environmental
radiation levels, other than temporary data measured in an emergency, can bemonitored every moment since the monitoring equipments are connected on line withthe monitoring posts located in the vicinity of a NPS. The on-line status of NPP that aresent from a licence holder in an emergency can be displayed on the monitors. The
results of estimation are also displayed by means of Emergency Response Support
System (ERSS), which forecasts progress of an abnormal NPS condition using plant
information.
The national government establishes arrangements to secure quick and coordinatedactivities in an emergency.
The national government conducts the comprehensive emergency drill based on the
program established by the competent minister.

2) Responsibilities of local governments
Each local government shall develop and revise the regional disaster prevention plan inaccordance with Article 40 of the Basic Law on Emergency Preparedness, and shall consult
beforehand with the Prime Minister for its development or revision.
3) Responsibilities of licence holders− Each licence holder shall develop his emergency action plan after consulting with
relevant local governments, and submit it to the Minister of METI before
commissioning of the reactor.
− Each licence holder shall establish an on-site organization for nuclear emergency
preparedness, and designate a Manager for Nuclear Emergency Preparedness who
administers the organization.
− The Manager for Nuclear Emergency Preparedness shall notify specific initial events tothe competent authorities.

16.3. Implementation of Nuclear Emergency Drill
The emergency preparedness action plan in accordance with the Basic Law on Emergency
Preparedness, and the Off-Site Center in the vicinity on the nuclear installation provided in theprevious section has been established for nuclear installation, and nuclear emergency drill is
implemented to confirm the effectiveness of these measures. The purpose of the nuclear emergency
drill is 1) to enhance understanding of, and adequate actions for, the nuclear emergency preparedness
by responsible personnel of the national government, local governments and the licence holder, and16-4

residents, and 2) to verify whether emergency measures function in predetermined way, and whether
information sharing and cooperation among related organizations are adequate. The national
government, local governments, designated public organizations and the licence holder cooperate andparticipate in the drill, which cover communication, monitoring, decision on emergency measures tobe taken, sheltering or evacuation etc., ranging from large scale national drill to licence holder’s
on-site drill. Drills implemented in the past years are shown below.
(1) Drills Planned by the National Government (Table 16-2 (1))
Nuclear emergency drills used to be planned and conducted by local governments with support andcoordination of the national government before the JCO criticality accident. The Special Law for
Nuclear Emergency, stipulated the drills to be planned and conducted by the national government.
Drills including accident management activities assuming a scenario results to the core damage havebeen implemented in the national emergency drills.
The drill planned by the national government has been conducted once a year as the comprehensive
nuclear emergency drill in collaboration with the national government, local governments, licenceholders, etc.
Drills implemented in and after year 2001 are as follows:− On October 27, 2001, a drill for the Unit 1 of the Tomari Power Station, (located in
Tomari Village, Furuu County, Hokkaido Prefecture) was conducted in collaboration
with the national government, the local governments of Hokkaido Prefecture, andrelevant towns and villages, Hokkaido Electric Power Co., Inc., and organizations
related to the emergency preparedness. About 2,700 persons including local residents
etc. participated in the drill. This was the first operation of “Hokkaido Nuclear
Emergency Preparedness Center,” which has been designated as the Off-Site Center asa base for implementing emergency measures.
− On November 7, 2002, a drill for the Unit 3 of the Ohi Power Station, (located in Ohi
Town, Ohi County, Fukui Prefecture) was conducted in collaboration with the national
government, the local governments of Fukui Prefecture and related cities and towns,
the Kansai Electric Power Co., Inc., and organizations relevant to the emergency
preparedness. About 4,000 persons including local residents etc. participated in the
drill. Vulnerable groups in emergency such as children etc. participated for the firsttime as a national drill. Moreover, evacuation to the sea was implemented inconsideration of the nature of the region.
− On November 26, 2003, a drill for the Unit 2 of the Genkai Nuclear Power Station,(located in Genkai Town, Higashi Matsuura County, Saga Prefecture) was conducted incollaboration with the national government, the local governments of Saga Prefecture,
Nagasaki Prefecture and related cities and towns, Kyushu Electric Power Co., Inc., andorganizations relevant to the emergency preparedness. About 9,400 persons including
local residents etc. participated in the drill. This drill was implemented over two
prefectures for the first time. Furthermore, the NSC performed training of advice
activities by tele-conference from the Tokyo headquarter to the local response
headquarter for the first time.
Results of the drills held every year are assessed and reflected to the items and methods of drills to be
implemented in and after the following fiscal year. Three kinds of method, participant’s questionnaire,check by an independent assessment agency, and observation by external experts, are adopted for theassessment.

16-5

(2) Drills Planned by the NSC
The NSC is conducting communication drills those aim enhancing the emergency communication
system and keeping up and/or improving its functions. The NSC also is conducting call and set up
drills of Emergency Technical Advisory Body those aim to confirm and improve the capability torespond properly and effectively in emergency.
(3)Drills Planned by Local Government (Table 16-2 (2) –(5))
The regional emergency prevention plan prescribes the local drills to be planned and conducted byeach local government, which METI and the NSC support by dispatching expert staffs..
(4) Drills Planned by Licence Holders
Each licence holder has implemented an on-site drill once a year including establishment of an
emergency response headquarter, notification and communication, emergency environmental
monitoring, etc. based on the licence holder’s emergency action plan for each site.
When the said site is a subject of the drill conducted by the local government, the on-site drill has been
implemented at the same time with the local drill implemented by the local government etc.
Each licence holder also has implemented a drill taking into consideration of accident management
activities, if necessary, in order to comprehensively confirm effectiveness of the organization
implementing the accident management.
(5) Participation in International Nuclear Emergency Exercise
Japan participated in the Joint International Nuclear Emergency Exercise (JINEX1) held in May 2001
sponsored mainly by the IAEA, learning lessons on cross border radiological emergency, and will
participate future international exercises.

16.4

International Framework and Relationship with Neighboring Countries

Japan is a contracting party to the Convention on Early Notification of a Nuclear Accident, and to theConventions on Assistance in the Case of a Nuclear Accident or Radiological Emergency. The
following system has been established for the notification of a nuclear accident to neighboring
countries:− For nuclear installations, the Ministry of Foreign Affairs has been designated as theauthority for notification and as the competent authority for foreign accidents, and theMinistry of METI has been designated as the competent authority for domestic
accidents.
− METI receives a report immediately on an accident in a nuclear installation on the basisof legal obligation of the licence holder.
− When occurrence of an accident is confirmed and it is predicted that release ofradioactive materials may affect neighboring countries, the IAEA and the countries that
may be affected by the accident are notified of the accident.
In accordance with an arrangement aiming at enhancement of the safety level of commercial powerreactors concluded with the People's Republic of China, on the basis of the bilateral agreement forpeaceful use of nuclear energy, the governments should mutually notify without delay of serious
events of nuclear installations. Bilateral inter-governmental agreement with the Republic of Korea
calls for cooperation in the establishment and operation of an early notification network for nuclear
safety.
16-6

If an accident should occur at a foreign nuclear installation and a request for assistance is made, Japan
will dispatch, on the basis of the Conventions on Assistance in the Case of a Nuclear Accident orRadiological Emergency, specialists in emergency monitoring and emergency medical treatment, andprovides materials and equipment such as radiation monitoring equipment and radiation protection
equipment.

16-7

Licensee
Nuclear Emergency
Preparedness
ManagerNational Government
NoticeLocal Government

Competent Minister
Notification- to prepare response organization to theevent reported- to judge occurrence of nuclear
emergency situation(Table 16-1 for judgment criteria)- to collect information and conduct
necessary action by the resident
Senior Specialist for Nuclear
Emergency- Recognition of events
to be reported(Table 16-1 forreport criteria)- Initial response
against emergency byonsite nuclear
emergency response
team

Relatedprefectural
governors
Request ofexperts
Dispatchof experts

Municipal
governors

Prime Minister- to declare “Nuclear Emergency”- to announce affected zone, outline ofevent, etc.
- to establish Nuclear Emergency
Response Headquarters

NuclearAdviceSafetyCommission

Nuclear Emergency Response
Headquarters
Director General: Prime Minister
Deputy Director: Minister of METI
Member: Minister of related ministries
Government offices
Directors of related agencies

Advice ordirection ofevacuation& sheltering

Residents

Direction

Establishments ofEmergency Response
Headquarters of each
local government

Participation

Local Nuclear Emergency Response
Headquarters

Self-Defense
ForcesEstablishment of Joint Council for Nuclear Emergency Response
To be established at Off-Site Center to share informational and coordinate
emergency response activities conducted by each organization
Emergency response
activities by on-site
emergency response
team in licence holder

Nuclear
SafetyCommission

Main activities of Joint Council- Accurate public information- Advice or directions of evacuation or
sheltering of residents- Measurement of radiation inenvironment- Rescue of sufferers- Restoration of facility

AdviceDirections and requests- Special supports: JAERI and National
Institute of Radiological Sciences- Fire extinguishing, Rescue and First-aid:
Fire and Disaster Management Agency- Security guard: National Police Agency

Prime Minister
To declare cancel of“Nuclear Emergency”

Abolition of Nuclear Emergency
Response Headquarters

Measures by national and local
governments and licensees- Pollution investigation,- health consultation,- rumor damage control

Fig.16-1 Nuclear Emergency Preparedness based on the Special Law for Nuclear Emergency

16-8

Kyowa Town

Fukui Pref.
Higashidoori Village(Preparing for Service)

Tsuruga City
Mihama Town
Ohi Town
Takahama Town

Onagawa Town
Kashiwazaki City
Ohkuma Town

Shika Town

Hitachinaka City
Matsue City
Omaezaki City

Karatsu City

Ikata Town

: Off-Site Center in theVicinity of Nuclear Power
Plants (16 Sites)

Sendai City

Fig. 16.2 Location of Off-Site Centers

16-9

Table 16 – 1Main Specific Events and the Nuclear Emergency specified in the Special Law for Nuclear Emergency

EventsCriteria for reporting by licensees and “Nuclear Emergency” declaration by national government
conditions of declaration of “Nuclear Emergency”

Events that licensees should report.

a) Dose of radiation near the siteboundary detected doseb) Detection of the radioactive materials
in usual release points, such as exhaustpipesc) Radiation by fire, explosion, etc. or
detection of radioactive materials (outside
the management zone)

16-10

5 micro Sv/h at one point for more than 10 min
5 micro Sv/h at more than 2 points at the same time
Radioactive materials worth to more than 5 micro Sv/h

500 micro Sv/h at one point for more than 10 min,
500 micro Sv/h at more than 2points at the same time
Radioactive materials worth to more than 500 micro Sv/hRadiation dose of more than 50 micro Sv/h
Release of radioactive materials worth to more than 5 micro Sv/hRadiation dose of more than 5 mSv/h
Release of radioactive materials worth to more than 500 micro Sv/h

When the nuclear reactor shutdown cannot be performed byusual neutron absorbers
Occurrence of leakage of nuclear reactor coolant which needs
operation of the emergency core coolant system (ECCS)
When all AC power supplies stops power supply for more than 5
minutes

When all of reactor shutdown functions are lostd) Individual events of each nuclear
installations (Example for reactor)- Failure of scram- Loss of reactor coolant- Loss of all AC power supplies

When water cannot be poured to the nuclear reactor by all ECCSs
When all measures for cooling reactor core are lost with loss of all AC
power supplies.

Response of the national government- The Minister of METI sends staff with expertise on request of - The Minister of METI reports the nuclear emergency to the Prime Minister
local governments.
immediately after confirming the situation.
- The resident Specialist on Nuclear Emergency Preparedness - The Prime Minister declares “Nuclear Emergency” and takes following
carries out necessary works.
responses;- to advice or direct related local governments on necessary measures
Following responses are carried out based on the agreement ofsuch as sheltering or evacuation.
related ministries, not specified in the Special Law for Nuclear- to establish the Nuclear Emergency Response Headquarters in Tokyo
Emergency.
and Local Nuclear Emergency Response Headquarters at Off-Site- Related ministries and agencies organize joint task group for theCenter.
incidents in Tokyo.
- to establish the Joint Council for Nuclear Emergency Response for- Related local organizations organize joint local task group in theinformation exchange among the national government and local
Off- Site Center.
governments.

Table 16-2.
Conductor

Nuclear Emergency Drills

Date

Nuclear Power Station(1) Drills conducted by National Government
METI
03/23/2000
Tsuruga Power Station (The Japan Atomic Power, Inc.)(Thurs.)
METI
10/28 /2000 (Sat.) Shimane Nuclear Power Station (Chugoku Electric Power
Co., Inc.)
METI
10/27/2001 (Sat.) Tomari Power Station (Hokkaido Electric Power Co.,
Inc.)
METI
11/07/2002
Ohi Power Station (The Kansai Electric Power Co., Inc.)(Thurs.)
METI
11/26/2003 (Wed.) Genkai Nuclear Power Station (Kyushu Electric Power
Co., Inc.)(2) Drills conducted by Local Governments (April 2000 - March 2001)
Tokai-mura
09/30/2000 (Sat.) Tokai Daini Power Station (The Japan Atomic Power,(Ibaraki Pref.)Inc.)
Niigata Pref.
10/27/2000 (Fri.)
Kashiwazaki Kariwa Nuclear Power Station(Tokyo Electric Power Co., Inc.)
Ehime Pref.
10/31/2000 (Tue.) Ikata Power Station (Shikoku Electric Power Co., Inc.)
Ishikawa Pref.
11/17/2000 (Fri.)
Shika Nuclear Power Station (Hokuriku Electric PowerCo.)
Saga Pref.
11/27/2000
Genkai Nuclear Power Station (Kyushu Electric Power(Mon.)
Co., Inc.)
Fukushima Pref.
11/28/2000 (Tue.) Fukushima Daiichi Nuclear Power Station(Tokyo Electric Power Co., Inc.)
Kagoshima
02/06/2001 (Tue.) Sendai Nuclear Power Station (Kyushu Electric Power
Pref.
Co., Inc.)
Hokkaido
02/08/2001
Tomari Power Station (Hokkaido Electric Power Co.,
(Thurs.)Inc.)
Fukui Pref.
03/22/2001
Takahama Power Station (The Kansai Electric Power Co.,
(Thurs.)Inc.)
Shizuoka Pref.
03/23/2001 (Fri.)
Hamaoka Nuclear Power Station (Chubu Electric Power
Co., Inc.)(3) Drills conducted by Local Governments (April 2001 - March 2002)
Miyagi Pref.
07/11/2001 (Wed.) Onagawa Nuclear Power Station (Tohoku Electric Power
Co., Inc.)
Ehime Pref.
11/01/2001
Ikata Power Station (Shikoku Electric Power Co., Inc.)(Thurs.)Shimane Pref.
11/07/2001 (Wed.) Shimane Nuclear Power Station (Chugoku Electric Power
Co., Inc.)
Saga Pref.
11/26/2001
Genkai Nuclear Power Station (Kyushu Electric Power(Mon.)
Co., Inc.)
Fukushima Pref.
11/28/2001 (Wed.) Fukushima Daini Nuclear Power Station(Tokyo Electric Power Co., Inc.)
Ishikawa Pref.
01/10/2002
Shika Nuclear Power Station (Hokuriku Electric Power(Thurs.)Co.)
Kagoshima
01/31/2002
Sendai Nuclear Power Station (Kyushu Electric Power
Pref.
(Thurs.)Co., Inc.)
Shizuoka Pref.
02/21/2002
Hamaoka Nuclear Power Station (Chubu Electric Power(Thurs.)Co., Inc.)
Fukui Pref.
03/30/2002 (Sat.) Mihama Power Station (The Kansai Electric Power Co.,Inc.)
(4) Drills conducted by Local Governments (April 2002 - March 2003)
Miyagi Pref.
09/03/2002 (Tue.) Onagawa Nuclear Power Station (Tohoku Electric Power
Co., Inc.)
Hokkaido
10/25/2002 (Fri.) Tomari Power Station (Hokkaido Electric Power Co.,
Inc.)
Ehime Pref.
10/25/2002 (Fri.) Ikata Power Station (Shikoku Electric Power Co., Inc.)

16-11

Kagoshima
Pref.
Fukui Pref.
Fukushima Pref.

10/29/2002 (Tue.)
11/07/2002(Thurs.)
11/08/2002 (Fri.)

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

Fukushima Daiichi Nuclear Power Station(Tokyo Electric Power Co., Inc.)
Shimane Pref.
11/08/2002 (Fri.) Shimane Nuclear Power Station (The Chugoku ElectricPower Co., Inc.)
Niigata Pref.
11/09/2002 (Sat.) Kashiwazaki Kariwa Nuclear Power Station(Tokyo Electric Power Co., Inc.)
Ishikawa Pref.
11/11/2002
Shika Nuclear Power Station (Hokuriku Electric Power(Mon.)
Co.)
Saga Pref.
11/25/2002
Genkai Nuclear Power Station (Kyushu Electric Power(Mon.)
Co., Inc.)
Nagasaki Pref.
01/30/2003
Genkai Nuclear Power Station (Kyushu Electric Power(Thus.)
Co., Inc.)
Shizuoka Pref.
02/04/2003 (Tue.) Hamaoka Nuclear Power Station (Chubu Electric Power
Co., Inc.)(5) Drills conducted by Local Governments (April 2003 - March 2004)
Ibaraki Pref.
09/30/2003 (Tue.) Tokai Daini Power Station (The Japan Atomic Power,
Inc.)
Hokkaido
10/24/2003 (Fri.) Tomari Power Station (Hokkaido Electric Power Co.,
Inc.)
Ehime Pref.
10/27/2003
Ikata Power Station (Shikoku Electric Power Co., Inc.)(Mon.)

Niigata Pref.
Miyagi Pref.
Fukui Pref.
Fukushima
Pref.
Shimane Pref.
Kagoshima
Pref.
Ishikawa Pref.

10/27/2000(Fri.)
10/29/2003(Wed.)
11/15/2003(Sat.)
11/28/2003(Fri.)
01/23/2004(Fri.)
01/28/2004(Wed.)
03/23/2004(Tue.)

Kashiwazaki Kariwa Nuclear Power Station(Tokyo Electric Power Co., Inc.)
Onagawa Nuclear Power Station (Tohoku ElectricPower Co., Inc.)
Tsuruga Power Station (The Japan Atomic Power,
Inc.)
Fukushima Daini Nuclear Power Station(Tokyo Electric Power Co., Inc.)
Shimane Nuclear Power Station (Chugoku ElectricPower Co., Inc.)
Sendai Nuclear Power Station (Kyushu ElectricPower Co., Inc.)
Shika Nuclear Power Station (Hokuriku ElectricPower Co.)

16-12

D. Safety of Installations

Article 17

SitingEach Contracting Party shall take the appropriate steps to ensure that appropriate
procedures are established and implemented:(i)for evaluating all relevant site-related factors likely to affect the safety of a nuclear
installation for its projected lifetime;(ii)

for evaluating the likely safety impact of a proposed nuclear installation on
individuals, society and the environment;(iii)

for re-evaluating as necessary all relevant factors referred to in sub-paragraphs (i)and (ii) so as to ensure the continued safety acceptability of the nuclear installation;(iv)

for consulting Contracting Parties in the vicinity of a proposed nuclear installation,
insofar as they are likely to be affected by that installation and, upon request
providing the necessary information to such Contracting Parties, in order to enable
them to evaluate and make their own assessment of the likely safety impact on theirown territory of the nuclear installation.

In Japan, in order to judge the appropriateness of the site for a nuclear installation, it is deemednecessary to conduct the safety impact assessment on natural phenomena and human induced
external events to the nuclear installation, the safety impact assessment on the postulated accident of
the nuclear installation to the general public in the vicinity, and the impact assessments on the sitingof the nuclear installation to the environment other than the safety, therefore, required legislations
and regulations for implementing relevant assessments has been provided, and the assessments arebeing conducted.
The probabilistic assessment had been performed to judge whether considerations on the fall of an
airplane would be necessary to be included in the design as a human induced external event, and theregulatory guide was provided and set forth as a standard assessment method, since the previous
report.

17.1 Basic Concept on the Siting of Nuclear Facilities
The following assessments must be taken into consideration when deciding upon the siting of nuclear
facilities, and are incorporated in the relevant legislation, etc.
− Safety impact assessment on a nuclear installation by natural phenomena andpostulated human induced external events− Safety impact assessment on the radioactive impact to the environment by a nuclear
installation should reactor accidents occur− Environmental impact assessment other than radioactive impact due to the siting of a
nuclear installation

17.2

Principal Assessment System Concerning the Siting of Commercial Power Reactors

The Reactor Regulation Law requires that location of a commercial power reactor must be selected
and its structures and components must be designed so that the radiological hazards can be prevented.
The adequacy of siting is examined in accordance with the Regulatory Guide for Reviewing Nuclear
Reactor Siting Evaluation and Application Criteria (hereinafter called, the Regulatory Guide for Reactor
Siting) etc. as part of safety examination of establishment license.

17-1

The Regulatory Guide for Reactor Siting requires that no such event that might induce serious
accidents has occurred in the past or could be expected to occur in the future at the proposed site andfurthermore, there should not be events that may aggravate accidents, and that reactors are isolated ata sufficient distance from the public in consideration of engineered safety features.
When deciding a site, an adequate attention in design shall be paid to the postulated external initiating
event specific to the site, in addition to the site conditions stipulated by the Regulatory Guide for
Reactor Siting.
In this respect, the Regulatory Guide for Safety Design prescribes that structures, systems andcomponents with safety functions shall be designed to sufficiently withstand appropriate design basis
seismic forces. As well, they shall be so designed that the safety of the commercial power reactor will
not be impaired by other possible natural phenomena than earthquake and also by postulated external
human initiated events.
The Regulatory Guide for Reactor Siting also prescribes that the dose to the public shall meet with theapplication criteria in consideration of the engineered safety features by establishing an exclusion areaand low population zone and ensuring sufficient distance from high population zones, when assessing
radiation impact to the public in the vicinity imposed by the postulated accidents in commercial
power reactor. Meanwhile, the Regulatory Guide for Safety Assessment provides events to beevaluated in siting, acceptance criteria and specific conditions, etc. to be used in the analysis.
Environmental impact assessment of all of the power stations including nuclear power stations is
performed in accordance with the Environmental Impact Assessment Law enforced in June 1999,
before when the departmental council decision of MITI (present METI) dated in July 1977 wasapplied. This subject is described in Section 17.5.

17.3 Evaluation to Events Caused by External Factor
The Regulatory Guide for Safety Design prescribes that the earthquakes, natural phenomena otherthan earthquake and external human initiated events shall be addressed in the design, being inaccordance with the prescription in the Regulatory Guide for Reactor Siting, stating “no such eventthat might cause serious accidents has occurred in the past nor could be expected to occur in the
future at the proposed site and furthermore, there should not be events that may aggravate accidents”.
On the seismic design, it is required that the structures, systems and components (SSCs)with safetyfunctions shall be designed in accordance with seismic classification, and shall be designed towithstand fully against the appropriate force of design basis earthquake.
It has been verified that the earthquake ground motions 'S1' that was derived with considerations ofthe "design basis maximum earthquake" assumed from the recorded earthquakes and active faults andthe earthquake ground motions 'S2' that was derived with considerations of the "design basis extreme
earthquake" that exceeds the "design basis maximum earthquake" are appropriate as the force ofdesign basis earthquake in accordance with the Regulatory Guide for Reviewing Seismic Design ofNuclear Power Reactor Facilities.
As classification on seismic design, SSCs are classified into three classes of A, B, and C from a view
point of radioactive impact to the environment which could be induced by an earthquake based on thisguidelines. And the basic policy with which the seismic design is performed is confirmed, so that theclass A SSCs can withstand the earthquake ground motions S1 and the class As SSCs that are
specifically important facilities among the class A SSCs can retain the safety function against theearthquake ground motions S2.

17-2

It is also required to confirm that the design is appropriate based on the technical standards provided
in the Electric Utility Law.
The NSC established the Task Group on Seismic Design Guideline under the Special Committee on
Safety Standards in July 2001, and started studies to develop more appropriate guidelines reflecting
the latest knowledge etc. to the Regulatory Guide for Reviewing Seismic Design of Nuclear Power
Reactor Facilities etc.
First, the Task Group on Seismic Design Guideline arranged and classified items that should bestudied concretely based on the latest knowledge and technology related to the seismic design, andestablished a working group which consists of specialists of many fields in order to make efforts incollecting, arranging, etc. of new knowledge.
Hereafter, deliberation and investigation at the Task Group will be effectively performed based on theoutcome of the working group.
For the assumed natural phenomena other than earthquake (floods, tsunami, breeze, freezing,snowfall, landslides, etc.), the SSCs with safety functions are required to be designed so that thesafety of the nuclear reactor facility will not be failed by any of these natural phenomena. Those SSCs
with safety functions of particularly high importance shall be designed to withstand against the most
severe conditions of natural phenomena or to withstand against combination of such natural forces
and loads induced by an accident.
Moreover, the SSCs with safety functions are required to be so designed that the commercial powerreactor should not be impaired by postulated human induced external event (airplane crashes, dam
collapse, explosions etc.).
On the consideration on then airplane fall, the standard evaluation method is shown with a guide tojudge whether design consideration as “an assumed human induced external event” is required ornot, in “Evaluation Standards of the Probability of Airplane Falling to a Commercial Power Reactor
Facility (Regulatory Guide)”, which NISA enacted as a Regulatory Guide in July 2002. Besides, forairplanes, flight over nuclear facilities is limited in principle.
Commercial power reactors are required to be provided with appropriate measures to prevent illegal
access to the reactor by third persons in Japan.

17.4 Evaluation for the Impacts to the Public of Accidents
In order to ensure safety of the public even from a worst accident, the Regulatory Guide for Reactor
Siting prescribes, as a fundamental siting condition, that a commercial power reactor be located with asufficient distance from the public taking into account the engineered safety features. The conditions
for fulfilling this requirement are as follows:A) The area within a specified distance from a commercial power reactor shall be the exclusion area,and no radiation hazard is imposed on the public in the vicinity outside the exclusion area, evenpostulating the occurrence of a major accident.
A major accident is defined in the above Guideline to be an accident, occurrence of which isconceivable as a worst scenario from a technical point of view with considering such factors as
the conditions at the site vicinity, the characteristics of the reactor and the engineered safety
features.
B) The area within a specified distance beyond the exclusion area shall be the low population zone,
and no substantial radiation damage is imposed on the public in the vicinity of the low population
17-3

zone, even postulating the occurrence of a hypothetical accident.
A hypothetical accident is defined in the above Guideline to be an accident, which exceeds amajor accident, and the occurrence of that is not conceivable from a technical point of view. The
Guideline for example, hypothesizes that some of engineered safety features in the reactor, which
are assumed to be effective in postulating a major accident do not function and corresponding
release of radioactive materials occurs.
C) A site of a nuclear reactor shall be located at a specified distance from high population zones.
The specified distance means a distance where cumulative value of whole-body dose in case of ahypothetical accident shall be small enough to be deemed acceptable based on the collective doseof view.
The application criteria on dose rate are specified in the attachments of the Regulatory Guide for
Reactor Siting. The meteorological observation methods, the statistical processing methods of theobserved data and the methods for the analysis of the atmospheric diffusion of the released
radioactive materials, to be used in the dose assessments, are prescribed in the Regulatory Guide for
Meteorological Observation for Safety Analysis of Nuclear Power Reactor Facilities.

17.5 Environmental Impact Assessment
The Environmental Impact Assessment Law was established to ensure business operators, that areundertaking large-scale projects that could have a serious impact on the environment, to conduct anenvironmental impact assessment properly and reflect the results of the assessment in implementing
the project in term of protecting the environment, and also set forth the procedures in conducting theenvironmental impact assessment. The assessment for commercial power stations including nuclear
power station must be performed in accordance with the provisions of the Environmental Impact
Assessment Law and the Electricity Utility Industry Law. All of nuclear power reactors are subject toassessment regardless of their scale. The procedure is summarized in Figure 17-1.
Business operator, prior to application for reactor establishment, must prepare a Scoping Document
presenting information concerning the contents of the project, items to be considered in anenvironmental impact assessment, method of survey, prediction, and assessment method to be
utilized, and must submit it to NISA, as well as to the local governments having jurisdiction over thearea deemed likely to be environmentally impacted by the project. NISA examines the Scoping
Document taking into consideration the comments submitted by the related prefectural governor(s), as
well as the comments of the residents and the views of the business operators regarding suchcomments, and gives recommendations on the contents of Scoping Document to the business
operator, if needed.
Then business operator shall prepare a draft environmental impact statement (draft EIS) after
conducting survey, prediction and assessment in consideration with the recommendation received
from NISA and establishing the measures for protecting the environment. The draft EIS must be
submitted to NISA, as well as to the related local governments. NISA, after examining the draft EIS,
taking into account the opinion of the Minister of Environment and the related Governors as well as
the comments of the residents and the views of the business operators regarding such comments, andreceiving the view of advisers on the environment protection, gives recommendations on theenvironmental assessment to the business operator if needed. Meanwhile, concerning the items withlarge environmental impact, business operators shall check and provide the necessary measures forprotecting the environment so that the environmental impact by the project would be reduced as low
as practical, considering the project plan and the state of the area environmentally impacted by the
project.

17-4

Finally, business operator shall prepare the environmental impact statement (EIS), taking into accountthe recommendation on the draft EIS, and submit it to NISA. NISA, after examining the EIS, orders
alteration of the EIS if needed, otherwise notices acceptance of the EIS to business operator. The
accepted EIS is distributed to the Ministry of Environment and related local governments.
At the stage of examining construction plan, NISA does not approve it in case that the plan does notconform to the accepted EIS.

17.6 Re-evaluation of Site Related Factors
All the factors related to site selection must be re-evaluated at the time of alteration of anestablishment license, such as new plant construction at the existing site, so as to review and assure
the continuous safe operation of commercial power reactors. Adequacy of the safety design is
re-evaluated referring to new findings and new experiences having impact on the design.

17.7 Arrangements with Neighboring Countries on Safety Impact of Nuclear Facilities
Commercial power reactor in Japan is so located at the place where there are no events liable toinduce serious accidents and so designed to secure the safety against postulated initiating events
including natural phenomena. It also implements the measures for the accident management.
Furthermore, because of the fact that Japan is an archipelago country and separated from neighboring
countries by a considerable distance, adverse impact of Japanese commercial power reactor overneighboring countries is deemed to be extremely small. Accordingly, no consultation has been madeso far with neighboring countries on the siting of commercial power reactors.

17-5

Residents

Business
Operators

Ministry of Economy,
Trade and Industry(NISA)

Local
Governments

Ministry of theEnvironment

Submittal of SD
Preparation of SD
Submittal of SD
Announcement
andNotification

Examination of SD(based on Commentsof Governor(s) and
Residents)

Governor’s
Comments

Outline ofComments withOperator’s Position

Review of
Resident Comments

InquirComments(Advised by theAdvisory Committee
on Environmental
Impact Assessment)

Submittal of
Resident’s
Comments

Prefectural
Governor(s)Mayors of theRelated Cities,
Towns andVillages

Recommendation with
Governor’s Comments

Conduction of Environmental
Impact Assessment

Submittal of Draft EIS

Preparation of
Draft EIS

Prefectural
Governor(s)Examination of
Draft EIS

Submittal of
Draft EIS

Inquiry

Announcement
and Notification(based on Governor(s)and Residents Opinion)

Governor’s
OpinionInquiry

Explanatory Meeting(Advised by theAdvisory Committee
on Environmental
Impact Assessment)

Outline ofcomments(with
Operator’s
Position)

Submittal of
Resident’s
Comments
Review of
Resident Comments

OpinionOpinionMayors of theRelated Cities,
Towns andVillages

Minister of theEnvironment

Recommendation with
Governor’s Opinion
Submittal of
accepted EIS

Submittal of EIS

Preparation of EIS

Notice of Acceptance(or Order to Change)

Finalization of EIS

Examination of
EIS

Minister of theEnvironment

Submittal of EIS
Prefectural
Governor(s)Notification
to Resident

Public Announcement

Mayors of
the RelatedCities,Towns andVillages

Proper measures forEnvironmental Preservation

Application or
Notification
Application or Notificationof Construction Plan
Approvalor Order to Change

NOTE :

EIS: Environment Impact Statement

Examination ofConstruction Plan
(Conformance to EIS, etc.)

SD: Scoping Document

Fig.17-1 Outline of the Environmental Impact Assessment on Nuclear Power Plant

17-6

Article 18

Design and Construction

Each Contracting Party shall take the appropriate steps to ensure that:(i) the design and construction of a nuclear installation provides for several reliable levels
and methods of protection (defense in depth) against the release of radioactive materials,
with a view to preventing the occurrence of accidents and to mitigating their radiologicalconsequences should they occur;(ii) the technologies incorporated in the design and construction of a nuclear installation areproven by experience or qualified by testing or analysis;(iii) the design of a nuclear installation allows for reliable, stable and easily manageable
operation, with specific consideration of human factors and the man-machine interface.
Nuclear facilities in Japan (light water reactors and fast breeder reactors) were designed, constructed andoperated based on the safety design concept, which are common to most Western countries, adopting almost thesame defense in depth system as prescribed in the Nuclear Safety Standards "NUSS" of the IAEA. Moreover, theknowledge obtained from operating experiences and various kinds of examination, analyses, research anddevelopment are utilized to realize of safer and easier facilities to carry out the maintenance management.
Furthermore, this new knowledge is reflected appropriately and successively on planning and revising ofguidelines etc. in order to improve the safety and reliability of nuclear reactors.

18.1

Licensing Process at the Design and Construction Stages of Nuclear Facilities

Licensing process at the design and construction stage for commercial power reactor in Japan are
described in the report of Article 7 with relevant laws and regulatory requirements applied.
Confirming safety and safety assessment at the design and construction stage for commercial powerreactor are described in the report of Article 14 with relevant laws and evaluation guidelines applied.
When design alteration of licensed commercial power reactor is required, the licence holder must
undergo verification of the safety affected by the alteration and inspection of the altered segment
including the safety analysis influenced by the design alteration, in the same procedure as the licensing
process as licensing a new installation.

18.2

Realization of Defense with Multiple Steps and Methods (Defense in Depth) andConfinement of Radioactive Materials at Design and Construction Stage

Commercial power rectors (light water reactors (BWRs and PWRs)) in Japan are designed,
constructed and operated based on the safety design principals, which are common among mostWestern countries and almost the same concept of "defense in depth" as prescribed in the Nuclear
Safety Standards (NUSS) of the IAEA.
In this section the first 3 levels of defense in depth concepts which are closely related to design andconstruction of nuclear installations are discussed, forth and fifth levels of defense in depth concept
which are severe accident management and emergency preparedness are discussed in sections 18.4 andreport on Article 16.
Original design of light water reactors in Japan was introduced from the United States. But, the later
design of reactors has been improved the facilities to be safer and easier in maintenance management
through series of Improvement and Standardization Program led by METI (then MITI), reflecting theoperating experiences of those who have obtained license for reactor establishment (hereinafter called
as the “licence holders”) and knowledge obtained in research and development program of nuclear
power industries.

18-1

(1) Implementation of the Defense in Depth Concept
The principle of "defense in depth" is as follows:− Prevention of deviating from normal operation restraint with conservative design,
manufacturing and construction of the nuclear plant in accordance with the relevant quality
level and engineering practices.
− Detection of the occurrence of an abnormal event at an early stage and taking preventive
measures against its progression into an accident. And− Control of the progression of accident and mitigation of its consequences by assuming that
progression to an accident is not prevented at the preceding stage.
In order to apply these fundamentals to design of nuclear facilities, the Regulatory Guide for Safety
Design (see Table 18-1) that was established by the NSC, stipulates the following items; The first
defense is to prevent the occurrence of an abnormal event. More specifically, as stated in therequirements in guidelines 1 to 10 (overall nuclear reactor facility) of the Regulatory Guide for Safety
Design, the first defense implies such measures of designing with a safety margin, implementing strict
quality control in fabrication, inspecting the facilities and component to be fabricated as required by
the design and preventing degradation of performance through monitoring, check and maintenanceduring the operation. Each component, equipment and system of nuclear reactor facility is to be
designed considering the importance of its safety function. The Regulatory Guide for Classification of
the Importance of Safety Functions for Light Water Nuclear Power Reactor Facilities requires that thequality control during design and manufacturing be conducted corresponding to the importance ofsafety function.
The second defense is to prevent the progression of the abnormal event. More specifically, as stated in
the requirements in guidelines 15 to 18 (Reactor Shutdown System), and 34 to 40 (Safety Protection
System) of the Regulatory Guide for Safety Design, the second defense implies the early detection of
the abnormal condition, its correction or taking measures in advance to prevent the progression into an
accident.
The third defense is to mitigate the consequence of an accident. More specifically, as stated in therequirements in guidelines 25 (Emergency Core Cooling System) and 28 to 33 (Reactor Containment)of the Regulatory Guide for Safety Design, the third defense implies taking measures to secure thesafety of the public in the vicinity by controlling the progression of the accident and mitigating its
consequence.
The safety of nuclear facilities is ensured through rigorous safety ensuring measures on the basis of the
defense in depth concept, which includes 1) preventing the occurrence of an abnormal event, 2)
detection of the abnormal event and the preventing progression into an accident, and 3) mitigating an
accident consequence. Consequently, through these measures, it is possible to reduce the potential forthe occurrence of a severe accident to the extent that its actual occurrence would be technologicallyinconceivable, and to maintain the risk of the nuclear facility at a sufficiently low level. Based on sucha status, preparation of the accident management is positioned as a measure to reduce the low risk
further beyond these protection levels. In addition, preparation of the accident management and theemergency measures, which has been carried on in Japan, are described in section 18.4, and in Article
16, respectively.
(2) Confinement of Radioactive Materials (or Three Barriers of Radiation Protection Walls)
Nuclear facilities shall be designed, constructed and operated, in such a way as to confine radioactive
materials within a series of physical barriers. These physical barriers are the fuel pellet, the fuelcladding, the reactor coolant pressure boundary and the reactor containment. The requirements forthese physical barriers in the Regulatory Guide for Safety Design etc. and the outcome of the design
improvements in them are as follows:
18-21) Fuel (Including Claddings)
The fuel assembly shall be so designed that a) the integrity will be retained under the various
conditions that could occur in the nuclear reactor in service; b) the safety protection system will
actuate the reactor shutdown system, etc. so that the allowable design limit of the fuel shall not be
exceeded at an abnormal transient during operation; c) the reactor core cooling will not be
impaired by a reactivity insertion accident and, more specifically, the maximum fuel enthalpy byanalysis will not exceed the specified value; and the emergency core cooling system will becapable of preventing major damage to the fuel in a loss of coolant accident, and the fuel cladding
metal water reaction will be limited to sufficiently small amount.
Regarding item a), the design requirements are stipulated in guidelines 11 and 12 of theRegulatory Guide for Safety Design. Regarding item b), the design requirements are stipulated in
guidelines 34 to 40 (Safety Protection System). Regarding item c), the design requirements are
stipulated in guidelines 12, 14 and 25. The requirements for safety evaluation are also stipulated
in the Regulatory Guide for Evaluating Reactivity Insertion Events of Light Water Nuclear Power
Reactor Facilities and the Regulatory Guide for Evaluating Emergency Core Cooling System
Performance of Light Water Nuclear Power Reactors.
2) Reactor Coolant Pressure Boundary
The reactor coolant pressure boundary shall be so designed that the integrity will be maintained
during normal and abnormal operating conditions; that the boundary will not exhibit brittle
behavior or develop rapid brittle fracture during normal operation, maintenance, testing, orabnormal conditions; that the leakage will be detected immediately and surely; that tests andinspections will verify its integrity throughout the service life of the nuclear reactor, which arerequired in guidelines 19 to 22 of the Regulatory Guide for Safety Design. Pressure on reactor
coolant pressure boundary will not exceed the specified value during reactivity insertion events,
which is required in guideline 14 of the Regulatory Guide for Safety Design.
3) Reactor Containment
The reactor containment shall be so designed that it will withstand the loads of design basis
accident and the appropriate design basis earthquake; that it will prevent leakage exceeding thepredetermined leakage rate; that it will allow periodic testing on the leakage rate; that its
boundary will not exhibit brittle behavior or develop rapid brittle fracture during normal operation,
maintenance, testing and in abnormal conditions; and that isolation valves should be placed in thepipelines that penetrate its walls, which are required in guidelines 28 and 29 of the Regulatory
Guide for Safety Design.

18.3

Prevention of Accidents and their Mitigation Systems (Regulatory Guide for Reviewing
Classification of Importance of Safety Functions for Light Water Nuclear Power Reactor
Facilities)

In Japan, the Regulatory Guide for Reviewing Classification of Importance of Safety Functions forLight Water Nuclear Power Reactor Facilities (hereinafter called as " Regulatory Guide forClassification of Importance") prescribe the system for preventing the occurrence of abnormalities andthe system for mitigating the impact of abnormalities. That is, since the Regulatory Guide for Safety
Design used at the safety examination must be appropriately applied according to the safety
importance of the subject structures, systems and components, safety functions and the classificationof importance of the structures, systems and components are defined in this " Regulatory Guide forClassification of Importance".

18-3

(1) The Concept of the Classification of Importance for the Safety Design

The importance of the safety function of the structures, systems and components are classified into
the following two classes and shown in the Regulatory Guide for Classification of Importance.
A) Those of which loss of the function could result to cause an abnormality of the nuclear reactor
facility, which causes excessive radiation exposure on general public or the working personnel (thesystem for preventing the occurrence of abnormalities, hereinafter called as “PS”). B) Those thathave the function to prevent the propagation of abnormality or terminate it quickly in an abnormal
situation of a nuclear reactor facility, and to protect general public or the working personnel frompossible excessive radiation exposure (the system for mitigating the impact of abnormalities,
hereinafter called as “MS”). The structures, systems and components, which belong to these PS andMS respectively, are classified into three classes in accordance with the importance of their safetyfunction. It stipulates, from the standpoint to ensure the safety function, that the basic objective foreach class shall meet the following requirements according to the technologies of design, construction
and tests, and operation management.
Class 1: Secure and maintain as high as reasonably achievable level of reliability.
Class 2: Secure and maintain a high level of reliability.
Class 3: Secure and maintain a level of reliability equal to or higher than that for general industry.
The classifications of the structures, systems and components and their safety functions are listed inTable 18-2.
(2) Installation of the PS and MS

The PS and MS installed in the light water reactors in Japan are as follows.
After grouping all light water reactors, currently installed in Japan, based on the reactor type and thecontainment type, the essential system for PS and MS which are installed in each nuclear reactor
facilities are shown in Table 18-3 and Table 18-4 for BWR and PWR respectively. These tables
summarize the system configuration and their classification of reactor shutdown system, emergency
core cooling system and heat removal system, the number of diesel generators and the containment
shape, as essential systems for preventing the occurrence of abnormalities and system for mitigating
the impact of abnormalities.

18.4

Preparation of Accident Management Policy

Since the TMI-2 accident, the researches on phenomena of severe accidents and PSA have been
conducted extensively worldwide. The NSC decided “Accident Management as a Measure for Severe
Accident at Light Water Nuclear Power Reactor Facilities” in 1992, and revised it in 1997. Licence holders
in Japan also have voluntarily implemented their own measures for preventing severe accidents andfor mitigating their consequences at the request of the MITI (then) based on the the NSC’s decision.
As embodiment of the accident management measures for operating commercial power reactors,
licence holders have been developed the accident management in orderly manner, substantiate theequipment during the outage of the periodic inspection and establishing operational measures such as
implementing system, procedures, education of personnel, etc. And the accident management related
to the internal events for 52 units of commercial power reactors under operation has alreadycompleted the preparation.
The accident management measures that were prepared by licence holders were reported to NISA in
May, 2002, together with the PSA results of internal events for representative reactor types for the
purpose of quantitatively verifying the effectiveness of enhancement of the safety.
18-4

While licence holders were developing accident management measures, NISA requested NUPEC(then) to evaluate the effectiveness of the accident management measures, and established the"Accident Management Workgroup" under the Nuclear and Industrial Safety Subcommittee to obtain
the opinion of specialists, and evaluation report was compiled and issued in October 2002. The report
was submitted to the NSC by NISA in the same month.
The PSA results of the internal events for all commercial power reactor facilities under operation(excluding representative reactor types) were reported to NISA by the licence holders in March 2004.
The development programs of the accident management for the commercial power reactors underconstruction (three units) were reported to NISA by the licence holders in July 2003, and theevaluation results etc. were reported to the NSC by NISA in September 2003. The NSC evaluated thereport and concluded it was reasonable in December 2003. In addition, the accident management
measures for the reactor facilities concerned are being prepared by the licence holders.

Measures to Ensure the Technical Reliability by Experience, Test and Analysis

18.5

In Japan, in order to enhance the safety and reliability of commercial power reactors, those activities
such as feedback of the operating experience and utilization of the technical knowledge obtained
through testing and analysis have been conducted, as describe below.
Those insights newly obtained through these activities have been timely incorporated in existing
guidelines and used to develop new guidelines.
(1) Feedback of Operating Experiences of Commercial Power Reactors−−−

The good practices and in-compliances identified through periodic inspections, as well as theexperience in design, construction and operation of domestic and foreign commercial powerreactors, were analyzed, and the results are incorporated in design modification,
improvement of construction methods, etc., if recognized to be effective, through theestablishment license, approval of construction plans and pre-service inspections, if
necessary.
For an accident or a failure occurred in a commercial power reactor, including foreign
reactors, the corrective measures are implemented after identifying the cause of failure.
From the standpoint of the comprehensive preventive maintenance of nuclear reactor
facilities, periodic safety review is performed for each commercial power reactor with theinterval of approximately ten years. And its safety and reliability are confirmed, reflecting
the results of comprehensive evaluation on operating experiences and the latest technicalknowledge. The situation of periodic safety review is described in Article 14.

(2) Feedback of the Knowledge Obtained Through Test and Analysis

Recognizing the importance of assuring the safety in development and utilization of nuclear energy,
preparatory researches of safety standards, guidelines, reference materials for acceptance decision insafety examination etc., as well as improvement of the safety itself, are promoted in Japan.
1) Implementation of Safety Research, Verification Test and Analysis
Since the 1976 fiscal year, the NSC has decided the safety research annual program upon threefields of nuclear facilities etc., environmental radioactivity and radioactive wastes as a five-year
plan, and conducted the safety researches at JAERI etc., periodically looking over the contents.
The 6th five-year research program is going on now.

18-5

On the other hand, METI has also entrusted and implemented various kinds of tests, analysis, etc.
to NUPEC, JAPEIC, etc. in order to demonstrate and verify the safety of nuclear facilities.
These verification tests and researches include safety researches on refinement of fuels, safety
researches on aging plants, various kinds of researches on the severe accident, researches on theprobabilistic safety assessment, researches on human and organization factors, researches on
decommissioning, researches on the nuclear emergency preparedness, seismic verification tests,
and vibration tests of steam generator tubes, etc.
The NSC has developed a new safety research plan (important safety research programs). In theplan, the NSC clarified the important research programs that should be implemented in the five
years starting from 2005 in order to improve nuclear safety regulations. In the plan, the safety
verification tests are deliberated as to be included as important safety research programs.
Regarding the analysis, the safety analysis codes necessary for the evaluation performed bypersons other than the applicant for a reactor establishment license are prepared and improved by
NUPEC (then , now JNES), and safety analysis for the newly applied commercial power reactor
and regulatory evaluation of the measures of accident management policy of operating nuclear
power reactors, etc. are performed using those codes.
2) Reliability Enhancement Activity by Licence Holders
Licence holders and manufacturers, etc. are also playing an active role in developing thetechnology through the Improvement and Standardizing Program and introducing new technology.
CRIEPI is also conducting the research such as human factor.
The remarkable results of the Improvement and Standardization Program are reflected to thedesign of Advanced BWR (ABWR) and Advanced PWR (APWR).
For ABWR, two units are already in operation, two units are under construction, and four units
are in preparation for construction at this time. Features of ABWR design includes elimination of
the large diameter re-circulation piping connected to the reactor vessel by adoption of reactor
internal pumps, alteration of the control rod drive mechanism during normal operation fromhydraulic to motor driven mechanism that is possible to make fine control of the position, and soon.
On the other hand, For APWR, two units are in preparation of construction at this time. The
basic design of APWR was developed based on the outcome of the Improvement andStandardization Program, and also reflecting latest new technologies and operation andmaintenance experience. APWR has the features such as simplification of the in-core structure byadoption of neutron reflectors which replaces with the baffle and former structure, upgrading of
the emergency core cooling system, and so on.
For BWRs, up to now, as for improvements of component reliability, improvement of structural
materials, removal of residual stresses, improvement of water chemistry, etc. have been carriedout, in order to prevent the stress corrosion cracking of the component which consists of reactor
core internals or the reactor coolant pressure boundary.
For PWRs, modifications such as improvements of heat transfer tube materials and improvementsof water quality of the secondary loop, etc. have been carried out to prevent damages of steam
generator heat transfer tubes.
Overall digitization has been carried out for instrumentation and control facilities including thesafety protection system of the new plants for both of BWRs and PWRs.

18-6

18.6

Consideration of Human Factors and the Man-Machine Interface

It is the safety requirements regarding operating management to make commercial power reactor morereliable, more stable and more easily manageable taking into human factors and man-machineinterface. These requirements are implemented in design and operation of the commercial powerreactors in Japan.
Considerations of the design to an operator behavior, requirements on the design of a control room andconcrete design to approach these requirements are described in the report of Article 12.

18-7

Table 18-1 Individual guidelines established in the NSC Regulatory Guide
for Reviewing Safety Design of Light Water Nuclear Power Reactor Facilities (1/2)(General requirements for nuclear reactor facilities)
Guideline 1. Applied standard and standards
Guideline 2. Design considerations against natural phenomena
Guideline 3. Design considerations against external human initiated events
Guideline 4. Design considerations against internal missile
Guideline 5. Design considerations against fire
Guideline 6. Design considerations environmental conditions
Guideline 7. Design considerations for share use
Guideline 8. Design considerations against operator actions
Guideline 9. Design considerations for reliability
Guideline 10. Design considerations for testability(Nuclear reactor and reactor shutdown system)
Guideline 11. Core design
Guideline 12. Fuel design
Guideline 13. Reactor characteristics
Guideline 14. Reactivity control system
Guideline 15. Independence and testability of reactor shutdown system
Guideline 16. Reactor shutdown margin by control rods
Guideline 17. Shutdown capability of reactor shutdown system
Guideline 18. Reactor shutdown system capability at the accident(Reactor cooling system)
Guideline 19. Integrity of reactor coolant pressure boundary
Guideline 20. Prevention of reactor coolant pressure boundary failure
Guideline 21. Detection of the reactor coolant pressure boundary leaks
Guideline 22. In-service test and inspection of reactor coolant pressure boundary
Guideline 23. Reactor coolant make-up system
Guideline 24. Systems for removing residual heat
Guideline 25. Emergency core cooling system
Guideline 26. System for transporting heat to ultimate heat sink
Guideline 27. Design considerations against loss of power(Reactor containment)
Guideline 28. Function of reactor containment
Guideline 29. Prevention of reactor containment boundary failure
Guideline 30. Isolation function of reactor containment
Guideline 31. Reactor containment isolation valves
Guideline 32. Reactor containment heat removal system
Guideline 33. System for controlling containment atmosphere(Safety protection system)
Guideline 34. Redundancy of safety protection system
Guideline 35. Independence of safety protection system
Guideline 36. Function of safety protection system during transients
Guideline 37. Function of safety protection system during the accident
Guideline 38. Function of safety protection system at time of failure
Guideline 39. Separation of safety protection system from instrument and control system
Guideline 40. Testability of safety protection system

18-8

Table 18-1 Individual guidelines established in the NSC Regulatory Guide
for Reviewing Safety Design of Light Water Nuclear Power Reactor Facilities (2/2)(Control room and emergency facility)
Guideline 41. Control room
Guideline 42. Reactor shutdown function from outside of control room
Guideline 43. Design considerations for control room habitability
Guideline 44. On-site emergency station
Guideline 45. Design considerations for communications equipment
Guideline 46. Design considerations for evacuation route(Instrumentation and control system and electrical system)
Guideline 47. Instrumentation and control system
Guideline 48. Electrical system(Fuel handling system)
Guideline 49. Fuel storage and handling system
Guideline 50. Prevention of fuel criticality
Guideline 51. Monitoring of fuel handling area
(Radioactive waste processing facility)
Guideline 52. Radioactive gaseous waste processing facility
Guideline 53. Radioactive liquid waste processing facility
Guideline 54. Radioactive solid waste processing facility
Guideline 55. Radioactive solid waste storage facility(Radiation management)
Guideline 56. Environmental radiation protection
Guideline 57. Radiation protection for personnel engaged in radiation work
Guideline 58. Radiation management for personnel engaged in radiation work
Guideline 59. Radiation monitoring

18-9

Table 18-2

Definitions and functions with respect to classifications ofimportance of safety function (1/2)
Classification
Definition
Function
Class 1 PS-1 Structures, systems and components where (1) Reactor coolant pressure
there is concern thatboundary function(a) a conspicuous damage to the core, or (2) Excessive reactivity insertion(b) significant damaging the core may
prevention function
occur,(3) Core shape maintenancedue to an event caused by such damage orfunction
malfunction.
MS-1 (1) Structures, systems and components(1) Reactor emergency shutdown
that implement an emergency shutdown
functionof the nuclear reactor, remove the(2) Sub-criticality maintenanceresidual heat, prevent excess pressurefunctionin the reactor coolant pressure(3) Function to prevent
boundary and prevent an impact ofover-pressurization of reactor
excessive radiation on the public in the
coolant pressure boundarysite vicinity, at the occurrence of an(4) Cooling function after reactor
abnormal condition.
shutdown(5) Core cooling function(6) Radioactive material
confinement function, shieldingof radiation and release
reduction functions(2) Other essential safety related(1) Generation function of an
structures, systems and components
actuation signal for theengineered safety features and to
the reactor shutdown system(2) Specially important safety
related functions
Class 2 PS-2 (1) Structures, systems and components(1) Function the builds in reactor
for which there is no concern of thecoolant (However, this excludes
immediate causing of conspicuous
small diameter piping, such asreactor damage or significant fuelinstrumentation, etc., excluded
damage due to an event that occurs
from the reactor coolant pressure
due to such a damage or malfunction,boundary and those that are not
however, for which there is a concern
connected directly to theof excessive release of radioactive
boundary.)
materials outside the site vicinity.
(2) Components not directly
connected to the reactor coolant
pressure boundary, which havethe radioactive materials storage
function(3) Function for the safe handling offuel(2) Structures, systems and components(1) Safety valve and relief valve
which must be actuated during normal
reclosing function
operation and upon an abnormaltransient during operation for which
there is a high potential that corecooling will be lost due to theconcerned malfunction.
Reference : “Examination Guideline for Classification of Importance of Safety Functions for Light Water
Reactor Facilities”, decision by the NSC in August 30, 1990.

18-10

Table 18-2
Classification
MS-2

Class 3

PS-3

MS-3

Definitions and functions with respect to classifications of importanceof safety function (2/2)
Definition
Function(1) Structures, systems and(1) Fuel pool water supply function(2) Function to prevent the discharge ofcomponents for adequately
radioactive materials
reducing the impact of radiationon the general public in thevicinity of the site, due to damage
or malfunction in the structures,
systems and components of the
PS-2.
(2) Structures, systems and(1) Function for determining thecomponent with a speciallysituation of the plant at the time ofimportant function in the responsean accident(2) Function for mitigation of abnormalof abnormal situations.
situations(3) Function for safe shutdown fromoutside the control room(1) Structures, systems and(1) Reactor coolant preserving function
components where initiating(components other than PS-1 andevents of abnormal situations takePS-2)(2) Reactor coolant circulation function
place, and which are other than(3) Radioactive material storage
PS-1 and PS-2 components.
function(4) Power supply (excluding
emergencies)(5) Plant instrumentation and control
function (excluding safety
protection function)(6) Plant operation supporting
functions(2) Structures, systems and(1) Function for preventing thecomponents which hold the
diffusion of fission products into
concentration of the radioactive
the reactor coolantmaterials in the reactor coolant to (2) Reactor coolant purification
functiona level low enough not to impair
normal operation(1) Structures, systems and(1) Function for mitigation of reactor
components which mitigatepressure increase(2) Function to control the power
events in conjunction with theincreases
MS-1 and MS-2, even when there(3) Reactor coolant make-up function
is an abnormality during
operation(2) Structures, systems and(1) Important for emergency responsecomponents required for theand function for recognizing
response of abnormal situations
abnormal situations

18-11

Table 18-3 Establishment situation of prevention and mitigation system (BWR nuclear installation) (1/2)
BWR 2 & 3

BWR 4

BWR 5

ABWR

Containment type

MARK-I

MARK-I

Improved MARK-I ,MARK-II and Improved MK-IIRCCVName of power
station

Unit 1 of Tsuruga PS (BWR2)
Unit.1 Fukushima Daiichi, (BWR 3)

Unit 1of Hamaoka NPS
Unit 1of Onagawa NPS
Unit 1 of Shimane NPS
Unit 2 of Fukushima Daiichi NPS
Unit 3 of Fukushima Daiichi NPS
Unit 4 of Fukushima Daiichi NPS
Unit 5 of Fukushima Daiichi NPS
Unit 2 of Hamaoka NPS

Reactor shutdown
systemSCRAM system
Stand-by Liquid Control System

SCRAM system
Stand-by Liquid Control System

18-12

Plant type

Unit 1 of Shika NPS (Improved MK-I)
Unit 2 of Shimane NPS (-ditto-)
Unit 2 of Onagawa NPS (-ditto-)
Unit 3 of Onagawa NPS (-ditto-)
Unit 3 of Hamaoka NPS (-ditto-)
Unit 4 of Hamaoka NPS (-ditto-)
Tokai Daini (MK-II)
Unit 6 of Fukushima Daiichi NPS, (-ditto-)
Unit 1 of Fukushima Daini NPS (-ditto-)
Unit 1 of Kashiwazaki Kariwa NPS (-ditto-)
Unit 2 of Fukushima Daini NPS (Improved
MK-II)
Unit 3 of Fukushima Daini NPS (-ditto-)
Unit 4 of Fukushima Daini NPS (-ditto-)
Unit 2 of Kashiwazaki Kariwa NPS (-ditto-)
Unit 3 of Kashiwazaki Kariwa NPS (-ditto-)
Unit 4 of Kashiwazaki Kariwa NPS (-ditto-)
Unit 5 of Kashiwazaki Kariwa NPS (-ditto-)
SCRAM system
Stand-by Liquid Control System

Unit 6 of Kashiwazaki Kariwa NPS
Unit 7 of Kashiwazaki Kariwa NPSSCRAM system
Stand-by Liquid Control System

Containment shape
Reactor Pressure Vessel

Reactor Pressure Vessel

Primary
Containment
Vessel

MARK-I

Primary
Containment
VesselImproved MARK-I

MARK-II

Reactor Pressure Vessel

Primary
Containment
VesselImproved MARK-II

Advanced BWR (RCCV)Table 18-3 Establishment situation of prevention and mitigation system (BWR nuclear installation) (2/2)
Plant type

BWR 2 & 3

BWR 4

Containment type

MARK-I type

MARK-I type

Systemconfiguration of
ECCS and heatremoval system

HPCI

18-13

IC

IC

CS

CS

CS

CS

CCS

CCS

CCS

CCS

RCIC
CS

BWR 5
Improved MARK-I type,
MARK-II type andImproved MARK-II types

LPCI

LPCI

LPCI

LPCI

RHR

RHR

RCIC
LPCS
LPCI/RHRRCCV type

HPCF
LPFL/RHR

HPCS

HPCI
CS

ABWR

LPCI

RCIC

HPCF

LPCI/RHR LPFL/RHR

LPFL/RHR

ADS

ADS

ADS

2 partitions

2 partitions

3 partitions

3 partitions

2

2

3

3

SHC

SHC
ADS
Divisions of system
configuration
Number of D/G

IC: Isolation Condenser.
CS: Core Spray Sys.
CCS: Containment Cooling Sys.
RHR: Residual Heat Removal Sys.

SHC: Shutdown Cooling Sys.
HPCI: High Pressure Core Injection Sys.
LPCI: Low Pressure Coolant Injection Sys.
HPCF: High Pressure Core Flooder

RCIC: Reactor Core Isolation Cooling Sys.
ADS: Automatic Depressurization Sys.
HPCS: High Pressure Core Spray Sys.
LPFL: Low Pressure Core Flooder

Plant Type

Table 18-4 Establishment situation of prevention and mitigation systems (PWR nuclear installation) (1/2)
4 Loop2 Loop3 LoopContainment type
Name of power
station

PCCV type
Unit 3 of Ohi PS
Unit 4 of Ohi PS
Unit 2 of Tsuruga PS
Unit 3 of Genkai NPS
Unit 4 of Genkai NPS

Reactor shutdown
systemContainment shape

Scram system
Boric acid injection system
PCCV type

18-14

Outer
ShieldingWall

Dry type
Dry type
Unit 1 of Ikata PS
Unit 1 of Takahama PS
Unit 2 of Ikata PS
Unit 2 of Takahama PS
Unit 1 of Mihama PS
Unit 3 of Takahama PS
Unit 2 of Mihama PS
Unit 4 of Takahama PS
Unit 1 of Genkai NPS
Unit 3 of Mihama PS
Unit 2 of Genkai NPS
Unit 1 of Sendai NPS
Unit 1 of Tomari PS
Unit 2 of Sendai NPS
Unit 2 of Tomari PS
Unit 3 of Ikata PS
Scram system
Scram system
Boric acid injection system
Boric acid injection system
Dry type

Reactor Containment

Outer
ShieldingWall

4 LoopIce condenser type
Unit 1 of Ohi PS
Unit 2 of Ohi PS

Scram system
Boric acid injection system
Ice condenser type

Outer
Shielding
Wall
Reactor Containment

Reactor Containment

Outer
Shielding
Wall

Reactor Containment
Reactor Vessel
Reactor Vessel

Reactor Vessel

Freestanding steel type
(no top dome)

Freestanding steel type(with top dome)

Reactor VesselTable 18-4 Establishment situation of prevention and mitigation systems (PWR nuclear installation) (2/2)
Plant Type

4 Loop2 Loop3 Loop4 LoopContainment type

PCCV type

Dry type

Dry type

Ice condenser type

Systemconfiguration of
ECCS and heatremoval system

ACC 4 units

ACC 2 units

ACC 3 units

ACC 4 units

HPIS

HPIS

HPIS

HPIS

LPIS
(/RHR)LPIS(/RHR)LPIS (/RHR)

LPIS (/RHR)

AFWS

AFWS

AFWS

(motor driven)

AFWS(motor driven)(motordriven)(motordriven)

18-15

AFWS

AFWS

(turbine driven)(turbine driven)

HPIS (/CHP)

HPIS(/CHP)

HPIS(/CHP)LPIS(/RHR)LPIS(/RHR)AFWS

AFWS(motor driven)(motor driven)

HPIS

HPIS

HPIS
(/CHP)

HPIS(/CHP)LPIS(/RHR)LPIS(/RHR)AFWS

AFWS(motor driven)(motor driven)

AFWS
AFWS

(turbine driven)(turbine driven)

Divisions of system
configuration

2 systems

2 systems

2 systems

2 systems

HPIS boosting
unnecessary

HPIS boosting necessary

HPIS boosting necessary

HPIS boosting necessary

Number of D/Gs
22
22
ACC: Accumulator, AFWS: Auxiliary Feed Water Sys, LPIS: Low Pressure Coolant Injection ., HPIS: High Pressure Injection Sys.
RHR: Residual Heat Removal Sys., CHP: Charging Pump

Article 19

Operation

Each Contracting Party shall take the appropriate steps to ensure that:(i)
the initial authorization to operate a nuclear installation is based upon an appropriate
safety analysis and a commissioning programme demonstrating that the installation, as
constructed, is consistent with design and safety requirements;(ii)
operational limits and conditions derived from the safety analysis, tests and operational
experience are defined and revised as necessary for identifying safe boundaries for
operation;(iii)
operation, maintenance, inspection and testing of a nuclear installation are conducted inaccordance with approved procedures;(iv)
procedures are established for responding to anticipated operational occurrences and to
accidents;(v)
necessary engineering and technical support in all safety-related fields is available
throughout the lifetime of a nuclear installation;(vi)
incidents significant to safety are reported in a timely manner by the holder of therelevant licence to the regulatory body;(vii)
programmes to collect and analyse operating experience are established, the results
obtained and the conclusions drawn are acted upon and that existing mechanisms areused to share important experience with international bodies and with other operatingorganizations and regulatory bodies;(viii) the generation of radioactive waste resulting from the operation of a nuclear installation
is kept to the minimum practicable for the process concerned, both in activity and involume, and any necessary treatment and storage of spent fuel and waste directly
related to the operation and on the same site as that of the nuclear installation take into
consideration conditioning and disposal.
Licence holder is allowed to commence operation after the license conditions specified by the Reactor
Regulation Law etc. are complied in the stage from licensing for establishment to the construction of commercial
power reactors.
As legal regulations for licence holders to operate reactors safely, it is obliged to provide the Operational Safety
Programs approved by the Minister of METI before commencement, and to observe necessary measures for
operation and maintenance of commercial power reactors like Periodic Inspection etc., all through operating life
time.
After the last reporting, demarcation of the Periodic Inspection and the Licensee’s Periodic Inspection wereclarified, and the scheme of the Periodic Safety Management Review is newly established.
Moreover, quality assurance activities, maintenance management activities, Periodic Safety Review, etc. aredecided to be included into the Operational Safety Program.
As an inspection to verify the integrity of equipment, licence holders conduct Licensee’s Periodic Inspections offacilities that are designated by the ordinance of the METI, and NISA (or JNES) perform his Periodic Inspection
attending the Licensee’s Periodic Inspection of important facilities for the public safety, or confirming the recordof the Licensee’s Periodic Inspection for verification of the safety. As for the Licensee’s Periodic Inspection, it isobliged for licence holders to inspect periodically and to record and keep the results.
Furthermore, JNES examines the implementation system of the Licensee’s Periodic Inspection (Periodic Safety
Management Review ), and notifies these results to NISA. NISA makes comprehensive evaluation on theimplementation system of the Licensee’s Periodic Inspection based on the notification by JNES.
As for the inspection to verify the licensee’s observance of activities for safe operation, the Nuclear Safety
Inspection is conducted by NISA, and NISA verifies whether processes such as implementing systems oflicensee’s activities for safe operation are appropriate in the light of quality assurance.
In addition, NISA has initiated the reexamination of the inspection system to evaluate the possibility to utilize19-1

risk assessments and/or performance evaluations.

19.1 Initial License
Licence holders in Japan are required by the Reactor Regulation Law to take the necessary measures
for safe operation of reactor facility and protection of specified nuclear fuel materials. Pursuant to thisprinciple, basic design (items in the main text of establishment license application document)
approved by the Minister of METI must be observed throughout each stage of detailed design,
construction and operation. In addition to the conditions in the application main text, major items in
the attachments are to be observed as well.
Licence holders are also required to observe the conditions of establishment license in the applicationof construction plan (or design approval for fuel assembly), in which detailed design for each facilityof a commercial power reactor is reviewed. Before the commissioning of a commercial power reactor,
NISA conducts pre-service inspections to ensure the compliance with the licensing conditions.
After fulfilling regulatory procedures up to the construction stage shown in Fig. 7-3 of Article 7,
licence holder is allowed to commence the operation of commercial power reactor.
The regulatory requirements for safe operation are prescribed in the Reactor Regulation Law. Thus,
licence holders must develop safety measures necessary for operation and maintenance of the reactor,
transportation and disposal of radioactive waste, prepare the Operational Safety Program and obtainapproval of them from the Minister of METI and comply with them, assign Chief Engineers ofReactors and designate a Person Responsible for Operation who is responsible to the specified
activities for safe operation and to make and keep operational records.
Moreover, in accordance with the Electricity Utilities Industry Law, it is specified that a Chief
Electrical Engineer and a Boiler and Turbine Chief Engineer shall be assigned and submitted notice tothe authority and also obliged that Licensee’s Periodic Inspection, Periodic Inspection and Periodic
Safety Management Review shall be undergone within the interval not exceeding 13 months.

19.2 Limiting Conditions for Operation
Operation and maintenance of commercial power reactors are carried out in accordance with the
Operational Safety Program approved by the Minister of METI in Japan.
Shown in Table 19-1 are the items included in Operational Safety Program. In item 3 of the program,the Limiting Conditions for Operation such as shutdown margin and reactor thermal limits, etc. are
included. Table19-2 shows the items of the Limiting Conditions for Operation for commercial powerreactors in Japan. If the LCO should not be complied, the Minister of METI could order the licenceholder to suspend the operation of the nuclear facility and so forth by the Reactor Regulation Law.
In Japan, commercial power reactor facilities were allowed to be operated only within the rated
electrical power. In December 2001, NISA reexamined the regulatory requirements, etc. and allowed
the plant operation at the rated thermal power to those plants, where the Operational Safety Programis revised, where the safety is verified, where the operation manual is prepared, and where theoperator training is implemented.

19.3 Regulations for Operation, Maintenance, Inspection and Testing
NISA posts a resident nuclear safety inspector at each commercial power reactor by the Reactor
Regulation Law to supervise the licence holder's observance on the Operational Safety Program, etc.
19-2

and conducts the Nuclear Safety Inspections four times a year.
Moreover, NISA is authorized to access to the nuclear facility and examine the records, documents andother necessary matters at any time when the Minister of METI recognized it is necessary.
Licence holders are obliged to include matters concerning quality assurance in the Operational Safety
Program in accordance with rules under the Reactor Regulation Law. Licence holders must establish
the organization to implement the quality assurance, and also must plan, implement, evaluate andimprove the activities for safe operation.
Licence holders are obliged to define maintenance management in the Operational Safety Program,and must define and implement policies, objectives, implementation plan, evaluation of the results,
corrective actions, and the record of maintenance management.
NISA confirms the implementing of quality assurance and maintenance management through the
Nuclear Safety Inspection.
Licence holders prepare various kinds of operation and test manuals in accordance with the
Operational Safety Program to define actual detailed operating procedures.
Licence holders set up a committee to discuss important matters related to safe operation such as themodification of the Operational Safety Program and of documented procedures beforehand.
Chief Engineers of Reactors qualified by governmental examination is assigned to each reactor by thelicence holder, and any appointment or dismissal is to be notified to NISA. The Chief Engineer ofReactor is authorized to express his view on safe operation to the site superintendent if he thinks it isnecessary, to gives advice or recommendation to site staff and to participate in planning the safe
operation.
Persons responsible for operation are appointed by the licence holder and assigned to every nuclear
reactor. His essential task includes patrolling through the premises regularly and recognizing theoperational conditions and safe operation etc. of the commercial power reactor under his
responsibility.
Operational records about the inspection of fuel assemblies and nuclear reactor, reactor operation,
radiation management, maintenance, incidents or failures and meteorology should be prepared andkept by the licence holder, by the Reactor Regulation Law.
Moreover, the Electricity Utilities Industry Law provides that the subject, method, result, etc. of theinspection are also required to be recorded and kept concerning the Licensee’s Periodic Inspection
result.
Licence holders must conduct a Licensee’s Periodic Inspection in order to verify that facilities conformto the technical standard. When a crack/(s) in important components is(are) discovered by theinspection, the licence holder shall evaluate the impact of the crack(s) on the fitness for services offacility, and the result shall be recorded, kept and also reported to NISA at the same time. Moreover,the safety related critical component must undergo and pass the Periodic Inspection conducted by
NISA and JNES.
The Periodic Inspection and the Licensee’s Periodic Inspection are conducted in shutdown conditionat the interval not exceeding 13 months from the date of commissioning or completion of the lastinspection.
Furthermore, licence holders must apply for the Periodic Safety Management Review on theimplementation system of his Licensee’s Periodic Inspection to JNES, in accordance with the19-3Electricity Utilities Industry Law. JNES report the result of the Periodic Safety Management Review to
NISA, and NISA evaluates the result. The scope of the succeeding safety management review may bevaried by JNES, with reflecting the NISA’s evaluation for licence holder’s performance.
Licence holders perform checks based on the Operational Safety Program in order to verify thecompliance to limiting conditions to operation.
Licence holders conduct a Periodic Safety Review of each reactor every 10 years, based on theReactor Regulation Law, as described in Article 14.
Before 30 years operation after commissioning, technical evaluation on aging is performed and thenext ten-year maintenance program should be planned, the ten-year maintenance program must be
re-evaluated every ten years thereafter.
For more effective and efficient inspection system, harmonizing to the basic policy of the NSC, NISA
intends to study on introduction of techniques of risk assessment or performance evaluation which are
already introduced in Europe and US into the Periodic Inspection and the maintenance management
for commercial reactors.
For this purpose, as the first step, the regulatory fields and the items in which the risk assessment andperformance evaluation should be utilized, are to be clarified, as the second step, the basic framework
and/or the roadmap of system introduction for short- and mid-terms, will be studied, then, as the third
step, the concrete design of institutional arrangement will be discussed later.

19.4 Response to Accidents and Anticipated Operational Occurrences
Licence holders are required to include “operation of nuclear reactor facility” in the Operational Safety
Program, in which the operational procedures for accidents and anticipated operational occurrences(abnormal events) as well as normal operation are described to cope with any incidents or abnormal
events smoothly.
In the procedures of "measures for any abnormal events", such procedures on recognition of thesituation, remedy to the cause, emergency measures, and a measure after reactor automatic scram andmanual startup of an emergency AC power supply and a gas processing system are included.
Moreover, licence holders are required to prepare "emergency measures " in " operation of nuclear
reactor facility ".
As "emergency measures", the licence holder defines, establishment of the nuclear emergency
preparedness organization, preparation of resources necessary to nuclear emergency preparedness,maintenance of the communication system among the related parties, implementation of nuclear
emergency exercises, official announcement of the emergency system, and the clearance of theemergency preparedness organization, etc. in accordance with the requirements of the Special Law ofEmergency Preparedness for Nuclear Disaster.
The details of an emergency preparedness are described in Article 16.

19.5 Engineering and Technical Support: Application of the Results of Research andDevelopment
METI has been promoting reliability verification test and research programs on major components andsystems to enhance the safety of commercial power reactors. For example, NUPEC (then) had
completed the demonstration test on the replacement method of BWR core shroud in 1997 and the19-4results have been utilized to confirm the reliability of the installation method and the welding method
for actual replacement. And the demonstration test on the replacement method of PWR reactor coreinternals was performed, and the outcome is to be utilized for actual replacement of the PWR internals
2004.
MEXT has been conducting safety research program as a part of nuclear science research. For
example, the research on deterioration and damage of the major components important to safety, suchas reactor pressure vessel under condition of the neutron irradiation is under way in JAERI,
accumulating the basic data for decision-making on the safety of long-term operation of powerreactors.
Safety assurance as prerequisite, and in order the nuclear power to play the role of a basic load electric
power, the licence holders are making efforts in technology developments for further improvement ineconomical efficiency and for the long life operation of light water reactors. For example, measures
for aging management covering the whole plant life, for major plant equipment of commercial powerreactors are systematically developed aiming for efficient operation and maintenance. Specifically, thestudy on material property data, development of monitoring technologies for degradation diagnosis,
development of life evaluation method, technology development for inspection, repair andreplacement of core internals etc. has been performed.
Various private sectors also have been conducting complementary activities. For example, JSME has
been developing and refining standards of industry associations for power generating components
based on the principle of neutrality, fairness and transparency. The rule to evaluate the structural
integrity of the nuclear equipment with flaws or cracks is provided in the "Rules on
Fitness-for-Service for Nuclear Power Plants" which was established in 2000 (partially revised in2002) by JSME.
As the fitness-for-service assessment system was introduced in October 2003, the Rules on
Fitness-for-Service for Nuclear Power Plants has been adopted as the evaluation standard, and NISA
has confirmed it is technically acceptable.
In addition to the standard of JSME, many efforts to decide various kinds of industrial standards havebeen made by Atomic Energy Society of Japan and Japan Electric Association. In order to use
industrial guidelines practically, rules for quality assurance and maintenance management, which
Japan Electric Association has developed, was verified by the regulatory body that they meetrequirements of quality assurance for commercial power reactors in December 2003.
19.6 Reporting of Incidents
Reactor Regulation Law and the Electricity Utilities Industry Law require licence holders to report thesituation and measures taken to the incidents or failures occurred in commercial power reactors to
NISA. The reporting criteria prescribed in these laws are shown in Table 19-3.
Licence holders are making efforts to perform feedback of the lesson learned from the situation andmeasures taken to these incidents, the corrective actions which were derived by root cause analysis toother commercial power reactors.
The frequency of unplanned reactor shutdowns per year of commercial power reactors in Japan isaround 0.2 times per reactor-year in recent years and well below the average of the world.
The International Nuclear Event Scale (INES) was introduced in August 1992 to assess eventsoccurred in commercial power reactors. Since then, no incident or accident of level 2 or above has
occurred in nuclear power plants and the most of events occurred are rated as level 0. INES results inJapan are shown in Appendix 2.5.

19-5

19.7 Collection, Utilization and Sharing of Operating Experience Information
NISA makes public of the incidents or failures immediately upon receiving the report and announces
the causes and recurrence-preventive measures when finalized. NISA assesses each incident or failure
in detail to abstract the lessons learned with respect to the safety, being advised by subcommittee
members of the Advisory Committee on Nuclear and Industrial Safety, who are experts on operation
management, inspection and radiation control. For example, the pipe rupture accident of the Unit 1 of
Hamaoka NPS occurred on November 7, 2001 was evaluated to be caused by the excessive pressure
force caused by rapid combustion of the non condensable gas (hydrogen) collected in the piping, andthe pipe resulted in ductility fracture. And the lesson learned was feed-backed, such as removal of thepiping etc., so that hydrogen gas might not be accumulated in the safety related piping of BWR plants
in Japan.
JNES has the system to collect and analyze safety information in and outside of the country. JNES
provides collected safety information and results of analysis quickly to NISA and share them with NISA.
JNES and NISA jointly established “Safety Information Review Meeting” to evaluate them and to takeadequate regulatory measure. Safety Information Review Meeting is held periodically.
In regard to international information exchange, the mechanism has been established to share theinformation on nuclear incidents and failures with the IAEA and OECD/NEA as well as in the bilateral
corporations with China, France, Korea, Sweden and the United States.
Meanwhile, licence holders collect and analyze information on domestic and foreign operating
experiences by themselves and through CRIEPI. Concerning to the safety information of domestic
plants, they developed a tool, “NUCIA” that is a nuclear information disclosure library, with which
information including minor events can be shared by all over Japan, and it is on the Internet since
October 2003. Moreover, overseas information exchange is performed through the institute of nuclear
power operation (INPO) and the World Association of Nuclear Operators (WANO) Tokyo Center.
Furthermore, each licence holder utilizes individual agreements on information exchange with utilities
and manufacturers in France, Germany and the United States. As a lessons learned form JCO
Criticality Accident, recognizing the importance to share safety information and foster safety culture in
all nuclear industries, all of the relevant nuclear industries established a private organization "Nuclear
Safety Network" in December 1999, as described in Article 10.
There are many feedback of operating experience by licence holders, which are reflected in preventive
maintenance and planned repair and replacement of parts. Examples for BWR are replacements of thecore shroud and the in-core monitoring housing etc.. An example for PWR is replacement of upper
head of reactor vessel.

19.8 Management of Spent Fuel and Radioactive Waste
Details are described in the National Report of Japan (September 2003) for the "Joint Convention on
the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management".

19-6

Table 19-1 Items to be Included in the Operational Safety Program
1) The duties of personnel engaged in the operation and management of the nuclear reactor facility,
and the organization
2) The following items with respect to safe operation education for personnel engaged in theoperation and management of the nuclear reactor facility
a. Policy for the safe operation education (including preparation of education program)b. The contents of safe operation education as followsi) Relevant laws and the Operational Safety Programii) Structure, performance and operation of the nuclear reactor facilityiii) Radiation managementiv) Handling of nuclear fuel materials and objects contaminated by themv) Measures to be taken in emergencies
c. Other necessary items for safe operation education of the nuclear reactor facility3) Operation of the nuclear reactor facility4) Safety reviews on the operation of the nuclear reactor facility5) Designation of radiation controlled areas, access controlled areas and environment monitoringareas, and restriction of access to these areas
6) Ventilation and drainage monitoring equipment
7) Monitoring of the dose, the dose equivalent, the concentration of radioactive materials and thesurface contamination density of radioactive materials of objects contaminated by radioactive
materials, and the decontamination
8) Management of radiation measuring instruments
9) Patrols and checks of the nuclear reactor facility and their associated measures10) Receipt, delivery, transport, storage and other handling of nuclear fuel materials
11) Disposal of radioactive waste12) Measures to be taken in an emergency13) Records on safe operation of the nuclear reactor facility (including compliance of the
Operational Safety Program)
14) Maintenance management of the nuclear reactor facility (except those contained in the next
item)15) Periodic assessment of the nuclear reactor facility16) Quality assurance of the nuclear reactor facility17) Other necessary items for safe operation of the nuclear reactor facility

19-7

Table 19-2 (Part 1) Items of Limiting Conditions for Operation (BWR)
SystemItem
Reactivity control
systemShutdown margin, Reactivity monitoring, Control rod motion monitoring,Control rod scram time, Control rod operation, Boron water injection
systemPower
distribution

Reactor thermal limit, Reactor thermal power and core flow

Control &Instrumentation

Instrument and control equipment

Reactor coolant
systemReactor re-circulation pump, Jet pump, Main steam relief and safety valve,
Reactor coolant leak rate,
System pressure monitoring of the emergency core cooling system andreactor isolation cooling system,
Concentration of Iodine 131 in reactor coolant, Reactor shutdown coolingsystem, Limit of temperature & temperature change rate limit of primarycoolant, Reactor pressure

Emergency corecooling system

Emergency core cooling system, Reactor core isolation cooling system

Reactorcontainment
vessel system

Main steam isolation valve, Reactor containment vessel & Isolation valve,
Vacuum break valve from suppression chamber to drywell, Averagetemperature of suppression pool,
Flammability control system, Oxygen concentration in containment vessel,
Reactor building, Reactor building H&V isolation valve, Standby gas
treatment system

Plant system

Cooling system and cooling sea water system for residual heat removal
system, Emergency diesel generator cooling system, Cooling system andcooling sea water system for Diesel generator of High pressure core spraysystem,Water level & temperature of spent fuel pool,
Central control room H&V system

Emergency power
supply system

Offsite power supply system, Emergency diesel generator,
Emergency diesel fuel, DC power supply,
Station power system

OthersWithdrawal of single control rod during reactor shutdown
Removal of single control rod drive mechanism,
Inspection with withdrawal of multiple control rods,
In-service leak-rate or hydrostatic test,
Inspection with switching of reactor mode

19-8

Table 19-2 (Part 2) Items of Limiting Conditions for Operation (PWR)
SystemItem

Reactivity
controlsystemShutdown margin, Critical boron concentration,
Moderator temperature coefficient, Control rod motion function, Control rod
insertion limits, Control rod position indication, Physics tests, Chemical andvolume control system (function of boron concentration)Power
distribution

Reactor thermal power limit, Heat flux hot channel factor, Nuclear enthalpy
rise hot channel factor, Axial neutron flux difference, Quadrant power tilt ratio

Instrument and control equipment
Control &Instrumentation
Primary
coolant
systemDNB ratio, Temperature & pressure and temperature change rate of primarycoolant, Primary coolant system, Pressurizer, Pressurizer safety valve,
Pressurizer relief valve, Low temperature over-pressurization protection,
Primary coolant leak rate, Steam generator tube leak monitoring, Leakmonitoring to residual heat removal system, Iodine 131 concentration inprimary coolant

Emergencycorecooling system

Accumulator tank, Emergency core cooling system, Refueling water storagetank, Boron injection tank

Reactorcontainment

Reactor containment vessel, Reactor containment vessel vacuum relief valve,
Reactor containment vessel spray system,
Annulus air cleanup system, Annulus

Plant system

Main steam safety valve, Main steam isolation valve,
Main feedwater isolation valve, Main feedwater control valve,
Main feedwater bypass control valve, Main steam relief valve, Auxiliary
feedwater system, Condensate water tank,Component cooling water system, Sea water system for component coolingwater system, Emergency circulation system of control room, Air cleanup
system of safety auxiliary equipment room, Air cleanup system of fuelhandling building

Emergency
power
supply system

Offsite power supply, Diesel generator, Emergency diesel fuel & lubricating
oil and starting air for emergency diesel generator, Emergency DC power
supply, Station bus bar for emergency

OthersBoron concentration in primary coolant,
Water level of reactor cavity, Reactor containment penetrations,
Water level & temperature of spent fuel pit

19-9Table 19-3 Reporting Criteria of Incidents and Failures Provided in Legislations
Provision of the Reactor Regulation Law
1. When nuclear fuel material was stolen or lost.
2. When a reactor was shut down by failure of a reactor facility or when it became necessary
to shut down a reactor during operation, or when reactor power output changes more than
5%, or when reactor power output change of more than 5% was required. Except when it
was one of the following and the licence holder announced officially about the situation of
the concerned failure.
i) When it occurs in the term of the Periodic Inspection provided in Article 54-1 of theElectricity Utilities Industry Law (Law No. 170, 1964) i.e. the failure in the equipmentsthat the functional and operational conditions of the failed equipment cannot bechecked under the reactor shutdown condition.
ii) When the failure did not cause any deviation from the limit of operation (it is arequirement defined in the Operational Safety Program for operation of the nuclear
reactor facility, and when it cause any deviation from the concerned conditions themeasure that the licence holder should take is also defined in the Operational Safety
Program, the same in this paragraph), and there is no change observed related withthe concerned failure, and when the licence holder performs inspection of the failed
equipment concerned.
iii) When the reactor output change is required to follow the limit of operation.
3. When a licence holder checked the equipment and structure important to the safety of thenuclear reactor facility provided by the Minister of METI (hereinafter called as "equipment
etc. important to safety" in this paragraph as), and when concerned equipment etc.
important to safety was considered that it does not satisfy the standard described in Article
9 or in Article 9-2 of the Ministerial Ordinance of Establishing Technical Standards for
Nuclear Power Generation Equipment (Ordinace No. 62 of MITI, 1965), or when it wasconsidered that it does not have function to ensure safety of the nuclear reactor facility.
4. When there was a failure of equipment etc. important to safety by the fire. Except theconcerned failure was associated to the measure of fire extinguishing or prevention of the
spread of fire.
5. Except for the preceding three items, when deviation from the limit of operation by the
failure of a the nuclear reactor facility (except those minor troubles whose impact on
operation of nuclear reactor is insignificant) was caused, or when the measure for theconcerned deviation defined in the Operational Safety Program was not implemented at thetime of deviation from the limit of operation.
6. When the failure of a reactor facility or occurrence of other undetermined situation had
caused any trouble to discharge gaseous radioactive wastes through the ventilation facility
or to discharge liquid radioactive wastes through the drainage facility.
7. When the concentration of radioactive materials in the air outside the environment
monitoring area exceeds the allowable limit in the case of discharge of gaseous radioactive
wastes through the ventilation facility.
8. When the concentration of radioactive materials in the water outside the environment
monitoring area exceeds the allowable limit in the case of the discharge of liquidradioactive wastes through the drainage facility.
9. When nuclear fuel materials or materials contaminated with nuclear fuel materials(hereinafter referred to as "nuclear fuel materials etc.") leaked out of the controlled area.

19-10

10. When nuclear fuel materials etc. leaked within the controlled area associated to failure of a
nuclear reactor facility or occurrence of other undetermined situation. Exceptions are thefollowings (except the case when new measures such as access control into theleakage-related place and key control have been taken or when the leaked substances havespread outside the controlled area):i) When revealed liquid nuclear fuel materials etc. did not spread out of the floodgate thatis installed in the circumference of the equipment of the concerned leakage forprevention of leakage spread.
ii) When the ventilation facility of the concerned area of the leakage was working
properly at the time when gaseous nuclear fuel materials etc. leaked.
iii) When the amount of radioactivity of the leaked nuclear fuel materials etc. is very little
and when the degree of the leakage is minor.
11. When the person who enters into the controlled area suffered radiation exposure due to thefailure of a nuclear reactor facility or occurrence of other undetermined situation, andwhen the effective dosage of concerned exposure exceeds or could exceeds five mSv for a
personnel engaged in radiation work or 0.5 mSv for a person other than the personnel
engaged in radiation work.
12. When the dosage of personnel engaged in radiation work exceeds or could exceed theallowable dose limit.
13. Other than those above items, when persons are injured or could be injured in the thenuclear reactor facility (except when the injury was other than radiation hazard and was notnecessary for hospitalization).
Provision of the Electricity Utilities Industry Law
1. Fatal and injury accidents associated to electric shock, or breakdown of the electric
structure of a nuclear power generation, or miss-operation, or omission of the necessary
operation of the electric structure of a nuclear power generation (limited to the case ofdeath or being hospitalized at hospital or clinic for treatment).
2. Electric fire accident (limited to the case of more than the partial destruction by fire. Except
matters referred to in the previous item and the next to the fifth item).
3. Causing damage to public property due to failure of the electric structure of a nuclear
power generation, or miss-operation, or omission of necessary operation of the electric
structure, accident by which usage of road, park, school and other institution or structure
were made impossible or accident which did influence socially (except referred to previous
two items).
4. Breakdown accident of main electric structures (except referred to previous three items andthe next item).
5. Incident that influenced other electric utility to force suspension of electric power supply ofthan 7,000 kW and less than 70,000 kW for more than one hour, or suspension of electric
power supply more than 70,000 kW for more than ten minutes, associated to the breakdownof the electric structure of a nuclear power generation, or miss-operation, or omission ofoperation necessary for the electric structure of a nuclear power generation.

19-11

ANNEXESTABLE OF CONTENTS
Annex 1 List of Nuclear Installations ........................................................................................... A1-1
Annex 2 Data on Nuclear Installations......................................................................................... A2-1
2.1 Capacity of Electricity of Commercial Nuclear Power Reactors ............................................. A2-1
2.2 Capacity Factor of Commercial Power Reactors ....................................................................... A2-1
2.3 Frequency of Unplanned Shutdown at Commercial Nuclear Power Reactors ......................... A2-2
2.4 Reported Events (by Laws & Notifications) of Commercial Nuclear Power Reactors ........... A2-2
2.5 Assessment of Events by INES for Commercial Nuclear Power Reactors .............................. A2-3
2.6 Human Error Induced Events Reported ..................................................................................... A2-3
2.7 Dose per Persons at Commercial Nuclear Power Reactors........................................................ A2-4
2.8 Averaged Dose at Commercial Nuclear Power Reactors ......................................................... A2-4
2.9 Radioactive Gaseous Waste (I-131) Released from Commercial Nuclear Power Reactors ..... A2-5
2.10 Radioactive Liquid Waste (except H-3) Released from Commercial Nuclear Power ReactorsA2-5
2.11 Radioactive Solid Waste Generation per Electricity Generation of Commercial Nuclear Power
Reactors ................................................................................................................................. A2-6
Annex 3 Legislation and Guidelines ............................................................................................. A3-1
3.1. Atomic Energy Basic Law (Excerpt)......................................................................................... A3-1
3.2. Law for Establishment of the Atomic Energy Commission and
the Nuclear Safety Commission................................................................................................. A3-1
(1) Law for Establishment of the Atomic Energy Commission and
the Nuclear Safety Commission (Excerpt) ............................................................................. A3-1
(2) Rules of Nuclear Safety Commission Secretariat Organization (Excerpt).............................. A3-3
3.3 Law for Establishment of the Ministry of Economy, Trade and Industry .................................. A3-3
(1) Law for Establishment of the Ministry of Economy, Trade and Industry (Excerpt) ............... A3-3
(2) Ordinance for Organization of Ministry of Economy, Trade and Industry (Excerpt)............. A3-4
(3) The Rules for Organization of the Ministry of Economy, Trade and Industry (Excerpt) ........ A3-5
3.4. The Law of the General Rules for Incorporated Administrative Agency and the Law
for Japan Nuclear Energy Safety Organization.......................................................................... A3-7
(1) The Law of the General Rules for Incorporated Administrative Agency (Excerpt) ............... A3-7
(2) The Law for the Incorporated Administrative Agency, Japan Nuclear Energy
Safety Organization ................................................................................................................ A3-9
3.5. The Law on the Regulation of Nuclear Source Material,
Nuclear Fuel Material and Reactors ........................................................................................ A3-10(1) The Law on the Regulation of Nuclear Source Material,
Nuclear Fuel Material and Reactors ..................................................................................... A3-10i(2) Ordinance for the Enforcement of the Law on the Regulationof Nuclear Source Material, Nuclear Fuel Material and Reactors (Excerpt)........................ A3-18(3) Rules Concerning Report to Nuclear Safety Commission Provided in
Article 72-3, Paragraph 2 of the Law for the Regulations of
Nuclear Source Material, Nuclear Fuel Material and Reactors ............................................ A3-19(4) Ordinance for Implementation of Inspection Etc. by Japan Nuclear Energy Safety Organizationin Accordance with the Provision of the Law for the Regulations of Nuclear Source Material,
Nuclear Fuel Material and Reactors ..................................................................................... A3-20(5) The Rule for the Installation, Operation, etc. of Commercial Nuclear Power Reactors(Excerpt) ............................................................................................................................. A3-22(6) Notification for Radiation Dose Rate Limits, etc. Based on the Provisions of
the Rules for Installation, Operation, etc. of Commercial Power Reactors (Excerpt).......... A3-35
3.6. Law for Technical Standards of Radiation Hazards Prevention (Excerpt) .............................. A3-36
3.7. Law on Compensation for Nuclear Damage (Excerpt) ........................................................... A3-37
3.8. Industrial Safety and Health Law ............................................................................................ A3-38(1) Industrial Safety and Health Law (Excerpt) ......................................................................... A3-38(2) Rules for Prevention of Damage from Ionizing Radiation (Excerpt)................................... A3-38
3. 9. Electricity Utilities Industry Law ........................................................................................... A3-39(1) Electricity Utilities Industry Law (Excerpt) .......................................................................... A3-39(2) Ministerial Order for Performing Inspections etc. by the Incorporated Administrative Agency,
Japan Nuclear Energy Safety Organization in Accordance with the Provisions of
the Electricity Utilities Industry Law ................................................................................... A3-52(3) Rules for the Enforcement of the Electricity Utilities Industry Law (Excerpt).................... A3-55(4) Ordinance of Establishing Technical Standards for Nuclear Power Generation Equipment(Excerpt) ............................................................................................................................... A3-68(5) Technical Standards on Dose Equivalent, etc. due to Radiation Relating to Nuclear
Power Generation Equipment (Excerpt)............................................................................... A3-69
3.10. Basic Law on Emergency Preparedness................................................................................ A3-69(1) Basic Law on Emergency Preparedness (Excerpt) ............................................................... A3-69(2) Ordinance for the Enforcement of the Basic Law on Emergency Preparedness (Excerpt) .. A3-71(3) Basic Plan for Emergency Preparedness (Summary) ........................................................... A3-71
3.11. Special Law of Emergency Preparedness for Nuclear Disaster ............................................ A3-73(1) Special Law of Emergency Preparedness for Nuclear Disaster (Excerpt)............................ A3-73(2) Ordinance for the Enforcement of the Special Law of Emergency Preparedness
for Nuclear Disaster (Excerpt).............................................................................................. A3-75
3.12 Environmental Impact Assessment Law (Excerpt) ................................................................ A3-77
3.13 Guidelines............................................................................................................................... A3-81(1) Regulatory Guide for Reviewing Nuclear Reactor Siting
Evaluation and Application Criteria ..................................................................................... A3-81
ii

(2) Regulatory Guide for Reviewing Seismic Design ofNuclear Power Reactor Facilities (Excerpt) ......................................................................... A3-82(3) Regulatory Guide for Reviewing Safety Design ofLight Water Nuclear Power Reactor Facilities (Excerpt) ..................................................... A3-84(4) The Emergency Preparedness Guidelines,“Emergency Preparedness of Nuclear Installations” ............................................................ A3-89

iii

Annex 1

List of Nuclear Installations(As of August, 2004)(1)

Commercial Power Reactors
License Holder
The Japan Atomic
Power Co.
Hokkaido ElectricPower Co., Inc.
Tohoku ElectricPower Co., Inc.

Tokyo ElectricPower Co., Inc.

In
Operation

Chubu ElectricPower Co., Inc.
Hokuriku ElectricPower Co.

Power Station & Unit
Tokai II Power Station
Tsuruga Power Station,
Unit 1
Unit 2
Tomari Power Station,
Unit 1
Unit 2
Onagawa NPS,
Unit 1
Unit 2
Unit 3
Fukushima Daiichi NPS,
Unit 1
Unit 2
Unit 3
Unit 4
Unit 5
Unit 6
Fukushima Daini NPS,
Unit 1
Unit 2
Unit 3
Unit 4
Kashiwazaki Kariwa NPS,
Unit 1
Unit 2
Unit 3
Unit 4
Unit 5
Unit 6
Unit 7
Hamaoka NPS,
Unit 1
Unit 2
Unit 3
Unit 4
Shika NPS,
Unit 1

A1-1

Reactor
Type
BWR

Power
[MWe]

1,100

Commis-si
oning
11/28/78

BWR
PWR

357
1,160

03/14/70
02/17/87

PWR
PWR

579
579

06/22/89
04/12/91

BWR
BWR
BWR

524
825
825

06/01/84
07/28/95
01/30/02

BWR
BWR
BWR
BWR
BWR
BWR

460
784
784
784
784
1,100

03/26/71
07/18/74
03/27/76
10/12/78
04/18/78
10/24/79

BWR
BWR
BWR
BWR

1,100
1,100
1,100
1,100

04/20/82
02/03/84
06/21/85
08/25/87

BWR
BWR
BWR
BWR
BWR
ABWR
ABWR

1,100
1,100
1,100
1,100
1,100
1,356
1,356

09/18/85
09/28/90
08/11/93
08/11/94
04/10/90
11/07/96
07/02/97

BWR
BWR
BWR
BWR

540
840
1,100
1,137

03/17/76
11/29/78
08/28/87
09/03/93

BWR

540

07/30/93

The Kansai
Electric Power
Co., Inc.
In
Operation

The Chugoku
Electric Power
Co., Inc.

Mihama Power Station,
Unit 1
Unit 2
Unit 3
Takahama Power Station,
Unit 1
Unit 2
Unit 3
Unit 4
Ohi Power Station,
Unit 1
Unit 2
Unit 3
Unit 4
Shimane NPS,
Unit 1
Unit 2

PWR
PWR
PWR

340
500
826

11/28/70
07/25/72
12/01/76

PWR
PWR
PWR
PWR

826
826
870
870

11/14/74
11/14/75
01/17/85
06/05/85

PWR
PWR
PWR
PWR

1,175
1,175
1,180
1,180

03/27/79
12/05/79
12/18/91
02/02/93

BWR
BWR

460
820

03/29/74
02/10/89

PWR
PWR
PWR

566
566
890

09/30/77
03/19/82
12/15/94

PWR
PWR
PWR
PWR

559
559
1,180
1,180

10/15/75
03/30/81
03/18/94
07/25/97

PWR
PWR(52 units)

890
890
45,742

07/04/84
11/28/85

PWR

912

Higashidori NPS, Unit 1

BWR

1,100

Shika NPS, Unit 2

ABWR

1,358

Hamaoka NPS, Unit 5**

ABWR

1,380

2009/12(Planned)
2005/10(Planned)
2006/03(Planned)
2005/01(Planned)(4 units)

4,750

PWR
PWR
ABWR

1538
1538
1,383

FY2013
FY2014
2012/03

ABWR

1,373

2011/03

ABWR
ABWR(6 units)

1,373
1,373
8,578

FY2013
FY2016

Ikata Power Station,
Unit 1
Shikoku Electric
Unit 2
Power Co., Inc.
Unit 3Genkai NPS,
Unit 1
Unit 2
Unit 3Kyushu Electric
Unit 4
Power Co., Inc.
Sendai NPS,
Unit 1
Unit 2
Subtotal
Hokkaido Electric Tomari Power Station
Unit3
Power Co., Inc.
Under
Construction

In
Planning

Tohoku ElectricPower Co., Inc.
Hokuriku ElectricPower Co.
Chubu ElectricPower Co., Inc.

Subtotal
The Japan Atomic Tsuruga Power Station
Unit3
Power Co.
Unit4
Ohma NPS, Unit 1
Electric Power
Development Co.
LTD
Shimane NPS, Unit 3
The Chugoku
Kaminoseki NPS,Electric Power
Unit 1
Co., Inc.
Unit 2
Subtotal

A1-2

The Japan Atomic
Power Co.

Tokai Power Station

GCR

166

07/25/66
Commercial
Operation
discontinued
on
03/31/1998

Under
Decommissioning

NotificationofDismantlingon
10/04/2001(2)

Reactors at the stage of research and development
LicenseHolderIn Preparation of
Decommissioning
Under
Construction
Note:

Japan Nuclear
Cycle
Development
Institute

Power Station& UnitFugen*

ReactorType
ATR

Monju **

FBR

Power
[MWe]

Commis-sioning

165

03/20/79

280

Commercial Operation
discontinued on
03/29/2003
Criticality on 04/05/94

In planning: Projects that were approved in the subcommittee of the Advisory Committee for
Natural Resources and Energy, and which are before obtaining construction plan approval* : This plant discontinued commercial operation on March 29, 2003. But this plant
corresponds to the category “reactor in operation” of the Convention on Nuclear Safety,
because it is in preparation of decommissioning.

**: These plants reached criticality and correspond to the category “reactor in operation” of
the Convention on Nuclear Safety

A1-3

Annex 2

Data on Nuclear Installations
2.1 Capacity of Electricity of Commercial Nuclear Power Reactors
60

50,00045,00035,000

Number of Units

40

30,00025,00020,00020

15,00010,000
5,000
0

0
'84

'85

'86

'87

'88

'89

'90

'91

'92

'93 '94 '95
fiscal year

Capacity of Electricity

'96

'97

'98

'99

'00

'01

'02

'03

Number of Units

2.2 Capacity Factor of Commercial Nuclear Power Reactors
100

80
Capacity Factor [%]Capacity of Electricity [MW]40,000

60

40

20

0
'84 '85 '86 '87 '88 '89 '90 '91 '92 '93 '94 '95 '96 '97 '98 '99 '00 '01 '02 '03
fiscal year

A2-1

2.3 Frequency of Unplanned Shutdown at Commercial Nuclear Power Reactors(except during commissioning)60

340
Number of Units

Frequency of Unplanned Shutdown
per reactor year

4

2

20
1

0

0
'84 '85 '86 '87 '88 '89 '90 '91 '92 '93 '94 '95 '96 '97 '98 '99 '00 '01 '02 '03
fiscal year
Automatic Shutdown

Manual Shutdown

Number of Units

2.4 Reported Events (by Laws & Notifications)of Commercial Nuclear Power Reactors

Number of Reported Events

80
3

60
2
40

1
20

0

0
'84

'85

'86

'87

'88

'89

'90

'91

'92

'93

'94

'95

'96

'97

'98

'99

'00

'01

fiscal year
Reported Events by Laws
Number of Reported Events per unit

A2-2

Reported Events by Notifications

'02

'03

Number of Reported Events per unit

4100

2.5 Assessment of Events by INES for Commercial Nuclear Power
Reactors

Number of Reported Events

30

20

10

0

'92

'93

'94

'95

'96

'97

'98

'99

'00

'01

'02

'03

fiscal year
Out of Scale

Level 0Level 1

2.6 Human Error Induced Events Reported
1.00

1.0
0.75
0.8

0.6

0.50

0.4
0.25
0.2

0.0

0.00
'84 '85 '86 '87 '88 '89 '90 '91 '92 '93 '94 '95 '96 '97 '98 '99 '00 '01 '02
fiscal year
Number of Human Error Induced Events per unit
Ratio of Human Error Induced Events to the Total Number of Reported Events

A2-3

Ratio of Human Error Failures

Number of Human Error Failures
per unit

1.2

2 .7 D o se p er P erso n s at C o m m ercial N u clear P ow er R eacto rs
80

5

4

3
40
2

Dose per Persons [mSv/per]Number of Persons [x 1,000]

60

20
1

0
'84

'8 5

'8 6

'8 7

'88

'8 9

'9 0

'91

'9 2

'9 3

'9 4

'95

'9 6

'9 7

'98

'9 9

'0 0

'01

'0 2

'0 3

fiscal year
N u m b er of P erson s E n gaged in R ad iatin W ork

D ose p er P erson s

2.8 Averaged Dose at Commercial Nucear Power Reactors

Dose per Unit [man Sv/Unit]

8

6

4

2

0
'84 '85 '86 '87 '88 '89 '90 '91 '92 '93 '94 '95 '96 '97 '98 '99 '00 '01 '02 '03
fiscal year

A2-4

2 .9 R ad io activ e G aseo u s W aste (I-1 3 1 ) R eleased
fro m C o m m ercial N u cear P o w er R eacto rs(N u m b er o f u n its is su m m ed fro m th eir in itial criticality.)
1 .0 E + 1 2

60

1 .0 E + 1 1

1 .0 E + 0 940

Number of Units

Released Radioactive Iodine [Bq]

1 .0 E + 1 0

1 .0 E + 0 8

1 .0 E + 0 7

1 .0 E + 0 6

20

1 .0 E + 0 5

1 .0 E + 0 4

1 .0 E + 0 3

0
'8 4

'8 5

'8 6

'8 7

'8 8

'8 9

'9 0

'9 1

'9 2

'9 3

'9 4

'9 5

'9 6

'9 7

'9 8

'9 9

'0 0

'0 1

'0 2

'0 3

fisca l year
R ele ase d R a d io a ctive Io d ine

N um b er o f U nits

R ele ase d R a d io a c tive Io d ine p e r unit60

1.0E+12
1.0E+11
1.0E+101.0E+0940

1.0E+08
1.0E+07
1.0E+06

20

Number of Units

Released Radioactive Liquid Waste (per Unit) [Bq]2.10 Radioactive Liquid Waste (except H-3) Released
from Commercial Nuclear Power Reactors

1.0E+05
1.0E+04
1.0E+030'84 '85 '86 '87 '88 '89 '90 '91 '92 '93 '94 '95 '96 '97 '98 '99 '00 '01 '02 '03

fiscal year
Released Radioactive Liquid Waste

Number of Units

A2-5

Released Radioactive Liquid Waste per Unit

2 .1 1 R a d io a c tiv e S o lid W a s te G e n e ra tio n p e r E le c tr ic ity G e n e ra tio n
o f C o m m e rc ia l N u c e a r P o w e r R e a c to r s(T o ta l q u a n tity o f r a d io a c tiv e s o lid w a s te is c o n v e rte d to th e d r u m o f 2 0 0 -lite rc a p a c ity .)

80

10

40
4

20
2

0

0
'8 4

'8 5

'8 6

'8 7

'8 8

'8 9

'9 0

'9 1

'9 2

'9 3

'9 4

'9 5

'9 6

'9 7

'9 8

'9 9

fis c a l y e a r
N u m b e r o f D ru m s

N u m b e r o f D ru m s p e r E le c tric ity G e n e ra tio n

A2-6

'0 0

'0 1

'0 2

'0 3

[drum/MW year]

Number of Drums [x 1,000]

6

Number of Drums per Electricity Generation

860

Annex 3 Legislation and Guidelines
3.1. Atomic Energy Basic Law (Excerpt)(Law No.186, December 19, 1955)
Latest Revision: Law No. 102, July 16, 1999
(Objectives)
Article 1.
The Objectives of this Law shall be to secure energy resources in the future, to achieve the progress ofscience and technology and the promotion of industries by encouraging the research, development and utilization of nuclear
power and thereby to contribute to the improvement of the welfare of the human society and of the national living standard.
(Basic Policy)
Article 2.
The research, development and utilization of nuclear power shall be limited to peaceful purposes, shall aim at
ensuring safety, giving priority, and shall be performed independently under democratic administration, and the results
obtained shall be made public and shall actively contribute to international cooperation.
(Establishment)
Article 4.
In the Cabinet Office, there shall be established the Atomic Energy Commission and the Nuclear Safety
Commission for the purposes of carrying out the planned national policies on the research, development and utilization of
nuclear power and of realizing the democratic operation of nuclear power administration.
(Functions)
Article 5.
The Atomic Energy Commission shall plan, consider and determine the matters (excluding those related to
implementing regulation for ensuring safety) related to the research, development and utilization of nuclear power.
2. The Nuclear Safety Commission shall plan, consider and determine the matters related to ensuring safety in the research,development and utilization of nuclear power.
(Organization, Operation and Authority)
Article 6.
The matters concerning the organizations, operations and authorities of the Atomic Energy Commission and
the Nuclear Safety Commission shall be provided by other laws.
(Control over Nuclear Source Materials)
Article 10.
The import, export, transfer, receipt and purification of nuclear source materials shall be entrusted,as provided by other law, only to those designated by the Government.
(Regulation concerning Nuclear Fuel Materials)
Article 12.
Those who attempt to produce, import, export, possess, hold, transfer, receive, use or transport
nuclear fuel materials shall be subject to the regulations to be enforced by the Government as provided by other Law.
(Regulation over Construction Etc. of Reactors)
Article 14.
Those who attempt to construct reactors shall be subject to the regulations to be enforced by the Government
as provided by other law. The same shall apply also to those who attempt to reconstruct or remove them.
Article 15.
Those who attempt to transfer or receive reactors shall be subject to the regulations to be enforcedby the Government as provided by other Law.
Article 16.
Those who have constructed, reconstructed, removed received reactors in compliance with theregulations referred to in the preceding two Articles shall, as provided by other law, obtain the approval of theGovernment for the operation plan prior to their operation.
(Measures for Prevention of Radiation Hazards)
Article 20.
The regulations on the manufacture, sale, use, measurement, etc. and any other safety and hygienic
measures relating to radioactive materials and radiation generating devices in order to prevent radiation hazards andto ensure the public safety shall be provided by other Laws.

3.2. Law for Establishment of the Atomic Energy Commission and the Nuclear Safety Commission(1) Law for Establishment of the Atomic Energy Commission and the Nuclear Safety Commission (Excerpt)(Law No. 188, December 19, 1955)
Latest Revision: Law No. 178, December 18, 2002
(Objectives and Establishment)
Article 1.
In order to ensure the democratic administration of the research, development and utilization of nuclear
energy (hereinafter referred to as "utilization of nuclear power"), there shall be established the Atomic Energy Commission
and the Nuclear Safety Commission in the Cabinet Office.
(3) Atomic Energy Commission(Assigned Duties)
Article 2.
The Atomic Energy Commission (hereinafter referred to as "the Commission" in this chapter) shall plan,deliberate and determine the matters referred to in the following subparagraphs:(i)
Matters concerning polices on the utilization of nuclear energy;(ii)
Matters concerning the comprehensive adjustment of affairs relating to the utilization of nuclear energy of related
administrative agencies;(iii) Matters concerning the estimation and the allocation of the expenses for the utilization of nuclear energy of related-- Provisional translation for information only --A3-1

administrative agencies;
Matters concerning the regulations on nuclear fuel materials and nuclear reactors (excluding matters that is under theassigned duties of the Nuclear Safety Commission);(v)
Matters concerning the encouragement of testing and research relating to the utilization of nuclear energy;(vi)Matters concerning the education and training (excluding matters concerning the teaching and research at universities)of researchers and engineers engaged in the utilization of nuclear energy;(vii) Matters concerning the collection of data, the preparation of statistics and the investigation relating to the utilizationof nuclear energy; and(viii) Matters important relating to the utilization of nuclear energy, other than those referred to in the preceding items(excluding matters that is under the assigned duties of the Nuclear Safety Commission).
(Organization)
Article 3.
The commission shall be organized of one chairman and four commissioners.
2. Two commissioners may be as part-time service.
(Chairman)
Article 4.
The chairman acts as a manager for the Commission matters, and represents the Commission.
2. The chairman shall designate the person from the full-time commissioners beforehand, who acts for the chairman when
the chairman fails to act.
(Appointment of the Chairman and the Commissioners)
Article 5. The Prime Minister appoints the chairman and the commissioners after the approval of both Parliaments.
2. When the official term of the chairman or the commissioner expires or when a vacant is produced, the Prime Minister
can appoint the chairman or the commissioners irrespective of the provision of the foregoing paragraph when the approval ofboth Parliaments cannot be acquired due to the closing of the diet, or the disbandment of the house of representatives.
3. In the case of the foregoing paragraph, approval of both Parliaments shall be acquired at the first diet after theappointment. In this case, the Prime Minister must dismiss the chairman or the commissioner right away when the subsequent
approval of both Parliaments cannot be acquired.
(Official Term of the Chairman and the Commissioners)
Article 6. The official term of the chairman and the commissioners shall be three years. However, a supplementary
chairman or the supplementary commissioners shall work for the predecessor's remaining length of the official term.
2. The chairman and commissioners may be reappointed.
3. Irrespective of the provision of the first paragraph, the chairman and the commissioners shall work for the postconsecutively until the successor is appointed even when the official term expires.
(Dismissal of the Chairman and the Commissioners)
Article 7. When the chairman or the commissioners are recognized that execution of the task cannot be performed for the
failure of the mind and the body or when they are recognized that the wrongdoing unsuitable as the chairman or as thecommissioner as well as the violation of obligations on a task to the chairman or the commissioners, the Prime Minister may
dismiss them after obtaining the approval of both Parliaments.
Chapter 3 Nuclear Safety Commission(Assigned Duties)
Article 13.
The Nuclear Safety Commission (hereinafter referred to as “the Commission” in this chapter) shallplan, deliberate and determine the matters referred to in the following subparagraphs:(i) Matters concerning policies on the regulations to ensure nuclear safety among the policies on utilization of nuclear
energy;(ii) Matters concerning the regulations to ensure nuclear safety among the regulations of the nuclear fuel material andnuclear reactors;(iii) Matters concerning the fundamentals of preventing hazards due to the utilization of nuclear energy;(iv) Matters concerning the fundamentals of measures for preventing hazards due to the fallout of radioactive materials; and(v) Matters concerning the regulations to ensure nuclear safety among important matters in utilization of nuclear energy
besides the matters referred to in the preceding Subparagraph (i) through Subparagraph (iii).
(Organization)
Article 14.
The commission shall be organized of five commissioners.
2. Two commissioners may be as part-time service.
(Chairman)
Article 15.
One chairman is assigned in the Commission mutually elected from full-time commissioners.
2. The provisions of Article 4 shall be applied correspondingly for the chairman.
(Committee on Examination of Reactor Safety)
Article 16. There shall be established the Committee on Examination of Reactor Safety in the Commission whichshall consist of the Examiners, the largest number of which is provided for in the Government Ordinance.
2. The Committee on Examination of Reactor Safety shall investigate and consider the matters concerning safety of nuclear
reactors by the direction of the Chairman.
(Committee on Examination of Nuclear Fuel Safety)
Article 19. There shall be established the Committee on Examination of Nuclear Fuel Safety in the Commission, which shallconsist of the Examiners, the largest number of which is provided for in the Government Ordinance.
2. The Committee on Examination of Nuclear Fuel Safety shall investigate and review the matters concerning safety of
nuclear fuel materials by the direction of the Chairman.
(Investigator for Emergency Preparedness and Response)
Article 20.
2. Several Investigators for Emergency Preparedness and Response (hereinafter referred to as " the Investigator"), the(iv)-- Provisional translation for information only --A3-2

largest number of which is provided for in the Government Ordinance, shall be assigned to carry out the investigation andreview of the matters authorized in the provisions of Article 15, Paragraph 4, and Article 20, Paragraph 5 and 6 of the Special
Law of Emergency Preparedness for Nuclear Disaster (Law No. 156, 1999).
(Recommendation)
Article 24. The Atomic Energy Commission or the Nuclear Safety Commission may make recommendation to the heads ofthe related administrative agencies through the Prime Minister about the assigned duties specified in the each Paragraphs of
Article 2 and Article 13, when necessary.
(Report etc.)
Article 25. The Atomic Energy Commission or the Nuclear Safety Commission may require the report and other necessary
cooperation such as submittal of references, presentation of opinions, and explanation to the heads of the related
administrative agencies to perform the assigned duties, when necessary.

(2) Rules of Nuclear Safety Commission Secretariat Organization (Excerpt)(Order No. 2 of Cabinet Office, January 6, 2001)(Divisions of the Secretariat)
Article 1. There shall be established four divisions in the Nuclear Safety Commission secretariat:
General Affairs Division
Regulatory Guides and Review Division
Radiation Protection and Accident Management Division
Subsequent Regulation Review Division(Assigned duties of the General Affairs Division)
Article 2. The General Affairs Division manages the following subparagraphs:(Abbreviated)(x)
The matters concerning policies on the regulations to ensure nuclear safety among the policies on the utilization of
nuclear energy (excluding matters that is under the assigned duties of other divisions); and(xi)
The matters concerning regulations to ensure nuclear safety among the regulations of the nuclear fuel material andreactors (excluding matters that is under the assigned duties of other sections).
(Assigned Duties of the Regulatory Guides and Review Division)
Article 3. The Regulatory Guides and Review Division shall manage the matters of the secretariat works referred to in thefollowing subparagraphs:(i) Matters concerning to the establishment of standards and guidelines to ensure nuclear safety; and(ii) Matters concerning the consultation based on provisions of the Law on the Regulation of Nuclear Source Material,
Nuclear Fuel Material, and Reactors (Law No. 166, 1957, hereinafter referred to as "Reactor Regulation Law").
(Assigned Duties of the Radiation Protection and Accident Management Division)
Article 4. The Radiation Protection and Accident Management Division shall manage the matters of the secretariat works
referred to in the following subparagraphs:(i) Matters concerning to ensure nuclear safety of nuclear installations in service (excluding matters that is under theassigned duties of the Subsequent Regulation Review Division);(ii) Matters concerning to ensure safety of the transportation of the nuclear source material, the nuclear fuel material, andthe radioisotope;(iii) Matters concerning the fundamentals of preventing hazards due to utilization of nuclear energy;(iv) Matters concerning the implementation of nuclear emergency response and other necessary measures; and(v) Matters concerning the fundamentals of measures preventing hazards due to fallout of radioactive materials (excluding
matters that is under the assigned duties of the Regulatory Guides and Review Division) besides the matters referred to in
the preceding subparagraph, such as.
(Assigned Duties of the Subsequent Regulation Review Division)
Article 5. The Subsequent Regulation Review Division shall manage the matters concerning regulation investigation(investigation of regulation after the designation, licensing, or approval of business, / licensing or approval of theestablishment, / licensing or approval of usage based on Reactor Regulation Law are meant here; the same meaning for the
next article) among the secretariat responsibilities.
(Safety Investigation Officer and Regulation Investigation Officer)
Article 6. Two Safety Investigation Officers and one Regulation Investigation Officer are assigned in the Nuclear Safety
Commission secretariat.
2. The Safety Investigation Officer shall take part of the secretariat works by receiving order concerning the important itemof investigation other than regulation investigation.
3. The Regulation Investigation Officer shall take part of the secretariat works by receiving order concerning the important
items of regulation investigation.

3.3 Law for Establishment of the Ministry of Economy, Trade and Industry(1) Law for Establishment of the Ministry of Economy, Trade and Industry (Excerpt)(Law No. 99, July 16, 1999)
Latest Revision: Law No. 92, June 18, 2003-- Provisional translation for information only --A3-3

(Assigned Duties)
Article 3. Ministry of Economy, Trade and Industry shall engage in enhancement of economical vitality of private sector andthe growth of economy and industries with emphasis on the harmonized development in international economical relationand shall engage in ensuring stable and efficient supply of mineral resources and energy.
(Assigned Affairs)
Article 4. In order to achieve assigned duties as described in the preceding article, the Ministry of Economy, Trade andIndustry shall administer the following affairs.
53. Matters relating to ensuring stable and efficient supplies of electricity, gas and thermal power.
54. Matters relating to planning, projecting and promotion of the fundamental policy concerning to the electricity
development;
55. Matters relating to the nuclear power policy as for utilization of energy;
56. Matters relating to the technology development of nuclear power as for utilization of energy;
57. Matters relating to the regulations for the refining, fabrication, storage, reprocessing and waste disposal business innuclear fuel cycle and the nuclear power installations and matters relating to ensure the safety of these business andinstallations; and58. Matters relating to ensuring the safety of nuclear power as for utilization of energy.
(omitted)
Chapter 4. External Agencies
Section 1. Establishment
Article 14. According to the definitions described in Article 3, Paragraph 3 of the National Government Organization Law,
the following external agency shall be established in the Ministry of Economy, Trade and Industry:
Agency of Natural Resources and Energy
Section 2. Agency of Natural Resources and Energy
Subsection 1. Duties and Assigned Affairs(Director-General)
Article 15. The head of the Agency of Natural Resources and Energy shall be named as the Director-General of the Agency
of Natural Resources and Energy.
(Assigned Duties)
Article 16. The Agency of Natural Resources and Energy shall engage in ensuring stable and efficient supply and thepromotion of appropriate utilization of mineral resources and energy and engage in ensuring industrial safety.
(Assigned Affairs)
Article 17. In order to achieve assigned duties as described in the preceding article, the Agency of Natural Resources andEnergy shall administer the affairs referred in No. 48 to No.59 of Article 4.
Subsection 2. Councils etc.
(Establishment)
Article 18. The Advisory Committee for Resources and Energy is established in Agency of Natural Resources and Energy.
(Advisory Committee for Resources and Energy)
Article 19. The Advisory Committee for Natural Resources and Energy shall administer the following affairs:(i) Concerning the energy master plan provided in Article 12, Paragraph 1 of the Fundamental Law for Energy Policy (Law
No. 71, 2002), matters provided in the Paragraph 3 of the said article shall be processed; and(i-2) Investigate and examine the important matters concerning the comprehensive policies relating to security of stable andefficient supply for mineral resources and energy, and an adequate utilization of energy, in response to an inquiry issued
from Minister of the Ministry of Economy, Trade and Industry.
Subsection 3. Special Agency(Nuclear and Industrial Safety Agency)
Article 20. Nuclear and Industrial Safety Agency shall be established in the Agency of Natural Resources and Energy.
2.
The Nuclear and Industrial Safety Agency shall be an organization for ensuring the safety of nuclear and other energy,
and industrial safety.
3.
The Nuclear and Industrial Safety Agency shall manage the assigned duties defined in Article 4, Paragraph 1, No. 57 to
No. 59.
4.
The head of the Nuclear and Industrial Safety Agency shall be named as the Director-General of the Nuclear andIndustrial Safety Agency. .
5.
The Director-General shall appoint or dismiss the staff and personnel of the Nuclear and Industrial Safety Agency.
6.
The place and internal organization of the Nuclear and Industrial Safety Agency shall be determined by the government
ordinance.

(2) Ordinance for Organization of Ministry of Economy, Trade and Industry (Excerpt)(Government Ordinance No. 254, June 7, 2000)
Latest Revision: Ordinance No.131, April 1, 2004
Chapter 2. External Agencies
Section 1. Agency of Natural Resources and Energy
Subsection 3. Special Agency(The Location of Nuclear and Industrial Safety Agency)
Article 132. The Nuclear and Industrial Safety Agency shall be placed in Tokyo.
(The Organization of the Nuclear and Industrial Safety Agency )-- Provisional translation for information only --A3-4

Article 133. One General for Nuclear and Industrial Safety shall be assigned in the Nuclear and Industrial Safety Agency.
2. The Director-General for Nuclear and Industrial Safety shall assist the Director-General of the agency, and shall manage
the affairs of the agency.
3. The remaining internal organization of the agency shall be provided by the Ministerial Order of Ministry of Economy,
Trade and Industry.

(3) The Rules for Organization of the Ministry of Economy, Trade and Industry (Excerpt)(Ministerial Order No. 1 of Ministry of Economy, Trade and Industry, January 6, 2001)
Latest Revision: Ministerial Order No. 59 of Ministry of Economy, Trade and Industry, April 1, 2004
Chapter 2. External Agencies
Section 1. Agency of Natural Resources and Energy
Subsection 2. Specific Agency
Title 1. Establishment of Specific Assignments etc.
(Deputy Director-General and Director-General for Safety Examination)
Article 261. Three Deputy Director-General and one Deputy Director-General for Safety Examination shall be assigned in
the Nuclear and Industrial Safety Agency.
2. Upon official orders, the Deputy Director-Generals shall participate in activities for planning and projecting of thematters important to the assigned affairs of the Nuclear and Industrial Safety Agency and shall manage the related affairs.
3. The Director-General for Safety Examination shall manage the assigned duties and affairs concerning to the examinationon the important items regarding to regulations for the nuclear related business of refining, processing, storing and disposingof wastes and commercial nuclear power reactors (hereinafter referred to as “nuclear business, etc.), upon official orders.
Title 2. Establishment of Divisions etc.
(Divisions Established in the Nuclear and Industrial Safety Agency)
Article 262. The following fifteen Divisions shall be established in the Nuclear and Industrial Safety Agency:
Policy Planning and Coordination Division;
Nuclear Safety Public Relations and Training Division;
Nuclear Safety Regulatory Standard Division;
Nuclear Safety Special Investigation Division;
Nuclear Power Licensing Division;
Nuclear Power Inspection Division;
Nuclear Fuel Cycle Regulation Division;
Nuclear Fuel Transport and Storage Regulation Division;
Radioactive Waste Regulation Division;
Nuclear Emergency Preparedness Division; andElectric Power Safety Division.
(Other divisions, omitted)(Assigned Affairs of the Policy Planning and Coordination Division)
Article 263. The Policy Planning and Coordination Division shall manage the assigned affairs as shown in the followings:
1. Matters relating to the secrecy;
2. Matters relating to the positions, appointment and dismissal, salary, punishment, service and other personnel affairs, andeducation and training of personnel (excluding the affairs assigned to Nuclear Safety Administration Division ) in the
Nuclear and Industrial Safety Agency;
5. Matters relating to the deliberation and transmission of proposal of laws, ordinances and orders, and other official
documents, etc.;
6. Matters relating to disclosure to the public of such information possessed at the Nuclear and Industrial Safety Agency;
7. Matters relating to the general coordination concerning to the assigned duties of the Nuclear and Industrial Safety
Agency;8. Matters relating to examination of administration performed by the Nuclear and Industrial Safety Agency;
9. Matters relating to public relation (excluding matters assigned to Nuclear Safety Public Relations and Training
Division);
10. Matters relating to the organization and members of the Nuclear and Industrial Safety Agency;------------ omission -----------19. Matters relating to projecting and planning, and promoting of the fundamental policy for ensuring nuclear safety andindustry safety of nuclear energy and other energy utilization (excluding matters assigned to Nuclear Safety Regulatory
Standard Division);
20. Matters relating to overall coordination of matters concerning to the law-suits on the assigned affairs of the Nuclear
and Industrial Safety Agency (excluding matters assigned to Nuclear Safety Special Investigation Division);
21. Matters relating to the organization and general management of an incorporated administrative agency, Japan Nuclear
Energy Safety Organization;
22. Matters relating to international cooperation concerning to regulating and ensuring the safety of nuclear business, etc.;
23. Matters relating to the international cooperation concerning to ensuring the safety in nuclear energy utilizations;
24. Matters relating to overall coordination of international cooperation concerning the assigned affairs of the Nuclear andIndustrial Safety Agency; and25. Matters relating to the general affairs of the Advisory Committee for Energy and Resources assigned to Nuclear andIndustrial Safety Agency.
-- Provisional translation for information only --A3-5

(Assigned Affairs of Nuclear Safety Public Relations and Training Division)
Article 264. *The Nuclear Safety Public Relations and Training Division shall manage the affairs as shown in thefollowings:(i)
Matters relating to the public relations to ensure the nuclear safety;(ii)
Matters relating to communication and coordination of the affairs on the Nuclear Safety Inspectors and Senior
Specialists for Nuclear Emergency;(iii) Matters relating to the budgets and numbers of Nuclear Safety Inspectors and Senior Specialists for Nuclear
Emergency;(iv)
Matters relating to the training and education necessary to occupational works of Nuclear Safety Inspectors, Senior
Specialists for Nuclear Emergency and other personnel who engage in the affairs for ensuring nuclear safety; and(v)
Matters relating to the examination and license certificate for the Chief Engineer of Reactors and Chief of Nuclear
Fuel Management.
(Assigned Affairs of Nuclear Safety Regulatory Standard Division)
Article 265. Nuclear Safety Regulatory Standard Division shall manage the affairs as shown in the followings:(i)
Matters relating to planning, projecting and promotion of the fundamental policy concerning technical matters toensure the nuclear safety;(ii)
Matters relating to collection, analysis, and supply of information on securing safety concerning nuclear business etc.;(iii) Matters relating to the overall coordination of affairs concerning enforcement of the Law for the Regulations of
Nuclear Source Material, Nuclear Fuel Material and Reactors (Law No. 166, 1957, hereinafter referred to as "Reactor
Regulation Law");(iv)
Matters relating to overall coordination of affairs concerning reporting to Nuclear Safety Commission provided in
Article 72-3 of the Reactor Regulation Law, and making communication with Nuclear Safety Commission; and(v)
Matters relating to the Rules for Nuclear Power Generation Facilities Concerning Nuclear Power Reactors at theStage of Research and Development (except matters concerning affairs provided in Article 270, Subparagraph (ii) and(iii), Article 271, Subparagraph (ii) and (iii), and Article 273, Subparagraph (i) and (ix)), and others for ensuringsafety (excluding matters relating to international cooperation) of these facilities (excluding matters assigned to
Nuclear Safety Public Relations and Training Division, Nuclear Safety Special Investigation Division, and Nuclear
Emergency Preparedness Division)
Assigned Affairs of Nuclear Safety Special Investigation Division)
Article 266. Nuclear Safety Special Investigation Division shall manage the affairs as shown in the followings:(i)
Matters relating to declarations provided in Article 66-4, Paragraph 1 of of the Reactor Regulation Law;(ii) Matters relating to the overall coordination of affairs concerning notification provided in Article 67, Paragraph 1 and 2of the Reactor Regulation Law; and(iii) Matters relating to overall coordination of affairs concerning to the law suits for ensuring nuclear safety.
(Assigned Affairs of the Nuclear Power Licensing Division)
Article 267. The Nuclear Power Licensing Division shall manage the affairs as shown in the followings:
1. Matters relating to the licensing for establishment and transfer of the commercial nuclear power reactors;
2. Matters relating to the succession of the title of commercial nuclear power reactor establishers;
3. Matters relating to the licensing of construction plan of nuclear power generating facilities (except turbine and auxiliary
boiler, same as in Paragraph 5) in the commercial nuclear power reactors;
4. Matters relating to the licensing for design of nuclear fuel materials in the commercial nuclear power reactors; and5. In addition to the above defined items, the items related to the Rules for Nuclear Power Generation Facilities ofCommercial Power Reactors (except the items related to the affair provided in the each subparagraph of the following
articles: Article 270, Subparagraph (ii) and (iii), Article 271, Subparagraph (ii) and (iii), and Article 273, Subparagraph(ix)), and others for ensuring safety (except matters relating to international cooperation) of these facilities (except theassigned affairs of Nuclear Safety Public Relations and Training Division and Nuclear Emergency Preparedness
Division).
(Assigned Affairs of Nuclear Power Inspection Division)
Article 268. The Nuclear Power Inspection Division shall manage the affairs as shown in the followings:
1. Matters relating to the inspections of the nuclear power installations of commercial nuclear power reactors based on theElectric Utilities Industry Law and the regulation by orders based on the law (except affairs assigned to the ElectricPower Safety Division);
2. Matters relating to the inspections for the nuclear fuel materials of the commercial nuclear power reactors;
3. Matters relating to the operation plan of commercial nuclear power reactors;
4. Matters relating to the approval of the safety preservation rules concerning to the commercial nuclear power reactors;
5. Matters relating to the inspection of the compliance with safety preservation rules concerning to the commercial nuclear
power reactors;
6. Matters relating to the Chief Engineer for Reactors concerning to the commercial nuclear power reactors; and7. Matters relating to the reporting that defined Article 67, Paragraph 1 and Paragraph 2 of the Regulation of Commercial
Nuclear Power Reactors (except the assigned affairs of the Nuclear Emergency Prepared.
(Assigned Affairs of Nuclear Fuel Cycle Regulation Division)
Article 269. Nuclear Fuel Cycle Regulation Division shall manage the affairs as shown in the followings:--- omitted --(Assigned Affairs of Nuclear Fuel Transport and Storage Regulation Division)
Article 270. Nuclear Fuel Transport and Storage Regulation Division shall manage the affairs as shown in the followings:--- omitted --(Assigned Affairs of Radioactive Waste Regulation Division)-- Provisional translation for information only --A3-6

Article 271. Radioactive Waste Regulation Division shall manage the affairs as shown in the followings:--- omitted --(Assigned Affairs of the Nuclear Emergency Preparedness Division)
Article 272. The Nuclear Emergency Preparedness Division shall manage the affairs as shown in the ;s:1. Matters relating to projecting and planning, and promoting of the policy concerning to the nuclear emergency;
2. Matters relating to the investigation and prevention of the nuclear accidents and incidents.
3. Matters relating to the physical protection;
4. Matters relating to overall coordination of the assigned affairs concerning to ensuring nuclear safety in response tonuclear emergency (as provided in Article 2, Paragraph 2 of the Special Law of Emergency Preparedness for Nuclear
Disaster, Law No. 156, 1999) and other incidents; and5. Matters relating to enforcement of the Special Law of Emergency. Preparedness for Nuclear Disaster.
(Assigned Affairs of the Electric Power Safety Division)
Article 273. The Electric Power Safety Division shall manage the affairs as shown in the followings:
1. Matters relating to construction, maintenance and operation of the electric equipment (limited to turbines and auxiliary
boilers for the nuclear power reactors);--- omitted --8. Matters relating to the investigation on the environmental preservation of the area influenced by establishment of thehydraulic generating power installation, the fossil generating power installation and the nuclear power installation; and9. Matters relating to the welding safety management inspection for the machinery and equipment of the fossil generating
power installation and the nuclear power installation.
3.4. The Law of the General Rules for Incorporated Administrative Agency and the Law for Japan Nuclear
Energy Safety Organization(1) The Law of the General Rules for Incorporated Administrative Agency (Excerpt)(Law No. 103, July 16, 1999)
Latest Revision: Law No. 98, July 31, 2002
Chapter I. General Provisions
Section 1. General Rules(Purpose etc.)
Article 1. This law is enacted for the purposes of providing the common matters, which are basis for operation and others of
the system for the Incorporated Administrative Agency and for ensuring establishment of the system for Incorporated
Administrative Agency and implementation of affaires and businesses, which are implemented by the Incorporated
Administrative Agency from the public viewpoint, in conjunction with the law that provides the name, purpose and the scopeof businesses of individual Incorporated Administrative Agency (hereinafter referred to as "the Individual Law"), tocontribute to people's peaceful lives and sound development of social economy.
2. The organization, operation, and management of individual Incorporated Administrative Agency shall be governed by thislaw, except as otherwise provided in the Individual Law.
(Definition)
Article 2. In this law, "Incorporated Administrative Agency" means a juridical person established in accordance with this law
and the Individual Law, for the purpose to implement the following matters efficiently and effectively. The matters areaffaires and businesses that are necessary to be enforced from the public viewpoints to secure the stability of people's lives,social economies, etc. that need not be implemented directly by the government with his initiative, but that might be notnecessarily implemented by private organizations, or that are required to be implemented by an organization exclusively.
(Publicity, Transparency and Independency of Businesses)
Article 3. The Incorporated Administrative Agency shall make efforts to manage the affaires and businesses properly andefficiently, in the light of necessities to implement those that are necessary to be enforced from the public viewpoints tosecure the stability of people's lives, social economies, etc.
2 The Incorporated Administrative Agency shall make efforts to keep transparency of the situation of the organization andmanagement to the public thorough the official announcement and others on the details of activities as provided by this law.
3 In application of this law and the Individual Law, the independency of the Incorporated Administrative Agency in managing
the businesses shall be taken into account as necessary.
(Name)
Section 2. Committee for Evaluation of the Incorporated Administrative Agency(Committee for Evaluation of the Incorporated Administrative Agency)
Article 12. The competent ministry for the Incorporated Administrative Agency (referred to the Cabinet Office or theindividual ministry that has control over the individual Incorporated Administrative Agency concerned, the same in thefollowings) shall establish a Committee for Evaluation of Incorporated Administrative Agency (hereinafter referred to as"Committee for Evaluation") under them to entrust the management of the affairs in relation to the Incorporated
Administrative Agency, which falls under his control.
2. The Committee for Evaluation shall manage the affairs listed in the following subparagraphs:(i)
Evaluation on the actual performance concerning the activities of the Incorporated Administrative Agency; and-- Provisional translation for information only --A3-7

(ii) Management of others that fall under the jurisdictions as provided by this law or Individual Laws.
Chapter III. Management of Businesses
Section 1. Businesses
Section 2. Medium-term Target and Others(Medium-term Target)
Article 29. The competent minister shall decide a medium-term target that the Incorporated Administrative Agency should
achieve for a period of two years or more but not more than five years (hereinafter referred to as "medium-term target"), andshall instruct the concerned Incorporated Administrative Agency, and make it public. The same shall also be applied in thecase of its alteration.
2. Matters listed in the following subparagraphs shall be provided in the medium-term target:(i) Period of the medium-term target (referred to the period that the competent minister defines within the range of theperiod as provided in the preceding paragraph, the same hereinafter);(ii) Matters concerning efficiency improvement of the business management;(iii) Matters concerning quality improvement of services supplied to the public and other activities;(iv) Matters concerning improvement of the financial situation; and(v) Other important matters concerning business management.
(Medium-term Plan)
Article 30. When the Incorporated Administrative Agency is instructed as provided in Paragraph 1 of the preceding article,
he shall prepare a plan to achieve the medium-term target concerned (hereafter, referred to as "medium-term plan"), based on
the medium-term target, in accordance with the order of the competent ministry, and shall obtain the authorization by thecompetent minister. The same shall also be applied in the case of its alteration.
(Fiscal-year Plan)
Article 31. The Incorporated Administrative Agency, before the beginning of every business fiscal year, shall prepare a plan
concerning the business management for the business fiscal year concerned (in the following paragraph, referred to as "fiscal
year plan"), based on the medium-term plan of which authorization has been obtained as provided in Paragraph 1 of thepreceding article, in accordance with the order of the competent ministry, and shall submit the notification about it to thecompetent minister and make it public. The same shall also be applied in the case of its alteration.
(Evaluation on the Actual Performance of Activities in Each Business Fiscal Year)
Article 32. The Incorporated Administrative Agency shall undertake the evaluation of the Committee on Evaluation on his
actual performance of activities in each business fiscal year, in accordance with the order of the competent ministry.
2. The evaluation provided in the preceding paragraph shall be conducted by investigating and analyzing the implementing
situation of the medium-term plan of the business fiscal year concerned, and by evaluating the entire actual performance ofbusinesses of the business fiscal year concerned comprehensively with consideration of the results of these investigations andanalyses.
3. When the Committee on Evaluation conducted the evaluation provided in Paragraph 1, he shall make notification of theresults to the Incorporated Administrative Agency concerned and the council provided by the government ordinance(hereinafter referred to as "Council") without delay. In this case, the Committee on Evaluation may make recommendations
concerning improvement of the business management and others to the Incorporated Administrative Agency concerned, when
the Committee on Evaluation deems it necessary.
4. When the Committee on Evaluation notify pursuant to the provision in the preceding paragraph, he shall make public thecontents concerning the notification (in the case of the recommendation pursuant to the provision in latter part of the said
paragraph, the contents concerning the notification and the details of recommendation) without delay.
5. The Council may give its view regarding the results of evaluation notified as provided in Paragraph 3 to the Committee on
Evaluation concerned, when the Council deems it necessary.
(Business Report Concerning the Medium-term Target)
Article 33. The Incorporated Administrative Agency shall submit the business report concerning the medium-term target
concerned to the competent minister and make it public, within three months after termination of the period of themedium-term target, in accordance with the order of the competent ministry.
(Evaluation on the Actual Performance of Businesses Concerning the Medium-term Target)
Article 34. The Incorporated Administrative Agency shall undertake the evaluation by the Committee on Evaluation on theactual performance of businesses of the period of medium-term target, in accordance with the order of the competent
ministry.
2. The evaluation provided in the preceding paragraph shall be conducted by investigating and analyzing the achievement
situation of medium-term target in the period of medium-term target concerned, and by evaluating the entire actual
performance of businesses in the period of the medium-term target concerned comprehensively with consideration of theresults of these investigations and analyses.
(Examination at Termination of Period of Medium-term Target)
Article 35. The competent minister, at the termination of period of medium-term target, shall examine necessity forcontinuing the businesses of the Incorporated Administrative Agency concerned, appropriateness of his organization, andother matters concerning the whole of organization and business, and shall take necessary measures based on the findings
derived from the examination.
-- Provisional translation for information only --A3-8

2. The competent minister, in conducting the examination provided in the preceding paragraph, shall ask for the view of theCommittee on Evaluation.
3. The Council, at the termination of period of medium-term target, may make recommendation to the competent ministerwith respect to alteration and abolition of main affaires and businesses of the Incorporated Administrative Agency concerned.

(2) The Law for the Incorporated Administrative Agency, Japan Nuclear Energy Safety Organization(Law No. 179, December 18, 2002)(Purpose)
Article 1. This law is enacted for the purposes of providing such items as the name, the objectives of the Japan Nuclear
Energy Safety Organization (hereinafter referred to as “the Organization”) and the scope of duties provided by theOrganization.
(Definition)
Article 2. "Nuclear facilities" in this law means the refining facilities defined in Article 3, Paragraph 2 Subparagraph (ii) of
the Law for the Regulations of Nuclear Source Material, Nuclear Fuel Material and Reactors (Law No. 166, 1957, hereinafterreferred to as "the Reactor Regulation Law"), the fabrication facilities defined in Article 13, Paragraph 2, Subparagraph (ii) of
the Reactor Regulation Law, the spent fuel storage facilities defined in Article 43-4, Paragraph 2, Subparagraph (ii) of theReactor Regulation Law, the reprocessing facilities defined in Article 44, Paragraph 2, Subparagraph (ii) of the Reactor
Regulation Law, and the waste disposal facility and the waste interim storage facilities defined in Article 51-2, Paragraph 2,
Subparagraph (ii) of the Reactor Regulation Law.
2. "Reactor facilities" in this law means the reactors defined in Article 23, Paragraph 1, Subparagraph (i) and (iv) of theReactor Regulation Law and their related facilities (in Paragraph 4, referred to as "reactor").
3. "Nuclear business" in this law means the refining business defined in Article 3, Paragraph 1 of the Reactor Regulation Law,
the fabrication business defined in Article 13, Paragraph 1 of the Reactor Regulation Law, the spent fuel storage business
defined in Article 43-4, Paragraph 1 of the Reactor Regulation Law, the reprocessing business defined in Article 44,
Paragraph 1 of the Reactor Regulation Law, and the disposal business defined in Article 51-2, Paragraph 1 of the Reactor
Regulation Law.
4. "Nuclear disaster" in this law means those ones that would be caused by the operation of nuclear business or by theoperation of reactors among the nuclear disasters defined in Article 2, Subparagraph (i) of the Special Law of Emergency
Preparedness for Nuclear Disaster (Law No. 156, 1999).
(Name)
Article 3. The name of the Incorporated Administrative Agency established in accordance with this law and the Law of theGeneral Rules for Incorporated Administrative Agency (Law No. 103, 1999, hereinafter referred to as "the Law of theGeneral Rules"), as provided in Article 2, Paragraph 1 of the Law of the General Rules, shall be the Japan Nuclear Energy
Safety Organization.
(Purpose of the Organization)
Article 4. The purpose of the Japan Nuclear Energy Safety Organization (hereinafter referred to as "Organization") is tomaintain the bases for ensuring the safety for utilization of energy produced by the nuclear power through performing theinspections of nuclear facilities and reactor facilities, the analysis and evaluation of the safety concerning the design of
nuclear facilities and reactor facilities and other safety-related services.
(Scope of Duties)
Article 13. The Organization shall perform the following duties to achieve the purposes provided in Article 4:(i) Inspection of nuclear facilities and reactor facilities and others similar to those;(ii) Analysis and evaluation of the safety concerning design of nuclear facilities and reactor facilities;(iii) Duties on prevention of nuclear disasters, prevention of possible expansion of the nuclear disaster and the restorationfrom the nuclear disaster;(iv) Investigation, testing, research, and training for ensuring the safety of utilizing energy of the nuclear power (referred toas "ensuring safety" in the following subparagraph);(v) Collecting, classifying and providing of information for ensuring safety; and(vi) Duties that are accompanied with the ones described in each of the preceding subparagraphs.
2. The Organization, in addition to the duties described in the preceding paragraph, shall perform the following duties:(i) Entry and inspection, questioning and taking samples pursuant to the provisions of Article 68, Paragraph 1 throughParagraph 3 of the Reactor Regulation Law; and(ii) Entry and inspection pursuant to the provisions of Article 107, Paragraph 1 through Paragraph 3 of the Electricity
Utilities Industry Law (Law No. 170, 1964).
3. The Organization, in addition to the duties provided in the preceding two paragraphs, may perform tasks for ensuringsafety of the nuclear energy, so far as no obstacle takes place in performing any duties provided in the preceding two
paragraphs, in response to the request of national administrative agencies.

-- Provisional translation for information only --A3-9

3.5. The Law on the Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactors(1) The Law on the Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactors(Excerpt)(Law No. 166, June 10, 1957)(Latest Revision: Law No. 179, December 18, 2002)(Objectives)
Article 1.
This Law, in accordance with the spirits of the Atomic Energy Basic Law (Law No. 186, 1955), is enacted forthe purposes of providing the necessary regulations on the refining business, the fabricating business, the storage business,the reprocessing business and the waste disposal business, as well as on the establishment and operation of reactors, and also
for the purpose of providing necessary regulations on the uses of internationally regulated substances to execute theagreements or other international arrangements concerning the research, development and use of atomic energy, in order toensure that the uses of nuclear source material, nuclear fuel material and reactors are limited to peaceful ones and carried out
in a planned manner, and at the same time, to ensure the public safety by preventing the hazards due to these materials andreactors and protecting nuclear fuel material.
(3) Regulations concerning nuclear fuel fabrication business(Licensing for business)
Article 13. Any person who wishes to operate a nuclear fuel fabrication business shall obtain the license of the Minister of
Economy Trade and Industry as provided for in the government ordinance. (Omitted)(Pre-service Inspection)
Article 16-3.
3. The Minister of Economy, Trade and Industry (hereinafter referred to as “the Minister of METI”) shall, as provided by theOrdinance of Ministry of Economy, Trade and Industry (hereinafter referred to as “Ministry of Economy, Trade andIndustry”), make the Japan Nuclear Energy Safety Organization (hereinafter referred to as “the Organization”) to perform apart of affairs concerning inspections described in Paragraph 1.
4. When the Organization performed a part of affairs concerning the inspection under the provisions of the preceding
paragraph, the Organization shall promptly, as provided by the Ordinance of Ministry of Economy, Trade and Industry, notify
the Minister of Economy, Trade and Industry of the results of inspection.
Chapter 4 Regulations Concerning Establishment, Operation, etc. of Nuclear Reactors(Peridic Inspection of Facility)
Article 16-5.
3. The Minister of METI shall, as provided by the Ordinance of Ministry of Economy, Trade and Industry (hereinafterreferred to as “Ministry of Economy, Trade and Industry”), make the Organization to perform a part of affairs concerninginspections described in Paragraph 1.
4. When the Organization performed a part of affairs concerning the inspection under the provisions of the preceding
paragraph, the Organization shall promptly, as provided by the Ordinance of Ministry of Economy, Trade and Industry, notify
the Minister of Economy, Trade and Industry of the results of inspection.
Chapter 4 Regulations Concerning Establishment, Operation, etc. of Nuclear Reactors(Licensing for Establishment)
Article 23.
Any person who wishes to establish a nuclear reactor shall obtain the license of the Minister as
provided for in the government ordinance in accordance with the classification of nuclear reactors set out in thefollowing subparagraphs:(i) Nuclear reactors for the purpose of electrical generation (to the exclusion of those coming under any of the following threesubparagraphs; hereinafter referred to as "commercial power reactors"): Minister of Economy, Trade and Industry;(iv) Nuclear reactors for the purpose of electrical generation as specified by government ordinance as reactors in the stage of
research and development: Minister of Economy, Trade and Industry;
2. Any person who wishes to obtain the license under the preceding paragraph shall present to the competent minister(minister specified in the government ordinance in accordance with the classification of nuclear reactors in the preceding
paragraph) an application containing the following items:(i)
The name and the address and, in case of a juridical person, the name of its representative;(ii)
The purpose for which reactors are to be used;(iii) The type, the thermal power and the number of reactors;(iv)
The name and the address of the factory or the place of business where reactors are to be established;(v)
The location, structure and equipment of reactors and their attached facilities (hereinafter referred to as "reactor
facilities");(vi)
The construction plan of reactor facilities;(vii) The type of nuclear fuel material to be used in reactors and the annual amount scheduled for use; and(viii) The method of disposal of spent fuel.
3. The Minister of Economy, Trade and Industry plans to enact, amend or repeal the Government ordinance relating to
subparagraph (iv) of paragraph 1, they must hear and pay due respect, in advance, to the opinions of the Atomic Energy
Commission and the Nuclear Safety Commission.
Article 24.
When an application for the license under Paragraph 1 of the Article 23 is rendered, the competent
minister shall not give the license unless he recognizes that the application comes under each of the following
subparagraphs:(ix)
That reactors will not be used for non-peaceful purposes;(x)That the license will cause no hindrance to the planned development and utilization of atomic energy;(xi)That the applicant (including the shipbuilding business operator, if the reactor is to be installed in a ship) has technical-- Provisional translation for information only --A3-10

ability and financial position sound enough to establish reactors, and has such technical ability as to operate themcompetently; and(xii) That the location, structure and equipment of reactor facilities are such that they will cause no hindrance to theprevention of the hazard by nuclear fuel material (including spent fuel, and so in the following), by materials
contaminated by unclear fuel material (including fission products, and so in the following) and by reactors.
2. In giving license under Paragraph 1 of the preceding Article, the competent minister shall hear and respect, in advance, theopinion of the Atomic Energy Commission with respect to the application of standards specified in Subparagraph (i),Subparagraph (ii) and Subparagraph (iii) (regarding the portion related to the financial position only) of the preceding
paragraph, and the opinion of the Nuclear Safety Commission with respect to the application of standards specified in
Subparagraph (iii) (regarding the portion related to the technical ability only) and Subparagraph (iv) of the said paragraph.
(Ineligibility for the License)
Article 25.
No person who comes under one of the following subparagraphs shall be given the license under
Article 23, Paragraph 1:(i) A person whose license under Article 23, Paragraph 1 has been cancelled as provided in the rule of Article 33, Paragraph
2 and whom two years have not yet elapsed from the day of the cancellation;(ii) A person who has been condemned to the penalty heavier than the fine for violation of the rules of this Law or theOrders based on this Law, and for whom two years have not yet elapsed after having executed or suspended to executethe penalty;(iii) A legally incompetent person; and(iv) A juridical person any of whose executive officers comes under one of the preceding subparagraphs.
(License and Report of the Change, Etc.)
Article 26. When a reactor establisher wishes to change any matter provided in Article 23, Paragraph 2,
Subparagraph (ii), Subparagraph (iii), Subparagraph (iv), Subparagraph (v) or Subparagraph (viii), he shall obtain thepermission of the competent minister, as provided by the government ordinance provided that this is not applicable tothe case provided in Subparagraph (iv) of the said paragraph, where only the name of a factory or a place of businessis to be changed.
2. When a reactor establisher has changed any matter provided for in Article 23, Paragraph 2, Subparagraph (i),Subparagraph (vi) or Subparagraph (vii), except case provided for in Article 32, Paragraph 1, he shall report the change to thecompetent minister within thirty days of the day of the change. This shall also apply to the matters provided for in
Subparagraph (iv) of the said paragraph, where only the name of a factory or a place of business has been changed.
4.The provisions of Article 24 shall apply mutatis mutandis to the permission under Paragraph 1.
(Approval of Design and Construction Methods)
Article 27. Any reactor establisher shall, as provided by the order of competent ministry, (the order issued bycompetent minister: same as in this chapter) obtain the permission of the competent minister, with respect to thedesign and method of construction of the reactor facilities (except for welding in the reactor facilities defined in
Article 28-2, Paragraph 1 in which welding is performed, same in the following paragraph and Paragraph 3) before
starting of the construction. This shall also apply to the alteration of the reactor facilities.
2. When any reactor establisher wishes to change the design and method of construction of the reactor facilities for which
the approval provided on the preceding paragraph has been obtained, they shall obtain the approval of the competent minister,as provided by the order of the competent ministry; this shall not apply to any of the minor changes provided by the order ofthe competent ministry.
3. The competent minister shall give the approval provided for in the preceding two paragraphs, if he recognizes that thedesign and method of construction relevant to the application for approval provided for in the preceding two paragraphs
satisfy each of the following subparagraphs:(i) The design and method of construction have been given approval based on Article 23, Paragraph 1 or Article 26,
Paragraph 1 or have been reported according to the provisions of Paragraph 2 of the said article; and(ii) The design and method of construction are in conformity with the technical standards defined by the order of thecompetent ministry.
(Pre-service Inspection)
Article 28.
Any reactor establisher shall not use reactor facilities until they have been put successfully throughthe inspection of the competent minister as to the construction work (except for welding in the reactor facilities
defined in Article 28-2, Paragraph 1 in which welding is performed - same in the following paragraph) andperformance of the reactor facilities, as provided by the order of the competent ministry. The same apply to thereactor facilities when they are altered.
2. The performance inspection is considered as passed when the reactor facilities conform to each of the following
subparagraphs:(i) That the construction work has been done in accordance with the design and methods of construction provided for in thepreceding Article; and(ii) That the performance is, in accordance with the technical standards provided by the order of the competent ministry.
(Method of Welding and Inspection)
Article 28-2. A reactor vessel and other reactor facility in which welding is performed shall be inspected by thecompetent minister specified by the order of the competent ministry, and the reactor establisher may not use thereactor facility until it passes the inspection. However, this shall not be applied to the cases specified in Paragraph 4
and the cases specified by the order of the competent ministry.
2. A person who wishes to receive the inspection mentioned in the above paragraph, he must obtain the approval of thecompetent minister concerning the method of welding according to the order of the competent ministry.
3. The inspection mentioned in paragraph 1 shall be considered as passed if the welding satisfies each of the following-- Provisional translation for information only --A3-11subparagraphs:(i) That the welding has been carried out according to the method approved as provided for in the previous paragraph; and(ii) That the welding is in conformity with the technical standards defined by the order of the competent ministry.
4. The rector facility involving welding defined in Paragraph 1, which has been imported, shall be inspected by the competent
minister concerning welding specified by the order of the competent ministry, and the establisher may not use the reactor
facility until it passes the inspection.
5. The inspection mentioned in the preceding paragraph shall be considered as passed if the welding is in conformity with thetechnical standards mentioned in item 2 of Paragraph 3.
(Periodic Inspection of Installation)
Article 29. Any reactor establisher shall, according to the order of the competent ministry, submit those reactor
facilities designated by government ordinance to the annual inspection of the competent minister that is maderegularly once a year.
2. The Periodic inspection provided for in the preceding paragraph shall be made as to whether or not the performance of thereactor facilities is up to the technical standards provided by the order of the competent ministry.
3. The provisions described in Article 16-5, Paragraphs 3 and Paragraph 4 shall be applied with necessary modifications to
the inspection described in Paragraph 1 (limited to those relevant to commercial power reactors or reactors described in
Article 23, Paragraph 1, Subparagraph (iv)).
(Operation Plan)
Article 30.
As provided by the order of the competent ministry (ministry of education, culture, sport, scienceand technology for the nuclear reactor as defined by Article 23, paragraph 1, item 3 with the purpose of electricalgeneration and ministry of economy, trade and industry), any reactor establisher is required to draw up a plan for theoperation of the nuclear reactor which he establishes, and submit it to the competent minister (Minister of education,
culture, sport, science and technology for the nuclear reactor as defined by Article 23, Paragraph 1, item 3 with the
purpose of electrical generation and Minister of economy, trade and industry). The same applies to the case when theplan is modified.
(Merger)
Article 31. In case of a merger of juridical persons who are reactor establishers (except in case of a merging ajuridical person who is a reactor establisher with a juridical person who is not a reactor establisher, with where thejuridical person who is a reactor establisher continues to exist), when the approval of the competent minister has beenobtained for the merger, the juridical person who is to continue to exist after the merger, or the juridical person who
has been establisher by the merger shall succeed to the status of the reactor establish.
2. The provisions of Article 24, Paragraph 1, Subparagraph (i), Subparagraph (ii) and Subparagraph (iii) andParagraph 2, and Article 25 shall apply mutatis mutandis to the permission as provided in the preceding paragraph.
(Inheritance)
Article 32.
In case of an inheritance with regard to a reactor establisher, the inheritor shall succeed to the statusof the reactor establisher.
2. The inheritor who has succeed to the status of the reactor establisher described in the preceding paragraph, shall report theinheritance to the competent minister with the documents to prove the inheritance within thirty days of the day of theinheritance.
(Cancellation of the License, Etc.)
Article 33. When a reactor establisher does not begin reactor operation without justifiable reason within the period asprovided in the order of competent ministry, or continuously suspended reactor operation of one year or more, the competent
minister may cancel the license as provided in Article 23, Paragraph 1.
2. When a reactor establisher comes under one of the subparagraphs, the competent minister may cancel the license under
Article 23, Paragraph 1 or order the suspension of operation for a period not exceeding one year:(i)When a reactor establisher comes under one of the Subparagraph (ii), Subparagraph (iii), and Subparagraph (iv) of
Article 25;
When he has changed the items for which he should have obtained the license specified in the provisions of(ii)
Article 26, Paragraph 1 without the license;(iii) When he violated the order based on the rules of Article 36;(iv) When he has violated the rules of Article 37, Paragraph 1 or Paragraph 4, or the order based on the provisionsof Paragraph 3 of the said Article;(v)
When he has violated the order based on the rules of Article 43;(vi) When he has violated the provisions as provided in Article 43-2, Paragraph 1;(vii) When he has violated the order provided in Article 12-2, Paragraph 3 that is applied mutatis mutandis to
Article 43-2, Paragraph 2; or(viii) When he has violated the provisions of Article 12-2, Paragraph 4 that is applied mutatis mutandis to Article
43-2, Paragraph 2.
(ix) When he has violated the provisions of Article 43-3, Paragraph 1.
(x)When he has violated the order provided in Article 12-5 that is applied mutatis mutandis to Article 43-3,
Paragraph 2.
(xi) When he has violated the provisions of Article 58-2, Paragraph 2, or the order provided in Paragraph 3 of thesaid article.
(xii) When he has violated the provisions of Article 59-2, Paragraph 2, or the order provided in Paragraph 4 of thesaid Article.
(xiii) When he has violated the provisions of Article 59-3, Paragraph 2.
(xiv) When he has violated the provisions of Article 61-8, Paragraph 1 or Paragraph 4, or the order provided in-- Provisional translation for information only --A3-12

Paragraph 3 of the said article.
(xv) When he has violated the condition as provided in Article 62, Paragraph 1 or Paragraph 2.
(xvi) When he has violated the provisions of Article 6 of the Law on Compensation for Nuclear Damage.
(xvi-2) When he has violated the order provided in Article 7, Paragraph 4, Article 8, Paragraph 5, Article 9,
Paragraph 7 or Article 11, Paragraph 6 of the Special Law for Nuclear Emergency.
(Records)
Article 34. Any reactor establisher shall, as provided by the order of the competent ministry, record items provided
by the order of the competent ministry concerning the operation of the reactor and other uses of the reactor facilities,
and keep this record at the factory or the place of business.
(Measures for Safety Preservation and the Protection of Specified Nuclear Fuel Material)
Article 35. Any reactor establisher or foreign nuclear ship operator shall, as provided by the order of the competent
ministry, take necessary safety preservation measures concerning the following items:(i)
Maintenance of reactor facilities;(ii)
Operation of reactors; and(iii) Transportation, storage or disposition of nuclear fuel material or material contaminated by nuclear fuel material.
(Transportation and disposition shall be restricted to transportation and disposition to be carried out in the factory or
the place of business where reactor facilities are installed. The same applies to Paragraph 1 of the following Article).
2. Any reactor establisher, when disposing of nuclear fuel material or material contaminated by nuclear fuel material
outside the factory or the place of business where reactor facilities are installed, shall take the necessary measures for safety
preservation, as provided by the order of the competent ministry.
(Suspension of the Use of Facilities, Etc.)
Article 36. When the competent minister recognizes that the performance of reactor facilities is not in conformity
with the technical basis provided for in Article 29, Paragraph 2, or the measures for the maintenance of reactor
facilities, or the operation of reactors, or the transportation, storage or disposal of nuclear fuel material or material
contaminated by nuclear fuel material, are in violation of the provisions of the order of the competent ministry or
ministry of land and transportation based on the rules of Paragraph 1 of the preceding Article, he may order any
reactor establisher to suspend use, to remodel, to repair or to change the location of reactor facilities, or to takenecessary safety preservation measures such as the designation of the method of operation of reactors.
2. When the competent minister recognizes that measures for the physical protection are in violation of the order of thecompetent minister based on Paragraph 2 of the preceding Article, he may order the reactor establisher to take remedial
measures.
(Operational Safety Program)
Article 37. Any reactor establisher shall, as provided by the order of the competent ministry, lay down the
Operational Safety Program (including the rules on the safety education on operation of the reactor, the same as inthis article)and obtain the approval of the competent minister before starting the operation of reactors. This shall also
apply to the alteration of it.
2. The competent minister shall not give the approval under the preceding paragraph, when he deems that the safety
regulations is not sound enough to prevent accidents by nuclear fuel material, material contaminated by nuclear fuel material
or reactors.
3. When the competent minister deems it necessary to prevent accidents by nuclear fuel material, material contaminated by
nuclear fuel material, or reactors, he may order any reactor establisher to alter their Operational Safety Program.
4. Any reactor establisher and employees of them shall observe the Operational Safety Program.
5. Any reactor establisher shall, according to the order of the competent ministry, be inspected regularly by the competent
minister of the compliance to the requirement of the preceding paragraph(Decommissioning of Reactors)
Article 38. When any reactor establisher (including person who is provided for in Article 66 Paragraph 1 and so in
the next paragraph) wishes to dismantle reactors, they shall, as provided by the order of the competent ministry,
report to the competent minister in advance.
2. When the report described in the preceding paragraph is made, the competent minister may, if he deems it necessary,
designate the method of dismantling reactors or order any reactor establisher to eliminate the contamination by nuclear fuelmaterial or to take other necessary measure to prevent accidents by nuclear fuel material, material contaminated by nuclear
fuel material or reactors.
(Transfer of Reactors)
Article 39. Any person who wishes to receive reactors or whole facilities including reactors from any reactor
establisher shall obtain the permission of the competent minister, as provided by government ordinance.
3. The rules of Article 24 and Article 25 shall apply mutatis mutandis to the permissions under the two preceding
paragraphs.
4. A person who, with the permission under Paragraph 1, has received reactors or whole facilities including reactors from areactor establisher shall succeed to the status of the reactor establisher with respect to the reactors.
(Chief Engineer of Reactors)
Article 40.
Any reactor establisher shall, as provided by the order of the competent ministry, appoint the chiefengineer of reactors among the persons who have a certificate of the chief engineer of reactors described in
Paragraph 1 of the following article, to make him supervise safety preservation concerning the operation of reactors.
2. Any reactor establisher have assignment the chief engineer of reactors described in the provisions of the preceding
paragraph, they shall report the notification to the competent minister within thirty days of the day of the notification. This
shall also apply to the dismissal of him.
(Certificate for the Chief Engineer of Reactors)-- Provisional translation for information only --A3-13

Article 41. The Minister of Education, Culture, Sports, Science and Technology and the Minister of Economy, Tradeand Industry shall grant a certificate of the chief engineer of reactors to a person who comes under one of thefollowing subparagraphs:(i) A person who has passed the qualification test of the chief engineer of reactors executed by the Minister of Education,
Culture, Sports, Science and Technology and the Minister of Economy, Trade and Industry; or(ii) A person whom Minister of Education, Culture, Sports, Science and Technology and the Minister of Economy, Tradeand Industry recognize as provided by the government ordinance, to have knowledge and experience equal to or morethan those person provided for in the preceding paragraph.
2. The Minister of Education, Culture, Sports, Science and Technology and the Minister of Economy, Trade and Industry
may not to grant a certificate for the chief engineer of reactors to a person who comes under one of the following
subparagraphs.
(i) A person who has been ordered to return his certificate of the chief engineer of reactors provided for in the provisions of
the following paragraph, and for whom one year has not yet elapsed from the day ordered to return; or(ii) A person who has been condemned to the penalty heavier than the fine for violation of the rules of this Law or the order
based on this Law, or has been executed the penalty or suspended the execution of it, and for whom two years have notyet elapsed after having executed or suspended to execute the penalty.
3. When a person who has been granted a certificate of the chief engineer of reactors has violated the rule of this Law or theorder on this Law, The Minister of Education, Culture, Sports, Science and Technology and the Minister of Economy, Tradeand Industry may order him to return his certificate.
4. The subjects, the procedures or other details of the qualification test for the chief engineer of reactors provided for in
Paragraph 1, Subparagraph (i), and the procedure for granting and returning certificate of the chief engineer of reactors shallbe provided by the order of Ministry of Education, Culture, Sports, Science and Technology and Ministry of Economy, Tradeand Industry.
(Duties of the Chief Engineer of Reactors, Etc.)
Article 42. The chief engineer of reactors shall be faithful in the discharge of his duties.
2. Any person who is engaged in the operation of reactor shall obey the instructions for the safety preservation given by thechief engineer of reactors.
(Order to Dismiss the Chief Engineer of Reactors)
Article 43. When the chief engineer of reactors has violated the rules of this Law or the order based on this Law, thecompetent minister may order any reactor establisher to dismiss him.
(Welding Inspection Performed by the Organization)
Article 61-24. The Minister of Economy, Trade and Industry shall make the Organization to perform the inspection describedin Article 16-4, Paragraph 1 and Paragraphs 4, Article 28-2, Paragraph 1 and Paragraph 4 (limited to the portion related tocommercial power reactors and reactors described in Article 23, Paragraph 1, Subparagraph (iv) and the associated facilities).
(Conditions of the Authorization or the License)
Article 62.
Except as established in the following paragraphs, the conditions may be attached to theauthorization or the license provided by this Law.
2. In the licensing of Paragraph 1, Article 23, necessary condition to observe international commitment in relation to thelimitation of utilization and transfer of international restricted material may be attached.
3. The conditions of the preceding two paragraphs shall be confined to the minimum necessary to ensure the enforcement of
the items concerning the authorization or the license, and shall not be such that they may obligate unreasonably the persons
who wish to obtain the authorization or license.
(Emergency Measures)
Article 64. With respect to the nuclear fuel material, the material contaminated with nuclear fuel material or thereactor which is possessed by a reactor establisher, a business operator, etc., (hereinafter referred to as "business
operators" in this Article), and any person who has been entrusted with transportation or storage by those persons,when there is a possibility of accident by nuclear fuel material, material contaminated with nuclear fuel material or areactor through earthquake, fire or any other disaster, or when such accident has actually occurred, they shall take theemergency measures at once, as provided by the order of the competent ministry.
2. Any person who has discovered the situation provided for in the preceding paragraph shall inform it to a police officer ora maritime safety official.
3. When the Minister of Economy, Trade and Industry considers it urgently necessary for the purpose of preventing hazards
due to nuclear fuel material, the material contaminated with nuclear fuel material or reactors, in the case stated in Paragraph 1,
he may order such persons as mentioned in the said paragraph, in accordance with the division of business operators
mentioned in the following items, to suspend the use of reactor facilities; to change the place where nuclear fuel material or
the material contaminated with nuclear fuel material is located; or to take other measures necessary to prevent hazards from
nuclear fuel material, the material contaminated with nuclear fuel material or reactors.
(Cancellation of the Authorization or the License, Measures Taken in Consequent of the Discontinuance of Business, Etc.)
Article 66. A reactor establisher whose authorization has been cancelled, in accordance with the provisions of Article
33 shall, as provided by the order of the competent ministry, take measures to transfer nuclear fuel material toeliminate contamination with nuclear fuel material or to dispose of nuclear fuel material or the material contaminatedwith nuclear fuel material, or to transfer internationally regulated substances (except nuclear fuel material).
4. When the competent minister recognizes that the measures taken by the persons defined in Article 4, Paragraph 1 shallnot be appropriate, he may order the persons defined in said paragraph to take the following measures:(i) Measures necessary for the prevention of hazards due to nuclear fuel material, the material contaminated with nuclear fuelmaterial or reactors.
(Notification of Termination of Business)-- Provisional translation for information only --A3-14

Article 65. When a reactor establisher discontinues operation of reactors relevant to the concerned license, he shall notify
the discontinuance to the competent minister as provided in the Ordinance of the competent ministry.
(Cancellation of the Authorization or the License, Measures Taken in Consequent of the Termination of Business, Etc.)
Article 66. A reactor establisher whose authorization has been cancelled, in accordance with the provisions of Article
33 shall, as provided by the order of the competent ministry, take measures to transfer nuclear fuel material toeliminate contamination with nuclear fuel material or to dispose of nuclear fuel material or the material contaminatedwith nuclear fuel material, or to transfer internationally regulated substances (except nuclear fuel material).
4. When the competent minister recognizes that the measures taken by the persons defined in of Article 4, Paragraph 1 shallnot be appropriate, he may order the persons defined in said paragraph to take the following measures:(i) Measures necessary for the prevention of hazards due to nuclear fuel material, the material contaminated with nuclear fuelmaterial or reactors.
(Rule for Affairs)
Article 66-2. The Organization shall define rules for implementation of affairs (hereinafter referred to as “rules of affairs”) ofinspection etc. (which means inspections and verifications, as well as a part of affairs concerning inspections andverifications, described in the following subparagraphs, the same shall be applied, hereinafter.) before starting businessconcerning affairs of inspection etc., and shall notify this to the minister as provided in the subparagraph concerned(hereinafter referred to as “the competent minister” in this Article and Article 68-2). The same shall be applied when the
Organization intends to modify them.
(i)A part of affairs concerning inspections provided in Article 16-3, Paragraph 3 (including the case where the said
paragraph is applied with necessary modifications to Article 28, Paragraph 3) and Article 16-5, Paragraph 3 (including
the case where the said paragraph is applied with necessary modifications to Article 29, Paragraph 3); The Minister of
Economy, Trade and Industry(ii)
Inspections provided in Article 61-24, Paragraph 1; The Minister of Economy, Trade and Industry
2. The competent minister may order to modify the rules of affairs concerning notification provided in the preceding
paragraph where the minister deems the said rules of affairs is not in conformity to perform the affairs of inspection etc.
appropriately and assuredly.
3. Items to be defined in the rules of affairs shall be provided by the order of competent ministry (which means the order by
the competent minister, the same shall be applied to the following article).
(Persons to Perform the Affairs of Inspection etc.)
Article 66-3. When the Organization performs the affairs of inspection etc., the Organization shall make the qualified person
provided by the order of competent ministry to perform the said affairs(Allegation to Competent Minister etc.)
Article 66-4. The employee of reactor establisher or radioactive disposal business operator may allege the fact of violation
when any reactor establisher violates the law or the order based on the law to competent minister or nuclear safetycommission.
2. The reactor establisher or radioactive disposal business operator shall not dismiss or act against him for his allegation.
(Collection of Reports)
Article 67. The Minister of Economy, Trade and Industry or public safety commissions of prefectures may request
reactor establisher or radioactive disposal business operator, as far as necessary for the enforcement of this Law, to
produce reports on his operations, as provided by the government ordinance, in accordance with the division ofbusiness operators listed in the items of Article 64, Paragraph 3.
2. Other than the request of the report as provided in the previous paragraph, Minister of Economy, Trade and Industry may
request reactor establisher or radioactive disposal business operator, as far as necessary for the enforcement of this Law, to
produce reports on his maintenance and inspection activity done to his facility, as recognized as necessary to prevent thehazards due to reactor, nuclear fuel material and material contaminated with nuclear fuel.
3. The Minister of Economy, Trade and Industry may, as far as necessary for the enforcement of this Law, make theOrganization to submit reports concerning their business in accordance with divisions of affairs of inspection etc. describedin subparagraphs of Article 66-2, Paragraph 1.
(Nuclear Facility Inspector and Nuclear Safety Inspector)
Article 67-2. Nuclear Facility Inspectors and Nuclear Safety Inspectors are assigned the Ministry of Economy, Trade andIndustry.
2. Nuclear Facility Inspectors assigned in the Ministry of Economy, Trade and Industry shall engage in the affairs concerninginspection provided in Article 28 through Article 29.
3. Nuclear Safety Inspectors assigned in the Ministry of Economy, Trade and Industry shall engage in the affairs concerninginspection provided in Articles 37, Paragraph 5.
4. The necessary matters concerning the number and qualification of Nuclear Facility Inspectors and Nuclear Safety
Inspectors defined by the Government Ordinance.
(Entry and Inspection, Etc.)
Article 68. The Minister of Education, Culture, Sports, Science and Technology, Minister of Economy, Trade andIndustry, minister of MLT or public safety commissions of prefectures may cause their officials, as far as necessary
for the enforcement of this Law (for the enforcement of this Law according to the division of business operators
listed in the items of Article 64, Paragraph 3 to enter the offices, factories or places of business so as to examine theirbooks, documents and other necessary matters, ask questions of persons concerned, and take samples of nuclear
source material, nuclear fuel material and other necessary materials in the minimum of amount required for test).
2. The Minister of Education, Culture, Sports, Science and Technology, Minister of Economy, Trade and Industry or
minister of MLT may cause their officials, as far as necessary for the enforcement of this law (for the enforcement of theprovisions of Article 28-2, Paragraph 1 related to commercial power reactors and their related facilities: the Minister of-- Provisional translation for information only --A3-15

Economy, Trade and Industry), to enter the offices factories, or the places of business of the persons who conduct welding of
the facilities specified in Article 28-2, Paragraph 1 so as to examine their books, documents and other necessary matters andask questions of persons concerned.
5. When officials make entrance in accordance with the provisions of the preceding three paragraphs, they shall carry theiridentification cards with them and show them when requested by persons concerned.
6. The authority provided for in the provisions from Paragraph 1 through Paragraph 4 shall not be construed as having been
granted for the purpose of criminal investigation.
(Order to the Organization)
Article 68-2. Competent minister may order the work to the Organization, when he recognize it is necessary to implement
the work concerning the inspection and the work provided in paragraph 7 of previous Article appropriately.
(Administrative Protest Etc.)
Article 70. Any person dissatisfied with the disposition or the omission of inspection or verification to be implemented by theOrganization in accordance with this law may file an administrative protest to the minister defined in the following
subparagraphs in accordance with the classification of inspection and verification specified in the following subparagraphs inaccordance with Administrative Review Law (Law No. 160, 1962):(i) Inspection as provided in Article 61-24, Paragraph 1; the Minister of Economy, Trade and Industry.
2. An appeal of annulment for the disposition in accordance with this law shall not be filed till a decision (the decision for theadministrative protest for the protest-able disposition as provided in the preceding paragraph) for the administrative protest ismade.
3. The provisions provided in Article 27, Paragraph 2 of the Administrative Procedure Law shall not be applied to the actionin accordance with this Law.
(Approval Etc. for Action Etc.)
Article 71. When the Minister of Education, Culture, Sports, Science and Technology, the Minister of Economy, Trade andIndustry or the Minister of Land, Infrastructure, and Transport makes disposition as provided in Paragraph 1 of Article 23,
Paragraph 1 of Article 23-2, Paragraph 1 of Article 26, Paragraph 1 of Article 26-2, Paragraph 1 of Article 31, Article 33 orParagraph 1 or Paragraph 2 of Article 39, or adds the condition as provided in Article 62, Paragraph 2 (hereinafter referred toas “takes action etc.” in this paragraph), the Minister of Education, Culture, Sports, Science and Technology, the Minister of
Economy, Trade and Industry or the Minister of Land, Infrastructure, and Transport shall have approval of the Minister of
Education, Culture, Sports, Science and Technology, the Minister of Economy, Trade and Industry or the Minister of Land,
Infrastructure, and Transport in advance in accordance with the classification specified in the following subparagraphs:(i) When the Minister of Education, Culture, Sports, Science and Technology takes disposition etc. involving a power
generating reactor as provided in Subparagraph (iii) of Article 23, Paragraph 1; the Minister of Economy, Trade andIndustry; and(ii) When the Minister of Economy, Trade and Industry makes disposition etc. involving a commercial power reactor or areactor provided in Article 23, Paragraph 1, Subparagraph (iv); the Minister of Education, Culture, Sports, Science andTechnology.
2. When the Minister of Education, Culture, Sports, Science and Technology, the Minister of Economy, Trade and Industry
or the Minister of Land, Infrastructure, and Transport recognizes it necessary to especially examine the particulars concerning
the approval asked as provided in the preceding paragraph, the Minister of Education, Culture, Sports, Science andTechnology, the Minister of Economy, Trade and Industry or the Minister of Land, Infrastructure, and Transport may demandnecessary reports of the relevant reactor establisher or the foreign nuclear ship operator, or may cause their officials to enter
the offices, factories or places of business of the reactor establisher or the foreign nuclear ship operator so as to examine theirbooks, documents and other necessary matters, ask questions to persons concerned.
3. The provisions of Articles 68, Paragraph 6 and 11 shall apply mutatis mutandis to entry and inspection provided in thepreceding paragraph.
15. When the Organization has implemented the inspection specified in Article 28-2, Paragraph 1 or Paragraph 4, theorganization shall promptly notify the Minister of Economy, Trade and Industry of the results of inspection.
16. In the case of preceding paragraph, the Minister of Economy, Trade and Industry shall promptly notify the Minister of
Education, Culture, Sports, Science and Technology of the results of inspection concerning the reactor provided in Article 23,
Paragraph 1, Subparagraph (iv).
(Report to Nuclear Safety Commission)
Article 72-3. The Minister of Economy, Trade and Industry shall report to Nuclear Safety Commission quarterly of thelicensing and inspection activity done concerning to the matters shown in the followings, in previous quarter, if necessary, he
may ask the opinion of NSC, he will take necessary measures to prevent hazard due to reactor, nuclear fuel material andmaterial contaminated with nuclear fuel material:(i)
Approval of the fitness-for-safety program and its alteration provided in Article37, Paragraph 1;(ii)
Approval of Design and Construction Methods provided in Article27, Paragraph 1 and Paragraph 2;(iii) Pre-service Inspection provided in Article 16-3, Paragraph 1 and Article 28, Paragraph 1.
(iv) Welding inspection provided in Article 16-4, Paragraph 1 and Article 28-2, Paragraph 1; and(v)
Periodic facility inspection provided for in Article 16-5, Paragraph 1 and Article 29, Paragraph 1.
2. Other than reports provided in the preceding paragraph, the Minister of Economy, Trade and Industry shall report to
Nuclear Safety Commission of the enforcement status of this law concerning to prevent hazard due to nuclear fuel materials
and materials contaminated with nuclear fuel materials or reactors in accordance with the provisions provided in the
Ordinance of the Ministry of Economy, Trade and Industry.
(Co-operation to the investigation by Nuclear Safety Commission)
Article 72-4. The reactor establisher or contractors on maintenance of reactor facilities must cooperate Nuclear
Safety Commission, when it conducts investigation concerning matters relating the report which is filed in-- Provisional translation for information only --A3-16

accordance with provisions of Paragraph 1 of previous article.
(Exception from Application)
Article 73. The provisions of Article 27, Article 28 and Article 29 shall not apply to the commercial powerreactors that are the reactor facilities to be inspected in accordance with the provisions of the Electricity Utilities
Industry Law (Law No. 170, 1964) and the order based on the said law.
(Exception for Affairs)
Article 74-2. The Inspection concerning the safeguard shall be submitted to the officer of Ministry of Economy,
Trade and Industry in accordance with the provision of Ordinance.
2. The officer of Ministry of Economy, Trade and Industry in accordance with the provision of the Ordinance may
manage the affairs that can be managed by the officer of Ministry of Education, Culture, Sports, Science andTechnology in accordance with the provision of Article 68, Paragraph 1, Paragraph 4, Paragraph 10 and Paragraph11.
3. The requirement of Article 68, Paragraph 5 and Paragraph 6 shall apply mutatis mutandis to such on-the-spot
inspection as prescribed in the preceding paragraph
Chapter 8 Penal Provisions
Article 77. Any person who comes under one of the following subparagraphs shall be condemned to penal servitude
of not more than 3 years and/or the fine of not more than three million yen;(iv) A person who has established reactors without the permission under Article 23,Paragraph 1;(v) A person who has violated the order of suspension of operation of reactors provided for in Article 33, Paragraph 2; and(vi) A person who has received a reactor or whole facilities (including a nuclear ship) including a reactor withoutobtaining the permission provided for in Article 39, Paragraph 1, or a nuclear ship without obtaining permission
provided in Paragraph 2 of the said Article.
Article 78.
Any person who comes under one of the following items shall be condemned to penal servitude of
not more than 1 year and/or to the fine of not more than one million yen:(iii) A person who, with regard to the matters for which the permission must be obtained specified in the provisions of Article
26, Paragraph 1, has changed matters provided in Article 23, Paragraph 2, Subparagraph (ii), Subparagraph (iii),
Subparagraph (iv), Subparagraph (v) or Subparagraph (viii), without the permission provided for in the said paragraph;(iv) A person who has used reactor facilities in violation of the provisions of Article 28, Paragraph 1 or Article 28-2,
Paragraph 1 or Paragraph 4;(v) A person who has violated the provisions of Article 40, Paragraph 1;(x) A person who has violated the provisions of Article 64, Paragraph 1 or of the order based on the provisions ofParagraph 3 of the said article.
Article 78-3. When the orders for the suspension of inspection work, as provided by Article 61-37 are violated, theexecutives or personnel of the designated inspection organization, etc. that has committed the violation shall bepunished with penal servitude for a term not exceeding 1 year or a fine not exceeding five hundred thousand yen.
Article 79. Any person who comes under one the following items shall be condemned to the fine of not more than
five hundred thousand yen:(i)A person who has violated orders based on the provisions of Article 36, Paragraph 1 or Paragraph 2;(ii)
A person who has violated the provisions of Article 37, Paragraph 1;(iii) A person who has violated the orders based on the provisions of Article 37, Paragraph 3;(iv)
Article 12-2, Paragraph 1, Article 22-6, Paragraph 1, Article 43, Paragraph 1, and Article 43-2(v)
A person who has dismantled reactors without making a report provided for in Article 38, Paragraph 1, or who has
violated the order based on the provisions of Paragraph 2 of the said article;(vi)
A person who has violated the conditions of Article 62, Paragraph 1; or(vii) A person who has violated the provisions of Article 66, Paragraph 1, or who has violated the order based on theprovisions of Paragraph 4 of the said article.
Article 80. Any person who comes under one of the following items shall be condemned to the fine of not more than
three hundred thousand yen:(i)A person who has failed to record, recorded falsely or failed to keep records, in violation of the provisions of Articles
34;(v) A person who has failed to mail a report provided for in Article 67, Paragraph 1, or who has reported falsely; or(vi) A person who has refused, obstructed, or evaded the entry inspection or collection of samples provided for in Article 68,
Paragraph 1 or Paragraph 2, or who has made no statement or made a false statement in response to relevant questions.
Article 80-4.
When any of the following violations has been committed, the executives or personnel of thedesignated inspection organization, etc. that has committed the violation shall be punished with a fine not exceeding
two hundred thousand yen:(i)
The organization has abolished all of its inspection work, disposal confirmation work, the work of confirming theitems transported in approved containers or the work of confirming the method of transportation without obtaining thepermission mentioned in Article 61-36;(ii)
The organization does not have account books, does not enter records in the books or made false entry into accountbooks in violation of the provisions of Article 61-38, Paragraph 1;(iii) The organization has not stored account books in violation of the provisions of Article 61-38, Paragraph 2;(iv)
The organization has not made the report mentioned in Article 67, Paragraph 2 or has made false report; or(v)
The organization has refused, obstructed or evaded the entry and inspection mentioned in Article 68-2, or it has madeno statement or has made false statement in response to relevant questions.
Article 81. When a representative of a juridical person, or an agent or any other employee of a juridical person or ofa person has violated the provisions in the following subparagraphs with respect to the business of the juridical-- Provisional translation for information only --A3-17person or the person, the juridical person shall be punished with such fines provided in the respective subparagraphor the person shall be punished with such fine described in the respective items, in addition to the punishment of theactual offender:(i)
Article 77, Subparagraph (iv), Subparagraph (v) or Subparagraph (vi) through Subparagraph (vii-4); fine notmore than three hundred million yen; or(ii)
Article 78, Subparagraph (ii), Subparagraph (iii), Subparagraph (iv), Subparagraph (viii) (excluding
provisions concerning to reactor establishers of testing and research reactors), Subparagraph (x) (excluding
provisions concerning to reactor establishers of testing and research reactors), Subparagraph (xi),
Subparagraph (xii), Subparagraph (xxviii), Subparagraph (xxix) or Subparagraph (xxx); fine not more than
one hundred million yen.
Article 82. Any person who comes under one of the following items shall be condemned to the administrative fine of
not more than one hundred thousand yen:(v)
A person who has failed to report as describe in Article 30, or reported falsely;(vi)
A person who has failed to report as described in Article 40, Paragraph 2; or(vii) A person who has failed, without any justified reason, or return the certificate for the chief engineer of reactors, inviolation of the order based on the provisions of Article 41, Paragraph 3.
Article 83. A person who has failed to report as described in Article 26, Paragraphs 2 or Article 32, Paragraph 2,
shall be condemned to the fine of not more than fifty thousand yen(2) Ordinance for the Enforcement of the Law on the Regulation of Nuclear Source Material, Nuclear Fuel
Material and Reactors (Excerpt)(Government Ordinance No.324, November 21, 1957)
Latest Revision: Ordinance No. 57, March 24, 2004
Chapter 2 Rules for Establishment, Operation etc. of Reactors(Application for License for the Establishment of Reactors)
Article 6. Such license as provided in Article 23, Paragraph 1 of the Law shall be obtained for every factory or place ofbusiness (in the case of a nuclear reactor being installed in a ship, every ship) in which a nuclear reactor is to be installed.
2. Persons proposing to obtain such permission as mentioned in the preceding paragraph shall make an application together
with their plan for raising the funds necessary for the construction of a reactor and other papers specified by the order of thecompetent ministry.
(Reactor at the Stage of Research and Development)
Article 6-2. Such reactors as determined by government ordinance as provided in Article 23, Paragraph 1,
Subparagraph (iv) of the Law shall for the time being be listed among the reactors of a type identical with that ofthose which had by January 3, 1979, been given such license as provided in Article 23, Paragraph 1 of the Law
before its revision under the Law for Partial Revision of the Atomic Energy Basic Law and Others (Law No. 86,
1978) or with that of those (referred to as "special reactors" in the following paragraph) which had by that time beenscheduled for construction under the basic program for the development of power reactors specified in Article 25,
Paragraph 1 of the Power Reactor and Nuclear Fuel Development Corporation Law (Law No.73, 1967) for purposes
as reactors designed for electric power generation, provided that those designed for electric power generation shallcome under any of the following Subparagraph (i) and Subparagraph (ii).
(i) Fast breeder reactors (the fast breeder reactor as referred to in Article 2, Paragraph 1 of the Power Reactor and Nuclear
Fuel Development Corporation Law (Law No. 73, 1967)).
(ii) Heavy water moderated, boiling light water cooled reactors (reactors using heavy water for moderator and boiling lightwater for coolant). (Application for Permission for Alterations affecting the Establishment of Reactors)
Article 8.
Reactor establisher, when proposing to obtain such license for alterations provided in Article 26, Paragraph 1of the Law, shall, as specified by the order of the competent ministry, submit to the competent minister an application inwhich the following particulars are entered:(i)
Their names or titles, domiciles and if they are juridical persons, the name of their representative;
The name and address of the factory or place of business dependent on the alteration;(ii)(iii) Details of the alteration;(iv)
Reason for the alteration; and(v)
If the alteration involves construction work, the plan for the work.
(Reactor Facilities Subject to Periodic Inspection of Installation)
Article 10. Those determined by government ordinance of such reactor facilities provided in Article 29, Paragraph 1of the Law shall be reactors, nuclear fuel material handling facilities, storage facilities, reactor cooling systemfacilities, instrumentation and control system facilities, disposal facilities, radiation management facilities, reactor
containment facilities, emergency power supply facilities and other facilities attached to reactors determined by orderof the competent ministry.
(Application for Permission of Transfer of Reactors)
Article 12. Persons proposing, in accordance with the provisions of Article 39, Paragraph 1 of the Law, to obtainlicense for a reactor or facilities as a whole including a reactor, shall, as specified in the order of the competent
ministry, submit to the competent minister an application in which the following particulars are entered:(i)
Their names or titles, domiciles and if they are juridical persons, the name of their representative;(ii) The names or titles and domiciles of their opponents, and if they are juridical persons, the name of their representative;(vi)
Purpose of use;-- Provisional translation for information only --A3-18

(vii) Type, thermal power and number of reactors;(vi)
The name and address of the factory or place of business where the reactor is installed;(vii) Location, structure and equipment of reactor facilities;(vii) The type of nuclear fuel material for use as fuel in the reactor and its annual amount scheduled for use; and(viii) Method of the disposal of spent fuel.
(Reporting)
Article 22. The Minister of Economy, Trade and Industry, in accordance with the provisions of Article 67, Paragraph 1 of theLaw, may cause refining business operators, fabrication business operator, commercial nuclear reactor operator (reactor
establishers specified in either item 1 or 4 of Article 23, Paragraph 1 of the Law, the same to the following paragraph) spent
fuel storage business operator, reprocessing business operator and disposal business operator etc. to report on, in addition to
the particulars mentioned in the preceding paragraph, such particulars as listed in the left column of the following Table withrespect to such persons as listed correspondingly in the lower column of the Table.
(i)Status of inventory or the change in quantity of nuclear fuel materials.
Establishers of(ii) The quantity of nuclear fuel materials inserted as fuel and its takeout.
commercial power(iii) The burn-up of nuclear fuel material.
reactors, etc.
(iv) The operating time and thermal power of the reactor.
(v) Status of radiation management.
(vi) Status of accidents damaging to persons in the reactor facilities.
(vii) Status of failures (with the exception of such failure may cause little trouble to theoperation of reactor) in the reactor facilities.
(viii) Status of disposal or transport of nuclear fuel material, etc. outside of the facilities orplace of business in which reactor facilities are established.
(ix) Status of accidents damaging to persons in the course of disposal or transport of nuclear
fuel material, etc. outside of the factories or place of business in which reactor facilities are
established.
6. The Minister of Education, Culture, Sports, Science and Technology, the Minister of Economy, Trade and Industry or the
Minister of MNLT may, under the provisions of Article 67, Paragraph 2 of the Law, cause designed inspection organization,etc. to report on the matters concerning the operation of their business.
(The Number and Qualification of Nuclear Facility Inspector and Nuclear Safety Inspector)
Article 23.
2. The number of Nuclear Facility Inspector of Ministry of Economy, Trade and Industry shall be one hundred andsixty-three.
3. The Nuclear Facility Inspector of Ministry of Economy, Trade and Industry shall have enough knowledge and experienceon structure, performance and fitness for safety of nuclear facilities.
4. The Nuclear Safety Inspector of Ministry of Economy, Trade and Industry shall have enough knowledge andexperience on the measures to be taken by the reactor establisher and spent fuel storage business operator in order toensure the fitness for safety, structure and performance of nuclear facilities.

(3) Rules Concerning Report to Nuclear Safety Commission Provided in Article 72-3, Paragraph 2 of the Law
for the Regulations of Nuclear Source Material, Nuclear Fuel Material and Reactors(Ordinance No. 2 of the Ministry of Education, Culture, Sports, Science and Technology, Ministry of
Economy, Trade and Industry and Ministry of Land, Infrastructure, and Transportation, March 31, 2003)
Rules Concerning Report to Nuclear Safety Commission Provided in Article 72-3, Paragraph 2 of the Law for the
Regulations of Nuclear Source Material, Nuclear Fuel Material and Reactors (Law 166, 1957) are provided asfollowings in accordance with Article 72-3, Paragraph 2 of the Law for the Regulations of Nuclear Source Material,
Nuclear Fuel Material and Reactors.
Article 1. In accordance with the provision of Article 72-3, Paragraph 2 of the Law for the Regulations of Nuclear
Source Material, Nuclear Fuel Material and Reactors (hereinafter referred to as “the Law”), the Minister of Education,
Culture, Sports, Science and Technology, the Minister of Economy, Trade and Industry or the Minister of Land,
Infrastructure, and Transport shall make quarterly reports to Nuclear Safety Commission of the implemented
inspection, verification and licensing activities in the previous quarter concerning to the items described in thefollowings:(i) Inspections provided in Article 12, Paragraph 5, Article 22, Paragraph 5, Article 37, Paragraph 5, Article 43-20,
Paragraph 5, Article 50, Paragraph 5, Article 51-18, Paragraph 6 and Article 56-3, Paragraph 5 of the Law;(ii) Verification provided in Article 51-6, Paragraph 1 of the Law; and(iii) Permission provided in Article 52, Paragraph 1 of the Law and Article 55, Paragraph 1 of the Law.
Article 2. Other than particulars specified in the preceding article, in accordance with the provision of Article 72-3,
Paragraph 2 of the Law, the Minister of Education, Culture, Sports, Science and Technology, the Minister of Economy,
Trade and Industry or the Minister of Land, Infrastructure or Transport shall report to Nuclear Safety Commission of
the enforcement status concerning the request of report and entry and inspection described in the following
subparagraphs promptly after the enforcement:(i) Request of the report provided in Article 67, Paragraph 1 of the Law (limited to those relevant to radiation control,
accident resulting in injury or death or failure conditions of facilities for preventing hazards due to nuclear fuelmaterials, materials contaminated with nuclear fuel materials or reactors); and-- Provisional translation for information only --A3-19

(ii) Entry and inspection provided in Article 68, Paragraph 1 and Paragraph 2 of the Law (limited to those relevant topreventing hazards due to nuclear fuel materials, materials contaminated with nuclear fuel materials or reactors).

(4) Ordinance for Implementation of Inspection Etc. by Japan Nuclear Energy Safety Organization in
Accordance with the Provision of the Law for the Regulations of Nuclear Source Material, Nuclear Fuel
Material and Reactors(Ordinance No. 112 of Ministry of Economy, Trade and Industry, September 24, 2003)
In accordance with provisions provided in Article 66-2, Paragraph 3 and Article 66-3 of the Law for the Regulationsof Nuclear Source Material, Nuclear Fuel Material and Reactors (Law 166, 1957), and for the purpose of enforcementof the Law, Ordinance for Implementation of Inspection Etc. by Japan Nuclear Energy Safety Organization inaccordance with the provision of the Law for the Regulations of Nuclear Source Material, Nuclear Fuel Material andReactors is as provided for in the followings.
(Definition)
Article 1. The meaning of terms used in this ordinance follows that of terms used in the Law for the Regulations of
Nuclear Source Material, Nuclear Fuel Material and Reactors (hereinafter referred to as “the Law”).
(Person who Implements Inspection Affairs and Welding Inspection)
Article 2. The person who implements a part of affairs concerning inspection provided in Article 16-3, Paragraph 3 of theLaw, Article 28, Paragraph 3 of the Law and Article 16-5, Paragraph 3 of the Law (including the case to apply mutatis
mutandis to Article 29, Paragraph 3 of the Law) (hereinafter referred to as “Inspection Affairs”) and the inspection provided
in Article 61-24, Paragraph 1 of the Law (hereinafter referred to as “Inspection”) that shall be performed by Japan Nuclear
Energy Safety Organization (hereinafter referred to as “the Organization”) shall be a personnel of the Organizationand qualified by one of the following subparagraphs specified in the order of competent ministry provided in Article
66-3 of the Law, and shall be appointed by the president of the Organization (hereinafter referred to as “Nuclear
Facility Examiner”):(i) A person who majored in a subject concerning science or engineering at the college (excluding junior college, same as in
Subparagraph (i) and Subparagraph (ii) of the following article and Article 5, Subparagraph (i)) as provided in the School
Education Law (Law No. 26, 1947) and graduated from it or a person who is recognized to have knowledge andexperience equal to or more than the former and have total of 2 years or more experience in the fitness-for-safety
affairs and other administrative affairs concerning fitness for safety (hereinafter referred to as “fitness-for-safetyadministrative affairs”) at a processing facility, a reactor facility, a reprocessing facility, a waste disposal facility,a specific waste management facility, a use facility, etc. (hereinafter referred to as “Nuclear Facility”) or havetotal of 3 years or more experience in affairs concerning design, construction, maintenance, inspection, quality
assurance or operation of the Nuclear Facility (hereinafter referred to as “fitness-for-safety affairs”), and finishedtraining as provided by the Minister of Economy, Trade and Industry;(ii) A person who majored in a subject concerning science or engineering at the junior college or the tertiary college
provided in the School Education Law and completed the course concerning the subject described above or a person who
is recognized to have knowledge and experience equal to or more than the former and have total of 4 years ormore experience in fitness-for-safety administrative affairs or have total of 5 years or more experience infitness-for-safety affairs, and finished training as provided by the Minister of Economy, Trade and Industry;(iii) A person who has total of 6 years or more experience in fitness-for-safety administrative affairs or have total of 7
years or more experience in fitness-for-safety affairs, and finished training as provided by the Minister of
Economy, Trade and Industry;(iv) A person who has a career as a Nuclear Facility Inspector;(v) A person who has a career as a Electric Structure Inspector provided in Article 104, Paragraph 2 of Electricity Utilities
Industry Law (Law 170, 1964) or a career as Electric Structure Inspection Personnel (a person specified in Article 3 ofOrdinance for Implementation of Inspection etc. by Japan Nuclear Energy safety Organization in accordance withthe provision of Electric Utilities Industry Law (the Ordinance No. 111 of Ministry of Economy, Trade andIndustry, 2003, hereinafter referred to as “Ministry Ordinance for Inspection”), and the same shall be applied,hereinafter), and finished training as provided by the Minister of Economy, Trade and Industry; or(vi) A person who the Minister of Economy, Trade and Industry recognized to have knowledge and experience equal
to or more than the persons described in the preceding subparagraphs.
(Person who Implements Welding Inspection)
Article 3. The person who implements welding inspection that shall be performed by the Organization shall be a personnel of
the Organization, and qualified by one of the following subparagraphs specified in the order of competent ministry
provided in Article 66-3 of the Law, and shall be appointed by the president of the Organization (hereinafter referred
to as “Welding Inspector”):(i)
A person who majored in a subject concerning welding engineering, nuclear engineering, naval architecture,mechanical engineering, metal engineering, electric engineering and chemical engineering at the college provided in
the School Education Law and graduated from it, and has total of 2 years or more experience in practice ofconstruction or inspection of Nuclear Facilities, and finished training as provided by the Minister of Economy,
Trade and Industry;(ii)
A person who majored in a subject concerning science or engineering (excluding particulars described in thepreceding subparagraph) at the college provided in the School Education Law and graduated from it, and has total of 4
years or more experience in practice of construction or inspection of Nuclear Facilities, and finished training as-- Provisional translation for information only --A3-20

provided by the Minister of Economy, Trade and Industry;
A person who majored in a subject concerning welding engineering, nuclear engineering, naval architecture,mechanical engineering, metal engineering, electric engineering or chemical engineering at the junior college or thetertiary college provided in the School Education Law and completed the course concerning subject described above,and has total of 4 years or more experience in practice of construction or inspection of Nuclear Facilities, andfinished training as provided by the Minister of Economy, Trade and Industry;(iv)
A person who has total of 6 years or more experience in practice of construction or inspection of Nuclear
Facilities, and finished training as provided by the Minister of Economy, Trade and Industry;(v)
A person who has a career as a Nuclear Facility Inspector;(vi)
A person who has a career as Electric Structure Inspector provided in Article 104, Paragraph 2 of the Electricity
Utilities Industry Law or a career as Electric Structure Inspection Personnel;(vii) A person who has experience in implementation for welding inspection, inspection provided in Article 61-24,
Paragraph 2 of the Law, inspection provided in subparagraphs of Article 61-24, Paragraph 2 of the Law before
amendment (hereinafter referred to as “the Old Law”) provided in Article 8 of supplementary provision of the
Law for Japan Nuclear Energy Safety Organization (Law No. 179, 2002) or old welding inspection (inspection
provided in Article 52, Paragraph 1 of Electricity Utilities Industry law before amendment provided in Article
9 of the Law on Consolidation and Rationalization for Standard, Licensing System Etc. concerning Ministry ofInternational Trade and Industry (Law No.121, 1999), the same shall be applied, hereinafter );(viii) A person who has experience in practice of the review provided in Article 52, Paragraph 3 of the Electricity
Utilities Industry Law; or(ix) A person who the Minister of Economy, Trade and Industry recognized to have knowledge and experience equal
to or more than the persons described in the preceding subparagraphs.
(Person who Implement Verification Affairs for Waste Disposal Facilities)(Particulars Stipulated in Rules for Affairs)
Article 7. Particulars that shall be stipulated in rules for affairs concerning Inspection Affairs specified in the order ofcompetent ministry provided in Article 66-2, Paragraph 3 of the Law shall be particulars shown in the followings:(i)
The name of the place of business and the area where the place of business implements Inspection Affairs;(ii)
Particulars for office hours that Inspection Affairs are implemented and day off;(iii) Particulars for duties of a Nuclear Facility Examiner;(iv) Particulars for appointment and dismissal and assignment of a Nuclear Facility Examiner.
(v)
Particulars for implementation method for Inspection Affairs;(vi) Particulars for preservation of books and documents for Inspection Affairs;(vii) Particulars for notifying the competent minister of the results of Inspection Affairs; and(viii) Other particulars necessary to implement Inspection Affairs.
2. Particulars that shall be stipulated in rules for affairs concerning welding inspection specified in the order of competent
ministry provided in Article 66-2, Paragraph 3 of the Law shall be particulars shown in the followings:(i)
The name of the place of business and the area where the place of business implements welding inspection
work;
(ii)
Particulars for office hours that welding inspection is implemented and day off;(iii) Particulars for method of collecting charge;(iv)
Particulars for duties of nuclear Welding Inspector;(v)
Particulars for appointment and dismissal and assignment of nuclear Welding Inspector;(vi)
Particulars for implementation method for welding inspection;(vii) Particulars for method of certification that the results of welding inspection are acceptable;(viii) Particulars for preservation of books and documents for welding inspection; or(ix)
Other particulars necessary to implement welding inspection.
3. The provisions of subparagraphs of Paragraph 1 shall apply mutatis mutandis to particulars that shall be stipulated inrules concerning verification affairs for waste disposal facilities in accordance with the order of competent ministry
provided in Article 66-2, Paragraph 3 of the Law. In the case, “Inspection Affairs” shall be translated into “verificationaffairs for waste disposal facility”, and “Nuclear Facility Examiner” shall be translated into “waste disposal facility
verification personnel” in these provisions.
4. The provisions of subparagraphs of Paragraph 2 shall apply mutatis mutandis to particulars that shall be stipulated inrules for affairs concerning disposal verification in accordance with the order of competent ministry provided in Article
66-2, Paragraph 3 of the Law. In the case, “welding inspection” shall be translated into “disposal verification”, “Welding
Inspector” shall be translated into “disposal verification personnel”, and “the results of welding inspection are
acceptable” shall be translated into “disposal was verified” in these provisions.
5. The provisions of subparagraphs of Paragraph 2 shall apply mutatis mutandis to particulars that shall be stipulated inrules for affairs concerning transporting material verification in accordance with the order of competent ministry provided
in Article 66-2, Paragraph 3 of the Law. In the case, “welding inspection” shall be translated into “verification fortransporting material”, “Welding Inspector” shall be translated into “transporting material verification personnel”,
and “the results of welding inspection are acceptable” shall be translated into “transporting material was verified” inthese provisions.
(Reporting)
Article 8. When the Organization implemented welding inspection, disposal verification and verification for transporting
material, the Organization shall promptly reports to the Minister of Economy, Trade and Industry of the results withinspection result report in Form No.1 for welding inspection, disposal verification result etc. report in Form No. 2 fordisposal verification and transporting material verification result report in Form No. 3 for transporting material verification.
(iii)-- Provisional translation for information only --A3-21

However, if the results were notified in accordance with the provision provided in Article 71, Paragraph 15 of the Law, theprovisions in this article are not applicable.
Article 9. Notification provided in Article 71, Paragraph 15 of the Law shall be notified with inspection result notification inForm No.1.
(Identification Card for Entry and Inspection, Etc. Implemented by the Organization)
Article 10. Identification card carried by the Organization personnel making entry and inspection, etc. provided in Article 68,
Paragraph 7 of the Law shall be in Form No. 4.

(5) The Rule for the Installation, Operation, etc. of Commercial Nuclear Power Reactors (Excerpt)(Ordinance No.77 of the Ministry of International Trade and Industry, December 28, 1978)
Latest Revision: Ordinance No.113 of the Ministry of Economy, Trade and Industry, September 24, 2003
(Definitions)
Article 1. The meaning of the terms used in this ministerial order are after tat of the terms used in the Law for the
Regulations of Nuclear Source Material, Nuclear Fuel Material and Reactors (herein after called Law)
2. In this ministerial order, the meaning of the following terms shall be as defined in the following respective items:(iv) "Control zones" means the reactor chamber, the spent fuel storage facility, the radioactive waste disposal facility, etc.
where there is a hazard that the dose equivalent may exceed the limit specified by the Minister of Economy, Trade andIndustry, and that the concentration of radioactive material in the air may exceed the level specified by Ministry of
Economy, Trade and Industry or that the density of radioactive material on the surface of objects contaminated byradioactive material may exceed the level specified by the Minister of Economy, Trade and Industry;(vi) "Environmental monitoring area" means that area surrounding control zones, the outside of which there is no
possibility of the dose equivalent at any location exceeding the limit of the dose equivalent specified by the Minister of
Economy, Trade and Industry.
(Application of License for Establishment of Nuclear Reactor)
Article 2.
Pursuant to Article 23, Paragraph 2 of the Law, the entries in the application for the license for the installationof nuclear reactors shall be made in accordance with the following subparagraphs:(i) For the thermal power of a nuclear reactor under Article 23, Paragraph 2, Subparagraph (iii) of the Law, the continuous
maximum thermal power shall be entered;(ii) For the location, structure and equipment of a nuclear reactor facility under Article 23, Paragraph 2, Subparagraph (iv)of the Law, the entry shall be made under the following divisions;A. Nuclear reactor facility locations,(a) Site area and shape(b) Locations of main nuclear reactor facilities within the site
B. Nuclear reactor facility general structure,(a) The aseismatic structure(b) Other main structures
C. Reactor core structure and equipment,(a) Reactor core(1) Structure(2) Maximum amount of fuel assemblies to load into the core(3) Main nuclear limitation values(4) Main thermal limitation values(b) Fuel assembly(1) Fuel material type(2) Cladding type(3) Fuel element structure(4) Fuel assembly structure(5) Maximum burn-up(c) Moderator and reflector types(d) Reactor vessel(1) Structure(2) Maximum operating pressure and temperature(e) Radiation shield structure(f) Other main items
D. Nuclear fuel material handling and storage facility structure and equipment,(a) Nuclear fuel material handling equipment structure(b) Nuclear fuel material storage equipment structure and storage capacity
E. Reactor cooling system facility structure and equipment,(a) Primary cooling equipment(1) Coolant type(2) Number and structure of main components and piping units(3) Coolant temperature and pressure(b) Secondary cooling equipment(1) Coolant type(2) Number and structure of main components-- Provisional translation for information only --A3-22

(c) Emergency cooling equipment(1) Coolant type(2) Number and equipment of main components and piping units(d) Other main items
F. Instrumentation and control facility structure and equipment,(a) Instrumentation(1) Nuclear instrumentation types(2) Other main instrumentation types(b) Safety protection circuits(1) Reactor shutdown circuit type(2) Other main safety protection circuit types(c) Control equipment(1) Number and structure of control material units(2) Number and structure of control material units drive equipment(3) Reactivity control capability(d) Emergency control equipment(1) Number and structure of control material units(2) Number and structure of main components(3) Reactivity control capability(e) Other main items
G. Radioactive waste disposal facility structure and equipment,(a) Gaseous waste disposal facility(1) Structure(2) Waste disposal capacity(3) Exhaust vent location(b) Liquid waste disposal equipment(1) Structure(2) Waste disposal capacity(3) Discharge port location(c) Solid waste disposal equipment(1) Structure(2) Waste disposal capacity
H. Radiation management facility structure and equipment,(a) Indoor management main equipment types(b) Outdoor management main equipment types
I. Reactor containment facility structure and equipment, and(a) Structure(b) Design pressure, temperature and leakage rate(c) Other main items
J. Structure and equipment of other facilities attached to the reactor.
(a) Structure of emergency power supply(b) Other main items(iii) For the construction plan provided in Article 23, Paragraph 2, Subparagraph (iv) of the Law, the construction sequenceand schedule shall be entered;(iv) For the nuclear fuel material type and the yearly projected consumption amount of the nuclear fuel material which is to
be used as the fuel of the reactor provided in Article 23, Paragraph 2, Subparagraph (vii) of the Law, their yearly
projected loading amount and burn-up shall be entered for the respective material types; and(v) For the spent fuel disposal method provided in Article 23, Paragraph 2, Subparagraph (viii) of the Law, the parties towhom it is to be sold, loaned or returned, and the method thereof, or its disposal method shall be entered.
2. The documents specified by the order of the competent ministry as provided in Article 6, Paragraph 2 of the Ordinancefor the Enforcement of the Law for the Regulations of Nuclear Source Material, Nuclear Fuel Material and Reactors(hereinafter referred to as “the Ordinance”) shall be as specified in the following subparagraphs:(i)
Expository documents related to the purpose of use of the reactor;(ii)
Expository documents related to the thermal power of the reactor;(iii) Documents describing the fund amount required for and the procuring plan for the construction;(iv)
Documents describing the procurement plan for the nuclear fuel material required for the operation of the reactor.
(v)
The expository documents related to the technical capability for the installation and operation of the reactor facility;(vi)
Expository documents on the meteorological, ground, hydraulic, seismic, social environment and other conditions of
the location where the reactor facility is to be installed;(vii) A 1:200,000 map for the area covering the distance of 20 km from the location of the planned reactor or its main
related facilities, and a 1:50,000 map for the area covering the distance of 5 km from the said location;(viii) Expository documents related to the safety design of the reactor facility;(ix) Expository documents related to the management of the radiation exposure to be caused by the nuclear fuel material
and by the objects contaminated by the nuclear fuel material, and on the disposal of the radioactive waste;(x) Expository documents related to the types, levels, impacts, etc. of reactor accidents to be assumed to occur in the eventof operational error of the reactor, of the faults of the machinery or devices, of earthquakes, of fire, etc.; and(xi) In the case of a juridical person, the articles of association or the endowment, the abridged copies of the register and the-- Provisional translation for information only --A3-23

recent inventory, balance sheet and profit and loss statement
3. The number of copies for the application as specified under Paragraph1 shall be one original and two duplicates.
(Pre-service Inspection Performed by the Organization)
Article 3-6-2. The part of affairs concerning inspections that the Minister of Economy, Trade and Industry shall make Japan
Nuclear Energy Safety Organization (hereinafter referred to as “the Organization”) perform in accordance with provisions ofArticle 16-3, Paragraph 3 of the Law, which is applied mutatis mutandis to Article28, Paragraph 3 of the Law, shall be
particulars provided in the following subparagraphs:(i)
The inspection concerning particulars provided in Article 3-5, Subparagraph (i) and Subparagraph (ii); and(ii)
The inspection concerning particulars provided in Article 3-5, Subparagraph (iii) and Subparagraph (iv) (excluding
inspection for the ventilation equipment to see if the performance is in conformity with the technical standard provided in
Subparagraph (iii) and Subparagraph (iv) of the preceding article).
(Notification for Pre-service Inspection Performed by the Organization)
Article 3-6-3. When the Minister of Economy, Trade and Industry received the application provided in Article 3-4, Paragraph
1 or the notification provided in the said article, Paragraph 2, the Minister of Economy, Trade and Industry shall notify theOrganization of the notification described following particulars provided in the following subparagraphs for the part of affairs
concerning inspections that the Organization shall perform in accordance with Article 16-3, Paragraph 3 of the Law that is
applied mutatis mutandis to the application provided in Article28, Paragraph 3 of the Law:(i)Names or titles, address, and if they are juridical persons, the name of their representative who undergo theinspection;(ii)
The name and address of the factory or place of business to undergo the inspection;(iii) The date when the inspection is undergone;(iv)
The place where the inspection is undergone;(v)
Objects of the inspection; and(vi)
Inspection methods,
2. The notification provided in the preceding paragraph shall be attached with copies of documents shown in the following
subparagraphs:(i)
The application provided in Article 3-2, Paragraph 1 and the annex provided in the said article, Paragraph 2 or theapplication provided in Article 3-3, Paragraph 1 and the annex provided in the said article, Paragraph 2; or(ii)
The application provided in Article 3-4, Paragraph 1 and the documents concerning the notification provided in thesaid article, Paragraph 2.
3. When any of the particulars described in the notification provided in Paragraph 1 has been altered, the Minister of
Economy, Trade and Industry shall promptly notify the Organization of the alteration.
(Notification on Results of Pre-service Inspection)
Article 3-6-4. The notification, provided in Article 16-3, Paragraph 4 of the Law that is applied mutatis mutandis to Article28,
Paragraph 3 of the Law, shall describe particulars of the following items:(i)Names or titles, address, and if they are juridical persons, the name of their representative who undergone theinspection;(ii)
The name and address of the factory or place of business to be undergone the inspection;(iii) The date when the inspection is undergone;
The place where the inspection is undergone;(iv)(v)
Objects of the inspection;(vi)
Inspection methods; and(vii) Inspection Results.
(Certificate of Compliance for Pre-service Inspection)
Article 3-7. If the results of the inspection provided in Article 28, Paragraph 1 of the Law are decided to be acceptable, theMinister of Economy, Trade and Industry shall issue a certificate of compliance of the Pre-service Inspection to theapplication concerned.
(Nuclear Facilities that Undergo Welding Inspection)
Article 3-8. The Nuclear Facilities that is defined in the Ordinance of the Ministry of Economy, Trade and Industry
provided in Article 28-2, Paragraph 1 of of the Law shall be as shown in the following subparagraphs:(i)
Vessels that belong to the radiation management facility or adjunct facilities to reactors provided in Article 2,
Paragraph 1, Subparagraph (ii), J of (excluding emergency power supply facilities, hereinafter referred to as “AdjunctFacilities” in this article), and are used as equipment important to safety in an emergency;(ii)
Vessels that belong to the reactor containment facility;(iii) Piping units that belong to the radiation management facility or attached facilities, and are used as equipment
important to safety in an emergency (excluding piping units provided in the following subparagraphs);(iv)
Piping units that are installed in a reactor containment, and the part of the piping units that lead to the stop valve
installed most close to the containment;(v)
Vessels that belong to the radioactive waste disposal facility, radiation management facility or adjunct facility(excluding vessels provided in Subparagraph (i)) or piping units belong to those facilities of which outer diameters
exceed 61mm (100mm for piping units used below 98kPa of the maximum operating pressure), and the contained
radioactive material concentration in the piping units is 37mBq per cubic centimeters or more (37kBq per cubic
centimeters for the contained radioactive material in liquid); and(vi)
Vessels that belong to the radioactive waste disposal facility, radiation management facility or adjunct facilities(excluding vessels provided in Subparagraph (i)) or piping units belong to those facilities of which outer diameters
exceed 150 millimeters (excluding piping units provided in Subparagraph (iii) and Subparagraph (iv), and thecontained radioactive material concentration in the piping units is below 37mBq per cubic centimeters (37kBq per-- Provisional translation for information only --A3-24

cubic centimeters for the contained radioactive material in liquid), and welded to the part subjecting to the pressure
exceeding the pressure (hereinafter referred to as “pressure resistant part”) provided for in the followings;
A.
The maximum operating pressure is1960kPa for vessels or piping units used for water, and the maximum
operating temperature of the vessels or piping units is below 100 degrees,B.
The maximum operating pressure is 98kPa for vessels with exception of the vessels provided in A, or
C.
The maximum operating pressure is 980kPa for piping units with exception of the piping units provided in A
(490kPa for the part of longitudinal joint).
(Application for Welding Inspection)
Article 3-9. A person, who wishes to undergo welding inspection for Nuclear Facilities provided in the preceding article inaccordance with Article 28, Paragraph 1 of the Law, shall submit the application to the Organization in accordance with rules
for affairs provided by the Organization in accordance with the provision of Article 66-2, Paragraph 1 of the Law.
(Implementation of Welding Inspection)
Article 3-10. Welding inspection, provided in Article 28-2, Paragraph 1 of the Law, shall be implemented for the processprovided in following subparagraphs:(i)
When welding works are carried out (excluding the case that the work concerning seal welding for vessels or piping
units provided in Article 3-8, Subparagraph (vi) of and the Minister of Economy, Trade and Industry approved to use
vessels or piping units without welding inspection because there is no problem from a view point of standardization of
welding works, standardization of materials used for welding, etc.);(ii)
When the condition is ready to implement the nondestructive inspection for weld where nondestructive inspection isrequired by the technical standard (hereinafter referred to as “Technical Standard for Welding”) provided in Article
28-2, Paragraph 3, Subparagraph (ii) of the Law;(iii) When the condition is ready to implement the mechanical examination for the butt weld in accordance with theTechnical Standard for Welding; or(iv)
When the condition is ready to implement the pressure test (excluding the case involving the seal welding for vessels
or piping units provided in Article 3-8, Subparagraph (vi)).
(The Case Welding Inspection is not Necessary)
Article 3-11. The case defined by the Ordinance of the Ministry of Economy, Trade and Industry, provided in the proviso of
Article 28-2, Paragraph 1 of the Law, shall be the case to use vessels or piping units provided in Article 3-8, Subparagraph(vi) with only seal welding (including the case that only the new welding is implemented for pressure resistant part).
Article 3-12. A person who wishes to obtain approval provided in Article 28-2, Paragraph 2 of the Law shall submit theapplication describing particulars provided for in the followings to the Minister of Economy, Trade and Industry for every
factory where welding is implemented:(i)
The name or title and the address, and in the case of a juridical person, the name of its representative;(ii)
The name of the factory where welding is to be implemented;(iii) The type and capacity of welding equipment;(iv)
The kind of implementing methods of the welding; and(v)
The name of the person who implement the welding and the scope of implementation of welding methods that theperson adopts.
2. Documents that clarify particulars provided for in the followings shall be attached to the application provided in thepreceding paragraph:(i)
Welding equipment;
Implementing welding methods; and(ii)(iii) The knowledge and skill of the person who implements the welding.
3. When the Minister of Economy, Trade and Industry recognizes that the welding methods concerning the application for
approval provided in Paragraph 1 falls under the following subparagraphs, the Minister of Economy, Trade and Industry shallpermit the welding provided in the said paragraph:(i)
The type and capacity of welding equipment using welding methods concerning the application are appropriate toimplement the welding;(ii)
The welding methods to be implemented are appropriate to ensure the weld strength; and(iii) The person who implements the welding has adequate knowledge and skill for the welding using welding methods
that the person adopts.
4. The number of copies for the application provided in Paragraph 1 shall be one original.
(Welding Inspection for Imports)
Article 3-13. A person who wishes to undergo welding inspection for the weld of imported Nuclear Facilities provided in
Article 3-8 with welds in accordance with provisions of Article 28-2, Paragraph 4 of the Law shall submit the application to
the Organization in accordance with rules for affairs provided by the Organization in accordance with the provision of Article
66-2, Paragraph 1 of the Law.
(Certificate of Compliance for Welding Inspection)
Article 3-14. If the results of welding inspection implemented in accordance with Article 28-2, Paragraph 1 or Paragraph 4 of
the Law are decided to be acceptable, the Organization shall issue a certificate of compliance for welding inspection andindicate it on the welded vessels or piping units with engraved marks or the alternative.
(Application for the Periodic Inspection of Facilities)
Article 3-15. A person who wishes to undergo the inspection of performance of the Nuclear Facilities in accordance with theprovision provided in Article 29, Paragraph 1 of the Law shall submit the application describing particulars provided for in
the followings to the Minister of Economy, Trade and Industry:(i)Names or titles, address, and if they are juridical persons, the name of their representative;(ii) The name and address of the factory or place of business where the reactor is installed;-- Provisional translation for information only --A3-25

(iii) The name of Nuclear Facilities to be undergone the inspection; and(iv) The items of the inspection and the date to be implemented.
2. When the particulars described in the application provided in the preceding paragraph has been altered, the alteration shallbe notified promptly to the Minister of Economy, Trade and Industry.
3. The number of submission of the application described in Paragraph 1and the notification described in the preceding
paragraph shall be one original and one duplicate.
(Periodic Inspection of Facility Implemented by the Organization)
Article 3-15-2. The part of affairs concerning inspection, which the Minister of Economy, Trade and Industry shall make theOrganization perform in accordance with Article 16-5, Paragraph 3 of the Law that is applied mutatis mutandis to Article 29,
Paragraph 3 of the Law, shall be the inspection to see if the performance is in conformity with the technical standard provided
in subparagraphs of Article 3-17 (excluding the inspection for ventilation equipment).
(Notification for Periodic Inspection of Facility Performed by the Organization)
Article 3-15-3. When the Minister of Economy, Trade and Industry receives the application provided in Article 3-15,
Paragraph 1 or the notification provided in the said article, Paragraph 2, the Minister of Economy, Trade and Industry shallnotify the Organization of notification describing the following particulars provided in the followings for the part of affairs
concerning the inspection that the Organization shall perform in accordance with Article 16-5, Paragraph 3 of the Law, which
is applied mutatis mutandis to Article 29, Paragraph 3 of the Law:(i)Names or titles, address, and if they are juridical persons, the name of their representative who undergo theinspection;(ii)
The name and address of the factory or place of business where the inspection is to be implemented;(iii) The date when the inspection is to be implemented;(iv)
The place where the inspection is to be implemented;(v)
Objects of the inspection; and(vi)
Inspection methods.
6. The notification provided in the preceding paragraph shall be attached with copies of documents provided in thefollowings:(i)
In the case that the adjunct facility of the reactor that has obtained approval in accordance with Article 27, Paragraph
1 of the Law is installed after decommissioning in accordance with the provision of Article 38, Paragraph 1 of the Law;
the application etc. and their annexes; or(ii)
The application provided in Article 3-15, Paragraph 1 and the documents concerning the notification provided in
Paragraph 2 of the said article.
3. When any of the particulars described in the notification provided in Paragraph 1 has been altered, the Minister of
Economy, Trade and Industry shall promptly notify the Organization of the alteration.
(Applying Mutatis Mutandis)
Article 3-15-4. The provision provided in Article 3-6-4 is applied mutatis mutandis to the periodic inspection of facilities
provided in Article 29, Paragraph 1 of the Law. In the case, “Article 16-3, Paragraph 4 of the Law that is applied mutatis
mutandis to Article28, Paragraph 3 of the Law” shall be translated into “Article 16-5, Paragraph 4 of the Law that is appliedmutatis mutandis to Article 29, Paragraph 3 of the Law”.
(Certificate of Compliance for the Periodic Inspection of Facilities)
Article 3-16. If the results of the periodic inspection of facilities provided in Article 29, Paragraph 1 of the Law are decided
to be acceptable, the Minister of Economy, Trade and Industry shall issue certificate of compliance concerning the periodic
inspection of the facility.
(Technical Standards for the Periodic Inspection of Facilities)
Article 3-17. Technical standards for the performance provided in Article 29, Paragraph 2 of the Law shall be particulars
provided in the followings:(i)
The adjunct facilities of the reactor that have obtained approval in accordance with Article 27, Paragraph 1 of the Law
after decommissioning in accordance with Article 38, Paragraph 1 of the Law;
A. The performance is in conformity with the technical standards provided in subparagraphs of Article 3-6; andB. Capability for protecting leakage from the adjunct facilities of the reactor and other performances shall bemaintained in the condition that the Minister of Economy, Trade and Industry decided the results for the
Pre-service Inspection provided in Article 28 of the Law to be acceptable, or(ii) Nuclear Facilities other than the facilities provided in the preceding subparagraphs; Capability for protecting leakage
from the Nuclear Facilities and other performances necessary to maintain after decommissioning shall be in conformity
with the technical standards provided in Ordinance of Establishing Technical Standards for Nuclear Power Generation
Equipment (Ordinance No. 62 of Ministry of International Trade and Industry, 1965).
(Operation Plan)
Article 4.
The operation plan of the reactor as specified in Article 30 of the Law shall be prepared for each reactor,
using Form 1, and the operation plan for three years starting from April 1 of the relevant year shall be submitted by January
31 of the year preceding the relevant year, every year after the year (each year from April 1 to March 31 of the following year,
the same applying hereinafter) in which the scheduled day of operation commencement belongs.
2. The operation plan for the case where a reactor installation license, or a license for alteration under Article 26, Paragraph
1 of the Law is received between Feb.1 and March 31, and the operation is to be started within this time shall be submitted
forthwith after the receipt of said license, notwithstanding the provision of the preceding paragraph.
3. When the operation plan under the preceding two paragraphs is changed, the changed operation plan shall be preparedusing Form 1, and shall be submitted for each reactor, within 30 days from the day of the change.
4. The number of copies of the operation plan of the preceding paragraphs 3 shall be one original.
(Record)-- Provisional translation for information only --A3-26

Article 7.
(3) The record specified in Article 34 of the Law must be recorded for each reactor, regarding the subjects listed in the left
column of the following table, in the manners specified in the middle column of the table, and shall be retained for the period
specified in the right column of the table.
Contents to be recorded

Occasion of recording(i)Reactor facility inspection record
Result of periodical self inspection under Article 11

Retention

Each inspection

Until next inspection forthe same subject

A. Thermal power, and the neutron flux density andtemperature in the core

Continuous

10 years

B. Temperature, pressure and flow rate of coolant atreactor core inlet and outlet

Every 1 hour during operation

10 years

C. Position of control element

Every 1 hour during operation

1 yearD. Temperature within re-combiner

Every 1 hour during operation

1 year

E. Purity and daily makeup volume of coolant andmoderator (liquid only) used in reactor

Once a day

1 yearF. Fuel assembly arrangement within reactor

Each arrangement or re-arrangement

10 years after removal

G. Reactor facility checking before and after start-up
and shutdown

Each startup and shutdown

1 year

H. Day and hour of operation start, criticality
attainment, operation change, emergency
shutdown and operation shutdown

Each of these events

1 yearI. Names of operation supervisor and operator, theirshift day and hour, and transferred message

Each operation start and shift

1 year

A. Amount of received and shipped fuel assembly(except for spent fuel), by type

Each receiving and shipping

10 years

B. Amount of fuel assemblies loaded to the reactor,
by type

Each loading

10 years after removal

C. Amount of spent fuel assemblies discharged, by
type

Each removal

10 years(ii) Operation record(iii) Record of fuel assembly

Each discharge or once every month

D. Burn-up of discharged spent fuel10 years

E. Arrangement of fuel assemblies in spent fuelstorage facility

Each arranging or rearranging

5 years

F. Amount of spent fuel shipped, by type, the period
from discharge to shipping and their radioactivity.

Each shipping

10 years

G. Inspection result of fuel assembly shape or property

Before loading and after discharge

10 years after discharge

A. Dose equivalent rate at the radiation shield sidewall of reactor core, spent fuel storage facility,
radioactive waste disposal facility, etc.

Once a day during operation

10 years

B. Mean concentration of radioactive substance for
one day and 3 months, at radioactive waste ventport or exhaust monitor equipment and drain port
or drain monitoring equipment

Once a day for daily mean
concentration, and once in 3 months
for 3-month mean concentration

10 yearsC.

Once a week

10 years(iv) Radiation management record

One-week dose equivalent of the externalradiation in the control zone, mean 1-weekconcentration of radioactive substance in the air,and radioactive substance concentration on thesurface of radioactive contaminated matter-- Provisional translation for information only --A3-27

D. One-year dose of personnel engaged in radiation
work starting from April 1. For female personnel
engaged in radiation work (except those who
diagnosed as sterility and those who notified will
for no pregnancy to the reactor establisher with
document the same applying hereinafter) for 3
months starting from April 1, July1, October 1 andJanuary 1. And one month dose of female
personnel engaged in radiation work whose
pregnancy is known by the reactor establisher
through the notification of the pregnant female
herself starting from the first day of the every
month until the delivery.

Once a year for 1-year dose, once in
3 months for 3-month dose and 1
month for 1-month dose.

The period specified
under Paragraph 5

E

Dose for the five years (including the year of theover exposure exceeding 20mSv starting April 1)
specified by the Minister of Economy, Trade andIndustry of the personnel engaged in radiation
work.

Once a year for 5-years that the
Minister of Economy, Trade andIndustry specified (during the period
after the year listed in the left
column).

The period specified
under Paragraph 5

F

Radiation exposure history of personnel engaged
in radiation work prior to the day of starting theradiation management work, during the year inwhich said day belongs

At the time of the worker's starting
said work

The period specified
under Paragraph 5

G. Quantity, by type, of nuclear fuel material or
objects contaminated by nuclear fuel material
which is transported outside the plant or businessplace, the type of container used for theirtransport, and the day, time and route of thetransport

Each transporting occasion

1 year

H. Type of radioactive waste delivered to waste
facility or dumped into the sea, the quantity ofradioactive substances contained in said
radioactive waste. In case of radioactive waste
contained in container, or solidified integrally withthe container, quantity of said containers, specificgravity, damping day, time location and method.

Each occasion of disposal or
dumping

Until the reactor
dismantling

I

Each sealing or solidifying

Reactor dismantling

Each spreading prevention anddecontamination

1 yearOnce a day

1 yearEach repairing

1 year

A. Day and hour of accident occurrence andrestoration

Each event

Until the dismantling ofreactorB. Conditions of and measures taken for accident

Each event

Until the dismantling ofreactorC. Causes of accident

Each event

Until the dismantling ofreactorD. Measure taken after accident

Each event

Until the reactor
dismantling

In case radioactive waste is sealed in or solidified
together with containers, the method for them

J. In case of taking measures for prevention of
spreading and decontamination for radioactive
substance, their conditions and the name of theperson responsible for them(v) Maintenance record
A. Patrolling and checking conditions of reactor
facility, and the name of person in charge
B.

Repairing condition of reactor facility, and thename of person in charge(vi) Accident record of reactor facility, etc.

-- Provisional translation for information only --A3-28

(vii) Meteorological records
A. Wind direction and velocity

Continuous

10 years

B. Precipitation

Continuous

10 years

C. Atmospheric temperatureContinuous

10 years

A. Implementation Plan of Safety Education

Every time planned

3 years

B. Date and Item of Education implemented

Every time implemented

3 years(viii) Record of Safety Education

C. The name of educatedEvery time implemented
3 years.
2. When direct measuring is difficult for the items to be recorded in accordance with the specifications in the preceding
paragraph, those records that allow the measuring results to be estimated may be used instead of the record of these items.
3. The dose equivalent rate under A, Subparagraph (iv) in the table of Paragraph 1 and the dose equivalent under C and dose
D and E of the same subparagraph shall be respectively recorded in accordance with the conditions specified by the Ministerof Economy, Trade and Industry
4. In recording the dose for Subparagraph (iv), in the table of Paragraph 1, the condition of exposure and the method of
measurement shall also be recorded, when, as a part of the radiation exposure records, the value exclusively related to the
exposure caused by the respiration of the air contaminated by radioactive substances is recorded.
5. The retention period for the records under D to E, Subparagraph (iv) in the table of Paragraph 1 shall be the record
retention period exceeded 5 years and the reactor establisher has submit the record to the organization specified by the
Minister of Economy, Trade and Industry, or in case the person related to the retention of the record lost the status of apersonnel engaged in radiation work.
6. The reactor establisher shall issue the copy of the record to the personnel engaged in radiation management work under D,
Subparagraph (iv) in the table of Paragraph 1, when said worker leaves his duty assignment.
(Quality Assurance)
Article 7-3. In case of taking necessary actions for fitness for safety as provided in Article 35, Paragraph 1 of the Law(hereinafter referred to as “fitness-for-safety activity”), quality assurance plan shall be established, and fitness-for-safety
activities shall be planed, implemented, evaluated and improved in accordance with the quality assurance plan, and thequality assurance plan shall be improved continuously.
(Quality Assurance Plan)
Article 7-3-2. Particulars provided for in the followings shall be stipulated in the quality assurance plan:(i)
Particulars for organization to implement the quality assurance;(ii)
Particulars for the plan of fitness-for-safety activities;(iii) Particulars for implementing fitness-for-safety activities;(iv)
Particulars for evaluation of fitness-for-safety activities; and(v)
Particulars for improvement of fitness-for-safety activities.
(Organization to Implement the Quality Assurance)
Article 7-3-3. The organization to implement the quality assurance shall fall under the followings:(i)Operated by the reactor establisher (in case of a juridical person, the representative);(ii)
Responsibility and authority concerning quality assurance are defined; and(iii) The framework with which the quality assurance plan is developed, implemented, evaluated and improved
continuously is established.
(Plan for Fitness-for-safety Activities)
Article 7-3-4. Particulars for fitness-for-safety activity plan in the quality assurance plan shall be particulars provided for in
the followings:(i)
Matters to clarify the processes of Japanese Industrial Standard Q9000 (2000) in accordance with Industrial
Standardization Law (Law No. 185, 1949) and their mutual relation in fitness-for-safety activities;(ii)
Matters to establish the framework with which fitness-for-safety activities are implemented taking in to considerationeach process of planning, implementation, evaluation and improvement, and improved continuously;(iii) In case of materials or services are procured from outside, matters to establish measures for its management;(iv)
Matters to determine contents to be implemented depending on their importance for fitness for safety;
Matters to develop procedures for appropriate management of documents and records concerning fitness-for-safety(v)
activities; and(vi)
Matters to establish the education and training system necessary for persons who implement fitness-for-safety
activities.
(Implementation of Fitness-for-safety Activity)
Article 7-3-5. Particulars for implementation of fitness-for-safety activities in quality assurance plan shall be particulars
provided for in the followings:(i)Each individual work that consists of fitness-for-safety activities (hereinafter referred to as “individual work”) shall be
carried out in accordance with the followings;
A. The implementing plan for individual work (hereinafter referred to as “implementing plan” in this article) shall be
developed with clearly defined objectives for individual work and requirements for individual work,-- Provisional translation for information only --

A3-29

B.

Individual work shall be implemented in accordance with the implementing plan. In the case, it shall be confirmed
in appropriate stages that the plan meets the requirements, andC. If the implementing plan is altered, contents of alteration shall be managed properly.
(ii)
In case when materials or services are procured from outside, particulars necessary for appropriate procurement andmanaging measures for compliance to the said particulars shall be specified;(iii) In order to confirm that the individual work meets requirements specified in the implementing plan, necessary
inspections and examinations shall be established and implemented;(iv)
Persons who implement the inspections and examinations depending on the importance for the fitness for safety
provided for in the preceding subparagraph shall be specified; and(v)
Appropriate measures to manage the condition not conformity with the requirements (hereinafter referred to as“nonconformity”) shall be established.
(Evaluation for Fitness-for-safety Activity)
Article 7-3-6. Particulars for evaluation of fitness-for-safety activities in the quality assurance plan shall be particulars
provided for in the followings:(i)
Necessary monitoring and measurement of condition of fitness-for-safety activities shall be implemented inaccordance with the plan;(ii)
In order to make it clear that the fitness-for-safety activities are implemented properly, audit shall be implemented inaccordance with the plan; and(iii) The evaluation described in the preceding subparagraph shall be implemented by the person other than the persons
implemented the subject individual work.
(Improvement of Fitness-for-safety Activity)
Article 7-3-7. Particulars for improvement of fitness-for-safety activities in the quality assurance plan shall be particulars
provided for in the followings:(i)Measures for corrective actions to prevent recurrence of nonconformity and measures for preventive actions toprevent potential nonconformity shall be established and implemented respectively;(ii)
Information from other facilities shall be reflected on the preventive actions as well as information obtained
implementing fitness-for-safety activities for establisher’s reactor facilities; and(iii) Results of the evaluation provided for in the preceding article shall be reflected properly.
(Prevention from Entering into Control Zones, Etc.)
Article 8. Pursuant to the provision of Article 35, Paragraph 1 of the Law, the reactor establisher shall set up control zones,
the maintenance and repair areas and the environmental monitoring areas, and shall execute the measures specified under thefollowing respective subparagraphs:(i) The following measures shall be taken for the control zones;
A. In addition to demarcating the area with walls, fences and other demarcation structures, the establisher shall distinguishthe area clearly from other areas with the provision of signs, and shall take such measures as personal entry restriction
and lock control, etc. in proportion to the level of hazard by radiation,
B. The installer shall prohibit eating, drinking and smoking where there is a danger of the oral ingestion of radioactive
substances,C. The establisher shall take measures to ensure that the radioactive substance concentration on the surface of the floor,
wall and other objects which are liable to come in contact with persons and which are contaminated by radioactive
substances does not exceed the surface concentration limit specified by the Minister of Economy, Trade and Industry,andD. For a person leaving or carrying objects out of the control zones, the installer shall take measures to assure that theconcentration of radioactive substances on the surfaces of body of that person, of the cloths, footwear and other articles
worn on the body, and of the articles to be carried (when the articles are contained in containers or packaged, thecontainers or the package) does not exceed one tenth of the surface concentration limit specified under C.
(ii)
For the maintenance and repair area, the establisher shall clearly distinguish the area from other areas through suchmethods as the installation of signs, and shall take such measures as the restriction of personal entry, the control of thelocks and the restriction on the out-transport of articles, according to the control requirements; and(iii) For the environmental monitoring area, the installer shall take the following measures;
A. The prohibition of the habitation of persons, and
B. The restriction of the entry of persons other than those who have duty assignments in the area, through such means
as the installation of fences of signs, etc. However, this provision does not apply when it is obvious that there is no
possibility of personal entry into the said area.
(Measures Related to Dose, Etc.)
Article 9.
Pursuant to the provision of Article 35, Paragraph 1 of the Law, the reactor installer shall, with respect to thedose, etc., for the personnel engaged in radiation management work, take the measures listed under the following
subparagraphs:(i)
Measures for preventing the personnel engaged in radiation management work from exceeding the dose limit
specified by Ministry of Economy, Trade and Industry; and(ii) Measures for preventing the concentration of radioactive substance in the air breathed by the personnel engaged inradiation work from exceeding the concentration limit specified by Ministry of Economy, Trade and Industry.
2. Notwithstanding the provision of the preceding paragraph, in the case of emergency without alternative recourse, such as
the occurrence or potential occurrence of hazard in the reactor facility, and the occurrence of damage in the reactor facility
which may seriously obstruct the operation of the reactor, the personnel engaged in radiation management work (for female
workers only to those who diagnosed as sterility and those who notified will for no pregnancy to the reactor establisher with
document ) may be made to perform emergency operations of which the dose equivalent does not exceed the dose equivalent-- Provisional translation for information only --A3-30

limit specified by Ministry of Economy, Trade and Industry.
(The Patrol and Checking of Reactor Facility)
Article 10.
Pursuant to the provision of Article 35, Paragraph 1 of the Law, the reactor establisher shall make personnel
engaged in radiation management work who are normally attendant in the control zone works patrol on the reactor facility, atleast once a day, and perform checking on the facilities and equipment items listed in the following items:(i)
The reactor cooling system facilities;(ii)
The control element drive equipment; and(iii) The power supply, water supply and drain, and ventilation facilities.
(Maintenance Management of Nuclear Facility)
Article 11. In accordance with Article 35, Paragraph 1 of the Law, reactor establisher shall take actions provided for in thefollowings concerning such measures as checkup, test, inspection, replacement, modification, repair and other necessary
actions that are implemented for maintenance management of nuclear facility (hereinafter referred to as “maintenancemanagement”):(i)Establishment of policies for maintenance management of nuclear facilities to maintain the performance of nuclear
facilities described in the application for approval provided in Article 23, Paragraph 1 of the Law or application for
approval of alteration provided in Article 26, Paragraph 1 of the Law and documents and their annexes that describe
conditions for the approval in accordance with Article 62, Paragraph 1 of the Law;(ii)
Establishment of objectives for maintenance that shall be achieved in accordance with the policy described in thepreceding subparagraph;(iii) Development of the maintenance management implementation plan specifying particulars provided for in thefollowing and implementation of them in accordance with the plan;
A. Particulars concerning the method, frequency and time for implementation of checkup, test, inspection, repair,modification, replacement, etc. of nuclear facilities,
B. Particulars concerning the method for confirmation and evaluation of the results of checkup, test, inspection, repair,modification, replacement, etc. of the nuclear facilities,
C. Particulars concerning corrective actions for the method, frequency and time for checkup, test, inspection, repair,modification, replacement, etc. of the nuclear facilities based on the results of confirmation and evaluation
described in Item B, and
D. Particulars concerning records of the maintenance management of the nuclear facilities.
(iv)
The plan concerning policies, objectives and implementation of the maintenance management of nuclear facilities
shall be periodically evaluated; and(v)
The results of the evaluation provided for in the preceding subparagraph shall be reflected on the plan concerning
policies, objectives and implementation of the maintenance management of nuclear facilities.
(The Operation of the Reactor)
Article 12.
Pursuant to the provision of Article 35, Paragraph 1 of the Law, the reactor establisher shall take the measuresrelated to the operation of the reactor as listed under the following subparagraphs:(i)
Entrusting the operation of the reactor to persons who have necessary knowledge in the operation of reactors;(ii) Not allowing the operation of the reactor to start, unless all the constituent persons required for the operation of thereactor are present;(iii) Ensuring that the person responsible for operation among the constituent persons as mentioned under the preceding
subparagraph is a receiver of a license from a party designated by the notice of Ministry of Economy, Trade andIndustry;(iv) Specifying the matters to be confirmed before starting operation, the matters required for the procedure of operationand the matters to be confirmed after the interruption of operation, and making the operators observe them;(v) When an emergency shutdown occurs, investigating the cause of the shutdown and the possible presence of damage,and restarting operation shall be made after verifying the absence of conditions preventing the restarting of operation;(vi) Specifying the measures to be taken in an emergency, and making the operators observe them;(vii) When conducting a trial operation, allowing it to be conducted upon confirming its purpose and method, and themeasures to be taken in an emergency; and(viii) When operating the reactor for the purpose of training trainees, specifying the matters to be observed by the trainees,and making the matters observed under the supervision of the operator.
(Storage)
Article 14. The reactor installer shall, pursuant to the provisions of Article 35, Paragraph 1 of the Law, take themeasures related to the storage of nuclear fuel material, as listed under the following subparagraphs:(i)
Nuclear fuel material shall be stored in storage facilities;(ii)
At easily visible locations of the storage facilities, the cautions on storage shall be displayed;(iii) When persons other than those engaged in the storage of nuclear fuel material enter the storage facilities, they shall bemade to obey the instructions of the persons engaged in the storage;(iv)
Necessary measures of cooling shall be taken on spent fuel; and(v) Nuclear fuel material shall be stored in such a manner that under no circumstance, the nuclear fuel material reaches thecriticality.
(Disposal Made at the Plant or Place of Business)
Article 15. The reactor establisher shall, pursuant to the provisions of Article 35, Paragraph 1 of the Law, in
disposing the radioactive waste in the plant or place of business where reactor facility is installed, take the measureslisted under the following subparagraphs:(iii) The disposal of radioactive waste shall be executed under the supervision of persons who possess thenecessary knowledge in disposal and radiation protection related to disposal, and during the disposal process,-- Provisional translation for information only --A3-31

the persons engaged in the said disposal process shall wear working cloths;
When persons other than the persons engaged in the disposal of radioactive waste enter the disposal facility,
they shall be made to obey the instructions of the persons engaged in the disposal;(v)
Gaseous radioactive waste shall be disposed by any one of the following listed methods:
A. Discharging through a gas exhausting facility;
B. Storage-disposing in a disposal tank that is provided with an effect of hazard prevention;(vi)
When disposing by the method A in the preceding paragraph, the concentration of the radioactive materiel in theexhaust gas shall be reduced as low as possible in the exhausting facility through such methods as filtration, theattenuation of radioactivity through the lapse of time and the dilution with large volume of air. In this case, theradioactive material concentration in the air outside the environmental monitoring area shall be maintained within theconcentration limit specified by the Minister of Economy, Trade and Industry, through the monitoring of theconcentration of radioactive material in the exhaust gas at the exhausting port or in the exhaust gas monitoring
equipment;(vii) When disposing by the method B of Paragraph 3, if there is a possibility of excessive overheating by the decay heat,etc. of the said storage-disposed radioactive waste, necessary cooling measures shall be taken;(viii) Liquid radioactive waste shall be disposed by any of the following listed methods;
A. Discharging through an effluent facility,
B. Storage-disposing in a disposal tank that is provided with a hazard prevention effect,
C. Sealing in a container, or solidifying with a container into an integral mass, and storage disposing in astorage-disposal facility having a hazard prevention effect,
D. Incinerating in the incineration equipment possessing a hazard prevention effect, andE. Solidifying in the solidifying equipment possessing a hazard prevention effect.
(ix)
When disposing by the method A in the preceding paragraph, the concentration of the radioactive material in theeffluent shall be reduced as low as possible through such methods in the effluent facility as filtration, evaporation,
adsorption by ion exchange resin, the attenuation of radioactivity through the lapse of time and the dilution with large
volume of water. In this case, the radioactive material concentration in the water at the outside boundary of theenvironmental monitoring area shall be maintained within the concentration limit specified by the Minister of
Economy, Trade and Industry, through the monitoring of the concentration of radioactive material in the effluent at theeffluent discharge port or in the effluent monitoring equipment;(x)When disposing by the method B of Subparagraph (vi), if there is a possibility of excessive overheating by the decay
heat, etc. of the said storage-disposed radioactive waste, necessary cooling measures shall be taken;(xi)
When disposing by method C of Subparagraph (vi), in case the radioactive waste is to be sealed in a container, thesaid container shall meet the following listed criteria;
A. The structure shall be impermeable to water, resistant to corrosion, and highly leak-proof against radioactive
waste,
B. Freedom from the possibility of cracking or breaking, andC. The lid of the container shall be hard to be removed.
(xii) When disposing by method C of Subparagraph (vi), in case the radioactive waste and the container are solidified
integrally, the container integrally solidified with the radioactive waste shall be capable of preventing the scattering or
leaking of the radioactive waste;(xiii) When disposing by method C of Subparagraph (vi), in case the radioactive waste is storage-disposed of in astorage-disposal facility provided with a hazard prevention effect, the following shall be observed;
A. When storage-disposing radioactive waste by sealing it in a container, necessary measures for preventing the
diffusion of contamination through an eventual occurrence of cracking or breaking in the said container such as
the enveloping of the said container in material that can absorb all the sealed radioactive waste, or the provisionof a receiving saucer that can contain all the sealed radioactive waste shall be taken,
B. When there is a possibility of excessive overheating by the decay heat, etc. of the said storage-disposedradioactive waste, necessary cooling measures shall be taken,
C. On the container in which radioactive waste is sealed, or integrally solidified with solidified radioactive waste, asign indicating radioactive waste shall be affixed, and a control number that allows the collation against thecontents recorded on the basis of the provision of Article 7 with respect to the said radioactive waste shall be
displayed, and
D. On the said storage-disposal facility, control cautions shall be displayed in the easily visible area.
(xii) Solid radioactive waste shall be disposed by any of the following listed methods;
A. Incinerating in incineration equipment provided with a hazard prevention effect,
B. Sealing in a container, or solidifying integrally with the container, and storage-disposing in a storage-disposal
facility provided with a hazard prevention effect,
C. Those radioactive wastes such as large machines that are very difficult to dispose by the method of B, or otherradioactive waste that requires decay over long time shall be storage-disposed in a storage-disposal facility
provided with a hazard prevention effect;(xiii) In the disposal method specified under B of Subparagraph (xii), when the radioactive waste is sealed in a container for
disposal, the examples described under Subparagraph (ix) and Subparagraph (xi) (excluding A) shall be adopted;(xiv) In the disposal method specified under B of Subparagraph (xii), when the radioactive waste is solidified integrally withthe container, the examples described under Subparagraph (x) and (xi) (excluding A) shall be adopted; and(xv) In the disposal method specified under C of Subparagraph (xii), the examples described under B and D of
Subparagraph (xi) shall be adopted.
(Periodic Evaluation of Nuclear Facility)(iv)-- Provisional translation for information only --A3-32

Article 15-2. The reactor establisher shall take actions provided for in the followings for every reactor (excluding the reactor
notified in accordance with Article 38, Paragraph 1 of the Law) and every period not exceeding 10 years in accordance with
Article 35, Paragraph 1 of the Law:(i) Evaluation of the implementing situation of fitness-for-safety activities at the nuclear facilities; and(ii) Evaluation of the situation of reflection of state of the art technical information on fitness-for-safety activities at thenuclear facilities.
2. The reactor establisher shall take actions provided for in the followings by the day elapsed 30 years from the date ofinitiation of reactor operation:(i) Technical evaluation for aging; and(ii) Development of 10 years plan concerning actions taken for maintenance of the nuclear facilities based on the technicalevaluation provided in the preceding subparagraph.
3. The evaluation and the plan provided for in the preceding subparagraph shall be reevaluated within a period not exceed 10
years.
(Operational Safety Program)
Article 16. Persons intending to have their Operational Safety Program approved under the provisions of Article 37,
Paragraph 1 of the Law shall specify the Operational Safety Program for the particulars listed in the following
subparagraphs, for each plant or business place, and shall submit an application describing them:(i) Matters pertaining to the duty assignment and organization of persons engaged in the operation and management of thenuclear reactor facility;(ii) Matters pertaining to the safety preservation education of persons engaged in the operation and management the nuclear
reactor facility as described below;
A. Matters on implementation policy of the safety preservation education (including procedure of planning), and
B. Matters on the contents of the safety preservation education and as follows,(1) Matters on related regulations and the safety preservation rule(2) Matters on the structure, performances and the operation of the nuclear installation(3) Matters on radiation management(4) Matters on the handling of nuclear fuel materials and materials contaminated by nuclear fuel material(5) Matters on measures to be take at an emergency(iii) Matters pertaining to the operation of the nuclear reactor facility;(iv)
Matters pertaining to the safety review of the operation of the nuclear reactor facility;(v)
Matters pertaining to the establishment of the control zone, the preservation area and the environmental monitoring
area, and to the entry restrictions, etc. into these areas;(vi)
Matters pertaining to the ventilation monitoring equipment and drain monitoring equipment;(vii) Matters pertaining to the monitoring of the dose and dose equivalent, the radioactive material concentration and thesurface radioactive material concentration on objects contaminated by radioactive material, and to thedecontamination;(viii) Matters pertaining to the management of the radiation measuring instruments;(ix)
Matters pertaining to the patrolling and checking of the nuclear reactor facility, and their related measures;(x)
Matters pertaining to the receiving and shipping, transport, storage and other handling of nuclear fuel material;(xi)
Matters pertaining to the disposal of radioactive waste;(xii) Matters pertaining to the measures to be taken in the case of emergency;(xiii) Matters pertaining to the recording of matters related to the safety preservation (including compliance tofitness-for-safety rules of nuclear facilities) of the nuclear reactor facility;(xiv) Matters pertaining to the maintenance management of nuclear facilities (excluding matters provided for in thefollowings);(xv) Matters pertaining to the periodic evaluation of nuclear facilities;(xvi) Matters pertaining to the quality assurance of nuclear facilities; and(xvii) Other necessary matters related to the safety preservation of the nuclear reactor facility.
2. The number of copies of the application under the preceding paragraph shall be one original.
(Inspection of compliance to the Operational Safety Program)
Article 16-2. Inspection based on the provision of Article 37, Paragraph 5 shall be implemented quarterly.
2. Matters provided in Article 37, Paragraph 5 apply mutatis mutandis to such as of Article 12, Paragraph 6 that is provided
by the order of Ministry of Economy, Trade and Industry are as follows:(i) Access to Office, the Factory or business place;(ii) Inspection of books, documents, facilities, components and other necessary items;(iii) Inquiry to employees and or related personnel; and(iv) Submission of nuclear source material, nuclear fuel material and the material contaminated by nuclear fuel material andother necessary sample (limited to the least necessary amount for testing).
(Assignment, Etc. of Chief Engineer of Reactors)
Article 19. Pursuant to the provisions of Article 40, Paragraph 1 of the Law, the appointment of a chief engineer ofreactors shall be made for each reactor. However, for reactors of the same type in the same plant or business place,the appointment of one chief engineer of reactors to two or more reactors is acceptable.
2. The number of copies of the notification document to be submitted under the provision of Article 40, Paragraph 2 of the
Law shall be one original.
(Measures in Emergency)
Article 20. Pursuant to the provisions of Article 64, Paragraph 1 of the Law, a reactor establisher shall take theemergency measures as provided in the following.
-- Provisional translation for information only --

A3-33

(i)

Wherein fire breaks out in the reactor facility, or wherein there is a possibility of fire reaching the reactor facility, tomake every effort to extinguish the said fire or to prevent its expansion and, at the same time, to report the situation to
the fire authorities.
(ii)
Wherein there is a possibility of transferring the nuclear fuel material to other locations, to transfer it to a safe location
as necessary, and to prohibit the entry of persons other than those related by demarcating the periphery of the location
with a rope, by installing signs, etc., and by stationing guards.
(iii) Wherein there is a need to prevent the occurrence of radiation hazard, to warn persons present both within the reactor
facility and its vicinity to evacuate.
(iv)
Wherein contamination by the nuclear fuel material has taken place, to prevent its expansion and to remove it
speedily.
(v)
Wherein there are persons suffering or who may possibly suffer from radiation hazard, to take emergency measures
such as their speedy rescue and evacuation.
(vi)
To take other necessary measures for the prevention of radiation hazards.
(Measures Accompanying Revocation of License)
Article 23. The reactor installer who has had their permission revoked in accordance with the provisions of Article
33 of the Law, the reactor establisher who has discontinued all the operation of the reactor, or in the case of
dissolution or death of reactor establisher the liquidator or trustee in bankruptcy, or the person who is to take chargeof the inheritance in the place of the inheritor of dead establisher in the case of the absence of succession pursuant to
the provision of Article 31, Paragraph 1, or Article 32, Paragraph 1 of the Law, shall assign the nuclear fuel material,
eliminate contamination, dispose the nuclear fuel material pursuant to the provisions of Article 66, Paragraph 1 of theLaw, and shall deliver the radiation management record as specified under Article 7, Paragraph 1 to the organization
specified by the Minister of Economy, Trade and Industry pursuant to Paragraph 4 of the said article.
2. The measures specified under the preceding paragraph shall be executed within 30 days from the day of the cancellation of
the permission, the day of discontinuing all operation, or the day of dissolution or death.
(Collection of Reports)
Article 24. The reactor installer shall prepare a report in Form 2 for each plant or business place, covering the period
as from April 1st of every year to March 31st of the subsequent year, in the case of the report on the dose equivalenton the radiation workers during one year, and the period as from April 1st of each year to September 30th, and asfrom October 1st to March 31st of the subsequent year, in the case of other reports, and shall submit them to the
Minister of Economy, Trade and Industry, within one month after the lapse of the applicable period.
2. The reactor installer shall, in the case of coming under any of the following subparagraphs, report the case immediately,
and report the situation and measures taken within 10 days:(i)
When nuclear fuel material is stolen or its whereabouts is unknown;(ii)
When a reactor is shut down by failure of a reactor facility or when it become necessary to shut down a reactor during
operation, or when reactor power output changes more than 5%, or when reactor power output change of more than 5%
is required. Except when it is one of the following and the establisher announced officially about the situation of theconcerned failure;
A. When it occurs in the term of the periodic inspection provided in Article 54-1 of the Electricity Utilities Industry
Law (Law No. 170, 1964) (limited to those equipment concerned to the failure, which functional and operationalsituation cannot be checked under the reactor shutdown condition),
B. When the failure does not cause deviation from the limit of operation (it is a requirement defined in thefitness-for-safety program for operation of the reactor facility, and when it cause any deviation from the concerned
conditions the measure that the establisher should take is also defined in the fitness-for-safety program, the samein this paragraph), and there is no change observed related with the concerned failure, and when the establisher
performs inspection of the failed equipment concerned, or
C. When the reactor output is required to follow the limit of operation.
(iii) When a reactor establisher has checked the equipment and structure important to the safety of the nuclear reactor
facility provided by the Minister of Economy, Trade and Industry (hereinafter called as "equipment etc. important tosafety" in this paragraph as), and when concerned equipment etc. important to safety is considered that it does notsatisfy the standard described in Article 9 or in Article 9-2 of the Ordinance of Establishing Technical Standards for
Nuclear Power Generation Equipment (Ordinance No. 62 of Ministry of International Trade and Industry, 1965), or
when it is considered that it does not have function to secure safety of the nuclear reactor facility;(iv)
When there is a failure of equipment etc. important to safety by the fire. Excluding the concerned failure is due to themeasure of fire extinguishing or prevention of the spread of fire;(v)
Except for the preceding three subparagraphs, when deviation from the limit of operation by the failure of a thenuclear reactor facility (except those minor troubles which impact on operation of nuclear reactor is insignificant) iscaused, or when the measure for the concerned deviation defined in the fitness-for-safety program is not implemented
at the time of deviation from the limit of operation;(vi)
When the failure of a reactor facility or occurrence of other unexpected situation is considered to have caused any
trouble in the situation of discharge of gaseous radioactive wastes through the ventilation facility or in the situation ofdischarge of liquid radioactive wastes through the drainage facility;(vii) When the concentration of radioactive materials in the air outside the environment monitoring area exceeds theallowable limit in the case of discharge of gaseous radioactive wastes through the ventilation facility;(viii) When the concentration of radioactive materials in the water outside the environment monitoring area exceeds theallowable limit in the case of the discharge of liquid radioactive wastes through the drainage facility;(ix)
When nuclear fuel materials or materials contaminated with nuclear fuel materials (hereinafter referred to as "nuclear
fuel materials etc.") leak out of the control zone;-- Provisional translation for information only --

A3-34

(x)

When nuclear fuel materials etc. leak within the control zone due to failure of a nuclear reactor facility or occurrenceof other unexpected situation. However, this is not the case in any of the followings (except the case when new
measures such as human entry restriction into the leakage-related place and key control have been taken or when theleaked substances have spread outside the control zone);
A. When revealed liquid nuclear fuel materials etc. do not spread out of the floodgate that is installed in thecircumference of the equipment of the concerned leakage for prevention of leakage enlargement,
B. When the function of ventilation facility of the concerned area of the leakage is maintained properly at the time
when gaseous nuclear fuel materials etc. leak, or
C. When the amount of radioactivity of the leaked nuclear fuel materials etc. is very little and when the degree of theleakage is minor.
(xi)
When the person who enters into the control zone suffered radiation exposure due to the failure of a nuclear reactor
facility or occurrence of other unexpected situation, and when the effective dosage of concerned exposure exceeds or
could exceeds five mSv for a personnel engaged in radiation work or 0.5 mSv for a person other than the personnel
engaged in radiation work;(xii) When the dosage of personnel engaged in radiation work exceeds or could exceed the allowable dose limit; or(xiii) Other than those above subparagraphs, when persons are injured or could be injured in the nuclear reactor facility(except for what hospitalization medical treatment is not needed for other than radiation hazard).
3. The number of copies for the application described in Paragraph 1 shall be one original.

(6) Notification for Radiation Dose Rate Limits, etc. Based on the Provisions of the Rules for Installation,
Operation, etc. of Commercial Power Reactors (Excerpt)(Notification No. 187 issued by the Ministry of Economy, Trade and Industry, March 21, 2001)(Dose as Specified Item 4 of Paragraph 2 of Article 1of Rules for Installation, Operation, etc. of Commercial Power Reactors)
Article 2. The dose, concentration, and density to be determined by the Minister of Economy, Trade and Industry, pursuant
to Article 1, Paragraph 2, Item 4 of the Rules for Installation, Operation, etc. of Commercial Nuclear Power Reactors(hereafter referred as "the Rules"), shall be as follows.
(i)
For dose, 1.3mSvs per 3 months.
(iii) For concentration, the average concentration in 3 months is one-tenth of the concentration limit determined in Article
7, Paragraph 1 through Paragraph 4.
(iv)
For density, one-tenth of the surface density limit determined in Article 5.
2. For the limit stipulated in the preceding paragraph, when both external radiation and radioactive materials must be
considered, the limit is given by converting the 3-month average dose and concentration to their fractions to the values
provided in Subparagraph 1 and Subparagraph 2 respectively. In this case, the dose and concentration shall be such that thesum of their fractions is less or equal to 1.
(Dose Limit provided in Article 1, Paragraph 2, Subparagraph 6 of the Rules)
Article 3. The dose limit to be determined by the Minister of Economy, Trade and Industry, pursuant to Article 1, Paragraph
2, Subparagraph 6 of the Rules, shall be as follows.
(i)
For effective dose equivalent, 1mSvs per year (one year start from April 1st).
(ii)
For skin and eye lens tissue dose equivalent, 50mSvs each per year.
(iii) For eye lens tissue dose, 15mSvs each per year
2. In spite of provision of the Subparagraph 1 of the preceding paragraph, effective dose limit may be determined as 5mSvs
when the Minister of Economy, Trade and Industry has so approved.
(Surface Density Limit)
Article 5. The surface density limits to be determined by the Minister of Economy, Trade and Industry, pursuant to Article 8,
Paragraph 1, Subparagraph C of the Rules, shall be as indicated in annexed Table 1.
(Dose Limit for Personnel Engaged in Radiation Works)
Article 6. For the dose limits to be determined by the Minister of Economy, Trade and Industry, pursuant to Article 9,
Paragraph 1, Subparagraph 1 of the Rules, the effective dose shall be as follows.
(i)
Five years determined in Article 4, Paragraph 3, 500mSvs.
(ii)
50mSvs per year.
(iii) For female (except for those who diagnosed as sterility and those who notified will for no pregnancy to the reactor
establisher with document and those who are specified in next Paragraph), 5mSvs per three-month starting April 1, July
1, October 1and January 1, except for determined in two preceding subparagraphs(iv) For the pregnant female, 1mSvs for internal exposure during the time of the reactor establisher noticed the pregnancy
by the notification of the worker herself to the delivery, in addition to the provision of Subparagraph 1 andSubparagraph 2.
2. For the dose limits to be determined by the Minister of Economy, Trade and Industry, pursuant to Article 9, Paragraph 1,
Subparagraph 1 of the Rules, the effective dose equivalent shall be as follows.
(i)
For eye lens, 150mSvs per year.
(iv) For skins, 500mSvs per year.
For abdominal region of pregnant female worker specified in Subparagraph (iv) of the preceding Paragraph, 2mSvs(v)
during the time in the preceding Paragraph.
(Concentration Limit for Personnel Engaged in Radiation Works)
Article 7. For the concentration limits to be determined by the Minister of Economy, Trade and Industry, pursuant to Article
9, Paragraph 1, Subparagraph (ii) of the Rules, the average concentration for three-month shall be as follows.
-- Provisional translation for information only --

A3-35

(i)

When the type of radioactive materials (Shown in annex Table 2. The same applies in next and the third Paragraphs)
is known, and that is only one type, the concentration given in the fourth column of annexed Table 2, for the type ofradioactive materials listed in the first column of that table.
(ii)
When the type of radioactive materials is known, and there are more than two types, the concentration whose sum of
the ratios of the concentration of each radioactive material to the concentration of radioactive material given in thepreceding paragraph become unity is the concentration of each radioactive material.
(iii) When the type of radioactive material is not known, the least concentration given in the fourth column of annexed
Table 2 (except those type of radioactive materials whose non existence in air is clear.).
(iv)
When the type of radioactive material is known, and the type of the radioactive material is not included in annexed
Table 2, the concentration of the second column in accordance with the division shown in the first column of theannexed Table 3.
(v)
When there are risks of both external radiation exposure and inhalation of airborne radioactivity, the concentration ofradioactive materials shall be such that the sum of its fraction of the effective dose equivalent for a year by exposure
from external radiation (hereinafter referred to as “external exposure”) to 50mSvs, and the fraction of airborne
radioactive materials concentration to that provided in the preceding paragraphs, is less or equal to 1.
(Dose Equivalent Limit in Emergency Work)
Article 8. Dose limits to be determined by the Minister of Economy, Trade and Industry, pursuant to Article 9, Paragraph 2of the Rules, is 100mSvs in effective dose equivalent.
(Concentration Limit at Outside of Environmental Monitoring Area)
Article 9. The concentration limit to be determined by the Minister of Economy, Trade and Industry, pursuant to Article 15,
Paragraph 4 and Paragraph 7 of the Rules, shall be as follows in average of three-month:(i)
When the type of radioactive materials (that given in annexed Table 2, the same applying in the following paragraphs
and the third paragraphs and next Item paragraph 1 to 3) is known and that is only one type, concentration in air givenin the column 5 of annexed Table 2, and that in water given in the column 6, for respective type of radioactivity;(ii)
When the types of radioactive materials are known and there are more than 2 different types of radioactive materials
in water or in air, the concentrations of radioactive materials shall be such that the sum of their fractions to therespective concentrations provided in the preceding paragraphs, is less or equal to 1;(iii) When the type of radioactive materials is unknown, the minimum concentration given in the column 5 of annexed
Table 2 (except those type of radioactive materials whose non existence in air is clear.) for air and in the column 6 forwater, respectively;(iv)
When the type of radioactive material is known, and the type of the radioactive material is not included in annexed
Table 2, the concentration of the third column for in air and the fourth column for in water, in accordance with thedivision shown in the first column of the annexed Table 3;(v)
When radioactive materials exist in water and in air and there are risks of both inhalation and oral intake,concentrations of radioactive materials in water and in air shall be such that the sum of their fractions to the respective
concentrations provided in the 1st, 3rd and precedent paragraphs, is less or equal to 1; and(vi)
When there are risks of both external radiation exposure and inhalation of radioactive materials in air or in water, theconcentration of radioactive materials shall be such that the sum of its fraction of the effective dose equivalent for ayear by external exposure to 1mSv, and the fraction of concentration for radioactive materials in air or in water to thatprovided in the preceding paragraphs, is less or equal to 1.
3. The provision of the preceding Paragraph 2 shall not be applied, if the Minister of Economy, Trade and Industry approvedin accordance with Article 3, Paragraph 2.
Annexed Table 1 (in relation to Article 5)
Division

Limit on Density (Bq/cm2)

Radioactive material that emits alpha particles

4

Radioactive material that does not emit alpha particles

40

3.6. Law for Technical Standards of Radiation Hazards Prevention (Excerpt)(Law No.162, May 21, 1958)
Latest Revision: Law No.160, December 22, 1999
(Objectives)
Article 1. The objectives of this law are to clarify the basic policy of enacting technical standards for radiation hazards
prevention and to arrange technical standards of radiation hazards prevention in an orderly manner through the establishmentof the Radiation Review Council within Ministry of Education, Culture, Sports, Science and Technology.
(Basic Policy)
Article 3. In enacting technical standards of radiation hazards prevention, the basic policy shall be to keep the radiation doseof personnel engaged in radiation management work to handle materials which generate radiation, etc. and of general public,at the radiation dose equal or less than what causes no danger of hazards.
(Establishment of Radiation Review Council)
Article 4. The Radiation Review Council (hereinafter referred to as the "Council") shall be established within Ministry of
Education, Culture, Sports, Science and Technology.
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(Assigned Duties of the Council)
Article 5. The Council shall investigate and review the matters prescribed in this law.
2. Concerning the matters of the preceding paragraph, the Council may state its opinions to the heads of related governmentalorganizations as necessary.
(Consults to the Council)
Article 6. When heads of related governmental organizations intend to establish technical standards of radiation hazards
prevention, they shall consult with the Council.

3.7. Law on Compensation for Nuclear Damage (Excerpt)(Law No.147, June 17, 1961)
Latest Revision: Law No. 54, May 30, 2003
(Objectives)
Article 1. It is the objectives of this Law to protect persons suffered from nuclear damage and also to contribute to the sounddevelopment of nuclear industry by means of establishing the basic system concerning the compensation in the case ofoccurrence of nuclear damage through operation of reactors, etc.
(Liability without Fault, Channeling of Liability, Etc.)
Article 3. When a nuclear damage is occurred owing to the operation of the reactor, etc. during the operation of the reactor,
etc. a nuclear business operator who is engaged in the operation of the reactor on the occasion, shall be liable for the damage,except for the case that the damage is caused by a extraordinary great natural disaster or by a serious social disturbance.
(Duty of Providing Financial Security)
Article 6 A nuclear business operator is prohibited from the operation of the reactor, etc. unless the financial security forcompensation of the nuclear damage (hereinafter referred to as "financial security") has been provided.
(The Content of the Damage Compensation Measure)
Article 7. The damage compensation measure shall be, except when the following article is applied, contract of liability
insurance for nuclear damage or conclusion or deposit of the indemnity agreement for compensation of nuclear damage, 60
billion yen per one factory or one business place by the measure (for operation of the nuclear reactor, etc. defined by thegovernment ordinance, the amount of money shall be as defined in the government ordinance not exceeding 60 billion yen.
Hereinafter referred to as "insured amount" below.), as the amount payable for compensation for nuclear damage thatobtained the approval of the Minister of Education, Culture, Sports, Science and Technology, or equivalent by the measurethat obtained the approval of the Minister of Education, Culture, Sports, Science and Technology.
2. When the Minister of Education, Culture, Sports, Science and Technology admits that it is necessity to ensure
implementation of the compensation for nuclear damage, in the case where the amount of money which should beappropriated for compensation for nuclear damage is under the insured amount as the concerned nuclear business operator
has compensated the nuclear damage in accordance with the provisions of Article 3, the said minister may order the nuclear
business operator concerned to make that amount equivalent to the insured amount with specified due date.
3. In the case provided in the preceding paragraph, the provision mentioned in the preceding article shall not be applied until
the order in accordance with the provision of the same paragraph is given (when the order in accordance with the provision of
the same paragraph is given, up to the due date specified by the order concerned).
(Contract of Liability Insurance for Nuclear Damage)
Article 8. The contract of liability insurance for the nuclear damage (hereinafter referred to as "liability insurance contract")shall be the contract under which an insurer (a liability insurance company provided in Article 2, Paragraph 4 of the
Insurance Business Law (Law No.105, 1995) or a foreign liability insurance company, etc. provided in Article 2, Paragraph 9of the same Law, that undertakes liability insurance; hereinafter an insurer is limited to this meaning) undertakes toindemnify a nuclear business operator for his loss arising from compensation for the nuclear damage of certain causes in casethe nuclear business operator becomes liable for the compensation of a nuclear damage and under which the insurant
undertakes to pay a premium to the insurer.
(Indemnity Agreement for Compensation of Nuclear Damage)
Article 10. The indemnity agreement for compensation of the nuclear damage (hereinafter referred to as "indemnity
agreement") shall be the contract under which the National Government undertakes to indemnify a nuclear business
operator for his loss arising from compensating for the nuclear damage not covered by the liability insurance contract
and other financial security for compensation for the nuclear damage in case the nuclear business operator becomes
liable for the compensation of a nuclear damage and under which the nuclear business operator undertakes to pay theindemnity fee to the National Government.
(Measures Taken by the National Government)
Article 16. In case the nuclear damage occurs, the National Government shall give to a nuclear business operator
undertaker (except nuclear business operator related to foreign nuclear ship) such aids as required for him tocompensate the nuclear damage, when the amount which he should compensate for the nuclear damage in accordancewith Article 3 exceeds the financial security amount concerned and when the National Government deems necessary
in order to fulfill the objectives of this Law.

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3.8. Industrial Safety and Health Law(1) Industrial Safety and Health Law (Excerpt)(Law No.57, June 8, 1972)
Latest Revision: Law No. 102, July 2, 2003
(Objectives)
Article 1. The objectives of this Law is to secure, in conjunction with the Labor Standards Law (Law No. 49, 1947), thesafety and health of workers in workplaces as well as to facilitate the establishment of comfortable working environment bypromoting comprehensive, and systematic countermeasures concerning the prevention of industrial accidents, such as taking
measures for the establishment of standards for the prevention of danger and injury, the classification of responsibility, andthe promotion of voluntary activities with a view to preventing industrial accidents.
Article 22. Employers shall take necessary measures for preventing health impairment as follows:(iii) Health impairment due to radiation, high temperature, low temperature, ultrasonic waves, noises, vibration, or abnormal
atmospheric pressure and others.
(Safety and Health Education)
Article 59. Employers shall, when they have employed new workers, give the said workers' education for the safety
and/or health concerning works in which they are engaged, as specified in the ordinance of the Ministry of Healthand Labor.
(Medical Checks)
Article 66. Employers shall, as specified in the ordinance of the Ministry of Health and Labor, execute medical
checks of workers conducted by physicians.
(2) Rules for Prevention of Damage from Ionizing Radiation (Excerpt)(Ordinance No. 41of the Ministry of Labor, September 30, 1972)
Latest Revision: Ordinance No. 175 of the Ministry of Health and Labor, December 12, 2003
(Basic Principle of Prevention of Radiation Hazards)
Article 1. Employers shall endeavor to minimize the exposure of workers to the ionizing radiation as far as possible.
(Illustration of a Control Zones, etc.)
Article 3. Employers performing radiation management work shall express clearly by marks the area defined as follows(hereinafter referred to as "control zones"):(i)Area where three months total of the effective dose from the external radiation and the effective dose from theradioactive materials in the air may exceed 1.3mSvs; or(ii)
Area where surface contamination may exceed the limits defined by the attached table.
2. The effective dose from the external radiation in Subparagraph (i) of the preceding paragraph shall be measured as to the
1 cm dose equivalent.
3. The effective dose from the radioactive materials in air in Paragraph 1, Subparagraph (i) shall be determined bymultiplying 1.3mSvs by the ratio of a tenth of the limit of the three months average concentration of the weekly average ofradioactive materials in air during the working hours in a week (where the working hours in a week exceeds 48 hours or lessthan 48 hours, use instead the figure obtained by multiplying the average concentration of the radioactive materials in air
during the working hours in a week by the result of dividing the working hours by 48 hours; in Article 25 this is referred to as
the "weekly average concentration") provided for by the Minister of Health and Labor.
4. Employers shall not allow anyone other than the necessary persons to enter control zones.
5. Employers shall post, in a location easily seen by workers in the control zones, notices for attention related to theattachment of measuring devices of exposure dose provided for in Article 8, Paragraph 3, notices for attention concerning thehandling of radioactive materials and other necessary notices for prevention of damages to health of workers due to radiation,such as emergency measures in case of an accident.
(Limits of Exposure for Personnel Engaged in Radiation Management Works)
Article 4. Employers shall ensure that the effective dose of personnel engaged in radiation management works in control
zones (hereinafter referred to as "personnel engaged in radiation management works") does not exceed 50mSvs annually, and
100mSvs in 5 years.
2. Regardless of the provision of the preceding paragraph, employers shall ensure that the effective dose of female
personnel engaged in radiation management works (excluding those who are infertile and those defined in Article 6) does notexceed 5mSvs in 3 months.
Article 5. Employers shall ensure that the equivalent dose of personnel engaged in radiation management works does notexceed 150mSvs annually for the eye lens, and 500mSvs annually for skin.
Article 6. Employers shall ensure that the effective dose from internal radiation, and equivalent dose in the abdominal regionof female personnel engaged in radiation management works who have been diagnosed as pregnant does not exceed 1, and2mSvs, respectively, from the time that pregnancy is diagnosed until birth.
(Limits of Exposure During Emergency Work)
Article 7. In the case of the accident which falls under any one of the subparagraphs in Article 42, Paragraph 1, and in whicha zone provided for in that paragraph has occurred, when the employer performs emergency work to prevent damages tohealth of workers due to radiation (hereinafter referred to as "emergency work"), regardless of the provisions of Article 4,
Paragraph 1 and Article 5, male and infertile female personnel engaged in radiation management works who perform such
emergency work may be exposed the dose in excess of the limits provided for in that article.
2. In the preceding paragraph, the effective dose, the equivalent dose for eye lens and the equivalent dose for skin, which
they expose during such emergency work shall not exceed 100, 300 and 1000mSvs, respectively.
-- Provisional translation for information only --A3-38

3. The preceding paragraph shall also apply when emergency work is performed by a male or infertile female workers otherthan personnel engaged in radiation management works.
3. 9. Electricity Utilities Industry Law(1) Electricity Utilities Industry Law (Excerpt)(Law No. 170, July 11, 1964)(Latest Revision: Law No. 92, June 18, 2003)(Objectives)
Article 1. The objectives of this Law are to protect the benefits of consumers of electricity and to contrive to promote thesound development of electric utilities industry, by ensuring the proper and reasonable operation of electric utilities industry
and to secure public safety and protect environment by regulating construction, maintenance and operation of electric
structures.
(Business Licensing)
Article 3. Any person (excluding specific-scale electric utility) who intends to carry on an electric utility shall obtain licensefrom the Minister of Economy Trade and Industry.
2. The License in the preceding paragraph shall be granted according to the category of a general electric utility, a wholesale
electric utility, and a specific electric utility.
(License Application)
Article 4. Any person who intends to obtain the license referred to in Paragraph 1 of the preceding article shall submit anapplication containing the information listed below to the Minister of Economy Trade and Industry.
(i)Name and address, or name and address of representative in the case of a corporation(ii)
Service area, a general electric utility to which electricity will be supplied, or supply location.
(iii) Following information on electric structures to be used for the applied electric utility:(a) Location of installations, type of motive power, frequency and output for electric power generation business;(b) Location of installations, frequency and output for electric power transformation business;(c) Location of installations, electricity mode, method of establishment, number of lines, frequency and voltage forelectric power transmission business; and(d) Electricity mode, frequency and voltage for electric power distribution business.
2. The application in the preceding paragraph must contain the business plan, statement of estimated business income andexpenditures, and other documents required by the ordinance of Ministry of Economy Trade and Industry.
(Criteria for Licensing)
Article 5. The license referred to in Paragraph 1 of Article 3 shall not be granted unless the Minister of Economy Trade andIndustry recognizes that the application for the license meets the following conditions:(i)
The commencement of the applied electric utility meets properly general electricity demand, demand of generalelectric utilities industry or demand at the service location;(ii)
There exists a sufficient financial basis and sufficient technical ability for the proper operation of the applied electricutility;(iii) The plan of the applied electric utility is sound;(iv)
The capacity of the electric structures to be used for the applied electric utility corresponds to the electricity demandin the service area or the service location in case that the applied electric utility is a general electric utility or a specificelectric utility;(v)
The commencement of the applied electric utility is not supposed to cause remarkable excess in electric structures forthe used of general electric utilities industry in all or part of the service area in case that the applied electric utility is a
general electric utility;(vi)
The commencement of the applied electric utility is not supposed to be in danger of obstructing the interests of usersof electricity within the service area of a general electric utilities industry in case that an application is for a specificelectric utility with a service location where is within the service area of that general electric utilities industry; and(vii) In addition to the conditions listed above, in case that an application is for a general electric utility or wholesale
electric utility, the commencement of the applied electric utility is necessary and appropriate for the promotion ofcomprehensive and reasonable development of electric utilities industry and for the public interest, and in case that an
application is for a specific electric utility, the commencement of the applied electric utility is appropriate in the lightof the public interest.
(License)
Article 6.
2. The license shall contain the following information:(i)
Date and number of the permission;(ii)
Name and address;(iii) Supply area, general electric utilities to which electricity will be supplied, or supply location.
(iv)
Following information on electric structures to be used for electric utility; and(a) Location of installations, type of motive power, frequency and output for electric power generation business.
(Obligations at Beginning the Business)
Article 7. An electric utility (excluding specific-scale electric utility) shall begin the licensed business within the time, notmore than ten years from the date when the permission is granted, designated by the Minister of Economy Trade andIndustry.
2. The Minister of Economy Trade and Industry, when it is deemed particularly necessary, may specify the time inaccordance with the preceding paragraph, classifying service area, a general electric utility to which electricity will be-- Provisional translation for information only --A3-39

supplied, or supply location.
3. The Minister of Economy Trade and Industry may, if deemed that there exist due reasons, extend the time designated in
Paragraph 1 in case that such extension is applied from an electric utility.
4. An electric utility shall notify the Minister of Economy Trade and Industry without delay when it begins the business.
(Alterations in Electric Structures, etc.)
Article 9. When an electric utility intends to alter the items referred to in Article 6, Paragraph 2, Subparagraph (iv), this shallbe notified to the Minister of Economy Trade and Industry, unless the alteration is so minor as specified in the ordinance ofMinistry of Economy Trade and Industry.
(Revocation of Licensing, etc.)
Article 15. The Minister of Economy Trade and Industry may revoke the license issued in accordance with Article 3,
Paragraph 1, when an electric utility does not begin the licensed business within the time specified in Article 7, Paragraph 1(or within the extended period specified in Paragraph 3 of the said article, the same, hereinafter).
2. Except as provided in preceding paragraph, the Minister of Economy Trade and Industry may revoke the license issued inaccordance with Article 3, Paragraph 1, when an electric utility has violated the provisions of this Law or an order based on
this Law and the violation is deemed to threaten the public interest.
(Duty of Electricity Supply, etc.)
Article 18. A general electric utility shall not refuse to supply electricity to correspond general electric demand within its
supply area (excluding demand at the supply locations where a specific electric utility has begun its business based on thelicense in accordance with Article 3, Paragraph 1 (hereinafter referred to as "area of business commencement") andspecific-scale electric demand).
(Supply Stipulations, etc. by General Electric Utility)
Article 19. A general electric utility shall set supply stipulations concerning power rates or other conditions for supply ofelectricity to correspond general electric demand (excluding specific-scale demand), and shall obtain the approval of the
Minister of Economy Trade and Industry in accordance with the ordinance of Ministry of Economy Trade and Industry. The
same is applied to modifications of the stipulations.
2. The Minister of Economy Trade and Industry shall approve the supply stipulations referred to in the preceding paragraphwhen it recognizes that the application for the approval meets the following conditions:(i)
The rates correspond to an appropriate rate of profit added to an appropriate cost under efficient management;(ii)
The rates are set clearly as a fixed rate or fixed amount according to the type of supply;(iii) Appropriate and clear determination has been made of matters related to the responsibilities of the general electricutility and the users of electricity, and of methods for allocating expenses related to electrical instruments, otherequipment, wiring work, and other construction work; and(iv)
There exists no unjust, discriminatory treatment of specific parties.
3. Notwithstanding latter part of Paragraph 1 of this article, a general electric utility may changes the power rates or otherconditions for supply of electricity defined in the supply stipulations (when the alteration has been notified in accordancewith the following paragraph, the modified supply stipulations, the same in this article) approved in accordance with
Paragraph 1 of this article, if the change meets the case described in the ordinance of Ministry of Economy Trade andIndustry; such that the change is reduction of the power rates or the change is not deemed to threaten the public interest..
4. A general electric utility shall notify the modified supply stipulations to the Minister of Economy Trade and Industry, as
specified in the ordinance of Ministry of Economy Trade and Industry, when it changes the power rates and other conditionsin accordance with the preceding paragraph
5. In the case that the Minister of Economy Trade and Industry deems that the modified supply stipulations submitted inaccordance with the preceding paragraph do not meet any of the following subparagraphs, he may order the general electricutility to reconsider the supply stipulations indicating a suitable deadline:(i)
The rates are set clearly as a fixed rate or fixed amount according to the type of supply;(ii)
Appropriate and clear determination has been made of matters related to the responsibilities of the general electricutility and the users of electricity, and of methods for allocating expenses related to electrical instruments, otherequipment, wiring work, and other construction work; and(iii) There exists no unjust, discriminatory treatment of specific parties.
6. Concerning to the rates of power and other supply conditions to apply the rates, a general electric utility may set the
stipulations established in the supply conditions which is different from those established by the supply stipulations received
the approval of Paragraph 1, so that the users of electricity may chose it replaces with the supply stipulations, when it isexpected that it contributes to efficient use of the equipment which is used for general electric utility and/or other efficiententerprise management of the concerned general electric utility.
7. When the general electric utility set the stipulations in accordance with the preceding paragraph, the stipulations(hereinafter referred to as "option stipulations") shall be notified to the Minister of Economy Trade and Industry inaccordance with the ordinance of Ministry of Economy Trade and Industry. The same shall be applied when the option
stipulations are altered.
8. In the case that the Minister of Economy Trade and Industry deems that the option stipulations submitted in accordancewith the preceding paragraph do not meet any of the following subparagraphs, he may order the general electric utility toreconsider the option stipulations indicating a suitable deadline:(i)
It contributes to the efficient use of the equipment, which is used for general electric utility, and/or other efficiententerprise management of the concerned general electric utility;(ii)
It is not deemed to threaten the profits of those who receive electric supply in the supply stipulations approved inaccordance with Paragraph 1 of this article;(iii) The rates are set clearly as fixed rate or fixed amount; or(iv)
There exists no unjust, discriminatory treatment of specific parties.
-- Provisional translation for information only --A3-40

(Depreciation, etc.)
Article 35. The Minister of Economy Trade and Industry may order a electric utility to establish and implement a method orfixed amount on suitable depreciation for fixed assets used for its electric utility (excluding specific-scale electric utility) or
to build up reserve funds or allocations in a specified method or amount, when deemed particularly necessary for the proper
management of an electric utility (excluding specific-scale electric utility),(Maintenance of Electric Structure for Business Use)
Article 39. A person who established electric structure for business use shall maintain it so that it is to be in conformity withthe technical standards specified in the ordinance of Ministry of Economy Trade and Industry.
2. The ordinance of the Minister of Economy Trade and Industry referred to in the preceding paragraph shall be based on thefollowings:(i)
To prevent electric structure for business use from causing harm to persons or to objects;(ii)
To prevent the electric structure for business use from causing electrical or magnetic interference on the function ofother electric equipment or other objects;(iii) To prevent damage of the electric structure for business use from causing remarkable interference to the supply ofelectricity by an electric utility; and(iv)
To prevent damage of the electric structure for business use from causing remarkable interference to the supply ofelectricity by a general electric utility, in case that these electric structures for business use are used for a generalelectric utility.
(Orders for Conformity with Technical Standards)
Article 40. The Minister of Economy Trade and Industry may order the person who established electric structure for business
use to repair, alter, or move the structure so that it conforms with the technical standards specified in the ordinance of the
Minister of Economy Trade and Industry described in Paragraph 1 of the preceding article, or to halt temporarily its use, orplace restrictions on the use of it, when deemed that the electrical structure for business use is not in conformity with thetechnical standards.
(Fitness-for-Safety Program)
Article 42. A person who established an electric structure for business use shall establish an fitness-for-safety program foreach responsible organization on the electric structure for business use, needed to be preserved as a unitarily, required by theordinance of Ministry of Economy Trade and Industry to ensure fitness for safety of the construction, maintenance andoperation of the electric structure for business use, and shall notify it to the Minister of Economy Trade and Industry prior to
beginning usage (or construction work if it is accompanied with licensee's welding inspection specified in Article 52,
Paragraph 1) of the electric structure for business use by the concerned organization.
2. A person who established an electric structure for business use shall notify the Minister of Economy Trade and Industry
without delay when he has altered his fitness-for-safety program.
3. The Minister of Economy Trade and Industry may order a person who established the electric structure for business use to
make changes its fitness-for-safety program, when deemed necessary to ensure fitness for safety of construction, maintenance,and operation of a concerned electric structure for business use.
4. A person who established an electric structure for business use and his employee shall comply with the fitness-for-safety
program.
(Chief Engineers)
Article 43. A person who established an electric structure for business use shall assign a person who had received license ofchief engineer as a chief engineer in order to supervise ensuring fitness for safety of construction, maintenance and operationof electric structure for business use, as specified in the ordinance of the Minister of Economy Trade and Industry.
3. A person who established an electric structure for business use shall notify a fact to the Minister of Economy Trade andIndustry without delay when he assigned a chief engineer (excluding the appointment with the permission referred to in thepreceding paragraph). The same is applied when the chief engineer is dismissed.
4. The chief engineer shall perform faithfully his duty on supervision of ensuring fitness for safety concerning construction,
maintenance and operation of electric structure for business use.
5. A person who engaged in construction, maintenance and operation of an electric structure for business use shall follow thechief engineer's instructions for fitness for safety.
(Chief Engineer's License)
Article 44. Types of chief engineer’s license for are as follows.
(i)Class I Chief Electrical Engineer’s License(ii)
Class II Chief Electrical Engineer’s License(iii) Class III Chief Electrical Engineer’s License.
(iv)
Class I Chief Boiler and Turbine Engineer’s License(v)
Class II Chief Boiler and Turbine Engineer’s License
2. The Minister of Economy Trade and Industry grant the Licenses License of Chief Engineer to those persons who meet anyof the followings:(i)Persons with an academic career or qualifications who have practical experience provided for in the ordinance of the
Minister of Economy Trade and Industry for each type of chief engineer’s licenses; and(ii)
Persons who have passed the qualification test for chief electrical engineer in case of a chief engineer’s license of
Subparagraph (i) through Subparagraph (iii) of the preceding paragraph.
3. The Minister of Economy Trade and Industry may refrain from issuing a chief engineer’s license to a person to whom anyof the following applies:(i)
A person who was ordered to return his chief engineer’s license, according to the following paragraph, within one
year after issuing the order; or(ii) A person who was ordered to pay a fine or undergo more severe punishment due to the violation of the provisions of-- Provisional translation for information only --A3-41

this Law or orders based on this Law, within two years after the punishment was completed or ended.
4. The Minister of Economy Trade and Industry may order the return of the chief engineer’s license if a person who hasreceived a chief engineer’s license has violated the provisions of this Law or orders based on this Law,.
5. The scope of construction, maintenance and operation of electric structure for business use which a person who hasreceived a chief engineer’s license may supervise on fitness for safety and procedural matters related to the issuance of chiefengineer’s licenses shall be provided in the ordinance of the Minister of Economy Trade and Industry.
(Qualification test for Chief Electrical Engineers)
Article 45. The qualification test for chief electrical engineers shall be conducted by the Minister of Economy Trade andIndustry for each type of chief engineer’s licenses, concerning knowledge and skills necessary for fitness for safety of
construction, maintenance and operation of an electric structure for business use.
2. The Minister of Economy Trade and Industry may entrust a designated party (hereinafter referred to as "designatedorganization for qualification test") to conduct the duties on execution of the qualification test for chief electrical engineers.
3. Details of the execution of qualification test for chief electrical engineers, including test subjects and test-taking
procedures, shall be provided in the ordinance of the Minister of Economy Trade and Industry.
(Environmental Impact Assessment concerning Electric Structure for Business Use)
Article 46-2. Environmental impact assessment and its procedures specified in Article 2, Paragraph 1 of the Environmental
Impact Assessment Law (Law No. 81 of 1997), with respect to construction work to establish or alter electric structure forbusiness use of the Class-1 Project specified in Article 2, Paragraph 2 or the Class-2 Project specified in Article 2, Paragraph
3 of the said law, are provided for in the said law and the concerned stipulations in this Law.
(Environmental Impact Assessment by Simplified Method)
Article 46-3. Any person who intends to perform construction work to establish or alter electric structure for business use of
the Class-2 Project specified in Article 2, Paragraph 3 of the Environmental Impact Assessment Law shall describe the resultof the environmental impact assessment for the construction work that has been performed by simplified method pursuant to
the ordinance of Ministry of Economy Trade and Industry, on a written report specified in the first half of Article 4,
Paragraph 1 of the said law, as well as the items specified in the same paragraph of the said law.
(Preparation of Planning Document)
Article 46-4. Any person (hereinafter referred to as a "specific business operator") who intends to perform construction work
which establishes or alters electric structure for business use and conforms to the project (hereinafter referred to as a "specificproject") specified in Paragraph 4 of Article 2 of the Environmental Impact Assessment Law shall describe items to beconsidered in an environmental impact assessment of the specific project and the methods of survey, prediction andassessment, irrespective of the provision of the fourth subparagraph of the same paragraph, in a planning document onenvironmental impact assessment (hereinafter referred to as a "planning document") specified in Paragraph 1 of Article 5 ofthe said law.
(Submittal of Planning Document)
Article 46-5. A specific business operator shall submit the planning document to the Minister of Economy Trade andIndustry at the same time when it is submitted pursuant to Paragraph 1 of Article 6 of the Environmental Impact Assessment
Law.
(Submittal of an Outline of Comments Regarding the Planning Document)
Article 46-6. A specific business operator shall describe his view for the comments, presented pursuant to Paragraph 1 of
Article 8 of the Environmental Impact Assessment Law, in the document specified in Article 9 of the said law, in addition to
the items specified in the same article.
2. A specific business operator shall submit the document pursuant to Article 9 of the Environmental Impact Assessment Law
to the Minister of Economy Trade and Industry at the same time when he submits the document pursuant to the same article.
(Comments of Governor of Prefectures regarding Planning Document)
Article 46-7. Comments of the governor of prefecture(s) pursuant to Paragraph 1 of Article 10 of the Environmental Impact
Assessment Law on the specific project shall be presented to the Minister of Economy Trade and Industry as a substitute forthe business operator, irrespective of the provision of the same paragraph.
2. In making the comments on specific project, pursuant to Paragraph 1 of Article 10 of the Environmental Impact
Assessment Law, the governor of prefecture(s) shall take into consideration the view of the business operator described in the
documents, specified in Article 9 of the said law, pursuant to Paragraph 1 of the preceding article as well as the provision of
Paragraph 3 of Article 10 of the said law.
(Recommendation on Planning Document)
Article 46-8. In case that planning document is submitted pursuant to Article 46-5, the Minister of Economy Trade andIndustry reviews scooping document, considering the comments of the governor of prefecture(s) made pursuant to Paragraph
1 of Article 10 of the Environmental Impact Assessment Law and paying due consideration to an outline of the comments
made pursuant to Paragraph 1 of Article 8 of the said law and the view of the business operator on the outline of comments,
submitted pursuant to Paragraph 2 of Article 46-6. The Minister may issue necessary recommendation to the specificbusiness operator on the items to be considered in an environmental impact assessment of the specific project and themethods of survey, prediction and assessment, within a time to be established by the ordinance of Ministry of Economy
Trade and Industry from the date when the document was submitted pursuant to Article 46-5, when deemed it to be thenecessary to assure proper measures to protect the environment.
2. The Minister of Economy Trade and Industry shall notify the purport to the specific business operator without delay when
he admits it unnecessary to issue the recommendation pursuant to the provisions of the preceding paragraph.
3. The Minister of Economy Trade and Industry shall provide a copy of the written report submitted pursuant to Paragraph 1
of Article 10 of the Environmental Impact Assessment Law to the specific business operator at the same time when he issues
recommendation pursuant to Paragraph 1 or notifies pursuant to Paragraph 2 of this article.
(Selection of Items to be Considered in Environmental Impact Assessment)-- Provisional translation for information only --A3-42

Article 46-9. A specific business operator, upon receiving the recommendation pursuant to Paragraph 1 of the precedingarticle, shall conduct further study, based on the recommendation, considering the comments made pursuant to Paragraph 1
of Article 10 of the Environmental Impact Assessment Law and paying due consideration to the comments made pursuant to
Article 8, Paragraph 1 of the said law, in the review pursuant to Article 11, Paragraph 1 of the said law.
(Preparation of Draft Environmental Assessment Statement)
Article 46-10. A specific business operator shall describe contents of the recommendation issued pursuant to Paragraph 1 of
Article 46-8, as well as the items specified in each subparagraph of Article 14, Paragraph 1 of the Environmental Impact
Assessment Law, in the draft of Environmental Assessment Statement (hereinafter referred to as a “draft EIS”) defined in thesame paragraph of the said law.
(Submittal of Draft EIS)
Article 46-11. A specific business operator, when submitting a draft EIS and its summary pursuant to the provisions ofArticle 15 of the Environmental Impact Assessment Law, shall submit them to the Minister of Economy Trade and Industry
at the same time.
(Submittal of Outline of Comments Regarding Draft EIS)
Article 46-12. A specific business operator, when submitting the document pursuant to Article 19 of the Environmental
Impact Assessment Law, shall submit it to the Minister of Economy Trade and Industry at the same time.
(Opinions of Related Governor(s) Regarding Draft EIS)
Article 46-13. Opinions of the related governors of prefectures pursuant to Article 20, Paragraph 1 of the Environmental
Impact Assessment Law on the specific project shall be presented to the Minister of Economy Trade and Industry as a
substitute for the business operator, irrespective of the provision of the same paragraph.
(Recommendation on Draft EIS)
Article 46-14. In case that draft EIS is submitted pursuant to Article 46-11, the Minister of Economy Trade and Industry
reviews draft EIS, considering the comments of the related governors of prefectures made pursuant to Article 20, Paragraph 1of the Environmental Impact Assessment Law and paying due consideration to an outline of the comments made pursuant to
Article 18, Paragraph 1 of the said law and the view of a business operator on the outline of comments, submitted pursuant to
Article 46-12. The Minister may issue necessary recommendation to the specific business operator on the environmental
impact assessment of the specific project, within a time to be established by the ordinance of Ministry of Economy Trade andIndustry from the date when the document was submitted pursuant to Article 46-12, when deemed it to be the necessary toassure proper measures to protect the environment.
2. The Minister of Economy Trade and Industry shall obtain an opinion from a viewpoint of protecting an environment fromThe Minister of Environment at the review conducted pursuant to preceding paragraph.
3. The Minister of Economy Trade and Industry shall notify the purport to a specific business operator without delay when headmits it unnecessary to issue the recommendation pursuant to Paragraph 1 of this article.
4. The Minister of Economy Trade and Industry shall provide a copy of the submittal pursuant to Article 20, Paragraph 1 of
the Environmental Impact Assessment Law to a specific business operator at the same time when he issues recommendation
pursuant to Paragraph 1 or notifies pursuant to Paragraph 2 of this article.
(Preparation of Environmental Impact Statement)
Article 46-15. A specific business operator, upon receiving the recommendation pursuant to Paragraph 1 of preceding article,
shall conduct further study, based on the recommendation, considering the comments made pursuant to Article 20, Paragraph
1 of the Environmental Impact Assessment Law and paying due consideration to the comments made pursuant to Article 18,
Paragraph of the said law, in the review pursuant to Article 21, Paragraph 1 of the said law.
2. A specific business operator shall describe contents of the recommendation issued pursuant to Article 46-8, Paragraph 1
and Paragraph 1 of the preceding article, as well as the items specified in each paragraph of to Article 21, Paragraph 1 of theEnvironmental Impact Assessment Law, in the Environmental Assessment Statement (hereinafter referred to as a “EIS”)
defined in the same paragraph of the said law.
(Submittal of EIS)
Article 46-16. A specific business operator, after preparing the EIS pursuant to Article 21, Paragraph 2 of the Environmental
Impact Assessment Law, shall submit it to the Minister of Economy Trade and Industry. The same shall be done when aspecific business operator alters the EIS in response to the order issued pursuant to Paragraph 1 of the following article.
(Order of Alteration)
Article 46-17. Regarding a specific project on which the EIS was submitted pursuant to preceding article, the Minister of
Economy Trade and Industry, may order the specific business operator to alter the EIS with setting the appropriate deadline
but within a time to be established by the ordinance of Ministry of Economy Trade and Industry from the day received theEIS pursuant to the same article, when deemed it to be especially necessary and appropriate to assure proper measurement toprotect the environment.
2. The Minister of Economy Trade and Industry shall notify the purport to the specific business operator without delay when
he admits it unnecessary to order pursuant to preceding paragraph.
(Submittal of EIS)
Article 46-18. The Minister of Economy Trade and Industry, when issuing the notification pursuant to Paragraph 2 of thepreceding article, shall submit the copy of the concerned EIS to the Minister of the Environment issued.
2. A specific business operator, upon receiving the notification pursuant to Paragraph 2 of the preceding article, shallpromptly submit the concerned EIS, its summary and the document describing the content of the order pursuant to Paragraph
1 of the preceding article to the related governors of prefectures and related mayors of cities, towns and villages, specified in
Article 15 of the Environmental Impact Assessment Law.
(Announcement and Exhibition to Public)
Article 46-19. Concerning the application of Article 27 of the Environmental Impact Assessment Law to a specific business
operator, "making a submission or notice pursuant to the provisions of Article 25, Paragraph 3" in that article shall be-- Provisional translation for information only --A3-43

construed to "receiving the notice pursuant to the provisions of Article 46-17, Paragraph 2 of the Electricity Utilities Industry
Law", "EIS" shall be construed to "concerned EIS", and "EIS, the summary, and the papers specified in Article 24" shall be
construed to "the concerned EIS, its summary and the document describing the content of the order pursuant to Paragraph 1of the same article".
(Consideration for Protection of Environment)
Article 46-20. A specific business operator shall implement the specific project paying proper consideration in protecting theenvironment pursuant to Article 38, Paragraph 1 of the Environmental Impact Assessment Law, and maintain and operate theelectric structure for business use concerning the specific project paying proper consideration in protecting the environment
pursuant to the contents of the EIS concerning the notification issued pursuant to Article 46-17, Paragraph 2.
(Technical Reinterpretation for Application of Environmental Impact Assessment Law)
Article 46-21. Technical reinterpretation for application of the provisions of the Environmental Impact Assessment Law overthe specific business operator and items required for application of the provisions of the said law to the specific business
operator other than those specified in this stipulation, shall be provided for in the government ordinance.
(Exemptions for Application of the Environmental Impact Assessment Law)
Article 46-22. Provisions of Article 22 through Article 26 and Article 33 through Article 37 of the Environmental Impact
Assessment Law shall not be applied to the specific project of the specific business operator.
(Construction Plans)
Article 47. Any person who intend to conduct construction work to establish or alter an electric structure for business use,
defined as extremely important to assure public safety in the ordinance of Ministry of Economy Trade and Industry, shallobtain an approval of the construction plans from the Minister of Economy Trade and Industry, unless the work is
unavoidably temporary one in case of an emergency such as destruction or damage of an electric structure for business use,
or a disaster.
2. A person who has received the approval pursuant to the preceding paragraph shall obtain the approval of the Minister of
Economy Trade and Industry if he intends to alter the construction plan for which the approval was granted, unless thealteration is minor one specified in the ordinance of the Minister of Economy Trade and Industry.
3. The Minister of Economy Trade and Industry shall grant the approval of each of two preceding paragraphs when theconstruction plan applying for approval pursuant to each of two preceding paragraphs meets all of the requirements set forth
below.
(i) The electric structure for business use conforms to the technical standards specified in the ordinance of Ministry of
Economy Trade and Industry referred to in Article 39, Paragraph 1.
(ii) The electric structure for business use shall be technically appropriate one in ensuring smooth supply of electricity whenin case that an electric structures for business use is devoted to a general electric utility.
(iii) Regarding a specific project, it shall conform to the EIS concerning the notification issued pursuant to Article 46-17,
Paragraph 2.
4. A person who establishes an electric structure for business use, in case of latter part of Paragraph 1, shall notify the fact toMinistry of Economy Trade and Industry without delay after beginning concerned work.
5. A person who received the approval pursuant to Paragraph 1, in case of latter part of Paragraph 2, shall notify the alteredconstruction plan to Ministry of Economy Trade and Industry without delay after altering it, unless the case is specified in theordinance of Ministry of Economy Trade and Industry.
Article 48. Any person who intends to conduct construction work to establish or alter an electric structure for business use(excluding the work defined in the ordinance of Ministry of Economy Trade and Industry, described in Paragraph 1 of thepreceding article) shall notify the Minister of Economy Trade and Industry of the construction plan. The same shall beapplied to alterations of concerned construction plan (excluding minor alterations specified in the ordinance of Ministry of
Economy Trade and Industry).
2. A person who has made the notification pursuant to the preceding paragraph may not begin the construction work
concerning the notification within thirty days from the day on which the notification was accepted.
3. The Minister of Economy Trade and Industry may reduce the time required by the preceding paragraph when theconstruction plan notified pursuant to Paragraph 1 of this article meets all of the requirements set forth below;(i) The requirements specified in each item of Paragraph 3 of the preceding article.
4. The Minister of Economy Trade and Industry may order the person who notified pursuant to Paragraph 1 of this article toalter or abolish the notified construction plan within thirty days (or extended period in case that the period defined in
Paragraph 2 of this article is extended pursuant to the following paragraph) from the accepted date of the notification, unlessthe construction plan notified pursuant to Paragraph 1 of this article is deemed to conform to any of the requirements in
Paragraph 3 of the preceding article.
5. The Minister of Economy Trade and Industry may appropriately extend the period specified in Paragraph 2 of this article,
when the review on assurance of conformability of the construction plan notified pursuant to Paragraph 1 of this article toeach requirements specified in Paragraph 3 of this article requires considerable period, and there exists reasonable reason forthe concerned review not to be completed within the period specified in Paragraph 2 of this article. In this case, the Ministerof Economy Trade and Industry, without delay, shall notify the extended period and the reason for the extension to the person
who notified.
(Pre-service Inspection)
Article 49. Regarding an electric structure for business use, defined as extremely important to assure public safety in theordinance of Ministry of Economy Trade and Industry, which is constructed or altered with the approval pursuant to Article
47, Paragraph 1 or Paragraph 2, or which is constructed or altered with the notification pursuant to Paragraph 1 of thepreceding article (excluding structure for which no notification has been made pursuant to Article 47, Paragraph 1, in casethat an order was issued concerning the construction plan referred to in Paragraph 4 of the said article), the structure shall be
subject to inspection on its work conducted by of the Minister of Economy Trade and Industry or an person designated by the-- Provisional translation for information only --A3-44

Minister of Economy Trade and Industry, in accordance with the ordinance of Ministry of Economy Trade and Industry, andshall not be used before the structure has passed such inspection, except a case provided in the ordinance of Ministry of
Economy Trade and Industry.
2. The electric structure for business use shall pass the inspection specified in preceding paragraph if it meets all of thefollowing requirements:(i)
The construction work was performed in accordance with the construction plan approved pursuant to Article 47,
Paragraph 1 or Paragraph 2 (including minor alterations, defined in the ordinance of Ministry of Economy Trade andIndustry, pursuant to latter part of Article 47, Paragraph 2), or the construction plan notified pursuant to Paragraph 1of the preceding article (including minor alterations, defined in the ordinance of Ministry of Economy Trade andIndustry, pursuant to the latter part of that paragraph); and(ii) It conforms to the technical standards specified in the ordinance of Ministry of Economy Trade and Industry referred toin Article 39, Paragraph 1.
3. In accordance with the ordinance of Ministry of Economy Trade and Industry, the Minister of Economy Trade andIndustry make the independent administrative agency, Japan Nuclear Energy Safety Organization (hereinafter referred to as
the "Organization") to carry out a part of affairs concerning the inspection provided in Paragraph 1, to examine whether the
specific electric structures for business use using nuclear power as motive force for electric power generation, which are
specified in the ordinance of Ministry of Economy Trade and Industry, meet all of the requirements provided in the preceding
paragraph.
4. When the Organization has carried out a part of affairs concerning the inspection pursuant to the preceding paragraph, theresults shall be notified without delay to the Minister of Economy Trade and Industry in accordance with the ordinance ofMinistry of Economy Trade and Industry.
(Pre-service Inspection on Safety Management)
Article 50-2. Any person who intends to establish an electric structure for business use, which are specified in the ordinanceof Ministry of Economy Trade and Industry submitting a notification to conduct construction work to establish or alter
pursuant to Article 48, Paragraph 1 (excluding structures for which no notification has been made pursuant to Paragraph 1 ofthe same article, in the case that an order was issued concerning the construction plan pursuant to Paragraph 4 of the same
article, and those which are specified in the ordinance of Ministry of Economy Trade and Industry of Article 49, Paragraph 1),
shall implement the self controlled inspection before use of the concerned electric structure for business use, and the resultsof the inspection shall be recorded and maintained in accordance with the ordinance of Ministry of Economy Trade andIndustry.
2. The electric structure for business use shall be confirmed that all of the following requirements are Ministry of Economy,
Trade and Industry in the inspection specified in the preceding paragraph (hereinafter referred to as "pre-service self
controlled inspection"):(i)
The construction work shall be conducted in accordance with the construction plan notified pursuant to Article 48,
Paragraph 1 (including minor alterations specified in the ordinance of Ministry of Economy Trade and Industry of thelatter part of the same paragraph); and(ii) It shall be in conformity with the technical standards specified in the ordinance of Ministry of Economy Trade andIndustry of Article 39, Paragraph 1.
3. A person who establishes the electric structure for business use, performing the pre-service self controlled inspection, shallundergo the examination on the organization for implementation of the pre-service self controlled inspection at the time
specified in the ordinance of Ministry of Economy Trade and Industry (in the case of receiving the notification pursuant toParagraph 7, at the time specified in the ordinance of Ministry of Economy Trade and Industry reflecting the past evaluation
results of the pre-service self controlled inspection of the concerned notice), for a person who establishes the electric
structure for business use specified in the ordinance of Ministry of Economy Trade and Industry, by the party enrolled by the
Minister of Economy Trade and Industry, and for other persons, by the Minister of Economy Trade and Industry.
4. The examination of the preceding paragraph, as a purport of safety management of electric structures for business use,shall be conducted concerning the pre-service self-controlled inspection on the implementing organization, inspection
methods, schedule control, and other items specified in the ordinance of Ministry of Economy Trade and Industry.
5. When the party enrolled by the Minister of Economy Trade and Industry in accordance with Paragraph 3 has carried out
the examination provided in the same paragraph, the results of the concerned examination shall be notified without delay to
the Minister of Economy Trade and Industry in accordance with the ordinance of Ministry of Economy Trade and Industry.
6. Based on the results of examination pursuant to Paragraph 3 (including the results of the examination notified pursuant to
the preceding paragraph), the Minister of Economy Trade and Industry shall comprehensively evaluate the implementing
organization of the pre-service self controlled inspection of the person who establishes the concerned electric structure forbusiness use.
7. The Minister of Economy Trade and Industry shall notify the results of the examination pursuant to Paragraph 3 and theevaluation of the preceding paragraph to the person who undergo the concerned examination.
(Inspection on Fuel Assembly)
Article 51. Nuclear fuel material to be used as fuel for nuclear power reactors (hereinafter referred to as "fuel material") shallbe subject to inspection by the Minister of Economy Trade and Industry at each of the fabrication processes, specified in theordinance of Ministry of Economy Trade and Industry, and shall not be used before it has passed the inspection, except a casespecified in Paragraph 3 and cases specified in the ordinance of Ministry of Economy Trade and Industry.
2. Fuel material shall pass the inspection specified in the preceding paragraph if it meets both of the following requirements:(i)
Its fabrication is performed in accordance with the design approved by the Minister of Economy Trade and Industry
in advance; and(ii)
It conforms to the technical standards specified in the ordinance of Ministry of Economy Trade and Industry.
3. Imported fuel material shall not be used unless it has passed the inspection of the Minister of Economy Trade and Industry.
-- Provisional translation for information only --A3-45

4. Imported fuel material shall pass the inspection described in the preceding paragraph if it conforms to the technicalstandards specified in the ordinance of Ministry of Economy Trade and Industry described in Paragraph 2, Subparagraph 2 ofthis article.
5. In accordance with the ordinance of Ministry of Economy Trade and Industry, the Minister of Economy Trade andIndustry makes the organization to carry out a part of affairs concerning the inspection specified in Paragraph 1 andParagraph 3.
6. When the Organization has carried out a part of affairs concerning the inspection pursuant to the preceding paragraph, theresults shall be notified without delay to the Minister of Economy Trade and Industry in accordance with the ordinance ofMinistry of Economy Trade and Industry.
(Inspection on Welding Safety Management)
Article 52. Any person who intends to establish electric structures specified below shall perform licensee's inspection on
weld of them before use pursuant to the ordinance of the Ministry of Economy Trade and Industry and the results of theinspection shall be recorded and maintained, except the case defined in the ordinance of Ministry of Economy Trade andIndustry; those electric structures (hereinafter referred to as "boilers, etc.") for power generation, which are boiler, turbine, orother mechanics or instrument specified in the ordinance of Ministry of Economy Trade and Industry, whose pressure parts(hereinafter referred to as "pressure part") are applied more than the pressure specified in the ordinance of Ministry of
Economy Trade and Industry are welded (hereinafter referred to as "specific boiler, etc." in Paragraph 3); those electric
structures (hereinafter referred to as "containment, etc.") for nuclear power reactor, which are containment vessel, or othermechanics and instruments specified in the ordinance of Ministry of Economy Trade and Industry, which are welded(hereinafter referred to as "specific containment, etc." in Paragraph 3); or those imported boilers, etc. whose pressure parts
are welded (hereinafter referred to as "imported specific boiler, etc." in Paragraph 3), or those welded containment, etc. which
are imported (hereinafter referred to as "imported specific containment, etc." in Paragraph 3).
2. In the inspection of the preceding paragraph (hereinafter referred to as "licensee's welding inspection"), it shall be
confirmed that the welding conforms to the technical standards specified in the ordinance of Ministry of Economy Trade andIndustry, referred to in Article 39, Paragraph 1.
3. A person who establishes the electric structures with performing the licensee's welding inspection shall undergo theexamination on the implementing organization for of the licensee's welding inspection by the Minister of Economy Trade andIndustry at the time specified in the ordinance of Ministry of Economy Trade and Industry (in the case of receiving thenotification pursuant to Article 50-2, Paragraph 7 applied with necessary modification to the Paragraph 5, at the time
specified in the ordinance of Ministry of Economy Trade and Industry reflecting the past evaluation result of the licensee's
welding inspection of the concerned notice), for a person who establishes the specific boiler, etc. applying nuclear power as
motive force for electric power generation or imported specific boiler, etc., which is specified in the ordinance of Ministry of
Economy Trade and Industry, or specific containment, etc. or imported specified containment, etc., which is specified in theordinance of Ministry of Economy Trade and Industry, by the Organization, and other persons, by the party designated by the
Minister of Economy Trade and Industry.
4. The examination of the preceding paragraph, as a purport of safety management of electric structures, shall be conducted
about the organization for implementation of the licensee's welding inspection, the inspection method, schedule control, andother items specified in the ordinance of Ministry of Economy Trade and Industry.
5.The provisions of Article 50-2, Paragraph 5 through Paragraph 7 shall be applied to the review provided in Paragraph 3
with necessary modification. In this case, the wording "the party designated by the Minister of Economy Trade and Industry
pursuant to Paragraph 3" in Paragraph 5 of the said article shall be construed to mean "the Organization or the party
designated by the Minister of Economy Trade and Industry pursuant to Paragraph 3", and the wording "concerned electric
structure for business use" in Paragraph 6 of the said article to mean "concerned electric structure".
(Periodic Inspection)
Article 54. Any person who establishes a specific important electric structure (boiler, turbine or other electric structures for
power generation, which is defined in the ordinance of Ministry of Economy Trade and Industry as a extremely important
items for ensuring public safety and includes the parts being applied pressure more than the specified pressure in theordinance of Ministry of Economy Trade and Industry, or nuclear power reactor or related components specified in theordinance of Ministry of Economy Trade and Industry, the same in the following paragraph)shall undergo the inspection by the Minister of Economy Trade and Industry in accordance with the ordinance of Ministry of
Economy Trade and Industry at the interval specified in the ordinance of Ministry of Economy Trade and Industry. But this is
not the case when specified in the ordinance of Ministry of Economy Trade and Industry.
2. In accordance with the ordinance of Ministry of Economy Trade and Industry, the Minister of Economy Trade andIndustry makes the Organization to carry out a part of affairs concerning the inspection pursuant to the ordinance of Ministryof Economy Trade and Industry described in the preceding paragraph, which examine the specific important electric structureusing nuclear power as motive force for electric power generation.
3. When the Organization has carried out a part of affairs concerning the inspection pursuant to the preceding paragraph, theresults shall be notified without delay to the Minister of Economy Trade and Industry in accordance with the ordinance ofMinistry of Economy Trade and Industry.
(Periodic Safety Management Inspection)
Article 55. Any person who establishes the specific electric structure (boiler, turbine, or other electric structure for power
generation, which is specified in the ordinance of Ministry of Economy Trade and Industry and includes the parts being
applied pressure more than the pressure specified in Paragraph 1 of the previous article, or nuclear power reactor or related
components specified in the ordinance of Ministry of Economy Trade and Industry, the same, hereinafter) shall implement
licensee's periodic inspection of the concerned specific electric structure and the results of the inspection shall be recorded
and maintained, in accordance with the ordinance of Ministry of Economy Trade and Industry.
2. In the inspection of the preceding paragraph (hereinafter referred to as "licensee's periodic inspection"), it shall be-- Provisional translation for information only --A3-46confirmed that the specific electric structure conforms to the technical standards specified in the ordinance of Ministry of
Economy Trade and Industry as referred to Article 39, Paragraph 1.
3. A person who establishes the specific electric structure with performing the licensee’s periodic inspection, at the concerned
licensee's periodic inspection on the specific electric structure using nuclear power as motive force for electric power
generation which is specified in the ordinance of Ministry of Economy Trade and Industry, when he deems that there is aportion with a possibility of deviation from the technical standard specified in the ordinance of Ministry of Economy Tradeand Industry as referred to Article 39, Paragraph 1 after the designated period of time, shall evaluate the time forecasted to bethat the portion concerned comes not meeting the technical standard specified in the said paragraph and other items specified
in the ordinance of Ministry of Economy Trade and Industry, and the results shall be recorded and maintained as specified in
the Ordinance of Ministry of Economy Trade and Industry, and moreover, he shall report the items specified in the ordinanceof Ministry of Economy Trade and Industry to the Minister of Economy Trade and Industry.
4. A person who establishes the specific electric structure with performing the licensee's periodic inspection shall undergo thereview on the implementing organization of the licensee's periodic inspection at the time specified in the ordinance ofMinistry of Economy Trade and Industry (in the case of receiving the notification pursuant to Article 50, Paragraph 7, at thetime specified in the ordinance of Ministry of Economy Trade and Industry reflecting the past evaluation results of thelicensee's periodic inspection of the concerned notification), for a person who establishes the specific electric structure
applying nuclear power as motive force for electric power generation, which is specified in the ordinance of Ministry of
Economy Trade and Industry, by the Organization, a person who establishes the specified electric structure other than thespecific electric structure applying nuclear power as motive force for electric power generation, which is specified in theordinance of Ministry of Economy Trade and Industry, by the party enrolled by the Minister of Economy Trade and Industry,
and for other persons, by the Minister of Economy Trade and Industry.
5. The review pursuant to the preceding paragraph, as a purport of safety management of specific electric structure, shall be
conducted on the implementing organization of the licensee's periodic inspection, inspection methods, schedule control, andother items specified in the ordinance of Ministry of Economy Trade and Industry.
6. Provisions of Article 50-2, Paragraph 5 through Paragraph 7 shall be applied with necessary modification to the review
provided in Paragraph 4. In this case, the wording "the party enrolled by the Minister of Economy Trade and Industry
pursuant to Paragraph 3" in Paragraph 5 of the said article shall be construed to mean "the Organization or the party enrolled
by the Minister of Economy Trade and Industry pursuant to Paragraph 4", and the wording "concerned electric structure forbusiness use" in Paragraph 6 of the said article to mean "concerned specific electric structure".
(Enrollment)
Article 67. Enrollment of Paragraph 3 of Article 50-2, Paragraph 3 of Article 52, or Paragraph 4 of Article 55 shall beenrolled upon application by persons who intend to perform the review (hereinafter referred to as "safety management
review") pursuant to those provisions for each division (hereinafter referred to as "division of review ") as shown in thefollowings, in accordance with the ordinance of Ministry of Economy Trade and Industry:(i)
Review of Article 50-2, Paragraph 3;(ii)
Review of Article 52, Paragraph 3; and(iii) Review of Article 55, Paragraph 4.
(Ineligibility Clause)
Article 68. Persons falling under any one of the followings cannot be enrolled for the enrollment specified in Paragraph 3 ofArticle 50-2, Paragraph 3 of Article 52, or Paragraph 4 of Article 55:(i)A person who has been condemned to the fine or heavier penalty for violation of the provisions of this law or theorders based on this law, and for whom two years have not yet elapsed after the execution of or after the relief fromthe execution of the penalty;(ii)
A person whose license in accordance with Article 78 has been cancelled and two years have not yet elapsed from theday of the cancellation; or(iii) A juridical person who has a person who comes under one of the preceding two subparagraphs in his officials
executing business.
(Criteria of Enrollment)
Article 69. The Minister of Economy Trade and Industry shall make the enrollment in accordance with Article 67 when aperson who applies an enrollment (hereinafter referred to as "applicant for enrollment" in this paragraph) conforms to all therequisites described in the following subparagraphs (in this case, a necessary procedure for the enrollment is specified in theordinance of Ministry of Economy Trade and Industry):(i)
Any person who falls under any of the following items shall perform the safety management review, and the numberof such persons shall be two or more per each division of review;(a) Any person who studied the course of electrical engineering, civil engineering, mechanical engineering,
management engineering or equal to these and graduated from the university (except for a junior college) based on
the School Education Law (1947, Law No. 26) or the old university based on the old University Order (1918,
Imperial Decree No. 388), and have practical experience engaged in such as construction, maintenance, practicaluse of electric structures or the practice of safety management review for two years or more in total,(b) Any person who studied the course of electrical engineering, civil engineering, mechanical engineering,
management engineering or equal to these and graduated from the junior college or the technical college based on
the School Education Law or the old technical school based on the old Technical School Order (1903, Imperial
Decree No. 61), and have practical experience engaged in such as construction, maintenance, practical use ofelectric structures or the practice of safety management review for four years or more in total,(c) Any person who has practical experience engaged in such as construction, maintenance, practical use of electric
structures or the practice of safety management review for six years or more in total, or(d) The applicant for enrollment shall not meet any of the following items which governed by those (hereinafter-- Provisional translation for information only --A3-47referred to as "establisher of the electric structure for safety management review" in this subparagraph) who
establishes the electric structure which shall undergo the safety management review in accordance with Paragraph
3 of Article 50-2, Paragraph 3 of Article 52, or Paragraph 4 of Article 55:
a. In the case of the applicant for enrollment is a business corporation or a corporation, the establisher of theelectric structure for safety management review is the parent company (which means “parent company” asprovided in Article 211-2, Paragraph 1 of the Commercial Code (1899, Law No. 48)),b. The rate of number of the officer and the office staff of the establisher of the electric structure for safety
management review (including persons who were the officer or the office staff of the concerned establisherof the electric structure for safety management review in the past two years) to that of the officers of theapplicant for enrollment (in the case of a copartner ship or a joint stock company, personnel who has
executive power) is over the half, andc. The applicant for enrollment (in the case of a corporation, the officer who has the right of representation) is
the officer or the office staff of the concerned establisher of the electric structure for safety management
review (including persons who were the officer or the office staff of the concerned establisher of the electric
structure for safety management review in the past two years).
2. The enrollment of Paragraph 3 of Article 50-2, Paragraph 3 of Article 52, or Paragraph 4 of Article 55 should state thefollowing items in the register book of safety management review agencies:(i)
Date of the enrollment and enrollment number;(ii)
Name or business name and address of the person who obtained the enrollment, and name and address of therepresentative in the case of a corporation; and(iii) Division of review.
(Renewal of Enrollment)
Article 70. When the enrollment pursuant to Paragraph 3 of Article 50-2, Paragraph 3 of Article 52, or Paragraph 4 of Article
55 is not authorized the renewal for every time period that is defined as three years or more in the government ordinance, itloses the effect by passage of the time period.
2. The preceding three articles shall be applied with necessary modification to the renewal of enrollment of the preceding
paragraph.
(Duties at the Safety Management Review)
Article 71. Any person who is enrolled pursuant to Paragraph 3 of Article 50-2, Paragraph 3 of Article 52, or Paragraph 4 of
Article 55 (hereinafter referred to as "safety management review agency") shall perform the safety management review
without delay at any time when the safety management review is required, unless there is a lawful reason to refuse.
2. The enrolled safety management review agency shall perform the safety management review with justice and also in theway specified in the ordinance of Ministry of Economy Trade and Industry.
3. The enrolled safety management review agency, when performing the safety management review, shall make those whoare specified in Article 69, Paragraph 1, Subparagraph 1 perform the safety management review.
(Change of Place of Business)
Article 72. The enrolled safety management review agency, when he is going to change the place of business performing thesafety management review, shall submit a notification to the Minister of Economy Trade and Industry two weeks before theday of change.
(Review rules)
Article 73. The enrolled safety management review agency shall define rules in relation to the activities of the safety
management review (hereinafter referred to as "review rules" in this section), and shall submit a notification to the Ministerof Economy Trade and Industry before the initiation of activities of the safety management review. The same shall be applied
to the modification of the review rules.
2. The implementing method of the safety management review, calculation formula of the charge for the safety management
review, and other items specified in the ordinance of Ministry of Economy Trade and Industry should be defined in thereview rules.
(Suspension or Discontinuance of Business)
Article 74. The enrolled safety management review agency, when he intends to suspend or discontinue all or part of his
activities of the safety management review, shall submit a notification on it beforehand to the Minister of Economy Tradeand Industry in accordance with the ordinance of Ministry of Economy Trade and Industry,.
(Providing and Inspection of Financial Statements, etc.)
Article 75. The enrolled safety management review agency shall prepare the assets inventory of the accounting year, balance
sheets and profit and loss statements or income and expenditure account statements, and accounts of business or business
reports (including electromagnetic records when these materials are prepared in the concerned electromagnetic records(records which are developed in an electronic method, a magnetic method, or other methods which cannot be recognized byhuman consciousness and used for information handling by an electronic computer, the same in this article.), or when theelectromagnetic records are prepared instead of these material, and it is referred to as "financial statements, etc." in thefollowing paragraph and Article 122-2) within three months after the end of the fiscal year and keep them for five years at theplace of business.
2. The person interested, etc. of the establisher of the electric structure, who conducts the licensee's welding inspection, theperiodic safety management review, and others may make following requests in at any time of the working hours of theenrolled safety management review agency. However, for the request of Subparagraph (ii) or Subparagraph (iv), he shall pay
the expenses defined by the enrolled safety management review agency.
(i)When the financial statements, etc. have been prepared in the document, request of inspection or making a copy of the
document concerned;(ii)
Request of the certified copy or the abridged copy of the document of the preceding subparagraph;-- Provisional translation for information only --A3-48

(iii)

When the financial statements, etc. have been prepared in electromagnetic records, request of inspection or making a
copy of what are displayed of the statements recorded on the electromagnetic record concerned by the method in
accordance with the ordinance of Ministry of Economy Trade and Industry; or(iv)
Request of supply of the statement recorded on the electromagnetic record of the preceding subparagraph in theelectromagnetic method, which is specified in the ordinance of Ministry of Economy Trade and Industry, or supply ofthe document which describes the statement concerned.
(Orders for Conformity)
Article 76. If an enrolled safety management review agency is deemed not to conform to any of the subparagraphs of Article
69, Paragraph 1, the Minister of Economy Trade and Industry may order the enrolled safety management review agency totake necessary measures to conform to those provisions.
(Orders for Improvement)
Article 77. If an enrolled safety management review agency is deemed not to conform to any of the provisions of Article 71,
the Minister of Economy Trade and Industry may order the enrolled safety management review agency to perform the safety
management review or to take necessary measures to improve the method of the safety management review or otheractivities.
(Revocation of Enrollment, etc.)
Article 78. The Minister of Economy Trade and Industry may order an enrolled safety management review agency to revoke
the enrollment pursuant to Paragraph 3 of Article 50-2, Paragraph 3 of Article 52, or Paragraph 4 of Article 55, or ordersuspension of all or part of its activities of safety management review for a period of time, unless the enrolled safety
management review agency is deemed to conform to any of the followings:(i)When he has violated the provisions of Article 50-2, Paragraph 5 (including the case applied with necessary
modification to Paragraph 5, Article 52 or Paragraph 6, Article 55), Article 71, Article 72, Paragraph 1 of Article 73,
Article 74, Paragraph 1 of Article 75, or the following article;(ii)
When he has come under one of Article 68, Subparagraph 1 or Subparagraph 3;(iii) When he has rejected the request provided in subparagraphs of Article 75, Paragraph 2 without any lawful reason;(iv)
When he has violated the order provided in the previous two articles; or(v)
When he has obtained the enrollment specified in Paragraph 3 of Article 50-2, Paragraph 3 of Article 52, or Paragraph
4 of Article 55 by means not justified.
(Accounting Books)
Article 79. An enrolled safety management review agency shall keep the accounting book and record the items specified in
the ordinance of Ministry of Economy Trade and Industry concerning the activities of the safety management review.
2. The accounting book described in the preceding paragraph must be kept in accordance with the ordinance of Ministry of
Economy Trade and Industry.
(Implementation of Safety Management Review Activities by the Minister of Economy Trade and Industry)
Article 80. The Minister of Economy Trade and Industry may implement all or part of the concerned activities of the safety
management review by himself, when nobody is enrolled for Paragraph 3 of Article 50-2, Paragraph 3 of Article 52, orParagraph 4 of Article 55, when he has received the notification to suspend or discontinue all or part of the activities of thesafety management review in accordance with Article 74, when he has revoked the enrollment of Paragraph 3 of Article 50-2,
Paragraph 3 of Article 52, or Paragraph 4 of Article 55 in accordance with Article 78 or ordered an enrolled safety
management review agency to suspend all or part of the activities of the safety management review, when he become
difficult to make an enrolled safety management review agency perform all or part of its activities of the safety management
review because of natural disaster or other reason, or when he deems it is necessary to implement the review.
2. In the case that the Minister of Economy Trade and Industry performs all or part of the activities of the safety management
review as provided in the preceding paragraph, the taking over of activities of the safety management review and othernecessary matters shall be specified in the ordinance of Ministry of Economy Trade and Industry.
(Designation of the Designated Organization for Safety Management Review)
Article 81. The designation specified in of Article 52, Paragraph 3 shall be conducted, pursuant to the ordinance of Ministryof Economy Trade and Industry, through the application of a party who intends to perform the review (hereinafter, referred
generically as "safety management review") specified in Article 52, Paragraph 3, for each division defined in the ordinance ofMinistry of Economy Trade and Industry.
(Duties of Safety Management Review)
Article 81-2. The organization designated in accordance with Article 52, Paragraph 3 (hereinafter referred to as "designatedorganization for safety management review") shall perform the safety management review without delay at any time when
the safety management review is demanded, unless there exist due reason to refuse.
2. The designated organization for safety management review, when he performs the safety management review, shall makethose specified in Article 69, Paragraph 1 applied with necessary modification to the following article (hereinafter referred toas "safety management review examiner") to performs the safety management review.
(Application with Modification)
Article 81-3. The following articles shall be applied to designated organizations for audit on safety management withappropriate modification; Article 68, Article 69, Article 72, Article 73, and Article 76 through Article 80. In this case, thewording "inspector" in Article76 shall be construed to mean "safety management review examiner".
(Electric Structure Inspector)
Article 104. The Electric Structure Inspector is assigned in Ministry of Economy Trade and Industry.
2. Electric Structure Inspectors engage in the office work for inspections specified in Paragraph 1 of Article 49, Paragraph 1
or Paragraph 3 of Article 51, or Paragraph 1 of Article 54, or for reviews specified in Article 50-2, Paragraph 3 or Article 55,
Paragraph 4.
3. Required matters concerning qualification of an Electric Structure Inspector are defined in the government ordinance.
-- Provisional translation for information only --A3-49

(Rules for Office Work)
Article 104-2. The Organization shall define the rules (hereinafter referred to as "rules of office work") for conducting theoffice work of inspection, etc. (including a part of the office work for inspections specified in Paragraph 1 of Article 49,
Paragraph 1 or Paragraph 3 of Article 51, or Paragraph 1 of Article 54, and for reviews specified in Article 52, Paragraph 3
and Article 55, Paragraph 4, the same, hereinafter) before the initiation of the activities concerning the office work ofinspection, etc., and shall make notification of the rules to the Minister of Economy Trade and Industry. The same shall beapplied to its alteration.
2. The Minister of Economy Trade and Industry may order to modify the rules of office work concerning notification
specified in the preceding paragraph, unless the Minister of Economy Trade and Industry deems that the said rules of office
work are appropriate to perform the office work of inspection, etc. properly and assuredly.
3. Items to be defined in the rules of office work are specified in the ordinance of Ministry of Economy Trade and Industry.
(Persons to Perform the Office Work of Inspection, etc.)
Article 104-3. When the Organization performs the office work of inspection, etc., the Organization shall make the personwith qualification provided in the ordinance of Ministry of Economy Trade and Industry perform the office work.
(Collection of Reports)
Article 106. The Minister of Economy Trade and Industry may request the establisher of an electric structure using nuclear
power as motive force for electric power generation (hereinafter referred to as "nuclear electric structure"), to the extent
necessary for enforcement of provisions of Article 39, Article 40, Article 47, Article 49 through Article 52, Article 54 andArticle 55, report or submit materials on the situation of activities for its fitness for safety of the nuclear electric structure inaccordance with the government ordinance.
2. Other than the matters provided in the previous paragraph, when the Minister of Economy Trade and Industry hasrequested the establisher of a nuclear electric structure to report or submit materials and when he deems especially necessaryfor ensuring the fitness for safety of the nuclear electric structure, the Minister of Economy Trade and Industry may request
the contractors on maintenance of the concerned nuclear electric structure to report required matters or present materials, tothe extent necessary for enforcement of provisions of Article 39, Article 40, Article 47, Article 49 through Article 52, Article
54 and Article 55.
3. Other than the matters provided in Paragraph 1, the Minister of Economy Trade and Industry may request a electric utility,
to the extent necessary for enforcement of this law, to report or submit materials on the situation of his business or accounting
in accordance with the government ordinance.
5. The Minister of Economy Trade and Industry may request the Organization to report or submit materials on the situationof his business, to the extent necessary for enforcement of this law.
(On-the-Spot Entry and Inspection)
Article 107. The Minister of Economy Trade and Industry may make his officials, to the extent necessary for enforcement ofprovisions of Article 39, Article 40, Article 47, Article 49 through Article 52, Article 54 and Article 55 enter factories orbusiness places, offices and other places of business of those who establish nuclear electric structures, fabricate fuel materials,
or weld boilers, etc. or containments, etc. (limited to those concerning nuclear electric structures) to examine their nuclear
electric structures, books, documents and other necessary matters.
2. Other than the on-the-spot entry and inspection provided in the previous paragraph, the Minister of Economy Trade andIndustry may make his officials, to the extent necessary for enforcement of this law, enter the business places, offices andother places of business of electric utilities to examine the situation of their business or accounting, or their nuclear electric
structures, books, documents and other necessary materials.
3. Other than the on-the-spot entry and inspection provided in Paragraph 1, the Minister of Economy Trade and Industry may
make his officials, to the extent necessary for enforcement of this law, to enter factories or business places, offices and otherplaces of business of those who establish electric structures for in-house use, or weld boilers, etc. or containments, etc. to
examine their electric structures, books, documents and other necessary matters.
4. The Minister of Economy Trade and Industry may make his officials, to the extent necessary for the enforcement of thislaw, enter the places (excluding places used as residence) where electric structures for general use are installed to examine
the electric structures for general use.
6. The Minister of Economy Trade and Industry may make his officials, to the extent necessary for enforcement of this law,enter the offices or other places of business of the Organization to examine the situation of his business, or books, documents
or other necessary materials.
9. The Minister of Economy Trade and Industry may make the Organization to conduct on-the-spot entry and inspection
specified in Paragraph 1 through Paragraph 3, when he deems it as necessary.
10. When the Minister of Economy Trade and Industry makes the Organization to conduct on-the-spot entry and inspectionin accordance with the previous paragraph, the Minister of Economy Trade and Industry shall direct the Organization
indicating the concerned place for on-the-spot entry and inspection and other necessary matters.
11. When the on-the-spot entry and inspection specified in Paragraph 9 has been carried out in accordance with the directionof the previous paragraph, the Organization shall report the results to the Minister of Economy Trade and Industry.
12. The officials of the Organization, who carry out the on-the-spot entry and inspection specified in Paragraph 9, shall carry
their identification cards with them and must show the cards when requested by persons concerned.
13. The authority specified in the provisions of Paragraph 1 through Paragraph 7 shall not be construed as having been
granted for the purpose of criminal investigation.
(Order to Organization)
Article 107-2. When the Minister of Economy Trade and Industry deems it is necessary to make an order for implementing
appropriate activities concerning the office work of inspection and the on-the-spot entry and inspection specified in
Paragraph 9 of the preceding article, he may make an order required for the activities to the Organization.
(Report to the Nuclear Safety Commission, etc.)-- Provisional translation for information only --A3-50

Article 107-3. The Minister of Economy Trade and Industry shall make the quarterly report on the situation of licensing,inspection and examination activities concerning the nuclear electric structure, provided in Paragraph 1 and Paragraph 2 ofArticle 47, Paragraph 1 of Article 49, Paragraph 3 of Article 50-2, Paragraph 1 and Paragraph 3 of Article 51, Paragraph 3 ofArticle 52, Paragraph 1 of Article 54, and Paragraph 4 of Article 55, for the previous quarter of the concerned quarter term to
the Nuclear Safety Commission, and shall take necessary measures to ensure the fitness for safety of the nuclear structurewith due consideration of the opinion of Nuclear Safety Commission, when it deems necessary.
2. Other than the reports provided in the preceding paragraph, the Minister of Economy Trade and Industry shall report thematters to ensure the fitness for safety of the nuclear structure on the situation of the enforcement of this law to the Nuclear
Safety Commission in accordance with the ordinance of Ministry of Economy Trade and Industry.
(Cooperation with Nuclear Safety Commission for Investigation)
Article 107-4. The establisher of the nuclear electric structure or the contractor on maintenance of the nuclear electric
structure shall cooperate with Nuclear Safety Commission, when the Commission conducts investigation concerning items
relating the report specified in the provisions of Paragraph 1 or Paragraph 2 of the preceding article.
(Penal Provisions)
Article 115. A person, who damages the electric structure used for electric utility or interfered power generation, powertransformation, power transmission or power distribution by causing a failure to the function of the electric structure used forelectric utility, shall be condemned to penal servitude for a term not exceeding five years or a fine of one million yen or less.
2. A person, who interferes power generation, power transformation, power transmission or power distribution by operating
the electric structure used for electric utility without permission, shall be condemned to penal servitude for a term notexceeding two years or a fine of a half million yen or less.
3. A person who engages in an electric utilities industry interfered power generation, power transformation, powertransmission or power distribution by not dealing with the job of maintenance or operation of the electric structure used forelectric utility without a justifiable reason, the same of the preceding paragraph shall be applied.
4. The attempted crime of Paragraph 1 and Paragraph 2 shall be penalized.
Article 116. A person, who comes under any of the following subparagraphs, shall be condemned to penal servitude of not
more than three years and/or a fine of three million yen or less:(i)
A person who operates the electric utility in violation of the provision of Article 3, Paragraph 1;(ii)
A person who violates the order or the disposition specified in the provision of Article 40 (limited to those concerning
nuclear electric structure); or(iii) A person who conducts construction work to establish or alter an electric structure in violation of the provision of
Article 47, Paragraph 1 (limited to those concerning nuclear electric structure).
Article 117. A person, who comes under any of the following subparagraphs, shall be condemned to penal servitude of not
more than two years and/or a fine of three million yen or less:(ii)
A person who rejects to supply electric power in violation of the provisions of Paragraph 1, Paragraph 3 or Paragraph
4 of Article 18; or(iii) A person who supplies electric power in violation of the provisions of Paragraph 5 through Paragraph 7 of Article 18.
Article 117-2. A person, who comes under any of the following subparagraphs, shall be condemned to penal servitude of not
more than one year and/or a fine of one million yen or less:(i)
A person who has used the electric structure in violation of the provision of Article 49, Paragraph 1 (limited to thoseconcerning nuclear electric structure), or Paragraph 1 or Paragraph 3 of Article 51;(ii)
A person who fails to make entries in the book, makes false entries in the books, fails to preserve the book, or make afalse report in violation of the provisions of Article 50-2, Paragraph 1, Article 52, Paragraph 1, Article 55, Paragraph
1 (limited to those concerning nuclear electric structure), or Paragraph 3 of the same article;(iii) A person who refuses, obstructs or evades the examination or inspection provided in Article 50-2, Paragraph 3,
Article 52, Paragraph 3, Article 54, Paragraph 1, or Article 55, Paragraph 4 (limited to those concerning nuclear
electric structure);(iv)
A person who violates an order for suspension of business of the safety management review specified in Article 78; or(v)
A person who fails to submit a report or material, or make a false report or material specified in Article 106,
Paragraph 1.
Article 118. A person who comes under any of the following subparagraphs shall be condemned to a fine of three million
yen or less:(i)
A person who rejects to supply electric power in violation of the provision of Article 18, Paragraph 2;(ii)
A person who violates the order specified in Paragraph 5 or Paragraph 8 of Article 19 or Paragraph 2 of Article 19-2;(viii) A person who fails to assign a Chief Engineer in violation of the provision of Article 43, Paragraph 1.
Article 119. A person who comes under any of the following subparagraphs shall be condemned to a fine of one million yen
or less:(iii) A person who conducts construction work to establish or alter an electric structure in violation of the order specified in
Article 48, Paragraph 4;(iv) A person who uses the electric structure in violation of the provision of Article 49, Paragraph 1 (excluding thoseconcerning the nuclear electric structure).
Article 119-2. A person, who is a executive officer or office staff of a designated organization for qualification test or a
support agency and commits a violating act which comes under any of the following subparagraphs, shall be condemned to afine of three hundred thousand yen or less:(iv) When he fails to make a report or material, or makes a false report or material specified in Article 106, Paragraph 7; or(v) When he refuses, obstructs or evades the inspection specified in Article 107, Paragraph 7.
Article 120. A person, who comes under any of the following subparagraphs, shall be condemned to a fine of three hundred
thousand yen or less:-- Provisional translation for information only --

A3-51

(i)

A person who fails to make a notification or make a false notification provided in Article 7, Paragraph 4 (including
the case when applied with necessary modification to Article 8, Paragraph 3), Article 9, Paragraph 1, Article 19-2,
Paragraph 1, Paragraph 1 or Paragraph 2 of Article 42, Article 43, Paragraph 3, Paragraph 4 or Paragraph 5 of Article
47, or Article 74;(vi)
A person who violates the order specified in Article 42, Paragraph 3;(vii) A person who conducts construction work to establish or alter an electric structure in violation of the order specified
in Paragraph 1 or Paragraph 2 of Article 48;(viii) A person who refuses, obstructs or evades the examination or inspection provided in Article 50-2, Paragraph 3,
Article 52, Paragraph 3, Article 54, Paragraph 1 or Article 55, Paragraph 4 (excluding those concerning nuclear
electric structure), or Article 107, Paragraph 2 through Paragraph 5;(x) A person who fails to describe or make a false description of the items specified in Article 79, Paragraph 1 to be appliedwith necessary modification to Article 57, Paragraph 4, Article 79, Paragraph 1, or Article 92-5, in violation of Article
79, Paragraph 1 to be applied with necessary modification to Article 79, Paragraph 1, or Article 92-5;(xi)
A person who fails to keep books in violation of Article 79, Paragraph 2 to be applied with necessary modification to
Article 57, Paragraph 4, Article 79, Paragraph 2 or Article 92-5; or(xii) A person who fails to submit a report or material, or makes a false report or material provided in Article 102,
Paragraph 2 through Paragraph 4 or Article 106, Paragraph 6.
Article 120-2. A person, who is executive officer or office staff of the Organization and commits a violating act that comesunder any of the following subparagraphs, shall be condemned to a fine of not more than two hundred thousand yen:(i)
When he fails to make a report, or makes a false report specified in Article 106, Paragraph 5; or(ii)
When he refuses, obstructs or evades the inspection specified in Article 107, Paragraph 6.
Article 121. When a representative of a legal person, or a legal person or an agent, an employee or other employees of aperson commits such violating act described in the following subparagraphs, with respect to the business of the legal personor the person, the legal person or the person shall be punished with such a fine as specified in the respective subparagraph, in
addition to the punishment of the actual offender:(i)
Article 112, Paragraph 2 or Paragraph 3; monetary penalty of three hundred million yen or less;(ii)
Article 112-2 (excluding Paragraph 4 concerned); monetary penalty of one hundred million yen or less; or(iii) Article 117, Article 117-2 (limited to Paragraph 4 concerned), Article 118, Article 119 or Article 120; monetary
penalty as specified in the respective article.
Article 122. A person, who comes under one of the following subparagraphs, shall be punished with an administrative fine of
one million yen or less:(iii) A person who has violated the order specified in Article 13, Paragraph 4, Article 35 or Article 46-17, Paragraph 1.
Article 122-2. In violation of the provision of Article 75, Paragraph 1 (including the case applied with necessary
modification to Article 92, Paragraph 5), a person who fails to prepare a financial statements, etc., fails to make entries in thefinancial statements, etc., or make false entries, or rejects without lawful reason the request specified in any subparagraphs in
Article 75, Paragraph 2 (including the case applied with necessary modification to Article 92, Paragraph 5), shall be punishedwith an administrative fine of two hundred thousand yen or less:
Article 122-3. A person, who is executive officer of the Organization and commits a violating act that comes under any of
the following subparagraphs, shall be punished with an administrative fine of two hundred thousand yen or less:(i)
When he fails to make a notification or make a false notification specified in Article 104, Paragraph 1; or(ii)
When he violates the order specified in Article 104, Paragraph 2 or Article 107-2.
Article 123. A person who falls under any of the followings shall be punished with an administrative fine of one hundred
thousand yen or less:(ii)
A person who has not returned chief engineer's license without due reason in violation of an order issued pursuant to
Article 44, Paragraph 4.

(2) Ministerial Order for Performing Inspections etc. by the Incorporated Administrative Agency, Japan
Nuclear Energy Safety Organization in Accordance with the Provisions of the Electricity Utilities Industry
Law(Ordinance of Ministry of Economy, Trade and Industry, No. 111, September 24, 2003)
In accordance with the provisions of Article 104-2, Paragraph 3 and Article 104-3 of the Electricity Utilities Industry Law(Law No. 170, 1964) and to enforce the said law, the Ministerial Order for Performing Inspections etc. by the Incorporated
administrative agency, Japan Nuclear Energy Safety Organization in Accordance with the Provisions of the Electricity
Utilities Industry Law is provided as follows.
(Definitions)
Article 1. The meaning of the terms used in this ministerial order are after that of the terms used in the Electricity Utilities
Industry Law (hereinafter referred to as “the Law”) and the Rules for the Enforcement of the Electricity Utilities Industry
Law (Ordinance of Ministry of International Trade and Industry No. 77, 1995)(Person Who Performs Inspection Affairs)
Article 2. Any person who performs a part of affairs concerning the inspections defined in Article 49, Paragraph 3, Article
51, Paragraph 5 and Article 54, Paragraph 2 of the Law (hereinafter referred to as “inspection affairs”) to be conducted by theincorporated administrative agency, Japan Nuclear Energy Safety Organization (hereinafter referred to as “the Organization”)
shall be a personnel of the Organization who comes under one of the following certificates provided in the ordinance ofMinistry of Economy, Trade and Industry described in Article 104-3 of the Law and designated by the head of theOrganization (hereinafter referred to as “Electric Structure Examiner”):-- Provisional translation for information only --

A3-52

(i)

Any person who studied the course of electrical engineering, civil engineering, mechanical engineering or
administrative engineering in and graduated from the university provided in the School Education Law (Law No. 26,
1947) (excluding the junior college, the same shall be applied in the following subparagraph, Article 3, Subparagraph 1
and Article 4, Subparagraph 1) or is recognized to have academic ability equal or more than that of the said person, andhas engaged for two years or more in the aggregate in the administrative affairs concerning construction, maintenanceand operation of an electric structure;(ii)
Any person who studied the course of electrical engineering, civil engineering, mechanical engineering or
administrative engineering in and graduated from the university provided in the School Education Law or is recognized
to have academic ability equal or more than that of the said person, and has engaged for three years or more in theaggregate in the practical business concerning construction, maintenance and operation of an electric structure;(iii) Any person who studied the course of electrical engineering, civil engineering, mechanical engineering or
administrative engineering in and graduated from the junior college or the technical college provided in the School
Education Law or is recognized to have academic ability equal or more than that of the said person, and has engaged
for four years or more in the aggregate in the administrative affairs concerning construction, maintenance and operationof an electric structure;(iv)
Any person who studied the course of electrical engineering, civil engineering, mechanical engineering or
administrative engineering in and graduated from the junior college or the technical college provided in the School
Education Law or is recognized to have academic ability equal or more than that of the said person, and has engaged
for five years or more in the aggregate in the practical business concerning construction, maintenance and operation ofan electric structure;(v)
Any person who has engaged for six years or more in the aggregate in the administrative affairs concerning
construction, maintenance and operation of an electric structure and is recognized by the Minister of Economy, Tradeand Industry to have considerable knowledge concerning construction, maintenance and operation of an electric
structure;(vi)
Any person who has engaged for seven years or more in the aggregate in the practical business concerning
construction, maintenance and operation of an electric structure and is recognized by the Minister of Economy, Tradeand Industry to have considerable knowledge concerning construction, maintenance and operation of an electric
structure;(vii) Any person who was Nuclear Facility Inspector specified in Article 67-2, Paragraph 2 of the Law for the Regulationsof Nuclear Source Material, Nuclear Fuel Material and Reactors (Law No. 166, 1957, hereinafter referred to as“Reactor Regulation Law”) or any person who has experience of a Nuclear Facility Examiner (which means a person
specified in Article 3 of the Ministerial Order for Performing Inspections etc. to be conducted by the incorporated
administrative agency, Japan Nuclear Energy Safety Organization (Ordinance of Ministry of Economy, Trade andIndustry No. 112, 1995, hereinafter referred to as “Ministerial Order for Inspection”), in accordance with the Reactor
Regulation Law, the same shall be applied hereinafter);(viii) Any person who was an Electric Structure Inspector; or(ix)
Any person who is recognized by the Minister of Economy, Trade and Industry to have knowledge and experienceequal or more than that of the person provided in the preceding subparagraphs.
(Person Who Performs Welding Safety Management Review)
Article 3. Any person who performs the welding safety management review to be conducted by the Organization shall be a
personnel of the Organization who are certified under one of the followings as provided in the ordinance of Ministry of
Economy, Trade and Industry described in Article 104-3 of the Law and designated by the head of the Organization(hereinafter referred to as “Welding Safety Management Reviewer”):(i)
Any person who studied the course of electrical engineering, civil engineering, mechanical engineering or
administrative engineering in and graduated from the university provided in the School Education Law or is recognized
to have academic ability equal or more than that of the said person, and has engaged for two years or more in theaggregate in the practical business concerning welding safety management review etc. (which means the inspection
described in Article 52, Paragraph 1 of the Electricity Utilities Industry Law before amendment as provided in Article 9of the Law for Consolidation and Rationalization of Standards, Certification Systems, Etc. Related to the Ministry ofInternational Trade and Industry (Law No. 121, 1999) (hereinafter referred to as “former welding inspection”), or
pre-service inspection, periodic inspection, pre-service safety management review, welding safety management review
or periodic safety management review, the same shall be applied, hereinafter) or the practical business concerning
construction, maintenance and operation of an electric structure, and finished the training provided by the Minister of
Economy, Trade and Industry;(ii)
Any person who studied the course of electrical engineering, civil engineering, mechanical engineering or
administrative engineering in and graduated from the junior college or the technical college defined in the School
Education Law or is recognized to have academic ability equal or more than that of the said person, and has engaged
for four years or more in the aggregate in the practical business concerning welding safety management review etc. or
the practical business concerning construction, maintenance and operation of an electric structure, and finished thetraining provided by the Minister of Economy, Trade and Industry;(iii) Any person who was a Nuclear Facility Inspector described in Article 67-2, Paragraph 2 of the Reactor Regulation
Law or has experience of a Nuclear Facility Examiner, and finished the training provided by the Minister of Economy,
Trade and Industry;(iv)
Any person who was an Electric Structure Inspector or has experience of an Electric Structure Examiner, and finishedthe training provided by the Minister of Economy, Trade and Industry;(v)
Any person who has engaged for six years or more in the aggregate in the practical business concerning welding
safety management review etc. or the practical business concerning construction, maintenance and operation of an-- Provisional translation for information only --A3-53

electric structure, and finished the training provided by the Minister of Economy, Trade and Industry;
Any person who has experience of performing the inspection defined in subparagraphs of Article 61-24 of the Reactor
Regulation Law, the inspection described in subparagraphs of Article 61-24 of the Reactor Regulation Law before
amendment provided in Article 8 of the supplementary provisions in accordance with the Law for Japan Nuclear
Energy Safety Organization (Law No. 179, 2002) or the former welding inspection, and finished the training provided
by the Minister of Economy, Trade and Industry;(vii) Any person who has experience of performing a pre-service safety management review or periodic safety
management review, and finished the training provided by the Minister of Economy, Trade and Industry;(viii) Any person who has experience of performing welding safety management review; or(ix)
Any person who is recognized by the Minister of Economy, Trade and Industry to have knowledge and experienceequal or more than that of the person provided in the preceding subparagraphs.
(Person Who Performs Periodic Safety Management Review)
Article 4. Any person who performs a periodic safety management review to be conducted by the Organization shall be a
personnel of the Organization who are certified under one of the followings as provided in the ordinance of Ministry of
Economy, Trade and Industry described in Article 104-3 of the Law and designated by the head of the Organization(hereinafter referred to as “Periodic Safety Management Reviewer”):(i)
Any person who studied the course of electrical engineering, civil engineering, mechanical engineering or
administrative engineering in and graduated from the university defined in the School Education Law or is recognized
to have academic ability equal or more than that of the said person, and has engaged for two years or more in theaggregate in the practical business concerning welding safety management review etc. or the practical businessconcerning construction, maintenance and operation of an electric structure, and finished the training provided by the
Minister of Economy, Trade and Industry;(ii)
Any person who studied the course of electrical engineering, civil engineering, mechanical engineering or
administrative engineering in and graduated from the junior college or the technical college defined in the School
Education Law or is recognized to have academic ability equal or more than that of the said person, and has engaged
for four years or more in the aggregate in the practical business concerning welding safety management review etc. or
the practical business concerning construction, maintenance and operation of an electric structure, and finished thetraining provided by the Minister of Economy, Trade and Industry;(iii) Any person who was a Nuclear Facility Inspector described in Article 67-2, Paragraph 2 of the Reactor Regulation
Law or has experience of a Nuclear Facility Examiner, and finished the training provided by the Minister of Economy,
Trade and Industry;(iv)
Any person who was an Electric Structure Inspector or has experience of an Electric Structure Examiner, and finishedthe training provided by the Minister of Economy, Trade and Industry;(v)
Any person who engaged for six years or more in the aggregate in the practical business concerning welding safety
management review etc. or the practical business concerning construction, maintenance and operation of an electric
structure, and finished the training provided by the Minister of Economy, Trade and Industry;(vi)
Any person who has experience of pre-service safety management review or periodic safety management review, andfinished the training provided by the Minister of Economy, Trade and Industry;(vii) Any person who has experience of welding safety management review, and finished the training provided by the
Minister of Economy, Trade and Industry; or(viii) Any person who is recognized by the Minister of Economy, Trade and Industry to have knowledge and experienceequal or more than that of the person provided in the preceding subparagraphs.
(Particulars to Specify in the Rules for Office Work)
Article 5. Particulars to be specified in the rules for office work concerning the inspection affairs provided in the ordinanceof Ministry of Economy, Trade and Industry described in Article 104-2, Paragraph 3 of the Law, and the notification of
results provided in Article 49, Paragraph 4, Article 51, Paragraph 6 and Article 54, Paragraph 3 of the Law, shall be thosedefined in the followings:(i)Name of the place of business and area where the place of business carries out the inspection affairs;(ii)
Particulars concerning working hours and holiday on the inspection affairs;(iii) Particulars concerning duties of the Electric Structure Examiner;(iv)
Particulars concerning appointment and removal of the Electric Structure Examiner and its allocation;(v)
Particulars concerning methods to perform the inspection affairs;(vi)
Particulars concerning preservation of books and documents relating to the inspection affairs;(vii) Particulars concerning notification of results of the inspection affairs to the Minister of Economy, Trade and Industry;and(viii) Other particulars necessary to perform the inspection affairs.
2. Particulars to be provided in the rules for office work concerning the welding safety management review provided in theordinance of Ministry of Economy, Trade and Industry described in Article 104-2, Paragraph 3 of the Law, and thenotification of results defined in Article 50-2, Paragraph 5 of the Law, which is applied correspondingly to Article 52,
Paragraph 5 of the Law, shall be those defined in the followings:(i)Name of the place of business and area where the place of business carries out business of the welding safety
management review;(ii)
Particulars concerning working hours and holiday on the business of the welding safety management review;(iii) Particulars concerning methods to receive the fee;
(iv)
Particulars concerning duties of the Welding Safety Management Reviewer;(v)
Particulars concerning appointment and removal of the Welding Safety Management Reviewer and its allocation;(vi)
Particulars concerning methods to perform the welding safety management review;(vi)-- Provisional translation for information only --A3-54

(vii) Particulars concerning preservation of books and documents relating to the welding safety management review;(viii) Particulars concerning notification of results of the welding safety management review to the Minister of Economy,
Trade and Industry; and(ix)
Other particulars necessary to perform business of the welding safety management review.
3. The provisions described in subparagraphs of Paragraph 2 shall be applied with necessary modification to the particulars tobe provided in the rules for office work provided in the ordinance of Ministry of Economy, Trade and Industry described in
Article 104-2, Paragraph 3 of the Law. In this case, the terms “Welding Safety Management Reviewer” and “Article 52,
Paragraph 5” referred to in these provisions shall be construed to mean “Periodic Safety Management Reviewer” and “Article
55, Paragraph 6”, respectively.
(Identification Card for Entry and Inspection Conducted by the Organization)
Article 6. The identification card to be carried on by each personnel of the Organization who performs the entry andinspection provided in the provision of Article 107, Paragraph 9 of the Law shall be in accordance with the correspondingform.

(3) Rules for the Enforcement of the Electricity Utilities Industry Law (Excerpt)(Ordinance of Ministry of International Trade and Industry No. 77, October 18, 1995)(Latest Revision: Ordinance of Ministry of Economy, Trade and Industry No. 31, March 16, 2004)(Approval, Etc. of Construction Plans)
Article 62. The construction work to establish or alter an electric structure for business use provided for in the ordinance ofMinistry of Economy, Trade and Industry referred to in Article 47, Paragraph 1 of the Law, (hereinafter referred to as"restricted construction work"), shall be as indicated in the middle row of annexed Table 2 according to the types of
construction work indicated in the left row of that table; or other work, constituting actions indicated in subparagraphs of
Article 7, Paragraph 1 of the Law Concerning Prevention of Disasters due to Collapse of Steep Slope (Law No. 57, 1969)
which are performed within steep slope collapse risk areas referred to in Article 3, Paragraph 1 of the said law (hereinafterreferred to as "steep slope collapse risk areas"), excluding the case that the work had already begun at the time of designationof that steeply inclined land collapse risk area and the cases of Article 2, Subparagraph 1 through Subparagraph 8 of the
Enforcement Ordinance of the Law Concerning Prevention of Disasters due to Collapse of Steep Slope (Government
Ordinance No. 206, 1966).
2. The minor alterations provided for in the ordinance of Ministry of Economy, Trade and Industry described in the proviso
of Article 47, Paragraph 2 of the Law shall be those alteration that do not involve the work indicated in the middle or rightrow of annexed Table 2 or the bottom row of annexed Table 4 or restricted construction work performed in steeply inclined
land collapse risk areas.
3. The cases provided for in the ordinance of Ministry of Economy, Trade and Industry described in the proviso of Article
47, Paragraph 5 of the Law shall be cases which do not involve alters in the particulars indicated in the construction planreferred to in Paragraph 1(i) of the following article.
Article 63. Any person who intends to obtain the approval of Article 47, Paragraph 1 or Paragraph 2 of the Law shall submit
an application for approval for a construction plan (or alteration), using Form 47 with the following documents attached.
However, if the application concerns construction work for alterations, it shall not be necessary to include the documents (ii)in the case of replacement or repair work, and it shall not be necessary to include the documents (ii) and (iii) in the case ofabolishment work.
(i)
The construction plan;
The documents, indicated in the lower row of annexed Table 3 according to the category indicated in the upper row of(ii)that column to which the concerned electric structure for business use belongs;(iii) The construction process table; and(iv)
In the case of construction work for alterations or altercations in the construction plan, a statement of the reasons
making the alterations necessary.
2. The construction plan of (i) of the preceding paragraph shall include the particulars indicated in the middle column ofannexed Table 3 (or the repair methods in the case that the application is for repair work) corresponding to the type of anelectric structure for business use for which the application was submitted. In this case, if the application is for construction
work for alteration (excluding work for replacement, repair, and abolition) or alterations in the construction plan, theseparticulars must be presented in a manner that facilitates comparison between the situation before the alterations and thesituation after the alterations.
3. In the case of divided application for approval, referred to in Article 47, Paragraph 1 of the Law, on the construction plan
indicated in the middle row of annexed Table 2, in addition to the documents of each items in Paragraph 1, a statement mustbe attached to the application, giving an overview of the construction plan of other portion than the portion concerned in theapplication.
Article 69. In the inspection described in Article 49, Paragraph 1 of the Law (hereinafter referred to as “pre-service
inspection”), the Electric Structure Inspector (in the case that the incorporated administrative agency, Japan Nuclear Energy
Safety Organization (hereinafter referred to as “the Organization”) implements a part of affairs concerning the pre-service
inspection on the basis of the provisions of Article 49, Paragraph 3 of the Law, the examiner of the Organization (whichmeans any person who has the certificate described in Article 104-3 of the Law, the same shall be applied hereinafter) shallperform the inspection items indicated in the right row of the following tables according to the construction process indicatedin the left row of the said tables.
(i)Construction of nuclear power station-- Provisional translation for information only --A3-55

Construction Step
A. When nuclear reactors,
reactor cooling systemequipment, measuring andcontrol system equipment, fuelequipment, radiation
management equipment,
disposal equipment or reactor
containment facilities becomes
ready for inspection on its
structure, strength or leakage

Inspection Items
The following items of inspections to verify the structure, functions or
performances of nuclear reactors, reactor cooling system equipment,
measuring and control system equipment, fuel equipment, radiation
management equipment, disposal equipment or reactor containment facilities:(i) Material inspection;(ii) Dimensional inspection;(iii) Visual inspection:(iv) Inspection to verify conditions of assembling and installation,
Pressure inspection, andLeak test;(vii)Inspection to verify conditions of the base on which the reactor
containment facility is installed directly.

B. When installation of thelower half of turbine
compartment has been
completed, and whenassembling of main body of
the auxiliary boiler iscompleted(i) The following items of inspections to verify the structure, function or
performance of the steam turbine;

A. Material inspection,
B. Dimensional inspection,
C. Visual inspection, and
D. Inspection to verify conditions of assembling and installation.
(ii) The following items of inspections to verify the structure, function or
performance of the auxiliary boiler;

A. Material inspection,
B. Dimensional inspection,
C. Visual inspection,
D. Inspection to verify conditions of assembling and installation,
E. Pressure inspection, andF. Leak test.
C. When the nuclear reactors
becomes ready for loading offuel assemblies

D. When nuclear reactors
becomes ready for starting
operation of the criticality
reaction
E. When all of theconstruction related to theconstruction plan arecompleted

Inspections to verify necessary functions or performances on the condition toload fuel assemblies in the reactor relating to the reactor cooling systemequipment, measuring and control system equipment, fuel equipment,
radiation management equipment, disposal equipment, reactor containment
facilities, ventilation stack, steam turbines, generators, transformers, voltage
regulators or voltage phase regulators, condensers, frequency converters or
rectifiers, breakers, batteries, control equipment to control operation of thepower station, and emergency standby power generation devices
Inspections to verify necessary functions or performances when the reactor
attains criticality relating to nuclear reactors, reactor cooling systemequipment, measuring and control system equipment, steam turbines andgenerators
Inspections to verify overall performance of the nuclear power station at power
operation of the reactor, and other necessary inspections to verify that theconstruction has been completed(ii)

Construction other than that defined in the preceding subparagraphConstruction Step
Inspection Items
When all of the construction
Inspections to verify performance of the specific electric structures for
related to the construction plan business use at normal operation, and other necessary inspections to verify thatare completed
the construction has been completed
Article 70. The cases provided for in the ordinance of Ministry of Economy, Trade and Industry described in the proviso of
Article 49, Paragraph 1 of the Law shall be as follows.
(i)
The case that a nuclear reactor is to be used in a testing, and the approval of the Minister of Economy, Trade andIndustry has been obtained concerning the time period and method of usage, and the reactor is used during the time
period and by the method for which that approval was obtained.
(ii)
The case that electric structures for business use other than the electric structures for business use referred to in thepreceding number are connected with power grids and used for testing within a time period notified in advance to the
Minister of Economy, Trade and Industry.
(iii) The case that electric structures for business use other than those referred to in Subparagraph (i) are used for testing
within a time period notified in advance to the Minister of Economy, Trade and Industry without being connectedwith power grids.
(iv)
The case that a portion of an electric structure for business use has been completed, and there are special
circumstances such that the completed portion must be used at a time other than their use for testing, and the approval-- Provisional translation for information only --A3-56

of the Minister of Economy, Trade and Industry has been obtained concerning the time period and method of usage,
and the concerned portion is used during the time period and by the method for which that approval was obtained.
(v)
The case that the Minister of Economy, Trade and Industry has indicated that an electric structure for business use
may be used without inspection, having deemed that there is no obstacle to such use based on the situation of its
location or the content of construction.
Article 73-2. The specific electric structures for business use provided in the ordinance of Ministry of Economy, Trade andIndustry described in Article 49, Paragraph 3 of the Law shall be any nuclear reactors, reactor cooling system equipment,
measuring and control system equipment, fuel equipment, radiation management equipment, disposal equipment, reactor
containment facility, ventilation stack, steam turbine, auxiliary boiler, generator, transformer, voltage regulator or voltage
phase regulator, condenser, frequency converter or rectifier, breaker, battery, or emergency standby power generation device.
2. A part of office works concerning inspections that the Organization conducts as provided in the provisions of Article 49,
Paragraph 3 of the Law shall be those described in the followings:(i)
Inspection items indicated in the right row of the table shown in Article 69, Subparagraph 1 at the step of Item A and
Items B in the left row of the said table;(ii)
The following inspection items of those indicated in the right row of the table shown in Article 69, Subparagraph 1 at
the step of Item C in the left row of the said table;
A. The following items of inspections to verify functions or performances of the reactor cooling system equipment,(1) In the case of a boiling water reactor type power generation installation, those relating to reactor coolant
recirculation equipment, circulation equipment of reactor coolant, reactor coolant make-up equipment,
component cooling equipment, reactor coolant cleanup equipment and devices to monitor leakage of reactor
coolant in the reactor containment facility,(2) In the case of a pressurized water reactor type power generation installation, those relating to circulationequipment of primary coolant, main steam and feed water equipment, residual heat removal equipment,chemical and volume control equipment, component cooling water equipment, sea water equipment anddevices to monitor leakage of primary coolant in the reactor containment facility, or(3) In the case of a sodium-cooled reactor type power generation installation, those relating to circulationequipment of primary coolant, circulation equipment of secondary coolant, primary sodium auxiliary
equipment, secondary sodium auxiliary equipment, primary argon gas system equipment, maintenance coolingsystem equipment, component cooling water equipment, sea water equipment and component cooling systemequipment.
B. The following items of inspections to verify functions or performances of the measuring and control systemequipment,(1) In the case of the boiling water reactor type power generation installation, those relating to the control
equipment of reactor, control rod drive systems, instrumentation devices, safety protection equipment (whichmeans measuring and control system equipment necessary for emergency reactor shut-down and actuating
engineered safety features, the same shall be applied hereinafter in this paragraph), instrument air systems andpower units for reactor coolant recirculation pumps,(2) In the case of the pressurized water reactor type power generation installation, those relating to the control
equipment of reactor, equipment with boric acid injection function, boron thermal regeneration equipment,
instrumentation devices, safety protection equipment and instrument air systems, or(3) In the case of the sodium-cooled reactor type power generation installation, those relating to the control rod
drive systems, instrumentation devices, sodium leak detection devices, burst cartridge detection system, safety
protection equipment and instrument air systems.
C. The following items of inspections to verify function or performance of the reactor containment facility,(1) In the case of the boiling water reactor type power generation installation, those relating to the vacuum relief
systems, reactor containment spray equipment, flammability control equipment and reactor containment
atmosphere dilution equipment,(2) In the case of the pressurized water reactor type power generation installation, those relating to thecontainment spray equipment, ice condenser equipment, vacuum relief equipment and pressure relief
equipment, or(3) In the case of the sodium-cooled reactor type power generation installation, those relating to the vacuum relief
equipment.
D. Inspections to verify functions or performances of fuel equipment, radiation management equipment, disposal
equipment, ventilation stacks, steam turbines, generators, transformers, voltage regulators or voltage phaseregulators, condensers, frequency converters or rectifiers, breakers and control equipment to control operation of thepower station.
(iii) The following inspection items of those indicated in the right row of the table shown in Article 69, Subparagraph 1 at
the step of Item D in the left row of the said table;
A. Inspections to determine fuel configuration and critical state in the reactor core to verify function or performance ofthe reactor,
B. Inspections to verify functions or performances of the reactor cooling system equipment, or
C. Inspections to verify interlocks between the reactor, steam turbines and generators relating to shut-down to verify
functions or performances of the measuring and control system equipment, steam turbines or generators.
(iv)
The following inspection items of those indicated in the right row of the table shown in Article 69, Subparagraph 1 at
the construction step E indicated in the left row of the said table;
A. The following items of inspections performed when the reactor is shut-down,-- Provisional translation for information only --A3-57

(1) The following items of inspections to verify functions or performances of the reactor cooling systemequipment,a) In the case of the boiling water reactor type power generation installation, those relating to the reactor
coolant recirculation equipment, circulation equipment of reactor coolant, reactor coolant make-up
equipment, component cooling equipment, reactor coolant cleanup equipment and devices to monitor
leakage of reactor coolant in the reactor containment facility,b) In the case of the pressurized water reactor type power generation installation, those relating to thecirculation equipment of primary coolant, main steam and feed water equipment, residual heat removal
equipment, chemical and volume control equipment, component cooling water equipment, sea waterequipment and devicess to monitor leakage of primary coolant in the reactor containment facility, orc) In the case of the sodium-cooled reactor type power generation installation, those relating to thecirculation equipment of primary coolant, circulation equipment of secondary coolant, primary sodium
auxiliary equipment, secondary sodium auxiliary equipment, primary argon gas system equipment,
maintenance cooling system equipment, component cooling water equipment, sea water equipment andcomponent cooling system equipment.
(2) The following items of inspections to verify functions or performances of the measuring and control systemequipment,a) In the case of a boiling water reactor type power generation installation, those relating to control
equipment of reactor, control rod drive systems, instrumentation devices, safety protection equipment,
instrument air systems and power units for reactor coolant recirculation pumps,b) In the case of the pressurized water reactor type power generation installation, those relating to thecontrol equipment of reactor, equipment with boric acid injection function, boron thermal regenerationequipment, instrumentation devices, safety protection equipment and instrument air systems,c) In the case of the sodium-cooled reactor type power generation installation, those relating to thecontrol rod drive systems, instrumentation devices, sodium leak detection devices, burst cartridge
detection systems, safety protection equipment and instrument air systems.
(3) The following items of inspections to verify function or performance of the reactor containment facility,a) In the case of the boiling water reactor type power generation installation, those relating to the vacuum
relief systems, reactor containment spray equipment, flammability control equipment and reactor
containment atmosphere dilution equipment,b) In the case of the pressurized water reactor type power generation installation, those relating to thecontainment spray equipment, ice condenser equipment, vacuum relief equipment and pressure relief
equipment, orc) In the case of the sodium-cooled reactor type power generation installation, those relating to thevacuum relief equipment.
(4) Inspections to verify functions or performances of the fuel equipment, radiation management equipment,
disposal equipment, ventilation stacks, steam turbines, generators, transformers, voltage regulators or voltage
phase regulators, condensers, frequency converters or rectifiers, breakers and control equipment to control
operation of the power station.
B. Inspections (excluding those relating to the reactor core isolation cooling system in the case of a boiling water
reactor type power generation installation) performed when the reactor is in power operation (excluding the case inoperation at rated power).
3. Irrespective of provisions of the preceding paragraph, when the Minister of Economy, Trade and Industry deems that it isnecessary to conduct inspections by himself in relation to structure, material, etc. of the specific electric structures forbusiness use, the Minister of Economy, Trade and Industry shall conduct by himself the inspections relating to the electric
structure concerned for specific business use.
4. When the Minister of Economy, Trade and Industry deems that it is necessary to conduct the inspections described in thepreceding paragraph, the Minister shall notify the Organization of it.
5. The Organization shall prepare an inspection instruction manual that provides for methods of the inspections described in
Paragraph 2 and other necessary particulars in accordance with the notification described in Article 71-2, Paragraph 2.
6. The notification described in Article 49, Paragraph 4 of the Law shall be made by letter specifying the following
particulars:(i)Name and address of the person, and in the case of a juridical person, the name of its representative who underwent
the inspection;(ii)
Name and location of the place of business related to the specific electric structures for business use subjected to theinspection;(iii) Date of the inspection;(iv)
Place where the inspection was performed;(v)
Object of the inspection;(vi)
Methods of the inspection; and(vii) Results of the inspection.
(Inspection of Fuel Assembly)
Article 77. Any person, who intends to obtain the approval of Article 51, Paragraph 2, Subparagraph (i) of the Law, shallsubmit an application for design approval of fuel assemblies using Form 54, with the following documents attached:(i)
Description on heat resistance, radiation resistance, corrosion resistance and other performance of the fuel assembly;(ii)
Calculation of mechanical strength of a fuel assembly (or a fuel element for fuel assembly composed of fuelelements);-- Provisional translation for information only --A3-58

(iii) Structural drawings of the fuel assembly;(iv)
Flow sheet of fabrication; and(v)
Description on Quality Assurance.
Article 78. Any person who intends to receive the inspection provided for in Article 51, Paragraph 3 of the Law shall submit
an application for inspection for imported fuel assemblies using Form 55, with the following documents attached, unless the
Minister of Economy, Trade and Industry indicates that it is not necessary to attach the documents judged from type anddesign, etc. of fuel assembly concerning the application:(i)
Description on heat resistance, radiation resistance, corrosion resistance and other performance of the fuel assembly;(ii)
Calculation of mechanical strength of the fuel assembly (or a fuel element for fuel assembly composed of fuelelements);(iii) Structural drawings of the fuel assembly;(iv)
Flow sheet of fabrication;(v)
Data of the test result, including composition, structure and strength, etc. of the fuel material, the fuel cladding andother parts; and(vi)
Description on Quality Assurance.
(Inspection of Welding Safety Management)
Article 80. The pressures provided in the ordinance of Ministry of Economy, Trade and Industry described in Article 52,
Paragraph 1 of the Law shall be as follows.
(i)
Regarding vessel and pipe for water whose maximum working temperature is less than 100 degrees, a maximum
working pressure of 1,960 kilopascals.
(ii)
Regarding vessel and pipe for liquefied gas, a maximum working pressure of 0 kilopascals.
(iii) Regarding vessel other than the containers referred to (i) and (ii) above, a maximum working pressure of 98
kilopascals.
(iv)
Regarding pipe other than the pipe referred to in (i) and (ii) above, a maximum working pressure of 980 kilopascals(or 490 kilopascals in the case of longitudinal seam portion of pipe which do not belong to fuel cell facilities).
(Periodic Inspections)
Article 89. The specific pressure structures provided in the ordinance of Ministry of Economy, Trade and Industry describedin Article 54 of the Law shall be steam turbines belonging to nuclear power stations.
Article 90. The nuclear power reactor and attached equipment provided in the ordinance of Ministry of Economy, Trade andIndustry described in Article 54, Paragraph 1 of the Law shall be reactor, the reactor cooling system, instrumentation andcontrol system, fuel equipment, radiation management equipment, disposal equipment, reactor containment facility, andauxiliary boiler, and emergency power generation devices.
Article 90-2. The inspection described in Article 54, Paragraph 1 of the Law (hereinafter referred to as “periodic inspection”)
shall be conducted for the matters provided in the following subparagraphs by witnessing the licensee’s periodic inspection
conducted by the person who undergo the periodic inspection by the Electric Structure Inspector (or the Electric Structure
Examiner of the Organization in the case that the Organization conducts a part of affairs concerning the periodic inspection inaccordance with the provisions of Article 54, Paragraph 2 of the Law), or verifying the record of the licensee’s periodic
inspection:(i)
In the case of steam turbines that belongs to the nuclear power station (referred to as “the steam turbine”, in thisarticle), the following matters related to licensee’s periodic inspection;
A. Nondestructive inspection of main body of the turbine, major valves, condensers, heat exchangers and major piping,andB. Inspections to check condition of assembling and installation of the main body of the turbine and the major valves,
and actuation inspection of fitness-for-safety devices.
(ii)
In the case of power reactors (limited to boiling water reactors) and associated facilities, matters indicated in the rightrow of the following table related to the licensee’s periodic inspection according to the type of electric structure
indicated in the left row of the said table;
Type of Electric Structure
Matters related to Licensee’s Periodic Inspection(i) Nuclear reactors
1. Nondestructive inspection of main bodies of reactor pressure vessels, reactor
pressure vessel support structures and associated structures of reactor pressure
vessels, and leak test of main bodies of reactor pressure vessels and reactor
pressure vessel support structures
2. Visual inspection of fuel assemblies for reuse
3. Inspection to determine fuel configuration in the reactor core
4. Inspection to determine shutdown margin of the reactor(ii) Reactor
cooling
1. Nondestructive inspection of Class I equipment (limited to the reactor coolingsystem equipment
system equipment, the same shall be applied in this subparagraph) and Class
III equipment (limited to reactor cooling system equipment, the same shall beapplied in this subparagraph) defined in Article 2 of the Technical Standards
on Structure, etc. of Nuclear Power Generation Equipment (Notification of
Ministry of International Trade and Industry No. 501, 1980) and support
structures thereof, and leak test of Class I and Class III equipment
2. Nondestructive inspection, leak test and actuation inspection of main steam
safety valves and main steam relief valves
3. Leak test and actuation inspection of main steam isolation valves
4. Nondestructive inspection of emergency core cooling system pumps and-- Provisional translation for information only --A3-59

major valves, and actuation inspection of emergency core cooling systems
Actuation inspection of emergency condenser systems
Nondestructive inspection of reactor core isolation cooling system pumps andmajor valves (limited to those relating to the advanced boiling water reactor),
and actuation inspection of reactor core isolation cooling systems
7. Actuation inspection of component cooling systems
1. Nondestructive inspection of Class I equipment (limited to measuring andcontrol system equipment, the same shall be applied hereinafter in thissubparagraph) and Class III equipment (limited to measuring and control
system equipment, the same shall be applied hereinafter in this subparagraph)defined in Article 2 of the Technical Standards on Structure, etc. of Nuclear
Power Generation Equipment and support structures thereof, and leak test ofClass I and Class III equipment
2. Nondestructive inspection of the control rod drive mechanism and control rod
drive hydraulic control system scram valves, and emergency control rod
insertion test of control rod drive hydraulic control systems
3. Actuation inspection of boric acid injection systems
4. Actuation inspection of safety preservation systems and reactor coolant
recirculation pump trip systems
Inspection of fuel holding function when power for fuel handling equipment is lost
1. Calibration and actuation inspection of the process monitoring equipment
2. Actuation inspection of standby gas treatment systems and performance test of
its filters
3. Actuation inspection of main control room standby circulation systems andperformance test of its filters
Actuation inspection of gaseous waste processing systems
1. Nondestructive inspection of Class III equipment (limited to the reactor
containment facility, the same shall be applied hereinafter in thissubparagraph) defined in Article 2 of the Technical Standards on Structure,etc. of Nuclear Power Generation Equipment and support structures thereof,
and leak test of Class III equipment
2. Leak rate test of the reactor containment facility
3. Leak test of the reactor building
4. Nondestructive inspection of major reactor containment isolation valves andactuation inspection of reactor containment isolation valves
5. Actuation inspection of reactor containment vacuum relief valves
6. Nondestructive inspection of reactor containment spray system pumps andmajor valves, and actuation inspection of the reactor containment spraysystem
7. Nondestructive inspection of major valves of the flammability control system
and actuation inspection of the flammability control system
1. Nondestructive inspection of the diesel engine, and actuation inspection andinspection to determine rated capacity of the diesel power generator
2. Inspection to identify charging condition of the direct current power supply
system5.
6.

(iii) Measuring andcontrol systemequipment(iv) Fuel equipment(v) Radiation
management
equipment(vi) Disposal equipment(vii) Reactor
containment
facility(vii) Emergency standby
power generation
device(iii)

In the case of power reactors (limited to pressurized water reactors) and associated facilities, matters indicated in theright row of the following table related to the licensee’s periodic inspection according to the type of electric structure
indicated in the left row of the said table;(The rest is omitted since the case of PWR is the same as that of BWR.)(iv)
In the case of steam turbines and power reactors (limited to boiling water reactors and pressurized water reactors) andassociated facilities (excluding emergency standby power generation devices), other matters related to licensee’s
periodic inspection that the Minister of Economy, Trade and Industry deems that it is necessary, in addition to thosedescribed in the preceding three subparagraphs; or(v)
In the case of steam turbines and power reactors (limited to boiling water reactors and pressurized water reactors) andassociated facilities (excluding emergency standby power generation devices), matters related to licensee’s periodic
inspection concerning overall performance at normal operation, in addition to those described in the preceding
subparagraphs.
Article 91. The time periods provided for in the ordinance of Ministry of Economy, Trade and Industry described in Article
54 of the Law shall be as follows.
(i)
For steam turbine belonging to nuclear power station, the time not earlier than one year but within 13 month after thedate when operation began or the date when the Periodic Inspection (defined in Article 54 of the Law) was completed.
(ii)
For items specified in the preceding article, the time not earlier than one year but within 13 month after the date when
operation began or the date when the Periodic Inspection was completed.
Article 92. The cases defined in the ordinance of Ministry of Economy, Trade and Industry described in the proviso of Article-- Provisional translation for information only --A3-60

54 of the Law shall be as follows.
(i)
The case that the Minister of Economy, Trade and Industry (or in the case of an electric structure for business use
related to the authority of No. 12 of the table in Article 8 of the ordinance, the director of the International Trade andIndustry bureau exercising such authority; the same applies in the next item) deems it unnecessary, based on the usage
situation, to perform an inspection at the time referred to in the preceding article, and has given approval, instructing
the time when the inspection should be performed.
(ii)
In the case that the Minister of Economy, Trade and Industry deems that, due to a disaster or other emergency, it
would be significantly difficult to perform an inspection at the time referred to in the preceding article, and has given
approval, instructing the time when the inspection should be performed.
Article 93. A person who intends to undergo the inspection referred to in Article 54, Paragraph 1 of the Law shall submit anapplication for the Periodic Inspection, using Form 61.
2. A person who undergoes the inspection referred to in Article 54, Paragraph 1 of the Law performed by a designatedorganization for inspection shall submit an application for the Periodic Inspection to the designated organization forinspection as required by that organization.
Article 93-4. The specific important electric structure provided in the ordinance of Ministry of Economy, Trade and Industry
described in Article 54, Paragraph 2 of the Law shall be any of steam turbines, nuclear reactors, reactor cooling systemequipment, measuring and control system equipment, fuel equipment, radiation management equipment, disposal equipment,
reactor containment facilities or emergency standby power generation devices.
2.The part of affairs, concerning the inspection conducted by the Organization in accordance with the provisions of Article 54,
Paragraph 2 of the Law, shall be those shown in the followings:(i)
Matters provided in Article 90-2, Subparagraph 1;(ii)
Matters provided in Article 90-2, Paragraph 2 excluding those provided in the followings;
A. Actuation inspection of the emergency core cooling system related to the reactor cooling system equipment,
B. Emergency control rod insertion test of the control rod drive hydraulic control system related to the measuring andcontrol system equipment,
C. Leak rate test of the reactor containment related to the reactor containment facility, and
D. Actuation inspection of the diesel power generator related to the emergency standby power generation device.
(iii) Matters provided in Article 90-2, Subparagraph 3 excluding for those provided in the followings;
A. Actuation inspection of the emergency core cooling system related to the reactor cooling system equipment,
B. Emergency control rod insertion test of the control rod drive system related to the measuring and control systemequipment,
C. Leak rate test of the reactor containment related to the reactor containment facility, and
D. Actuation inspection of the diesel power generator related to the emergency standby power generation device.
3. Irrespective of provisions of the preceding paragraph, when the Minister of Economy, Trade and Industry deems that it isnecessary to conduct inspections by himself, in relation to structure, material, etc. of the specific important electric structure,
the Minister of Economy, Trade and Industry shall conduct by himself the inspections relating to the specific importantelectric structure concerned.
4. When the Minister of Economy, Trade and Industry recognize necessary to conduct the inspections described in thepreceding paragraph, the Minister shall notify the Organization of it.
5. The Organization shall prepare an inspection instruction manual that defines methods of the inspections described in
Paragraph 2 and other necessary matters in accordance with the notification described in Article 93-2, Paragraph 2.
6. The notification, described in Article 54, Paragraph 3 of the Law, shall be made by letter specifying the following
particulars:(i)Name and address of the person who underwent inspections and, in the case of a juridical person, the name of its
representative;(ii)
Name of the power station to be installed with the specific important electric structure that underwent inspections;(iii) Date of inspections;(iv)
Place where the inspections were performed;(v)
Object of the inspections;(vi)
Methods of the inspections; and(vii) Results of the inspections.
Article 94. The electric structure provided in the ordinance of Ministry of Economy, Trade and Industry described in Article
55, Paragraph 1 of the Law shall be any of those shown in the followings. However those belonging to the emergency
standby power generation devices shall be excluded:(i) Steam turbine (limited to that belonging to a nuclear power station or that related to a power generation equipment of
which power is equal or more than 1,000kW).
2. The power reactor and associated facilities, specified in the ordinance of Ministry of Economy, Trade and Industry
described in Article 55, Paragraph 1 of the Law, shall be any of nuclear reactors, reactor cooling system equipment,
measuring and control system equipment, fuel equipment, radiation management equipment, disposal equipment, reactor
containment facilities, auxiliary boiler and emergency standby power generation devices.
Article 94-4-2. The specific electric structure for power generation by nuclear power as prime mover, which is defined in theordinance of Ministry of Economy, Trade and Industry described in Article 55, Paragraph 3 of the Law, shall be any ofvessels and pipes belonging to Class I equipment defined in Article 2 of the Technical Standards on Structure, etc. of Nuclear
Power Generation Equipment (excluding a joint and sealing portion such as a flange etc., the steam generator heat transfer
tube and pipe made of austenitic low carbon stainless steel for nuclear industry (limited to the material in which carbon-- Provisional translation for information only --A3-61

content is not more than 0.02% and of which breaking strength is not less than 520 N/mm2)) and core support structures(limited to core shrouds or shroud support rings).
2. As provided in the provisions of Article 55, Paragraph 3 of the Law, the evaluation shall be performed through the methods
indicated in the right row of the following table according to the matter indicated in the left row of the said table,
respectively.
Matters for Evaluation
Methods for Evaluation(i) When the electric structure will
Evaluations shall be performed for each electric structure
possibly become not in conformity
concerned in accordance with the following subparagraphs:
with the provisions of Article 9-2 of
1. Estimate the cause of any damage such as cracks, holes andthe Ordinance of Establishingothers (hereinafter referred to as “crack etc.”) identified at
Technical Standards for Nuclear Powerthe licensee’s periodic inspection. In addition, identify theGenerating Equipment (Ordinance of
shape and dimension of the crack etc.;
Ministry of International Trade and
2. Predict the development of the crack etc. during theIndustry No. 62, 1965, referred to aspredetermined time period, which shall be determined on the“the Ordinance”, in this subparagraph)basis of the identified shape and dimension of the crack etc.
described in the preceding subparagraph; and3. Determine when the electric structure will possibly become
not in conformity with the Ordinance indicated in the leftrow, when the crack etc. is assumed to develop as predicted.
(ii) Details of actions to be taken such as
In the case that any action such as repair is requested as a result of
repairthe evaluation performed through the methods for evaluation
indicated in the right row of the preceding subparagraph, the time,
scopes and methods for the action should be appropriate.
3. Descriptions of the record of the evaluation results described in Article 55, Paragraph 3 of the Law shall include thefollowing particulars:(i)Date of the evaluation;(ii)
Object of the evaluation;(iii) Method of the evaluation;(iv)
The evaluation results;(v)
Name of persons who performed the evaluation;(vi)
In the case that any action such as repair has been taken on the basis of the evaluation, details of the action;(vii) Organizations who implemented the evaluation;(viii) Process control for implementation of the evaluation;(ix)
In the case that any licensee collaborated in the evaluation, particulars concerning management of the licensee
concerned;(x)Particulars concerning management of the evaluation records; and(xi)
Particulars concerning education and training relating to the evaluation;
4. The record of the evaluation results described in Article 55, Paragraph 3 of the Law shall be retained until five years elapse
after the evaluated specific electric structure is disposed of.
5. The report of the evaluation results described in Article 55, Paragraph 3 of the Law shall be made on the particulars shownin Paragraph 3, Subparagraphs 1 through Subparagraphs 6 immediately after the evaluation for the said matters is completed.
(Rules for Office Work)
Article 104-2. The Organization shall define rules for conducting affairs of inspection etc. (which means a part of affairs
concerning inspections defined in Article 49, Paragraph 3, Article 51, Paragraph 5 and Article 54, Paragraph 2, and reviews
defined in Article 52, Paragraph 3 and Article 55, Paragraph 4, the same shall be applied, hereinafter) (hereinafter referred toas “rules for office work”), and shall submit it to the Minister of Economy, Trade and Industry before starting the activities
relating to the affairs of inspection etc. This shall be applied to its alteration also.
2. In the case that the Minister of Economy, Trade and Industry deems that the rules for office work submitted in accordancewith the preceding paragraph is not appropriate for conducting the affairs of inspections etc. properly and certainly, theMinister may order the Organization to alter the rules for office work.
3. Affairs to be specified in the rules for office work are provided in the ordinance of Ministry of Economy, Trade andIndustry.
(Person Who Performs the Affairs of Inspection etc.)
Article 104-3. The Organization, when conducting the affairs of inspection etc., shall make the person who has the certificate
specified in the ordinance of Ministry of Economy, Trade and Industry perform the affairs of inspection etc.
(Audit)Article 105. The Minister of Economy, Trade and Industry shall audit the business and accountings of general electricity
utilities and wholesale electric utilities every year.
(Collection of Reports)
Article 106. The Minister of Economy, Trade and Industry may request any person who establishes an electric structure forpower generation by nuclear power as prime mover (hereinafter referred to as a “electric structure for nuclear power
generation”), to the extent as necessary for the enforcement of the provisions of Article 39, Article 40, Article 47, Articles 49
through 52, Article 54 and Article 55, to make report or submit documents on the status of his business concerning fitness forsafety of the electric structure for nuclear power generation as specified in the government ordinance.
2. In addition to those specified in provisions of the preceding paragraph, in the case that the person who establishes the-- Provisional translation for information only --A3-62

electric structure for nuclear power generation has produced reports or submitted documents upon request as specified in theprovisions of the said paragraph, the Minister of Economy, Trade and Industry may request the contractors on maintenance ofthe electric structure for nuclear power generation concerned, to the extent as necessary for enforcement of the provisions ofArticle 39, Article 40, Article 47, Articles 49 through 52, Article 54 and Article 55, to make report or submit documents onnecessary matters if he deems that it is necessary to ensure fitness for safety of the electric structure for nuclear power
generation.
3. In addition to those specified in provisions of the Paragraph 1, the Minister of Economy, Trade and Industry may request
any electric utility, to the extent as necessary for the enforcement of the Law, to make report or submit documents on thestatus of his business or accountings, as specified in the government ordinance.
4. In addition to those specified in provisions of the Paragraph 1, the Minister of Economy, Trade and Industry may request
any person who establishes an electric structure for personal use or the designated investigation agency, to the extent as
necessary for the enforcement of the Law, to make report or submit documents on the status of his business or accountings, as
provided in the government ordinance.
5. The Minister of Economy, Trade and Industry may request the Organization, to the extent as necessary for the enforcementof the Law, to make report or submit documents on status of its business.
6. The Minister of Economy, Trade and Industry may request the designated safety management review agency or thedesignated inspection agency, to the extent as necessary for the enforcement of the Law, to make report or submit documentson the status of his business or accountings.
(Entry and Inspection)
Article 107. The Minister of Economy, Trade and Industry may make their officials, to the extent as necessary for theenforcement of the provisions of Article 39, Article 40, Article 47, Articles 49 through 52, Article 54 and Article 55, enter afactory or a place of business such as sales offices, business offices or others of any person who establishes electric structures
for nuclear power generation, fabricates fuel assemblies or performs welding of boilers or containments etc. (limited to thoserelated to electric structures for nuclear power generation), and inspect equipment such as electric structures for nuclear
power generation, books, documents and others.
2. In addition to the entry and inspection as provided in the preceding paragraph, the Minister of Economy, Trade andIndustry may make their officials, to the extent as necessary for the enforcement of the Law, enter a place of business such as
sales offices, business offices or others of any electric utility, and inspect status of his business or accountings, or equipment
such as electric structures, books, documents and others.
3. In addition to the entry and inspection specified in the preceding paragraph, the Minister of Economy, Trade and Industry
may make their officials, to the extent as necessary for the enforcement of the Law, enter a factory or a place of business suchas sales offices, business offices or others of any person who establishes electric structures for personal use or performs
welding of boilers or containments etc., and inspect equipment such as electric structures, books, documents and others.
4. The Minister of Economy, Trade and Industry may make their officials, to the extent as necessary for the enforcement of
the Law, enter any place where an electric structure for general use is established (excluding any place used as a residence),
and inspect the electric structure for general use.
5. The Minister of Economy, Trade and Industry may make their officials, to the extent as necessary for the enforcement of
the Law, enter any business office or place of business of the designated investigation agency, and inspect status of his
business, books, documents and others.
6. The Minister of Economy, Trade and Industry may make their officials, to the extent as necessary for the enforcement of
the Law, enter any business office or place of business of the Organization, and inspect status of his business, books,
documents and others.
7. The Minister of Economy, Trade and Industry may make their officials, to the extent as necessary for the enforcement of
the Law, enter any business office or place of business of the designated safety management review agency or any businessoffice of the designated inspection agency, and inspect status of its business, books, documents and others.
8. When officials make entrance in accordance with the provisions of the preceding paragraphs, they shall carry theiridentification cards with them and show them when requested by persons concerned.
9. The Minister of Economy, Trade and Industry may make the Organization conduct an entry and inspection as specified in
Paragraph 1 through Paragraph 3, when the Minister deems that it is necessary.
10. When the Minister of Economy, Trade and Industry makes the Organization conduct an entry and inspection inaccordance with the provisions of the preceding paragraph, the Minister shall make the order indicating the place of the entry
and inspection concerned and other necessary matters.
11. When the Organization conducted the entry and inspection as provided in the Paragraph 9 in accordance with the order
described in the preceding paragraph, the Organization shall report to the Minister of Economy, Trade and Industry of its
results.
12. When personnel of the Organization make entrance in accordance with the provisions of Paragraph 9, they shall carry
their identification cards with them and show them when requested by persons concerned.
13. The authority specified in the provisions of Paragraph 1 through Paragraph 7 shall not be construed as having been
granted for the purpose of criminal investigation.
(Order to the Organization)
Article 107-2. The Minister of Economy, Trade and Industry may make orders ad necessary to the Organization concerning
his business relating to affairs of inspection etc. or business of an entry and inspection specified in Paragraph 9 of thepreceding article, when the Minister recognize that it is necessary to ensure those business to be conducted appropriately.
(Report etc. to Nuclear Safety Commission)
Article 107-3. The Minister of Economy, Trade and Industry shall report to Nuclear Safety Commission quarterly of thelicensing, inspection and review activities performed in the preceding quarter relating to electric structures for nuclear power
generation provided in Article 47, Paragraph 1 and Paragraph 2, Article 49, Paragraph 1, Article 50-2, Paragraph 3, Article 51,-- Provisional translation for information only --A3-63

Paragraphs 1 and Paragraph 3, Article 52, Paragraph 3, Article 54, Paragraph 1 and Article 55, Paragraph 4, and shall takenecessary measures to ensure fitness for safety related to the electric structures for nuclear power generation, to obtain
opinions of Nuclear Safety Commission if the Minister deems that it is necessary.
2. In addition to the report in accordance with the preceding paragraph, the Minister of Economy, Trade and Industry shallreport to Nuclear Safety Commission of the status of enforcement of the Law for ensuring fitness for safety related to theelectric structures for nuclear power generation, as specified in the ordinance of Ministry of Economy, Trade and Industry.
(Collaboration with Nuclear Safety Commission for Investigation)
Article 107-4. Any person who establishes an electric structure for nuclear power generation or any contractors on
maintenance of an electric structure for nuclear power generation shall collaborate with Nuclear Safety Commission,
when the Commission conducts an investigation on matters related to the report in accordance with the provisions ofParagraph 1 or Paragraph 2 of the preceding article.

Power Station

Annexed Table 2 (related to Articles 62 and 65)
Type of Construction

Matters that Need Licensing(i) Construction for1. Establishment of a power station

establishment

excluding the followings:(1) Establishment of a hydraulicpower station;(2) Establishment of a thermal
power station;(3) Establishment of a fuel cell
power station;(4) Establishment of a solar cell
power station; and(5) Establishment of a wind power
station.

(ii) Construction for

Establishment of a power generation

alterationequipment excluding the followings:(1) Establishment of power(1) Establishment of a power

generation equipment

generation equipment ofhydraulic power station;(2) Establishment of a power
generation equipment ofthermal a power station;(3) Establishment of a power
generation equipment of fuelcell power station;(4) Establishment of a power
generation equipment of solar
cell power station; and(5) Establishment of a power
generation equipment of wind
power station.

-- Provisional translation for information only --A3-64

Matters that Need Prior Notification

(iii) Nuclear equipment
A. Nuclear reactors

1. Modifications of those related to a

1. Modifications of those related to aboiling water reactor type power

boiling water reactor type power

generation installation specified ingeneration installation (excluding

the followings:

those indicated in the middle row)

(1) Those accompanied by alterationof reactor type, rated thermalinternal structures.

power, excess reactivity,

2. Repair of those related to a boilingreactivity coefficient or

water reactor type power generation

moderator;

installation specified in the(2) Those relating to the reactor

followings:(1) Replacement of those related tocore;(3) Reactor reflector systems;

main body of reactor pressure(4) The main body of reactor

vessel (excluding the surveillancepressure vessels (excluding thetest specimen) or reactor pressure

surveillance test specimen);vessel associated structures (limited(5) Those relating to reactor
pressure vessel support

to those related to the reactor
coolant pressure boundary); and(2) Those that affect performances or

structures;(6) Those relating to reactor

strength of those related to thepressure vessel associatedreactor core (limited to core support

structures; andstructures), the main body of(7) Those relating to reactor

reactor pressure vessel (excludingpressure vessel internal

the surveillance test specimen),structures (limited to spargers,

reactor pressure vessel support

internal piping or in-core guidestructures, reactor pressure vesseltubes).

associated structures or reactor

2. Modifications of those related to apressure vessel internal structures

pressurized water reactor type(limited to spargers, internal piping,power generation installation or ain-core guide tubes).

sodium-cooled reactor type power

3. Repair of those related to a

generation installation specified in
the followings:(A list of equipment concerned is tobe followed hereinafter as is the casewith the boiling water reactor typepower generation installation, but it
is omitted and represented by thatof the boiling water reactor typepower generation installation.)

B. Reactor cooling system

related to reactor pressure vesselpressurized water reactor type power
generation installation or asodium-cooled reactor type power
generation installation specified in
the followings:(A list of equipment concerned
followed hereinafter as is the case forthe boiling water reactor type power
generation installation, but it is omitted
and represented by that of the boilingwater reactor type power generation
installation.)

Omitted.

Omitted.

Omitted.

Omitted.

D. Fuel equipment

Omitted.

Omitted.

E. Radiation management

Omitted.

Omitted.

equipment
C. Measuring and control
system equipment

equipment-- Provisional translation for information only --A3-65

F. Disposal equipment

Omitted.

Omitted.

G. Reactor containment

Omitted.

Omitted.

H. Ventilation stack

Omitted.

Omitted.

I.

Steam turbine

Omitted.

Omitted.

J. Auxiliary boiler

Omitted.

Omitted.

K. Fuel equipment that

Omitted.

Omitted.

Omitted.

Omitted.

(2) Transformer

Omitted.

Omitted.

(3) Voltage regulator or

Omitted.

Omitted.

(4) Condenser

Omitted.

Omitted.

(5) Electric power

Omitted.

Omitted.

Omitted.

Omitted.

Omitted.

Omitted.

(8) Breaker

Omitted.

Omitted.

(9) Battery (limiting toOmitted.

Omitted.

Omitted.

Omitted.

Omitted.

Omitted.

Omitted.

Omitted.

facility

belongs to the auxiliary
boiler
L. Smoke processing
facilities that belongs tothe auxiliary boiler

voltage phaseregulatorcondenser(6) Shunt reactor or
current-limiting
reactor(7) Frequency converteror rectifiers

those to be or has
been installed at anuclear power station)(10) Electronic power
inverter
2. Associated equipment(1) Control equipment tocontrol operation of apower station(2) Emergency standby
power generation
device (limiting tothat to be or has been
installed at a nuclear
power station)

Annexed Table 3 (related to Articles 63 and 66)
Type of Electric
Particulars to be Described-- Provisional translation for information only --A3-66

Appended documents (limited to(i)Structure

General descriptions

Power station

1. Name and location of thepower station (perfectname of municipality
shall be described)
2. Power of the power
station
5. In the case that the power
station is related to theClass II project provided
in Article 2, Paragraph 3of the Environmental
Impact Assessment Law(excluding specificproject), descriptions
indicating that the action
described in Article 4,
Paragraph 2 of the saidlaw (including the casewhere the said
subparagraph is appliedwith necessary
modifications toParagraph 4 of the said
article and Article 29,
Paragraph 2 of the saidlaw) has been taken-- Provisional translation for information only --Descriptions
according toequipment (limited tothose concerning
details of construction
related to license
application or
notification)

those concerning details of
construction related to license
application or notification)

Overview diagram for electric powertransmission
Descriptions indicating that theelectric structure for business use istechnically appropriate one inensuring smooth supply of electricity(limited to the electric structure forbusiness use related to power grid of
equal or more than 170kV that isdevoted to a general electric utility)
In the case that the power station
related to Class II project provided in
Article 2, Paragraph 3 of theEnvironmental Impact Assessment
Law (excluding specific project),
descriptions concerning the action
described in Article 4, Paragraph 3,
Subparagraph 2 of the said law(including the case where the said
subparagraph is applied withnecessary modifications to Paragraph
4 of the said article and Article 29,
Paragraph 2 of the said law)
In the case that an smoke generating
facility described in Article 2,
Paragraph 2 of the Air Pollution
Control Law is established,descriptions concerning its smoke
In the case that an specific facility
described in Article 2, Paragraph 1 of
the Noise Control Law is establishedin the area designated as provided in
Article 3, Paragraph 1 of the said law,descriptions concerning its noise
In the case that an specific facility
described in Article 2, Paragraph 1 of
the Vibration Control Law isestablished in the area designated asprovided in Article 3, Paragraph 1 ofthe said law, descriptions concerning
its vibration
In the case that an specific facility
described in Article 2, Paragraph 2 of
the Law Concerning Special
Measures against Dioxins isestablished, descriptions concerning
dioxins
In the case relating to a restrictedconstruction work carried out in asteep slope collapse risk area,
descriptions concerning preventive
actions against collapse of the steep
slope (which means one provided in
Article 2, Paragraph 1 of the Law
concerning Prevention of Disasters
due to Collapse of Steep Slope, thesame shall be applied hereinafter) in
the area concerned
Contour map specifying outline of the

A3-67

1. Nuclear reactors

Omitted.

Omitted.

power station
Floor plans and cross sectional
drawings specifying configuration ofmajor equipment
Single-line diagrams (descriptions ofground wires (excluding instrumenttransformer) shall include type ofwire, size and class of grounding)Document that fully describes detailsof new technology
Omitted.

2. Reactor coolingsystem equipment
3. Measuring andcontrol systemequipment
4. Fuel equipment
5. Radiation
management
equipment
6. Disposal
equipment
7. Reactor
containment
facility
8. Ventilation stack
9. Steam turbine
10. Auxiliary boiler
11. Fuel equipmentthat belongs to a
auxiliary boiler

Omitted.

Omitted.

Omitted.

Omitted.

Omitted.

Omitted.

Omitted.
Omitted.

Omitted.
Omitted.

Omitted.
Omitted.

Omitted.

Omitted.

Omitted.

Omitted.

Omitted.

Omitted.

Omitted.
Omitted.
Omitted.
Omitted.

Omitted.
Omitted.
Omitted.
Omitted.

Omitted.
Omitted.
Omitted.
Omitted.

Omitted.

Omitted.

Omitted.

12.Smokeprocessing
facilities thatbelongs to
auxiliary boiler(4) Ordinance of Establishing Technical Standards for Nuclear Power Generation Equipment (Excerpt)(Ordinance of Ministry of International Trade and Industry No. 62, June 15, 1965)
Latest Revision: Ordinance of Ministry of Economy, Trade and Industry No. 102, September 22, 2003
(Definitions)
Article 2. Terminology used in this Ministerial Order is defined in the following respectively:(vii) "Control zones" means the areas within a nuclear power station where there is a hazard that the dose from externalradiation may exceed the limit specified separately by the ministerial notification, and that the concentration ofradioactive material in the air (excluding those included in the air or water naturally, the same shall be applied
hereinafter) may exceed the level specified separately by the ministerial notification or that the density of radioactive
material on the surface of objects contaminated by radioactive material may exceed the level specified separately by
the ministerial notification; and(viii) "Environmental monitoring area" means those areas surrounding control zones, the outside of which there is no
possibility of the dose exceeding the limit of the dose specified separately by the ministerial notification.
(Instrumentation Devices)
Article 20. Nuclear power station shall be equipped with the devices directly to measure the followings. In this case, when it
is difficult to measure directly, the said devices may be replaced with devices indirectly to measure the followings;(vii) The concentration of radioactive materials in ventilation gases at the outlets of ventilation tubes or at locations nearthose outlets;(viii) The concentration of radioactive materials in discharge at the outlets of draining points or at locations near those-- Provisional translation for information only --A3-68

outlets; and(x) The dose equivalent rates in control zones and zones adjacent to monitoring areas.
(Alarm Devices, Etc.)
Article 21. Nuclear power station shall be equipped with automatic alarming devices through reliably detecting thosefollowing events; a danger of remarkable obstacles in operation of reactor caused by loss of function of its components or
mis-operation, a remarkable increase in the concentration of radioactive materials referred to in Subparagraph (vii) of thepreceding article or in the dose equivalent rate referred to in Subparagraph (x) of the said article, a danger of remarkable leakof radioactive liquid waste form facilities for processing or storing radioactive waste in liquid form (excluding that in gaseous
form, the same shall be applied, hereinafter).
(Biological Shields)
Article 27. Biological shields shall be installed at places inside nuclear power station where it is necessary to prevent
radiation hazards due to external radiation.
(Ventilation Facilities)
Article 28. Ventilation facilities shall be installed at places inside a nuclear power station where it is necessary to prevent
radiation hazards due to air polluted with radioactive materials.
(Prevention of Contamination by Radioactive Materials)
Article 29. In buildings of nuclear power stations that are frequently accessed by people, the surfaces of walls, floors, andother portions that could become contaminated with radioactive materials, and the portions which could be touched by people,
shall be such as to allow easy removal of contamination by radioactive materials.
(Waste Processing Equipment, Etc.)
Article 30. In nuclear power stations, equipment must be installed for the processing of radioactive waste.

(5) Technical Standards on Dose Equivalent, etc. due to Radiation Relating to Nuclear Power Generation
Equipment (Excerpt)(Notification No. 188 Issued by Ministry of Economy, Trade and Industry, March 21, 2001)(Dose, Etc. Related to Control Zones)
Article 1.
Article 2 and Article 11 of the Notification, issued by Ministry of Economy, Trade and Industry No.187, 2001
(Notification for Dose Equivalent Limits on the Basis of the Rules for Commercial Power Reactor, hereinafter referred to as“the Notification”), shall apply to dose from external radiation, concentrations of radioactive materials in air, orconcentrations of radioactive materials on the surfaces of objects contaminated with radioactive materials specified in theprovisions of Article 2, Subparagraph (vii) of the Ordinance of Establishing Technical Standards for Nuclear Power
Generation Equipment (hereinafter referred to as the "Ministerial Order"),.
(Dose Limits Related to Environmental Monitoring Areas)
Article 2.
The provisions of Articles 3 and 11 of the Notification shall also apply to dose limits specified in the provisionsof Article 2, Subparagraph (viii) of the Ministerial Order.
(Concentrations of Radioactive Materials Outside Environmental Monitoring Areas)
Article 3.
The provisions of Article 9 of the Notification shall also apply to the concentrations of radioactive materials in
the air outside environmental monitoring areas and in the water at the boundaries with environmental monitoring areas,
specified in the provisions of Article 30, Paragraph 1, Subparagraph (i) of the Ministerial Order.

3.10. Basic Law on Emergency Preparedness(1) Basic Law on Emergency Preparedness (Excerpt)(Law No. 223, November 15, 1961)
Latest Revision: Law No. 99, May 31, 2000
(Objectives)
Article 1. This law is a provision for the establishment of necessary disaster countermeasures systems through the National
Government, local governments and other public agencies to protect the national land, and the lives, health, and assets of thecitizens from disaster, and clarifies the parties responsible for the same. It also specifies the principles regarding preparationof disaster countermeasures plans, disaster prevention, disaster emergency countermeasures, financial measures for disasterrecovery and disaster countermeasures, and fundamentals of other necessary disaster countermeasures, thereby contributing
to the development And promotion of comprehensive and systematic disaster countermeasures administration to maintainsocial order and ensure public welfare.
(Definition)
Article 2. The terminology used in this law is defined in the following respectively:(i) Disaster: Disaster means damage due to wind-storm, heavy rainfall, heavy snowfall, flood, high tide, earthquake,tsunami, volcanic eruption and other abnormal natural phenomena, or large fire and/or explosion, and other causes
specified in government ordinances according to the disaster level.
(Responsibility of the National Government)
Article 3.
The National Government shall be responsible for taking all possible steps with respect to disastercountermeasures by mobilizing all of its organizations and functions, in view of its mission to protect the national land, andlives, health, and assets of citizens from disaster.
2. In order to perform the responsibility referred to in the preceding paragraph, the National Government is to prepare a-- Provisional translation for information only --A3-69

plan that should be the bases of disaster prevention, disaster emergency countermeasures, and disaster recovery, execute thesaid plan in accordance with the legislation, make promotion and overall coordination of the affairs or activities handled by
the local governments, designated public agencies, and designated local public agencies etc., and rationalize the bearing ofexpenses in connection with disasters.
3. In performing the assigned duties, the designated administrative agencies and designated local administrative agencies
have to cooperate each other to ensure the full performance of the responsibility of the National Government referred to in
the Paragraph 1.
4. The chiefs of the designated administrative agencies and designated local administrative agencies shall recommend,
instruct, advise, and take other adequate measures for the relevant prefectures or municipalities with regard to their duties sothat the preparation and execution of the local disaster countermeasures plans in accordance with the provisions of this Law
should be performed smoothly by the relevant prefectures and municipalities.
(Responsibility of Prefectures)
Article 4. In order to protect the region of the prefectures, and the lives, health, and assets of the residents of the relevant
prefectures from disaster, the governments of prefectures shall have a responsibility, by the cooperation of the related
agencies and other local governments, to prepare disaster countermeasures plans with regard to the regions of the relevant
prefectures, execute the same in accordance with the regulations, assist the municipalities and designated local publicagencies within the region in the performance of their duties and activities for disaster countermeasures, and make an overall
coordination.
2. Agencies of prefectures shall cooperate each other in the performance of their assigned duties so that the responsibility of
the governments of prefectures referred to in the preceding paragraph should be fully accomplished.
(Responsibility of Municipalities)
Article 5. Being bases of local governments, the municipal governments shall, prepare plans for disaster countermeasures inregard to the regions of the relevant municipalities with cooperation of the related agencies and other local governments, andshall execute the same in accordance with the legislation on their own responsibility, in order to protect the regions of therelevant municipalities, and the lives, health, and assets of the residents of the relevant municipalities from disaster.
2. The mayors of municipalities shall make efforts to develop such organizations as fire fighting agencies and flood control
squadrons, and enrich the organizations established in public organizations aiming for disaster countermeasures within theadministrative territory of the relevant municipalities and voluntary organizations of residents for disaster countermeasuresestablished by the spirit of neighbors cooperation (referred to as “voluntary disaster countermeasures organizations” in
Article 8, Paragraph 2), and make full use of the functions of municipalities, in order to accomplish the responsibility referred
to in the preceding paragraph.
3. In performing the assigned duties, municipal agencies such as fire fighting agencies and flood control squadrons shallcooperate each other so that the responsibility of municipalities provided for in the paragraph 1 should be fully accomplished.
(Responsibility of Designated Public Agencies and Designated Local Public Agencies)
Article 6. The designated public agencies and designated local public agencies shall prepare plans for disastercountermeasures with regard to their respective duties, execute the same in accordance with the legislation, and shall be
responsible for cooperating the relevant prefectures and municipalities in relation to their duties, so that the preparation andexecution of disaster countermeasures plans in accordance with the provisions of this Law should be conducted smoothly by
the National Government as well as governments of prefectures and municipals.
2. In view of the public nature of their duties or the public interest, the designated public agencies and designated local
public agencies have to contribute to disaster countermeasures through their respective duties.
(Establishment of Central Disaster Prevention Council and Assigned Duties)
Article 11. The Central Disaster Prevention Council shall be established in the Cabinet's Office.
2. The Central Disaster Council shall be responsible for the following matters:(i)
To prepare the basic plan of disaster countermeasures and promote the execution of the same;(ii)
To prepare plans regarding emergency measures and promote the execution of the same on the occasion of emergency
disasters;(iii) To deliberate important issues regarding disaster countermeasures in response to an inquiry from the Prime Minister;and(iv)
The affairs placed under its authority in accordance with the provisions of the legislation, aside from the above items.
4. The Prime Minister shall submit the following matters to the Central Disaster Prevention Council for deliberation:(i)
Basic policies on disaster countermeasures;(ii)
Important items regarding overall coordination of disaster countermeasures;(iii) General principles on emergency measures needed temporarily on the occasion of emergency disasters;(iv)
Proclamation of emergency situation of disaster; and(v)
Other important matters relating to disaster countermeasures to be deemed necessary by the Prime Minister.
(Organization of the Central Disaster Prevention Council)
Article 12. The Central Disaster Prevention Council shall consist of a chairman and council members.
2. The chairman shall be the Prime Minister.
(Disaster Countermeasure Headquarters)
Article 23. Governors of prefectures or mayors of municipals may establish a disaster countermeasure headquarters
in accordance with the disaster countermeasures plans of prefectures or municipals when the above is deemednecessary to enhance disaster countermeasures when a disaster has occurred or is likely to occur in the jurisdiction of
the said prefectures or municipalities.
2. The head of the disaster countermeasures headquarters shall be the general manager of the disaster countermeasures
headquarters, who shall be the governor of prefecture or the municipal mayor.
(Establishment of Emergency Disaster Countermeasures Headquarters)-- Provisional translation for information only --A3-70

Article 24. When an emergency disaster occurs, in view of the scale and other circumstances whereof a special
necessity is recognized in order to enhance disaster emergency countermeasures, the Prime Minister may establish
the Emergency and Disaster Countermeasures Headquarters in the Prime Minister's Office on a temporary basis
regardless of the provisions of National Government Organization Law, Article 40, Item 2.
(Organization of Emergency and Disaster Countermeasures Headquarters)
Article 25. The head of the Emergency and Disaster Countermeasures Headquarters shall be the General Manager ofthe Headquarters and shall be a state minister.
(Establishment of Urgency and Disaster Countermeasures Headquarter)
Article 28-2. When an extraordinary and intense emergency disaster occurs, and a special necessity is recognized inorder to enhance temporary damage restoration measures, the Prime Minister may, subject to the approval of the
Cabinet Council, establish the Urgency and Disaster Countermeasures Headquarters in the Prime Minister's Office ona temporary basis regardless of the provisions of National Government Organization Law, Article 8, Item 3.
(Organization of Urgency and Disaster Countermeasures Headquarters)
Article 28-3. The head of the Urgency and Disaster Countermeasures Headquarter shall be the General Manager ofthe Headquarters and shall be the Prime Minister. (or the state minister designated by it in advance in the case that
there are unavoidable circumstances under which the Prime Minister can not assume the position.)(Preparation and Official Announcement of the Basic Plan of Disaster Countermeasures)
Article 34. The Central Disaster Prevention Council shall prepare the Basic Plan of Disaster Countermeasures;
examine the same, taking the result of scientific research on disaster and disaster prevention and the situations ofprevious disaster as well as the effect of the disaster emergency countermeasures applied thereto into consideration
on an annual basis; and shall revise the same when it is deemed necessary to do so.
Article 35. The Basic Plan of Disaster Countermeasures shall cover the followings;(i)Comprehensive, long-term planning regarding disaster countermeasures;(ii)
Matters requiring stress in the plan of disaster countermeasures and the local disaster countermeasures plan; and(iii) Matters that shall be the standards for the preparation of the plan of disaster countermeasures and local disastercountermeasures and shall be recognized as necessary by the Central Disaster Prevention Council, aside from thosereferred to in the preceding items.
(Plan of Disaster Countermeasures of the Designated Administrative Agencies)
Article 36. The chiefs of the designated administrative agencies shall prepare the plan of disaster countermeasures in
conjunction with the assigned duties in accordance with the Basic Plan of Disaster Countermeasures, shall examine
the same on an annual basis, and shall revise the same when it is deemed necessary to do so.
(Local Disaster Countermeasures Plans of Prefectures)
Article 40. Disaster countermeasures councils of prefectures shall prepare disaster countermeasures plans of theirprefectures in conjunction with the jurisdiction of the relevant prefectures in accordance with the Basic Plan ofDisaster Countermeasures, shall examine the same on an annual basis, and shall revise the same when deemednecessary. In this instance, the relevant local disaster countermeasures plans of prefectures shall not be contrary to
the plan of disaster countermeasures.
(Municipal Local Disaster Countermeasures)
Article 42. Municipal disaster countermeasures councils (or mayors of municipals of the relevant municipalities
where a municipal disaster countermeasures council is not established; the same would apply hereunder in thisarticle) shall prepare municipal local disaster countermeasures plans in conjunction with the jurisdiction of the said
municipalities in accordance with the Basic Plan of Disaster Countermeasures, examine the same on an annual basis,and shall revise the same when deemed necessary. In this case, the relevant municipal local disaster countermeasuresplans shall not be contrary to plans of disaster countermeasures or local disaster countermeasures plans of prefecturesof the prefectures containing the relevant municipalities within their jurisdiction.
(2) Ordinance for the Enforcement of the Basic Law on Emergency Preparedness (Excerpt)(Government Ordinance No. 288, July 9, 1962)
Latest Revision: Ordinance No.553, December 27, 2000
(Causes Specified by the Government Ordinance)
Article 1. The causes specified under Item 1, Article 2 of the Basic Law on Disaster Countermeasures (hereinafter referred toas "the Law") shall be those large-scale accidents involving the release of a large amount of radioactive materials, the sinking
of a vessel resulting in heavy casualties, and the like.

(3) Basic Plan for Emergency Preparedness (Summary)
Volume 10. “Nuclear Emergency Response”(Central Emergency Prevention Council: May 2000)
1. Preface- Each body decides that countermeasures are taken so that it can respond to all the situations assumed, and establishes
systems, which can cope with them even when an unexpected situation occurs.
- The emergency preparedness guideline " Emergency Preparedness of Nuclear Installations", defined by the Nuclear Safety
Commission in special and technical items should be respected.
2. Emergency Prevention(1) Collection of information, Establishment of communication systems- The National Government, local governments, nuclear business operators, etc. collect information even in nights and-- Provisional translation for information only --A3-71

holidays in order to expect the perfect in nuclear emergency prevention and establish communication systems.
- The National Government and local governments establish and maintain a leased communication line network.
(2) Establishment of emergency response systems- The National Government (Cabinet Office) establishes and maintains the operation center equipped with required
machinery and materials.
- Regulatory ministries and offices establish and maintain the operation center equipped with required machinery andmaterials such as an emergency speedy radioactivity influence prediction system (hereinafter referred to as "SPEEDI
network system"), an emergency response support system (hereinafter referred to as "ERSS").
- The National Government, local governments, nuclear business operators, etc. establish emergency personnel gatheringsystems.
- The National Government establishes the Nuclear Emergency Response Headquarter and the Local Nuclear Emergency
Response Headquarter immediately after the declaration of a nuclear emergency situation. Moreover, the National
Government specifies a countermeasure facility beforehand where related staff of the National Government, local
governments, and nuclear business operators, etc. meet, share information and carry out emergency situation
countermeasures.
- The Nuclear Safety Commission establishes emergency gathering systems such as an emergency technical advice system,
etc.
- The National Government, public institutions, nuclear business operators, etc. establish an emergency monitoring system.
- The National Government establishes a specialist dispatch system.
- The National Government defines beforehand the transfer measures of necessary personnel to the Local Nuclear
Emergency Response Headquarters, etc.
- The local governments make a plan concerning evacuation and guidance beforehand, and make known widely to residents
in everyday life about evacuation places, the evacuation methods, etc.
- The National Government and local governments establish the emergency medical dispatch system for emergency medical
activities.
(3) Emergency preparedness drills, training and spread of knowledge of emergency preparedness- The National Government, local governments, nuclear business operators, etc. carry out practical training.
- The National Government, local governments and nuclear licensees complete and reinforce trainings of emergency
prevention personnel.
- The National Government and local governments make efforts in the spread and education of knowledge of emergency
preparedness to residents.
(4) Promotion of the research about emergency prevention, etc.
- The National Government makes efforts in promotion of the technology and research of nuclear emergency
prevention.
3. Emergency Response(1) Notifications of specific event occurrence information- A nuclear business operator notifies the Official Residence (Cabinet Office), the Ministry of Economy, Trade and Industry,
the local government and the Senior Specialist for Nuclear Emergency etc. within 15 minutes after a specific event
discovery or receipt of a report of discovery.
- A local government notifies the Senior Specialist for Nuclear Emergency, when the numerical detection value, whichshould be notified as a specific event occurrence, is discovered in a monitoring post. The Senior Specialist for Nuclear
Emergency directs to check the situation of the installation to the nuclear business operator and reports the result to the
Ministry of Economy, Trade and Industry and the local government.
(2) Reports of the emergency operator activity information, damage information, etc. after a specific event occurrence- A nuclear business operator reports periodically situation of the installation, situation of emergency response activities of
the nuclear business operator and the situation of the Emergency Response Headquarters, situation of damage, etc. to the
Official Residence (Cabinet Office), the Ministry of Economy, Trade and Industry, the local government, the Senior
Specialist for Nuclear Emergency, etc.
- The National Government holds related ministries and government offices emergency response connection meeting and alocal emergency response connection meeting consisting of related bodies.
- The Ministry of Economy, Trade and Industry directs to the Senior Specialist for Nuclear Emergency to collectinformation at the spot and to perform connection, adjustment, etc. among the nuclear business operator, the local
government, the local emergency response connection meeting, etc.
(3) Connection of the emergency response activity information and emergency information after a declaration of nuclear
emergency situation.
- Local Nuclear Emergency Response Headquarter, specific public institutions, local governments of the emergency
response enforcement zone, specific district public institutions, the nuclear business operator and other relatedorganizations share continuously required information. Moreover, each organization performs adjustment required about
the emergency response.
(4) Activity for the early grasp of radioactivity influence- A local government strengthens monitoring at ordinary times, when a report of specific event occurrence is received froma nuclear business operator.
- While the National Government predicts the state of nuclear reactor installation etc. by ERSS, it carries out radioactivity
influence prediction by SPEEDI network system, and connects information required for enforcement of emergency
response to the local government, etc.
(5) Response after the declaration of nuclear emergency situation- The Prime Minister establishes the Nuclear Emergency Response Headquarter, which makes himself the director general.
-- Provisional translation for information only --A3-72

(The deputy director-general is the Minister Specializing in Safety Regulation.)- The Nuclear Emergency Response Headquarter Director establishes the Local Nuclear Emergency Response Headquarter.
- The Local Nuclear Emergency Response Headquarter succeeds quickly office works of the local emergency responseconnection meeting.
- The director of the Local Nuclear Emergency Response Headquarter is the vice minister of the ministries and government
offices specializing in safety regulation.
- The Local Nuclear Emergency Response Headquarter organizes the Joint Council for Nuclear Emergency Response inlocal emergency response facility with the emergency response headquarters (or local response headquarter) of prefecturesand municipal governments that have jurisdiction of enforcement zone of emergency response. The Council is constituted
with director of the Local Nuclear Emergency Response Headquarter, each emergency response headquarters ofprefectures and municipal governments, specification public institutions and the nuclear business operator, etc..
- Roles and assignments of the Joint Council for Nuclear Emergency Response are discussed and fixed by relatedorganizations beforehand. In the Joint Council for Nuclear Emergency Response, the work group of a small number ofpeople is selected beforehand, which defines the response policies in the spot in an emergency.
- The Nuclear Safety Commission calls an emergency technical advice organization immediately, sends a member of the
Nuclear Safety Commission and a member of the emergency response investigation committee specified beforehand to thespot when a report of specific event occurrence is received from ministries and government offices for safety regulation.
- The Nuclear Safety Commission performs technical advice about emergency response to the Nuclear Emergency Response
Headquarter director.
(6) Emergency response activity- The Self-Defense Forces dispatches a corps for emergency.
- The local governments carry out response activities of evacuation guidance of residents etc., shipment regulation ofcontaminated food, ingestion restriction of food and drink, stable iodine-tablet recipe directions, etc. if needed.
- The local governments, the Self-Defense Forces, etc. carry out rescue and first aid activities. The National Police Agency
and the Fire Protection Agency carry out measures for wide area aids, such as sending of a wide area rescue team and an
emergency fire protection rescue team respectively, if needed.
- The emergency exposure medical treatment team consisting of the medical personnel of the National Institute ofRadiological Sciences, National Hospitals, and attached hospitals of National Universities etc. carries out medical
activities at the spot.
- The Nuclear Emergency Response Headquarter, the Local Nuclear Emergency Response Headquarter, specificgovernmental agencies, specific public institutions, local governments, and nuclear business operators offer exact and fine
information.
4. Emergency Restoration- When recognizing that it becomes unnecessary to carry out emergency response, the Prime Minister hears opinions of the
Nuclear Safety Commission, and declares release of a nuclear emergency situation.
- Local governments cancel various restriction measures based on investigation of the area by environmental
monitoring etc. and judgments of specialists sent by the National Government and emergency response
investigation committee of the Nuclear Safety Commission, etc.

3.11. Special Law of Emergency Preparedness for Nuclear Disaster(1) Special Law of Emergency Preparedness for Nuclear Disaster (Excerpt)(Law No. 156, December 17, 1999)(Purpose)
Article 1. In view of the particularity of nuclear disaster this Law stipulates the responsibilities of nuclear business operatorsfor nuclear disaster prevention and special measures such as the issue of the Notification of Activating Nuclear Emergency
Organization, the establishment of a Nuclear Disaster Countermeasures Headquarters, the implementation of immediate
emergency countermeasures, and other issues related to nuclear disasters; and tightens countermeasures against nuclear
disasters in conjunction with the Law for the Regulations of Nuclear Source Material, Nuclear Fuel Material and Reactors(Law 57-166, hereinafter referred to as "LRNR"), the Basic Law on Disaster Countermeasures (Law 61-223), and other lawson the prevention of nuclear disasters, with the ultimate goal of protecting the life, body and property of national from hazard
in the event of nuclear disasters.
(Duties of nuclear business operators)
Article 3. In accordance with the provisions of this Law and related laws, nuclear business operators are obliged to take thesafest measures to prevent the occurrence of nuclear disasters (including the probability of a nuclear disaster), measures toprevent the propagation of nuclear disasters and measures for restoration there from.
(Duties of the National Government)
Article 4. In accordance with the provisions of this Law and related laws, the National Government shall take measuresnecessary for the implementation of immediate emergency countermeasures including the establishment of a Nuclear
Disaster Countermeasures Headquarters, provision of necessary instructions to local authorities, and for the implementationof nuclear disaster prevention countermeasures and ex-post-facto countermeasures of nuclear disasters, in order to fulfill its
obligations as prescribed in Article 3, Paragraph 1 of the Basic Law on Disaster Countermeasures.
2. The chiefs of designated administrative agencies (or the designated administrative agency itself, if a committee orcouncil system agency; also applies to the succeeding provisions; the same shall apply hereinafter except for Article 17,
Paragraph 6, Clause 3 and Article 20, Paragraph 3) and of designated local administrative agencies shall provide-- Provisional translation for information only --A3-73

recommendations and advice to local authorities and take appropriate measures with respect to assigned duties in their charge,
in order to allow smooth execution of nuclear disaster prevention countermeasures, immediate emergency countermeasures,and ex-post-facto countermeasures of nuclear disasters by local authorities, as stipulated in this Law.
3. The competent Minister shall properly exert competencies stipulated in this Law, instruct and advise nuclear business
operators, and take appropriate measures, in order to allow smooth implementation of nuclear disaster prevention
countermeasures, immediate emergency countermeasures, and ex-post-facto countermeasures of nuclear disasters by nuclear
undertakes in accordance with the provisions in this Law.
(Duties of local authorities)
Article 5. In accordance with the provisions of this Law and related laws, local authorities shall fulfill their duties concerning
nuclear disasters as prescribed in Article 4, Paragraph 1 and Article 5, Paragraph 1of the Basic Law on Disaster
Countermeasures, by taking measures necessary for the implementation of nuclear disaster prevention countermeasures,
immediate emergency countermeasures, and ex-post-facto countermeasures of nuclear disasters.
(Disaster prevention work plan of nuclear business operators)
Article 7. In accordance with the provisions of the order of the competent Ministry, at each establishment of nuclear
enterprise, nuclear business operators shall prepare a disaster prevention work plan of nuclear business operators with respect
to nuclear disaster prevention countermeasures, immediate emergency countermeasures, ex-post-facto countermeasures ofnuclear disasters, and other measures necessary to prevent the occurrence and propagation of nuclear disasters and to restore
there-from. Once prepared, these plans shall be reviewed annually and revised as necessary, and shall not infringe upon theregional disaster prevention plan as prescribed in Article 2 Clause 10 of the Basic Law on Disaster Countermeasures and thepetroleum-industry-complex disaster prevention plan as prescribed in Article 31 Paragraph 1 of the Law on Disaster
Prevention Plans at Petroleum Industry Complexes.(Both disaster prevention plans are referred to together as “the regionaland other disaster prevention plans” in the succeeding Paragraph.)
3. When a nuclear business operator has prepared or modified a disaster prevention work plan in accordance with theprovisions of Paragraph 1, it shall immediately report this fact to the competent Minister and release essential details of the
preparation or the modification to the public.
4. When a nuclear business operator is deemed to be in violation of the provisions of Paragraph 1, or its disaster prevention
work plan of nuclear business operators is not deemed sufficient to prevent the occurrence or propagation of nuclear disasters
involving the establishment of nuclear enterprise, the competent Minister may order the nuclear business operator to modify
the plan or prepare the alternative to it.
(Nuclear disaster prevention organization)
Article 8. Nuclear business operators shall organize a nuclear disaster prevention organization at each of their establishments.
(Management personnel for nuclear disaster prevention)
Article 9. Nuclear business operators shall appoint management personnel for nuclear disaster prevention at each of theirestablishments to manage the nuclear disaster prevention organization.
(Notification duty of management personnel for nuclear disaster prevention)
Article 10. When the management personnel for nuclear disaster prevention detect or are notified of the detection, by meansof the methods designated by government ordinance, of radiation doses exceeding the level designated by government
ordinance, or of other events designated by government ordinance near the boundary of the area of the establishment of
nuclear enterprise, they shall immediately report the finding to the competent Minister, competent governor of prefecture,competent mayor of the municipality, and governors of the related neighboring local governments (or if the event occurs
during transportation outside an establishment, to the competent Minister and to the governor of prefecture and mayor of themunicipality who have jurisdiction over the area in which the event occurred, as stipulated by the order of the competent
Ministry and the disaster prevention plan of nuclear business operators. Upon being so notified, the competent governor ofprefecture and governors of the related neighboring local governments shall report the event to the mayors of the related
surrounding municipalities.
2. The governor of prefecture or the mayor of the municipality, who has been notified in accordance with the prescription in
the former part of the preceding Paragraph, may request the competent Minister to dispatch personnel who have special
knowledge to assess the situation in accordance with the provision of the government ordinance, at which time the competent
Minister shall dispatch personnel who are deemed appropriate.
(Designation of the Off-site Centers)
Article 12. For each establishment of nuclear enterprise, the competent Minister shall designate facilities as bases for
immediate emergency countermeasures taken by the persons as prescribed in Article 26 Paragraph 2. These facilities(hereinafter referred to as the "Off-site Center") shall be located in an area of the prefecture where the relevant establishment
is located, and meet other requirements as prescribed by the order of the competent Ministry.
(Disaster prevention exercise plan by the National Government)
Article 13. A disaster prevention exercise prescribed in Article 48, Paragraph 1 of the Basic Law on Disaster
Countermeasures, as applicable after amended as per the provisions of Article 28, Paragraph 1, (excluding those executed byresponsible personnel for disaster prevention as designated in the relevant Paragraph in accordance with the provisions of adisaster prevention plan or a disaster prevention work plan of nuclear business operators), shall be executed according to plan
prepared by the competent Minister in accordance with the order of the competent Ministry.
(Notification of Activating Nuclear Emergency Organization)
Article 15. When a nuclear emergency situation as prescribed in the succeeding paragraphs is deemed to have occurred, thecompetent Minister shall immediately submit to the Prime Minister both drafts of notification as prescribed in the succeeding
Paragraph and instructions as per the provisions of Paragraph 3, in addition to provide necessary information on the situation.
(i)
The radiation dose reported to the competent Minister in accordance with the former part of the provisions of Article
10, Paragraph 1 or the radiation dose detected by the methods and radiation-measuring devices designated in thegovernment ordinance exceeds the threshold for radiation doses in abnormal level designated in the government-- Provisional translation for information only --A3-74

ordinance.
An event designated in the government ordinance as indicating the occurrence of a nuclear emergency situation, in
addition to the events prescribed in the preceding Clause.
2. Upon receipt of the report and drafts prescribed in the preceding Paragraph, the Prime Minister shall immediately issue
an official announcement (hereinafter referred to as "Notification of Activating Nuclear Emergency Organization")concerning a notification of a nuclear emergency situation and the items outlined in the succeeding clauses.
(i)
Areas where immediate emergency countermeasures should be taken(ii)
Summary of the nuclear emergency situation.
(iii) Issues exhaustively notified to residents, visitors, and public and private groups in the areas designated in Clause (a)(hereinafter referred to as "residents"), in addition to the information in the preceding Clause (1) and Clause (2).
3. Upon receipt of the information and drafts prescribed in Paragraph 1, the Prime Minister shall immediately provide
instructions and/or recommendations of refuge by evacuation or sheltering to the mayors of municipalities and governors ofprefectures who have jurisdiction over the areas designated in Clause (1) of the preceding Paragraph, in accordance with theprovisions of Article 60 Paragraphs 1 and 5 of the Basic Law on Disaster Countermeasures, as applicable after being
amended as per the provisions of Article 28, Paragraph 2, and provide instructions of other measures related to immediate
emergency countermeasures.
4. Once immediate countermeasures to prevent the propagation of a nuclear disaster are deemed no longer necessary, thePrime Minister shall immediately consult the Nuclear Safety Commission and issue an official announcement to cancel the
nuclear emergency situation (hereinafter referred to as "a Notification of Deactivating Nuclear Emergency Organization").
(Establishment of Nuclear Disaster Countermeasures Headquarters)
Article 16. After issuing Notification of Active Nuclear Emergency Organization, the Prime Minister shall establish Nuclear
Disaster Countermeasures Headquarters temporarily at the Prime Minister's Office after holding a Cabinet council, for
executing immediate emergency countermeasures concerning relevant nuclear emergency situation, irrespective of theprovisions of Article 83 of the National Government Organization Law (Law 48-120).
(Organization of the Nuclear Disaster Countermeasures Headquarters)
Article 17. The Prime Minister (or a Minister of State appointed in advance should the Prime Minister be deemed underunavoidable circumstances) shall act as the Superintendent General of the Nuclear Disaster Countermeasures Headquarters, achief of the Headquarters.
(Competency of the Superintendent General of the Nuclear Disaster Countermeasures Headquarters)
Article 20. 4. When deemed necessary to request support from the Defense Agency for swift and efficient implementation of
the immediate emergency countermeasures in its implementation zone notified by the relevant Nuclear Disaster
Countermeasures Headquarters, the Superintendent General of the Nuclear Disaster Countermeasures Headquarters may
direct the Director-General of the Defense Agency to dispatch the troops in accordance with the provisions of Article 8 of the
Self-Defense Forces Law (Law 54-165).
(Joint Council of Nuclear Disaster Countermeasures)
Article 23. Once a Notification of Activating Nuclear Emergency Organization has been issued, the On-Site Nuclear Disaster
Countermeasures Headquarters and the Disaster Countermeasure Headquarters of the prefecture and municipalities whichhave jurisdiction over the implementation zone of the immediate emergency countermeasures, in which the Notification has
been issued, shall establish a Joint Council of Nuclear Disaster Countermeasures in order to exchange the information on therelevant nuclear disaster and to aid cooperation in implementing their immediate emergency countermeasures.
(Technical Experts for Nuclear Disaster Prevention)
Article 30. Technical Experts for Nuclear Disaster Prevention shall be appointed in the Ministry of Education, Culture,
Sports and Technology and the Ministry of Economy, Trade and Industry.
2. Technical Experts for Nuclear Disaster Prevention shall provide guidance and advice to the establishments of nuclear
enterprise designated, by the Director-General of the Minister of Education, Culture, Sports and Technology or the Ministerof Economy, Trade and Industry, as those for which they are responsible. Relevant guidance and advice shall be given to the
preparation of nuclear disaster prevention work plans of nuclear business operators in accordance with the provisions ofArticle 7, Paragraph 1, the establishment of nuclear disaster prevention organizations in accordance with Article 8, Paragraph
1, and the nuclear disaster prevention countermeasures implemented by nuclear business operators. Technical Experts shallfurther collect necessary information to recognize the situation upon receipt of reports in accordance with the provisions of
the former part of Article 10, Paragraph 1, provide advice for the collection of information and emergency measures
implemented by local public agencies, and handle any additional affairs necessary to smoothly prevent the occurrence andpropagation of nuclear disasters.
(ii)(2) Ordinance for the Enforcement of the Special Law of Emergency Preparedness for Nuclear Disaster(Excerpt)(Government Ordinance No. 195, April 5, 2000)(Events to be reported)
Article 4. The reference value specified in the government ordinance in Article 10, Paragraph 1 of the Law is a radiation doseof 5mSvs per hour.
2. The detection of radiation dose in accordance with the government ordinance of Article 10, Paragraph 1 of the Law shallbe performed by measuring the gamma ray radiation dose per unit of time (which shall be two minutes or less) by one ormore of the radiation-measuring devices installed in accordance with the provisions of Article 11, Paragraph 1 of the Law,
converting it into a value per hour, and determining whether this value is higher than the radiation dose specified in thepreceding paragraph. No radiation dose shall be deemed detected if the measured value falls within the purview of one of the-- Provisional translation for information only --A3-75succeeding Clauses.
(i)
The radiation dose is detected at only one point (with the restriction that the detection time is less than 10 minutes).
(ii)
The radiation dose is detected during a thunderstorm
3. When the radiation doses, detected as per the provisions of the proceeding Paragraph, at all radiation-measuring devices
installed in accordance with the provisions of Article 11, Paragraph 1 of the Law are less than that in Paragraph 1, and thevalue measured by one or more of the relevant radiation-measuring devices is 1mSv or more per hour, the detection ofradiation dose in accordance with the provisions of Article 10, Paragraph 1 of the Law shall be performed by totaling theradiation dose detected by the relevant radiation-measuring devices in accordance with the relevant paragraph and theneutron radiation dose measured in accordance with the provisions of the order of the competent Ministry in the vicinity of
the facilities for the operation of reactors, irrespective of the provisions of the preceding paragraph.
4. The event to be specified by the government ordinance in Article 10, Paragraph 1 of the Law is one of those specified in
the succeeding clauses.
(i)A radiation dose over the reference value specified in Paragraph 1 is detected in accordance with the provisions ofParagraph 2 or the preceding paragraph.
(ii)
Radioactive materials whose radiation level is higher than the reference value specified as equivalent to the radiationdose as specified in Paragraph 1 by the order of the competent Ministry at the boundary of the relevant establishmentof nuclear enterprise, are detected at the ventilation tubes, wastewater draining points, or similar points in the facility
for the operation of reactors of the relevant establishment.
(iii) The radiation dose or radioactive materials specified in the succeeding items are detected at locations (excluding thosespecified in the preceding clause) other than in specified control zones (i.e., the zone specified by the order of thecompetent Ministry where radiation exposure dose for personnel shall be controlled) inside the facility for theoperation of reactors within the site of the relevant establishment.
(a) Radiation dose of 50mSvs or more per hour.
(b) Radioactive materials that exceed the reference quantity specified in the order of the competent Ministry as
equivalent to a dose of 5mSvs per hour at the relevant locations.
(iv)
A radiation dose of 100mSvs or more is detected in accordance with the provisions of the competent Ministry at apoint 1m distant from a vessel used for transportation outside an establishment.
(v)
Inability to shut down a reactor as specified in Article 23, Paragraph 1, Clause 1 of the Law for the Regulations of
Nuclear Source Material, Nuclear Fuel Material, and Reactors (Law 57-166) by inserting normal neutron absorbents,
where a reactor being referred to as "an operational power reactor" in Article 6, Paragraph 4, Clause 4 of the relevantlaw, and other events specified, for each characteristic of the facility for the operation of reactors and of the vessels
used for the transport outside an establishment, by the order of the competent Ministry as potentially leading to anuclear emergency, in addition to those specified in the preceding clauses.
(Nuclear emergency situation)
Article 6. The radiation-measuring devices specified in the government ordinance in Article 15, Paragraph 1, Clause 1 of the
Law shall be installed in the prefecture of the competent governor of prefecture or governors of the related neighboring local
governments and have performance equivalent to that of the radiation-measuring devices specified in Article 11, Paragraph 1of the Law.
2. The measuring method specified in the government ordinance in Article 15, Paragraph 1, Clause 1 of the Law shall be
performed by repeating measurement of gamma ray radiation doses per unit of time (which shall be 10 minutes or less) andconverting them into values per hour, wherein the relevant value is deemed as not detected if detection occurs during athunderstorm.
3. The reference values, specified in the government ordinance in Article 15, Paragraph 1, Clause 1 of the Law, shall bethose in the succeeding clauses for the detected radiation doses specified therein.
(i)
500mSvs per hour: for the detected radiation doses as specified in Article 4, Paragraph 4, Clause 1 (i.e., the doses
obtained by totaling the neutron radiation dose specified in Paragraph 4, Clause 3 and the doses measured by therelevant radiation-measuring devices when the values measured by one or more of the radiation-measuring devices
installed in accordance with the provisions of Article 11, Paragraph 1 of the Law, are 5mSvs or more), or the radiationdose detected by the method in the preceding paragraph and by using the radiation-measuring devices in Paragraph 1.
(ii)
5mSv per hour: for the detected radiation doses specified in the item (a) in Article 4, Paragraph 4, Clause 3.
(iii) 10mSv per hour: for the detected radiation doses specified in Article 4, Paragraph 4, Clause 4.
4. The event specified as indicating the occurrence of a nuclear emergency situation in Article 15, Paragraph 1, Clause 2 of
the Law is one of those specified in the succeeding clauses.
(i)Radioactive materials whose radiation levels at the boundary of the relevant establishment are equal to or exceed thereference value specified by the competent Ministry as equivalent to the dose specified in Clause 1 of the preceding
paragraph are detected at the locations specified in Article 4, Paragraph 4, Clause 2 in accordance with the provisionsof the competent Ministry.
(ii)
Radioactive materials whose radiation levels at the locations specified in Article 4, Paragraph 4, Clause 3 are equal toor exceed the reference value specified by the competent Ministry as equal to 500mSvs per hour are detected atrelevant locations in accordance with the provisions of the competent Ministry.
(iii) Nuclear fuel materials are at a stage of criticality (i.e., a state where a fission chain reaction is continuing) within thefacilities for the operation of reactors (excluding the interior of reactor main bodies).
(iv)
Inability to shut down an operational power reactor by inserting emergency neutron absorbents, and other events
specified, for each characteristic of the facility for the operation of reactors and the vessels used for the transportation
outside an establishment, by order of the competent Ministry as indicating the occurrence of a nuclear emergency, in
addition to those specified in the preceding three clauses.

-- Provisional translation for information only --

A3-76

3.12

Environmental Impact Assessment Law (Excerpt)(Law No. 81, June 13, 1997)
Latest Revision: Law No. 73, May 19, 2000

(Purpose)
Article 1. Because it is extremely important, in terms of protecting the environment, for a corporation that is undertaking a
project that changes the shape of the terrain or that involves the construction of a new structure, or that is engaging in othersimilar activities, to conduct an environmental impact assessment in advance of such a project, the purposes of this law are toensure that proper consideration is given to environmental protection issues relating to such a project and, ultimately, toensure that present and future generations of this nations people enjoy healthy and culturally rewarding lives. In order toachieve these purposes, this law sets forth procedures and contains other provisions designed to clearly define theresponsibilities of the government regarding environmental impact assessments and to ensure that such assessments are
conducted properly and smoothly with respect to large-scale projects that could have a serious impact on the environment,
and prescribes measures to reflect the results of such environmental impact assessments in implementing such projects and in
determining the content of such projects.
(Definitions)
Article 2. In this law, "Class-1 Project" shall mean a large-scale project (in this and the following paragraph, scale shall mean
the measurable aspects of a project, such as the land area to be altered and the size of any structure(s) to be built) that isdesignated by government ordinance as likely to have a serious impact on the environment and that is one of the following:(i) A project in any of the following categories;(e) A project to construct or modify a power generating structure to supply electricity to corporate entities, as prescribedin Article 38 of the Electricity Utilities Industry Law (Law No. 170 of 1964).
(Responsibilities of the National Government and Other Parties)
Article 3. Fully recognizing that it is important for an environmental impact assessment to be conducted before a project is
implemented, the National Government, local governments, proponents, and citizens shall endeavor from their respective
positions to ensure that such an environmental impact assessment is conducted properly and smoothly, and that otherprocedures stipulated in this law are properly and smoothly followed, in order to avoid or to reduce as much as possible theenvironmental burdens resulting from the project, and in order to assist in giving proper consideration to the protection of theenvironment in regard to the implementation of the project.
(Preparation of a Planning Document)
Article 5. The proponent shall prepare a planning document concerning the environmental impact assessment (hereinafterreferred to as a "planning document"). Said planning document shall present information concerning the items listed below
regarding the scope of the environmental impact assessment (limited to those items relating to survey, prediction, andassessment activities) relating to the relevant project, pursuant to ministerial regulations regarding the various types ofprojects referred to in Article 2, Paragraph 2, Subparagraphs (i) (a) through (m);(i)
The name and address of the;(ii)
The purpose and content of the relevant project;(iii) The general conditions of the area in which the relevant project will be implemented (hereinafter referred to as the"relevant project implementation area") and its vicinity; and(iv)
The items to be considered in an environmental impact assessment of the relevant project, and the survey, prediction,
and assessment methods to be utilized (if such methods have not yet been determined, then the items to be consideredin the environmental impact assessment of the relevant project).
(Submission of Planning Document; Other Procedures relating to a Planning Document)
Article 6. After preparing a planning document, the proponent, pursuant to the ministerial regulations applicable to thevarious types of projects referred to in Article 2, Paragraph 2, Subparagraph (i) (a) through (m), shall submit the planningdocument to the governor of prefecture(s) and to the mayors of the cities, towns, and villages having jurisdiction over thearea deemed likely to be environmentally impacted by the relevant project.
2. In order to ensure that the area referred to in the preceding paragraph is appropriate in scope for seeking opinions, fromthe standpoint of protecting the environment, regarding the environmental impact assessment of the relevant project, thecompetent cabinet minister shall consult with the Minister of the Environment and shall prepare ministerial regulations
setting forth standards to ensure that such scope is appropriate.
(Making a Planning Document Public and Available for Public Inspection)
Article 7. For the purpose of inviting comments, from the standpoint of protecting the environment, regarding both the items
to be considered in an environmental impact assessment and the survey, prediction, and assessment methods to be utilized,
the proponent, upon preparing the planning document, shall make public, pursuant to a regulation to be adopted by the
Ministry of Environment, the fact that a planning document has been prepared, and shall make the planning document
available for public review in the area referred to in Paragraph 1 of Article 6 for one month from the date on which theplanning document is made known to the public.
(Submission of Comments regarding a Planning Document)
Article 8. A person who has comments, from the standpoint of protecting the environment, regarding a planning document
may submit such comments to the proponent during a period that shall commence on the date that the document becomes
known to the public and that shall end two weeks after the day following the termination of the period during which thestatement is to be available for public review.
(Submission of an Outline of Comments regarding a Planning Document)
Article 9. After termination of the period referred to in the preceding Article 8, the proponent shall submit to the governor ofprefecture(s) having jurisdiction over the area stipulated in Article 6, Paragraph 1 and to the mayors of the cities, towns and-- Provisional translation for information only --A3-77

villages having jurisdiction over said area, a document outlining the comments submitted pursuant to the provisions of thepreceding Article 8.
(Comments of Governors of prefectures and Other Officials with regard to a Planning Document)
Article 10. Upon receiving the document referred to in Article 9, the governor of prefecture(s) referred to in that same article
shall send to the proponent written comments, from the standpoint of protecting the environment, regarding the planningdocument, within a time period to be established by government ordinance.
2. While abiding by the provisions of Paragraph 1, the governor of prefecture(s) shall seek comments, from the standpoint ofprotecting the environment, from the mayors of the cities, towns, and villages referred to in Article 9, regarding the planningdocument and shall set a deadline by which time such comments must be received by the governor of prefecture(s).
3. While abiding by the provisions of Paragraph 1, the governor of prefecture(s) shall take into consideration the comments
submitted by the aforementioned mayors of the cities, towns, and villages pursuant to the preceding Paragraph 2, as well as
the comments outlined in the documents referred to in the preceding Article 9.
(Selection of Items Considered in the Environmental Impact Assessment)
Article 11. The proponent shall give due consideration to comments expressed pursuant to Paragraph 1 of the preceding
Article 10, shall take into consideration comments expressed pursuant to Article 8, Paragraph 1 in reviewing matters listed in
Article 5, Paragraph 1, Item (4), and shall select both the items to be considered in an environmental impact assessment
relating to the relevant project and the survey, prediction, and assessment methods to be utilized, pursuant to ministerial
regulations applicable to the various types of projects referred to in Article 2, Paragraph 2, Subparagraph (i) (a) through (m).
2. When deemed necessary for making selections pursuant to the provisions of the preceding Paragraph 1, the proponent
may submit a document to the competent cabinet minister expressing the proponents desire to receive documents that provide
technical advice.
3. With a view to ensuring the matters set forth in the Items under Article 14 of the Environment Basic Law, the ministerial
regulations referred to in Paragraph 1 shall be adopted by the competent cabinet minister in consultation with the Minister ofthe Environment, in order to establish guidelines for selecting, on the basis of already acquired scientific knowledge, both theitems that are regarded as necessary to be considered in an environmental impact assessment in order to properly conduct anenvironmental impact assessment relating to the relevant project, and the methods for reasonably conducting survey,
prediction, and assessment activities.
(Conducting an Environmental Impact Assessment)
Article 12. On the basis of the items and methods selected pursuant to the provisions of Paragraph 1 of the preceding Article
11, the proponent shall conduct an environmental impact assessment relating to the relevant project in accordance with theministerial regulations applicable to the various types of projects referred to in Article 2, Paragraph 2, Subparagraph (i), (a)through (m).
2. The provisions of Paragraph 3 of the preceding Article 11 shall apply mutatis mutandis to the ministerial regulations
referred to in the preceding Paragraph 1. In such a case, the wording "guidelines for selecting, on the basis of alreadyacquired scientific knowledge, both the items that are regarded as necessary to be considered in an environmental impact
assessment in order to properly conduct an environmental impact assessment relating to the relevant project, and the methods
for reasonably conducting survey, prediction, and assessment activities shall be construed to mean "guidelines concerning
measures to protect the environment."(Publication of Basic Guidelines)
Article 13. In consultation with the heads of relevant administrative organizations, the Minister of the Environment shalladopt and publish basic guidelines relating to the guidelines that are to be established by the competent cabinet minister
pursuant to the provisions of Article 11, Paragraph 3.
(Preparation of a Draft Environmental Impact Statement)
Article 14. After conducting an environmental impact assessment relating to the relevant project pursuant to the provisions ofArticle 12, Paragraph 1, the proponent, in preparation for hearing comments, from the standpoint of protecting theenvironment, regarding the results of the environmental impact assessment, shall prepare a draft environmental impact
statement (hereinafter referred to as a "draft EIS") that shall deal with the following matters, in accordance with theministerial regulations applicable to the various types of projects referred to in Article 2, Paragraph 2, Subparagraph (i), (a)through (m):(i)
Matters listed in Article 5, Paragraph 1, Subparagraph (1) through Subparagraph (3);(ii)
An outline of the comments referred to in Article 8, Paragraph 1;(iii)
Comments of the governor of prefecture(s), as referred to in Article 10, Paragraph 1;(iv)
Views of the proponent regarding the comments referred to in Subparagraph (2) and Subparagraph (3);(v)
Items to be considered in an environmental impact assessment and the survey, prediction, and assessment methods tobe utilized;(vi)
Contents of the technical advice received, if any, referred to in Article 11, Paragraph 2;(vii) The following results of the environmental impact assessment:(a) An outline of the results of surveys, predictions, and assessments as classified according to the items to be
included in the environmental impact assessment (including those items regarding which the nature and extent of
the environmental impact did not become clear even though an environmental impact assessment was conducted);(b) Measures for protecting the environment (including details regarding how such measures were developed);(c) Measures for determining the current conditions of the environment, if the measures referred to in (b) are meant tocope with environmental conditions that become known in the future;(d) An overall assessment of the likely environmental impact of the relevant project; and(viii) If the environmental impact assessment has been consigned in whole or in part to another person, the name and addressof that person.
2. The provisions of Article 5, Paragraph 2 shall apply mutatis mutandis to the preparation of the draft EIS.
-- Provisional translation for information only --A3-78

(Submission of a Draft EIS)
Article 15. After preparing a draft EIS, the proponent shall submit the draft EIS and a document summarizing it (referred toas "summary in the following Articles 16 and 17) to: (1) the governor of prefecture(s) having jurisdiction over the area
recognized as likely to be environmentally impacted by the relevant project, as determined by the ministerial regulations
referred to in Article 6, Paragraph 1 (such governor of prefecture(s) hereinafter referred to as "related governor(s)"; such area,
hereinafter referred to as "related area," includes such area as is recognized to be added to the area on the basis of comments
submitted pursuant to Article 8, Paragraph 1 and Article 10, Paragraph 1, and also on the basis of the results of theenvironmental impact assessment conducted pursuant to Article 12, Paragraph 1); and to (2) the mayors of the cities, towns,
and villages having jurisdiction over the related area (hereinafter referred to as "related mayors").
(Making a Draft EIS Public and Available for Public Inspection)
Article 16. After submitting the materials pursuant to the preceding Article 16, the proponent, for the purpose of acquiring
comments, from the standpoint of protecting the environment, regarding the results of the environmental impact assessment
relating to the draft EIS in accordance with the provisions of a regulation to be adopted by the Ministry of Environment, shall
publicly announce that the draft EIS and other items have been prepared in accordance with said regulation of the Ministry ofEnvironment, and shall make the draft EIS and the summary available for public review in the related area for one monthfrom the date of the aforementioned public announcement.
(Explanatory Meetings, etc.)
Article 17. In accordance with the provisions of a regulation to be adopted by the Ministry of Environment, the proponent
shall hold explanatory meetings to make the public aware of the contents of the draft EIS (hereinafter referred to as"explanatory meetings") in the related area during the period of public review. If within the related area there is no
appropriate place at which to hold such explanatory meetings, the meetings may be held outside the related area.
2. The proponent shall determine the date, time, and place of the explanatory meetings and shall publicly announce them atleast one week before the date on which a meeting is scheduled to be held, in accordance with the provisions of a regulation
to be adopted by the Ministry of Environment.
3. In determining the date, time, and place of an explanatory meeting, the proponent may seek the opinion(s) of the related
governor(s).
4. If the proponent cannot hold an explanatory meeting that has been publicly announced pursuant to Paragraph 2, forreasons that are not attributable to the proponent and are provided for in a regulation to be adopted by the Ministry ofEnvironment, the proponent shall not be obligated to hold that explanatory meeting. In such a case, however, the proponent,
pursuant to provisions of a regulation to be adopted by the Ministry of Environment, shall endeavor to make the public awareof the contents of the draft EIS, through such means as publicly presenting a summary during the period of public review.
5. The content of and procedures to be followed in holding an explanatory meeting, other than those stipulated in thepreceding Paragraphs, shall be determined by a regulation to be adopted by the Ministry of Environment.
(Submission of Comments regarding a Draft EIS)
Article 18. Anyone who has comments, from the standpoint of protecting the environment, regarding a draft EIS may
express such comments by submitting a document to the proponent during a period that shall commence on the date of the
public announcement referred to in Article 16 and that shall end two weeks after the day following the expiration of theperiod of public review referred to in that same Article 16.
2. The content of and procedures to be followed in submitting comments as referred to in the preceding Paragraph shall be
determined by a regulation to be adopted by the Ministry of Environment.
(Submission of an Outline of Comments, etc. regarding a Draft EIS)
Article 19. After the end of the period referred to in Paragraph 1 of the preceding Article 18, the proponent shall submit to
the related governor(s) and related mayors a document containing both an outline of the comments received pursuant to thesame Paragraph 1 and the proponent's views regarding such comments.
(Opinions of Related Governor(s) and Others Regarding a Draft EIS)
Article 20. After receiving a document referred to in the preceding Article 19, the related governor(s) shall express in writing
their opinions, from the standpoint of protecting the environment, regarding the draft EIS within a period to be determined bygovernment ordinance.
2. The provisions of Article 10, Paragraphs 2 and Paragraphs 3 shall apply mutatis mutandis to the expression of
opinions by the related governor(s) regarding the draft EIS. In such a case, the wording "the mayors of the cities,
towns and villages referred to in the preceding Article 9" in Paragraph 2 of the same Article 10 shall be construed tomean "the related mayors"; the wording "the preceding Paragraph" in Paragraph 3 shall be construed to mean "thepreceding Paragraph as applied mutatis mutandis to Article 10, Paragraph 2"; and the wording "documents referred toin the preceding Article 9" in Paragraph 3 shall be construed to mean "both the comments presented in the document
referred to in Article 19 and the proponents views regarding such comments."(Preparation of an Environmental Impact Statement)
Article 21. In reviewing the items dealt with in a draft EIS, the proponent shall consider any opinions that are expressedpursuant to Paragraph 1 of the preceding Article 20, and shall pay attention to comments referred to in Article 18, Paragraph
1. If the proponent considers it necessary to amend the aforementioned items (only insofar as the project after such
amendment will be classified as a relevant project), the proponent shall take measures to amend each of the items inaccordance with the classifications listed below:(i)Amending matters referred to in Article 5, Paragraph 1, Subparagraph (ii) (except amendments stipulated bygovernment ordinance, including reduction of the scale of the project, minor amendments as defined by government
ordinance, and other amendments as defined by government ordinance): To conduct an environmental impact
assessment and to follow other procedures specified in Articles 5 through Article 27.
(ii)
Amending matters referred to in Article 5, Paragraph 1, Subparagraph (i), or in Article 14, Paragraph 1, Subparagraph(ii) through Subparagraph (iv) and Item (6), or in Article 8 (except those covered by the preceding Item): To conduct-- Provisional translation for information only --A3-79

the environmental impact assessment and to follow other procedures specified in the following Paragraph 2 and in
Articles 22 through Article 27.
(iii)
Other than those specified in the two preceding Subparagraph (i) and Subparagraph (ii): To conduct an environmental
impact assessment with regard the aforementioned amended portions of the relevant project, pursuant to theprovisions of ministerial regulations referred to in Article 11, Paragraph 1 and in Article 12, Paragraph 1.
2. Except in a case covered by Subparagraph (i) of the preceding Paragraph 1, the proponent shall prepare theenvironmental impact statement (hereinafter referred to as "EIS") in accordance with the ministerial regulations applicable tothe various types of projects referred to in Article 2, Paragraph 2, Subparagraph (i), (a) through (m); the EIS shall incorporate
following matters relating to: (a) if an environmental impact assessment was conducted pursuant to the provisions of
Subparagraph (3) of the same Paragraph 2, the results thereof and the results of environmental impact assessment conducted
for preparing the draft EIS; or (b) if an environmental impact assessment was not conducted pursuant to the provisions of thesame subparagraph, the results of environmental impact assessment conducted for preparing the draft EIS.
(i)
Matters referred to in Subparagraph (1) through Subparagraph (8) in Article 14 Paragraph 1.
(ii) An outline of comments referred to in Article 18, Paragraph 1.
(iii) Opinions of the related governor(s), as referred to in Article 20, Paragraph 1.
(iv) The proponent's views regarding the comments and opinions referred to in the two preceding Subparagraph (2) and
Subparagraph (3).
(Making the EIS Public and Available for Public Review)
Article 27. When making a submission or notice pursuant to the provisions of Article 25, Paragraph 3, the proponent,
pursuant to a regulation to be adopted by the Ministry of Environment, shall make public the fact that an EIS and other items
stipulated in the regulation to be adopted by the Ministry of Environment have been prepared, and, for a period of one monthfrom the date of such publication, shall make available for public review in the related area the EIS, the summary, and thepapers specified in Article 24.
(Restrictions on the Implementation of a Relevant Project)
Article 31. A proponent may not implement a relevant project (if amended pursuant to the provisions of Article 21,
Paragraph 1, and if the project is a relevant project after said amendment, then the project after said amendment) prior to a
public announcement as required by Article 27.
2. If a proponent seeks to amend information referred to in Article 5, Paragraph 1, Subparagraph (ii) after a publicannouncement has been made as required by Article 27, the proponent need not conduct an environmental impact assessment
or follow other procedures pursuant to the provisions of this Law if: (a) the purpose of said amendment is to reduce the scaleof the project; or (b) the amendment is minor, as defined by government ordinance; or (c) the amendment is of another typespecified by government ordinance.
(Additional Environmental Impact Assessment and Other Procedures after Public Announcement of an EIS)
Article 32. If, after a public announcement has been made as required by Article 27, the proponent decides that, due tospecial factors such as changes in the environmental conditions in and around the relevant project implementation area, it isnecessary to amend matters referred to in Article 14, Paragraph 1, Subparagraph (v) or Subparagraph (vii) in order to giveproper consideration to the protection of the environment in implementing the relevant project, the proponent may conduct anadditional environmental impact assessment and may implement other procedures relating to the relevant project pursuant to
the provisions of Articles 5 through Articles 27 or Articles 11 through Articles 27.
2. If a proponent seeks to conduct an environmental impact assessment or to implement other procedures pursuant to thepreceding Paragraph 1, the proponent shall without delay make that known to the public in accordance with the provisions ofa regulation to be adopted by the Ministry of Environment.
(Proponents Consideration for Protection of the Environment)
Article 38. In implementing a relevant project, the proponent thereof shall give proper consideration to the protection of theenvironment pursuant to the contents of the EIS relating to the project.
(Communication with Local Governments)
Article 49. The proponent and others shall maintain close communication with, and may seek cooperation from, related local
governments concerning public announcements, public reviews, and the holding of explanatory meetings as provided for inthis Law.
(Technological Development)
Article 51. In order to improve technologies necessary for conducting environmental impact assessments, the National
Government shall endeavor to promote research and development of such technologies and to disseminate the results thereof.
(Exemptions, etc.)
Article 52. The provisions of this Law shall not apply to air pollution, water pollution (including deterioration of waterconditions other than water quality and soil at the bottom), or soil pollution caused by radioactive substances.
(Competent Cabinet Minister)
Article 58. A competent cabinet minister in this Law shall be as indicated by the following Subparagraphs according to thetype of project referred to in each Subparagraph:(v)
A project of the type referred to in Article 2, Paragraph 2, Subparagraph (ii), (e) of this Law: the minister responsible
for clerical work relating to implementation of the project and the minister responsible for clerical work relating to
any license, special permit, permission, authorization, approval or report relating to a project of the type referred to in(e) of the same Subparagraph (ii).
(Relation to other Laws)
Article 60. An environmental impact assessment and other procedures relating to a Class-1 or Class-2 Project of the type of
project referred to in Article 2, Paragraph 2, Subparagraph (i) (e) shall be subject to this Law and the Electricity Utilities
Industrial Law.

-- Provisional translation for information only --A3-80

3.13. Guidelines(1) Regulatory Guide for Reviewing Nuclear Reactor Siting Evaluation and Application Criteria(Decision of the Atomic Energy Commission, May 27, 1964, Partially Revised by the NSC, March 27, 1989)
In April 1958, the Atomic Energy Commission established the Specialty Subcommittee on Reactor Safety Standards toenact scientific and technical standards for the safety of reactor facilities. On November 2, 1963, the Committee submitted areport regarding the Regulatory Guide for Nuclear Reactor Siting Evaluation and Application Criteria as a preliminary stage
before establishing the standards for nuclear reactors to be placed on land.
The Atomic Energy Commission studied the Report and specified the Regulatory Guide for Nuclear Reactor
Siting Evaluation and Application Criteria, as in the Separate Sheet 1. The Commission also specified tentative
criteria regarding the radiation dosage, etc., as in the Separate Sheet 2, which are required in application of thisGuideline.
[Separate Sheet 1]
Regulatory Guide for Nuclear Reactor Siting Evaluation and Application Criteria
A safety review is conducted prior to the establishment of a nuclear reactor to be placed on land. This Guide is used inthis safety review by the Council on Reactor safety Examination to examine the adequacy of the nuclear reactor siting
conditions in relation to accident.
1. Basic Concept
1.1 Fundamental Siting Conditions
Regardless of the establishment location, nuclear reactors are required to be designed, constructed, operated andmaintained to prevent accidents. The following site conditions are, however, required in principle to ensure public safety incase of accident:(1) There have as yet been no event liable to induce large accident and no such event is expected to occur in the future.
There have also been very few events deemed liable to expand disaster;(2) In relation to their safety guarding facilities, nuclear reactors shall be located at a sufficient distance from the public; and(3) The environment of the nuclear reactor site including its immediate proximity shall be such that appropriate measures
for the public can be implemented as required.
1.2 Basic Goal
Based on a policy of ensuring public safety even in case of accident and promoting an sound nuclear development, thisGuideline provides the following three basic goals:a) Not to incur radiation damage to the neighboring public, even when assuming a serious accident that is deemed to havea possibility of occurrence under the worst scenario from technical point of view, by considering the events in the site
vicinity, the characteristics of the nuclear reactor and related safety guarding facilities (hereinafter termed major
accident);b) To prevent any significant radiation hazard to the neighboring public when an accident, which exceeds the major
accident level and which is not expected to occur from technical point of view, is hypothesized (hereinafter termed
hypothetical accident), for example, by hypothesizing that safety guarding facilities which are assumed to be effective inpostulating a major accident do not function, and corresponding release of radioactive materials occurs; andc) Effect on the collective dose of a hypothetical accident shall be sufficiently small.
2. Guideline for Site Review
When examining the adequacy of the site conditions, it is necessary to ensure that the following three conditions are
satisfied at least in order to achieve the previously described basic goals.
2.1 Regarding the area surrounding a nuclear reactor, an area of a specified distance from the nuclear reactor shall be
the non-residential area.
Here, the specified distance means a distance where person may be exposed to radiation damage if they remain withinthat distance under a major accident. non-residential area means the area where the public does not reside in principle.
2.2 The area within the specified distance from the nuclear reactor and outside the non-residential area shall be thelow population zone.
Here, the specified distance means the range wherein the public may be exposed to significant radiation hazard due to ahypothetical accident unless certain countermeasures are provided.
The low population zone means, for instance, a low population density zone where appropriate countermeasures can beprovided to prevent significant radiation hazard.
2.3 The nuclear reactor site shall be located at the specified distance from the dense population zone.
Here, the specified distance means the distance where the cumulative value of whole-body dose in case of a hypotheticalaccident shall be small enough to be deemed acceptable based on the viewpoint of collective dose.
3. Application
This Guideline shall be applied for the siting review of nuclear reactors having 10,000KW or larger thermal output. In
case of nuclear reactors under 10,000KW thermal output, this Guideline shall be used as a reference in their siting review.
[Separate Sheet 2]
Tentative Criteria to apply Regulatory Guide for Nuclear Reactor Site Evaluation and Application Criteria
The criteria shall be used when the Guideline on the Separate Sheet 1 is applied by the Council on Reactor Safety
Examination to review the safety of nuclear reactors to be placed on land.
1. The following dosage values shall be applied as the criteria for the specified distance in Guideline 2.1.
- Thyroid (child): 1.5Sv- Whole body: 0.25Sv
2. The following dosage values shall be considered as the tentative criteria for the specified distance in Guideline 2.2.
-- Provisional translation for information only --A3-81

- Thyroid (adult): 3Sv- Whole body: 0.25Sv
3. The tentative criteria for the specified distance in Guideline 2.3 shall be referred to overseas examples, for instance, for
20,000man-Sv.
Supplement:(i)
The tentative criteria above are provided from the administrative aspect and are based on the currently available
information regarding the radiation effect and comparison studies with overseas examples regarding the type andcontent of the diffusion of radioactive materials from nuclear reactors due to accidents. Since the biological effect ofradiation and collective dose remains somewhat unclear at this time, research in this field shall be promoted further inJapan. Considering international trend as well, these criteria shall be reviewed accordingly.
(ii)
The tentative criteria above are provided based on a concept different from that for the emergency criteria in responseto an actual nuclear reactor accident (dose in relation to food & drink intake and evacuation, etc.)(iii) The tentative criteria above are used for the safety review prior to nuclear reactor establishment to examine theadequacy of the siting conditions in relation to an accident. The criteria to prevent public radiation damage due tonormal reactor operation are specified in the Law for the Regulation of Nuclear Source Materials, Nuclear Fuel
Material and Nuclear Reactors (No. 166, 1957), and the Prime Ministers Ordinance and the Notification of the
Science and Technology Agency based on the previously mentioned law.
(iv)
Tentative Criteria 1 and 2 above are provided for nuclear reactors which use ordinary uranium fuel. It is necessary toconsider separate criteria when the criteria in addition to those for thyroid and whole body are considered importantfrom the damage aspect.

(2) Regulatory Guide for Reviewing Seismic Design of Nuclear Power Reactor Facilities (Excerpt)(Decision of the Nuclear Safety Commission, July 20, 1981)
1. Introduction
This guide was provided in September 1978 by the Atomic Energy Commission of those days, based on theengineering knowledge of seismological, geological and other studies with experiences of the safety examinations,in order to evaluate the adequacy of the design policy in the safety examination process of the seismic design of
nuclear power reactor facilities.
The revision of this guide performed this time is on determination methods of static seismic force, etc. because
it is considered as appropriate to utilize the new findings.
Incidentally, this guide shall be revised reflecting the newly accumulated findings and experiences, whennecessary.
2. Scope of Application
This guide shall be applied for the land-based nuclear power reactor facilities.
(Partially Omitted)
3. Basic Policy
Nuclear power reactor facility shall maintain its structural integrity against any postulated seismic force likely
to occur at the site so that no earthquake leads to a major accident. Moreover, buildings and structures shall be, in
principle, of rigid construction and the important buildings and structures shall be supported on bedrock.
4. Classification of Importance in Seismic Design
Each nuclear power reactor facility shall be classified into the following categories corresponding toimportance in seismic design from the standpoint of the impact on environment by the possible radiation resulted
from earthquake.
(1) Classification by Function
Class A ---- Facilities containing radioactive material or related directly to equipment containing radioactive
material and whose loss of function might lead to the release of radioactive material toatmosphere, facilities required to prevent the occurrence of such accidents, and facilities
required to mitigate the consequences resulting from the spread of radioactive material in theevent of an accident and whose influence and effect in mitigating such consequences issignificant.
Class B ---- Facilities of the same categories as the above Class A, but whose influences and effects are small.
Class C ---- Facilities except for class A and B, and ones only required to maintain the same safety as required forgeneral industrial facilities.
(2) Facilities by Classes(a) Class A facilities are as follows:(i) Equipment/piping systems composing of the reactor coolant pressure boundary(ii) Spent fuel storage pool(iii) Facilities to add the negative reactivity rapidly to shutdown the reactor and to maintain the
shutdown mode of the reactor(iv) Facilities to remove the decay heat from the reactor core after reactor shutdown(v) Facilities necessary to remove the decay heat from the reactor core after the failure of reactor
coolant pressure boundary(vi) Facilities to prevent the propagation of radioactive material directly as a pressure barrier at the
failure of reactor coolant pressure boundary(vii) Facilities except those in the category vi) above, and ones to mitigate the release of radioactive-- Provisional translation for information only --A3-82

material to the atmosphere at the accident which involves the release of radioactive material
In addition, Class A facilities belonging to i), ii), iii), iv), and v) are especially designated as Class As.
(Omitted)
5. Evaluation Method for Seismic Design(1) Policy
The nuclear power reactor facilities shall be designed in accordance with the following basic policies of the seismic
design for each category of classification.
(a) The integrity of each facility of Class A shall be maintained against the larger seismic force either the seismic force
due to the maximum design earthquake or the static seismic force shown below. In addition, safety function ofeach facility of Class As shall be preserved against the seismic force by the extreme design earthquake
shown below.
(b) The integrity of each facility of Class B shall be maintained against the static seismic force shown below. And, as
for the facility that is probable to resonate with earthquake, the influences shall be evaluated.
(c) The integrity of each facility of Class C shall be maintained against the static seismic force shown below.
(d) In each items shown above, the integrity of the upper class facility shall not be impaired corresponding to thedamage of the lower class facility.
(2) Determination Method of Seismic ForceThe seismic forces due to the maximum design earthquake and the extreme design earthquake and the static
seismic force, mentioned in Section 5. (1), shall be determined by the following methods.
(a) Seismic forces due to the maximum design earthquake and the extreme design earthquake
The horizontal seismic forces due to the maximum design earthquake and the extreme design earthquake shall be
determined by the basic earthquake ground motions, specified in Section 5.(3).
And, horizontal seismic forces shall be combined with the vertical seismic force concurrently and in the mostadverse fashion, which is determined by using the vertical seismic coefficient obtained by multiplying the
maximum acceleration amplitude of the basic earthquake ground motion by a half (1/2). However, thevertical seismic coefficient shall be assumed to be constant in the height direction.
(b) Static earthquake force(i) Buildings and structures
Horizontal seismic forces shall be determined by multiplying the weight at the height and above by thefollowing story shear coefficient corresponding to the importance of the facility.
Class A
story shear coefficient
3.0C IClass B
story shear coefficient
1.5C IClass C
story shear coefficient
1.0C I
Here, C I of the story shear coefficient shall be 0.2 in the standard case, and shall be fixed considering thevibration characteristics of buildings and structures, the category of the ground, and so on.
For the facilities of Class A, the vertical seismic force shall also be considered, and both horizontal andvertical seismic forces shall be combined concurrently and in the most adverse fashion. The vertical seismic
force shall be determined by using the vertical seismic coefficient, which shall be 0.3 in standard case andshall be fixed considering the vibration characteristics of buildings and structures, the category of the ground,and so on. However, the vertical seismic coefficient shall be assumed to be constant in the height direction.
(ii) Equipment and piping systems
The seismic forces of each class shall be determined in the similar manner as the above (i), using the value of
20% more than each corresponding value of horizontal and vertical seismic coefficient, where the horizontal
seismic coefficient takes place of the story shear coefficient for building and structures.
Both horizontal and vertical seismic forces shall be combined concurrently and in the most adverse fashion. However,the vertical seismic coefficient shall be assumed to be constant in the height direction.
(3) Evaluation Methods for the Basic Earthquake Ground Motions
The design earthquake ground motions for seismic design of reactor facilities shall be derived from the earthquake
motions at the free surface of the base stratum in the proposed site.
The design earthquake ground motions at the free surface of the base stratum (hereafter referred to as “the design basis
earthquake ground motions”) at the proposed site shall be determined in accordance with the fundamental concepts indicatedin the following items:(a) The basic design earthquake ground motions are classified into S1 and S2 depending upon their intensities;(i)
For the earthquakes causing the above mentioned basic design earthquake ground motions S1 (hereafter referred
to as “ maximum design earthquakes”), reference is made to the earthquake among the recorded earthquakes thatwould have the greatest effect on the proposed site and surrounding region and which may occur again in thesame fashion, or among those earthquakes that might be induced by highly active faults in the near future.
(ii) For earthquakes causing the above-mentioned basic design earthquake ground motions S2 (hereafter referred toas “extreme design earthquakes”), reference is made to the earthquake among those earthquakes exceeding the
maximum design earthquake that would have the greatest effect on the proposed site based on engineering judge
following a seismological review of past earthquakes, the nature of any active faults and the seismo-tectonic
structure underlying the site and the surrounding region.
(b) For earthquakes generating the design basis earthquake ground motions S1 and S2, both distant and nearfield epicentral
distances shall be considered. In addition, the shallow focus earthquake shall be considered for the design basis
earthquake ground motions S2; and(c) In determining the design basis earthquake ground motions, full consideration shall be given to the following items;(i)
The magnitude, epicenter, hypocenter, aftershock area and maximum intensity of earthquake ground motion (or-- Provisional translation for information only --A3-83

estimated value), and resultant damage (including destruction rate of structures, overturning of tombstones, etc.)
in earthquakes that have affected the site and the surrounding region in the past,(ii) The statistical expectation of the intensity of the past destructive earthquake ground motions,(iii) The magnitude of the earthquake and the distance between the site and its center of energy release, and(iv) Past observation records for the general region as well as those for the site, including any results of bedrock
property investigations.
(d) Pursuant to the above items, the design basis earthquake motions shall be such that each of the following parameters
can be evaluated as appropriate;(i)
The maximum amplitude of the earthquake ground motion,(ii) The frequency characteristics of the earthquake ground motion, and(iii) The duration of earthquake ground motion and the time dependent change of the amplitude envelope curves.
6. Load Combinations and Allowable Limits (Omitted)
COMMENTARY
In relation to dynamic analysis, an explanation is given of “evaluation of the design basis earthquake ground motions”,“evaluation of active faults”, “static seismic force” and “combinations of seismic forces with other loads and allowable
limits”.
I. Evaluation of the Design Basis Earthquake Ground Motions
1. The meaning and interpretation of the terminology concerning the design basis earthquake ground motions are given as
follows:(1) The “free surface of the base stratum” is a nearly flat surface of the base stratum extending over a considerable area,
and above which neither surface layers nor structures are assumed to be present. The base stratum is firm bedrock
which was formed in general in the Tertiary or earlier era and which is not significantly weathered.
(2) An “active fault” is a fault that has moved during the Quaternary period (i.e. within the last 1.8 million years) and thus
is capable of causing earthquakes in the future. Judge as to the activity of a fault shall be based on a topographicaland geological investigation, and on instrumental observations taken during past earthquakes, etc.
(3) A “seismo-tectonic structure” is a region of the geologic structure, which extends over a given area, and which has acommon earthquake occurrence pattern in terms of intensity, hypo-central depth, generating mechanism, frequency,
etc.
2. It was decided to classify the design basis earthquake ground motions according to their intensities into the twocategories, S1, and S2, which correspond to the importance of the buildings, structures, equipment and piping of the reactor
facilities.
(1) The earthquakes to be taken into account in determining the design basis earthquake ground motions S1 are thoseearthquakes that are considered likely to occur. Namely, it is deemed appropriate to consider that, according to thehistorical evidence, the earthquakes which affected the site and the surrounding region in the past are likely to occur
again in the near future and can be expected to have the same effect on the site and the surrounding region. The
occurrence of earthquakes in the near future at highly active faults that would affect the site must also be considered.
From these earthquakes, the earthquake which is referred to as the design basis maximum earthquake ground motions
would give the largest ground motion to the base stratum of the site. Further, it is assumed that such earthquakes
would actually occur and it is for this reason that buildings, structures, the equipment and the piping are subject to thedesign basis earthquake ground motions S1.
(2) The earthquakes to be taken into account in determining the design basis earthquake ground motions S2 are assumed torecur because, in some cases, it is not possible from a seismological standpoint to disregard the possibility of anearthquake whose intensity is higher than that of the maximum design earthquake. Therefore in those cases where
there is some evidence indicating that the earthquakes stronger than the maximum design earthquake have occurred inrelatively recent era, an engineering review should be done. However, from our knowledge of the seismo-tectonic
structure and from the data of past earthquakes, it can be concluded that there will be an upper limit to the intensity ofearthquakes in each region of earthquake occurrence. Therefore it is possible to estimate the intensity of theearthquakes and to define the region of earthquake occurrence, based on the nearby active faults and theseismo-tectonic structure underlying the site. From these earthquakes, the earthquake that would produce the largest
ground motions in the base stratum of the site shall be referred to as the extreme design earthquake. Further it isassumed that such an earthquake would actually occur and it is for this reason that, the buildings, structures, theequipment and the piping are subject to the design basis earthquake ground motions S2.
In addition, it was decided that the earthquakes with both distant and nearfield epicentral distances will be considered
in determining the maximum and extreme design earthquakes because some characteristics of earthquake groundmotions at the free surface of the base stratum will be different depending on the epicentral distance.
(Omitted)(3) Regulatory Guide for Reviewing Safety Design of Light Water Nuclear Power Reactor Facilities (Excerpt)(Decision of the Nuclear Safety Commission August 30, 1990)
IV. General Requirements for Reactor Facilities
1. Applied Codes and Standards
Design, selection of materials, fabrication and inspection of structures, systems and components with safety functions
shall conform to those codes and standards which are recognized appropriate in the light of the importance of their safetyfunctions.
-- Provisional translation for information only --A3-84

2. Design Considerations against Natural Phenomena(1) Structures, systems and components with safety functions shall be assigned to appropriate seismic categories, with theimportance of their safety functions and possible safety impacts of earthquake-induced functional loss taken into
consideration, and be designed to sufficiently withstand appropriate design seismic forces.
(2) Structures, systems and components with safety functions shall be so designed that the safety of the reactor facilities
will not be impaired by other postulated natural phenomena than earthquake. Structures, systems and components with safetyfunction of especially high importance shall be of the design that reflects appropriate safety considerations against theseverest conditions of anticipated natural phenomena or appropriate combinations of natural forces and accident loads.
3. Design Considerations against External Human-Initiated Events(1) Structures, systems and components with safety functions shall be so designed that the safety of the reactor facilities
will not be impaired by postulated external human-initiated events.
(2) Reactor facilities shall be so designed that structure, systems and components with safety functions are protected byappropriate means against any unjustifiable access by third persons.
4. Design Considerations against Internal Missiles
Structures, systems and components with safety functions shall be so designed that the safety of the reactor facilities
will not be impaired by postulated missiles that may take place within the reactor facilities.
5. Design Considerations against Fire
Reactor facilities shall be so designed that their safety will be protected against fire by appropriate combination of threemeasures of fire prevention, fire detection and extinguishment and mitigation of fire effects.
6.Design Considerations against Environmental Conditions
Structures, systems and components with safety functions shall be designed to withstand all environmental conditions
under which their safety functions are expected.
7. Design Considerations for Share Use
Structures, systems and components with safety functions shall be so designed that in case they are shared by two or
more reactor facilities, the safety of the reactors will not be impaired by the shared use.
8. Design Considerations against Operator Actions
Reactor facilities shall be designed to reflect appropriate preventive considerations against operators' mis-operation.
9. Design Considerations for Reliability(1) Structures, systems and components with safety functions shall be so designed that their adequately high reliability will
be ensured and maintained as required according to the importance of their safety functions.
(2) Systems with safety functions of especially high importance shall be designed with multiplex or diversity andindependence considering their physical makeup, working principles, assigned safety functions, etc.
(3) The systems referred to in item (2) above shall be designed to be capable of fulfilling their safety functions even in caseof loss of external power supply in addition to an assumption of a single failure of any of the components that comprisethe systems.
10. Design Considerations for Testability
Structures systems and components with safety functions shall be designed to be capable of being tested or inspected toverify their integrity and capability by adequate methods consistent with the importance of their safety functions during
reactor operation and shutdown.
V. Nuclear Reactor and Reactor Shutdown System
11. Core Design(1) Core shall be designed to assure, with the aid of the functions of associated reactor cooling system, reactor shutdown
system, instrumentation and control system, and safety protection system, that the acceptable fuel design limits are notexceeded during normal operation and abnormal transients.
(2) Components, other than fuel rods, that make up the core or are located in proximity to it within the reactor pressure
vessel shall be designed to be capable of ensuring safe reactor shutdown and proper core cooling during normal operation andabnormal situation.
12. Fuel Design(1) Fuel assemblies shall be designed not to lose their integrity despite various unfavorable factors that may take place
during their use in the nuclear reactor.
(2) Fuel assemblies shall be designed not to be excessively deformed during transport or handling.
13. Reactor Characteristics
Core and associated systems shall be designed to have inherent characteristics to suppress the reactor power rise and tobe well capable of controlling reactor power oscillation if it occurs.
14. Reactivity Control System(1) Reactivity control system shall be designed to be capable of regulating reactivity changes expected to occur during
normal operation, thereby maintaining necessary situation of operations.
(2) The maximum reactivity worth of control rods and reactivity insertion rate shall be such that postulated
reactivity-initialed events will not results in a damage of the reactor coolant pressure boundary nor destruction of thecore, core support structures and reactor pressure vessel internals that may impair core cooling.
15. Independence and Testability of Reactor Shutdown System
Reactor shutdown system shall be designed to have at least two independent systems capable of making the core
sub-critical from hot standby or hot operational conditions and maintaining the core sub-critical under hot conditions. They
shall also be designed to allow testing with respect to their functional capability.
16. Reactor Shutdown Margin by Control Rods
Control rod-dependent system in the reactor shutdown systems shall be designed to be capable of making the core
sub-critical under hot and cold conditions even when one control rod with the maximum reactivity worth is withdrawn out of-- Provisional translation for information only --A3-85the core and cannot be inserted.
17. Shutdown Capability of Reactor Shutdown System(1) At least one independent system out of the reactor shutdown systems shall be designed to be capable of making the core
sub-critical under hot conditions during normal operation and abnormal transients without leading to the acceptable fueldesign limits being exceeded and capable of maintaining the core sub-critical under hot conditions.
(2) At least one independent system out of the reactor shutdown systems shall be designed to be capable of making the core
sub-critical under cold conditions and of maintaining the core sub-critical under cold conditions.
18. Reactor Shutdown System Capability at the Accident
At least one independent system included in the reactor shutdown systems shall be designed to be capable of making thecore sub-critical at the accident, and at least one independent system included in the reactor shutdown systems shall be
designed to be capable of maintaining the core sub-critical at the accident.
VI. Reactor Cooling System
19. Integrity of Reactor Coolant Pressure Boundary(1) Reactor coolant pressure boundary shall be so designed that its integrity will be ensured during normal operation andabnormal situation.
(2) Pipelines connected to the reactor coolant system shall be in general fitted with isolation valves.
20. Prevention of Reactor Coolant Pressure Boundary Failure
Reactor coolant pressure boundary shall be designed not to exhibit brittle behavior and develop any rapid propagating
failure during normal operation, maintenance, testing and abnormal situation.
21. Detection of Reactor Coolant Pressure Boundary Leaks
Means shall be provided for quick and proper detection of the leakage of the reactor coolant, if any, from the reactor
coolant pressure boundary.
22. In-Service Test and Inspection of Reactor Coolant Pressure Boundary
Reactor coolant pressure boundary shall be designed to be capable of being tested and inspected to verify its integrity
throughout the service life of the nuclear reactor.
23. Reactor Coolant Make-up System
Reactor coolant make-up system shall be designed to be capable of supplying as much coolant as required at a proper
flow rate to restore the necessary inventory of the reactor coolant in case of a limited leakage.
24. Systems for Removing Residual Heat
(1) Systems for removing residual heat shall be designed to be capable of removing fission product decay heat and otherresidual heat from the core during reactor shutdown , thereby preventing the acceptable fuel design limits and design
conditions for the reactor coolant pressure boundary from being exceeded.
(3) Systems for removing residual heat shall be properly provided with multiplexity or diversity and independence so thatthey can fulfill their safety functions even in case of loss of external power supply in addition to the assumption of asingle failure of any of the components that comprise the systems. They shall also be designed to allow testing withrespect to their functional capability.
25. Emergency Core Cooling System(1) Emergency core cooling system shall be designed to be capable of preventing serious damage of fuel and of limiting thereaction between fuel cladding metal and water to a sufficiently small amount in case of a postulated loss of reactor coolant
resulting from a break in piping, etc.
(2) Emergency core cooling system shall be designed with multiplex or diversity and independence so that the system canfulfill its safety functions even in case of loss of external power supply in addition to an assumption of a single failure of anyof the components that comprise the system.
(3) Emergency core cooling system shall be designed to be capable of being tested and inspected on a periodical basis. The
emergency core cooling system shall also be designed to allow testing and inspection of each constituent system
independently so that the integrity and redundancy of the emergency core cooling system can be verified.
26. System for Transporting Heat to Ultimate Heat Sink
(1) System for transporting heat to an ultimate heat sink shall be designed to be capable of transferring heat generated or
accumulated in structures, system and components with safety functions of especially high importance to an ultimate heatsink.
(2) Systems for transporting heat to an ultimate heat sink shall be properly provided with multiplex diversity andindependence so that they can fulfill their safety functions even in case of loss of external power supply in addition to anassumption of a single failure of any of the components that comprise the systems. They shall also be designed to allow
testing with respect to their functional capability.
27. Design Consideration against Loss of Power
Reactor facilities shall be so designed that safe shutdown and proper cooling of the nuclear reactor after shutting down
can be ensured in case of a short-term loss of total AC power.
VII. Reactor Containment
28. Functions of Reactor Containment(1) Reactor containment shall be designed to withstand the load (pressure, temperature, dynamic load) resulting from thepostulated events for reactor containment design and an appropriate seismic load and prevent the specified leakage rate frombeing exceeded with the aid of properly operating isolation functions.
(2) Reactor containment shall be so designed that the leakage rate of the entire containment can be measure under aspecified pressure on a periodical basis.
(3) Reactor containment shall be designed to allow leakage tests at such important portions as penetrations for electric
cables, pipelines, etc. and access openings.
29. Prevention of Reactor Containment Boundary Failure-- Provisional translation for information only --A3-86

Reactor containment boundary shall be designed not to exhibit brittle behavior and develop any quickly propagating
failure during normal operation, maintenance, testing and abnormal situation.
30. Isolation Function of Reactor Containment(1) The pipelines that penetrate the reactor containment walls shall in general be fitted with containment isolation valves.
(3) The containment isolation valves to be fitted in principal piping shall in general be designed to be automatically andproperly closed in case of an accident that necessitates the retention of isolation function.
31. Reactor Containment Isolation Valves(1) Containment isolation valves shall be located as close to the reactor containment as practicable.
(2) Installation of the containment isolation valves shall be subject to the followings:(i)
Of the piping that open inside the reactor containment or connect with the reactor coolant pressure boundary,which are not closed outside the reactor containment, shall in general be provided with one containment isolation
valve inside the reactor containment and one outside;(ii)
Of other piping than (i) above, which are closed inside or outside the reactor containment, shall in general beprovided with one containment isolation valve outside the reactor containment;(iii) Containment isolation valves shall not lose their isolation function due to loss of driving power after they areclosed; and(iv)
The containment isolation valves shall allow performance tests to be conducted on a periodical basis, of which
important ones shall be testable for leakage.
32. Reactor Containment Heat Removal System(1) Reactor containment heat removal system shall be designed to sufficiently reduce the containment pressure andtemperature resulting from the release of energy in case of the postulated events for reactor containment design.
(2) Reactor containment heat removal system shall be designed with multiplex or diversity and independence so that thesystem can fulfill its safety functions even in case of loss of external power supply in addition to an assumption of a single
failure of any of the components that comprise the system. The system shall also be designed to provide testability.
33. System for Controlling Containment Facility Atmosphere(1) Containment facility atmosphere cleanup system shall be designed to be capable of reducing the concentration ofradioactive materials release to the environment at the postulated events for reactor containment design.
(2) Flammable gas concentration control system shall be designed to be capable of controlling the concentration ofhydrogen or oxygen present in the reactor containment in case of the postulated events for reactor containment design,
thereby maintaining the integrity of the containment facility.
(3) The systems for controlling containment atmosphere shall be designed with multiplex or diversity and independence sothat they can fulfill their safety functions even in case of loss of external power supply in addition to an assumption of asingle failure of any of the components that comprise the systems. They shall also be designed to allow testing with respect totheir function capability.
VIII. Safety Protection System
34. Redundancy of Safety Protection System
Safety protection system shall be designed with redundancy so that a single failure of any of the components orchannels that comprise the system or removal from service of any component or channel does not result in loss of safetyfunction of the system.
35. Independence of Safety Protection System
Safety protection system shall be designed such that the channels comprising the system are separated from each othertaking into account the independence between them as much as practicable, thereby preventing loss of its safety function
during normal operation, maintenance, testing and abnormal situation.
36. Function of Safety Protection System during Transients
Safety protection system shall be designed to detect the abnormal state during anticipated operational occurrences andinitiate automatically the operation of appropriate systems including the reactor shutdown system in order to ensure that theacceptable fuel design limits are not exceeded.
37. Function of Safety Protection System at the accident
Safety protection system shall be designed to detect the abnormal situation in an accident and initiate automatically theoperation of the reactor shutdown system and necessary engineered safety features.
38. Function of Safety Protection System at time of failure
Safety protection system shall be designed to allow the reactor facilities to be settled in a state of safety eventually incase of driving power loss, system cut-off or any other unfavorable situation.
39. Separation of Safety Protection System from Instrumentation and Control System
Safety protection system shall be designed to be functionally separated from instrumentation and control systems so thatthe system does not lose its safety functions by the influence from instrumentation and control systems in case that the both
systems share common elements.
40. Testability of Safety Protection System
Safety protection system shall be designed to be capable of being tested in general during reactor operation on aperiodical basis and allow testing of each constituent channel independently so that the integrity and multiplex of the system
can be verified.
IX. Control Room and Emergency Facilities
41. Control RoomControl room shall be so designed that the situation of operations and principal parameters of reactor and principal
related facilities can be monitored and that prompt manual control can be performed, whenever required, to maintain safety.
42. Reactor Shutdown Function from Outside of Control Room
Reactor facilities shall be designed to have the following functions that allow reactor to be shut down from an-- Provisional translation for information only --A3-87

appropriate location outside the control room:1) Quick hot shutdown of the nuclear reactor together with necessary instrumentation and control in order to maintain thereactor facilities in a safe state; and
2) Maintenance of cold shutdown state of the nuclear reactor with appropriate control procedure.
43. Design Considerations for Control Room Habitability
Control room shall be designed to be protected against fire, properly shielded so as to allow personnel to have access toor stay in the control room for necessary operations at the accidents, and protection against toxic gases and gaseousradioactive materials likely to be released due to fire or accident by means of proper ventilation system.
44. On-site Emergency Station
Reactor facilities shall be designed to allow establishment, in the nuclear power station, of an on-site emergency stationfrom which necessary instruction will be furnished at the accidents.
45. Design Considerations for Communications Equipment
Reactor facilities shall be provided with adequate alarm systems and communications equipment that allow necessary
instructions and messages to be given properly to all the people present in the nuclear power plant at the accidents. The
communications equipment between nuclear power plant and necessary outside places shall be provided with multiplex or
diversity.
46. Design Considerations for Evacuation Route
Reactor facilities shall be provided with emergency lights that function even in case or ordinary light power loss andhave safe evacuation routes provided with concise and permanent guide mark.
X. Instrumentation and Control System and Electrical System
47. Instrumentation and Control System(1) Instrumentation and control system shall be designed with adequate considerations for the following
requirements during normal operations and abnormal transients:(i) The parameters necessary to ensure the integrity of the core, reactor coolant pressure boundary, reactor containment
vessel boundary and associated systems shall be controlled and maintained within appropriate predicted range; and(ii) Monitoring of the aforementioned parameters within predicted variation limits shall be possible so as to allow
necessary countermeasures to be taken as required.
(2) Instrumentation and control system shall be designed to enable monitoring, and recording as required, of the parameters
necessary to recognize the status of accident and take countermeasures by adequate method over sufficient range at theaccidents. The system shall also be designed to enable monitoring or estimation of the status of reactor shutdown and corecooling in particular by use of two or more kinds of parameters.
48. Electrical System(1) Electrical system shall be designed to allow the structures, systems and components with safety functions of especiallyhigh importance to be fed by either external power or emergency auxiliary power system when they need electric power tofulfill their safety functions.
(2) External power system shall be connected to the power grid with two or more power transmission lines.
(3) Emergency auxiliary power system shall incorporate multiplexity or diversity and independence and have enoughcapacity and capability to accomplish the following properly even with an assumption of a single failure of its components:(i) Shutting down and cooling the nuclear reactor without the acceptable fuel design limits and design conditions for thereactor coolant pressure boundary being exceeded in case of abnormal transients; and(ii) Cooling the core and ensuring the integrity of the reactor containment and safety functions of other necessary systems
and components at the accidents, such as loss of reactor coolant.
(4) The electrical system associated with safety functions of high importance shall be designed such that their important
portions can be tested and inspected on appropriate and periodic basis.
XI. Fuel Handling Systems
49. Fuel Storage and Handling System(1) Storage and handling systems for fresh and spent fuels shall be designed so as to meet the following requirements:(i)
Appropriate periodical testing and inspection of structures, systems and components with safety functions shall bepossible;(ii)
Storage system shall have appropriate containment and air purification system;(iii) Storage system shall have appropriate storage capacity; and(iv)
Handling system shall have capability to prevent the dropping of fuel assemblies during transfer.
(2) Storage and handling systems for spent fuels shall be designed so as to meet the following requirements, in addition to
the aforementioned.
(i)
Proper shielding for radiation protection shall be available.
(ii)
Storage system shall have the system capable of fully removing decay heat and transporting it to an ultimate heatsink with associated purification system.
(iii) Prevention of excessive decrease of cooling water inventory in the storage systems and proper leakage detection
shall be possible.
(iv)
Storage systems shall not lose their safety functions even in case of postulated dropping of fuel assemblies during
handling.
50. Prevention of Fuel Criticality
Fuel storage and handling systems shall be so designed that criticality can be prevented in any postulated case by use ofgeometrical safety layout or other appropriate means.
51. Monitoring of Fuel Handling Area
Fuel handling area shall be so designed that the situation leading to the loss of decay heat removal capability andexcessive radiation levels can be detected and that such situation can be properly communicated to the personnel or-- Provisional translation for information only --A3-88corrective measures can be automatically taken against such situation.
XII. Radioactive Waste Processing Facility
52. Radioactive Gaseous Waste Processing Facility
Processing facility for radioactive gaseous wastes generated through the nuclear reactor operation shall be so designedthat the quantity and concentration of radioactive materials released to the environment can be reduced as low as reasonably
achievable through proper filtration, retention, decay, management, etc.
53. Radioactive Liquid Waste Processing Facility(1) Processing facility for radioactive liquid wastes generated through the nuclear operation shall be so designed that thequantity and concentration of radioactive materials released to the environment can be reduced as low as reasonably
achievable through proper filtration, evaporation process, ion exchange, retention, decay, management, etc.
(2) Radioactive liquid waste processing facility and associated facilities shall be designed to reflect preventive
considerations against the leakage of liquid radioactive materials from the systems and uncontrolled release of those materials
to out site.
54. Radioactive Solid Waste Processing Facility
Processing facility for radioactive solid wastes generated from the reactor facilities shall be designed to reflect
preventive considerations against the dispersion of radioactive materials in the process of crushing, compression, burning,solidification, etc. of the radioactive wastes.
55. Radioactive Solid Waste Storage Facility
Radioactive solid waste storage facility shall have enough capacity to store radioactive solid wastes generated from thereactor facilities and be designed to reflect preventive considerations against the spread of contamination by the wastes.
XIII. Radiation Management
56. Environmental Radiation Management
Reactor facilities shall be so designed that the dose rate by direct and skyshine gamma rays generated during normal
operation around the site can be reduced as low as reasonably achievable.
57. Radiation Protection for Personnel Engaged in Radiation Work
(1) Reactor facilities shall be so designed as to reflect necessary considerations for radiation protection in order to reducethe dose equivalent rate in the areas accessible to radiation workers as low as reasonably achievable by means of shielding,component layout, remote handling, prevention of the leakage of radioactive materials, ventilation, etc., taking work
efficiency of radiation workers into account.
(2) Reactor facilities shall incorporate radiation protection measures that will allow radiation workers to perform necessary
operations during abnormal situation.
58. Radiation Management for Personnel Engaged in Radiation Work
Reactor facilities shall be provided with radiation management facility that adequately monitor and control radiation
exposure in order to protect workers from radiation. Radiation management facility shall be so designed that necessary
information can be displayed in the control room or in other appropriate places.
59. Radiation Monitoring
Reactor facilities shall be designed to enable proper radiation monitoring over at least reactor containment atmosphere,
monitoring area surrounding the reactor facility and release paths of radioactive materials at the normal operation andabnormal situation and to allow necessary information to be displayed in the control room or in other appropriate places.

(4) The Emergency Preparedness Guidelines, “Emergency Preparedness of Nuclear Installations”(Excerpt)(Decision of the Nuclear Safety Commission, June 1980)
Latest Revision: June 2001
Chapter 1
Preface
Chapter 2
Emergency Preparedness-General
Chapter 3
Zone to be Performed Substantial Emergency Preparedness
3-2
Selection of Zone
Standards of "Zone to be Performed Substantial Emergency Preparedness" (hereinafter referred to as EPZ(Emergency Planning Zone)) are defined with sufficient margin in a distance from a nuclear facility even assuming
situations, which cannot dare happen technically in nuclear installations making sufficient safety countermeasures.
(Abbreviation) The standards of EPZ are shown in Table 1 depending on types of nuclear installations.
Table 1 Standard of EPZ depending on types of nuclear installations
Types of installations

Distance (radius) of standard of EPZ

Nuclear power stations, nuclear reactors in a research and development
stage, and nuclear reactors of more than 50MW in experimental research
stage

About 8-10km

Chapter 4
Emergency Environmental Radiation Monitoring
4-1 Objective, etc.
In a nuclear installation, when there is an unusual release of radioactive materials or radiations or its fear, anenvironmental monitoring planned particularly in order to obtain the information about radioactive materials or radiations ofcircumference environment, is called "emergency monitoring" and it consists of the 1st phase monitoring performed quickly-- Provisional translation for information only --A3-89

at the time of occurrence of a nuclear emergency situation and the 2nd phase monitoring carried out to assess the general
influence to the circumference environment. (Followings are abbreviated)
Chapter 5 Guideline for Enforcement of Emergency Response
5-1 Notification Criteria and Emergency Situation Judgment Criterion in the Abnormal Situation Occurrence
In the Special Law for Nuclear Emergency, considering the characteristic of nuclear installations, relations withcountermeasure activities, etc., criteria about preparation and start of nuclear emergency preparedness activities are definedso that it can apply to all nuclear installations.
(1) Notification criteria to related persons and response to applicable events
1) Contents of notification criteria(a) At the vicinity of boundary of a nuclear installation, dose rate of space radiations at one point of 5microSv/h ormore for more than 10min. or at more than two points simultaneously 5microSv/h or more (when gamma rays are
1microSv/h or more, the total doses of 5microSv/h or more by measuring neutrons, excluding case due tothunders.)(b) Release of the radioactive materials with which a radioactivity level after spreading corresponds 5microSv/h ormore near the boundary of a nuclear installation at normal release portions, such as a stack, etc. (release whichcorresponds 50microSv or more by an event when it is managed by accumulated release).
(c) A space radiation dose rate of 50microSv/h or more, or release of radioactive materials corresponding to
5microSv/h or more in the place outside a management zone etc. when a fire, explosion, etc. arises.
(d) A space radiation dose rate of 100microSv/h or more, or radioactive materials etc. in the point 1m from atransportation container when an accident occurred during conveyance outside nuclear installations.
(e) Occurrence of a criticality accident or a state of its fear.
(f) Individual events based on the characteristic of nuclear installations in light water reactors and shut down of thenuclear reactor by insertion of control rods cannot be performed.
2) Responses when an event applicable to notification criteria occurs(a) Responses of nuclear operator
While a nuclear operator should notify to the National Government, governors of prefectures, and municipal
governors quickly, he carries out emergency response required for the grasp of the information about the influence
on residents in the vicinity, etc. and prevention of occurrence or expansion of a nuclear emergency and also needs toreport the development of the incident to these organizations precisely.
(b) Responses of the National Government
While the National Government collects quickly the incident information, etc. in the nuclear installation throughthe Senior Specialist for Nuclear Emergency, it needs to send personnel and specialists of Japan Atomic Energy
Research Institute etc. to the spot. Moreover, response to alert conditions such as attaining share of the information
between the related persons and discussing countermeasures should be prepared according to the expansion situationof the incident by holding the emergency response connection meeting between related ministries and government
offices, etc.
(c) Responses of local governments
Governments of prefectures and municipals need to collect information, obtaining cooperation of the Senior
Specialist for Nuclear Emergency and to prepare an alert condition according to the expansion situation of theincident. Moreover, from the viewpoint of the grasp of the influence to the circumference, while the monitoring at
usual times is strengthened, preparation of emergency monitoring is started.
Besides, this stage is strictly a stage of preparation required for prevention of occurrence or expansion of a
nuclear emergency and responding pertinently is important so as not to give unnecessary anxiety and confusion toresidents in the related organizations. In addition, as response at the spot in an initial stage, the role of the Senior
Specialist for Nuclear Emergency is important, and contents of performances, etc. need to be defined beforehand.
(2) A nuclear emergency situation and its response
1) The contents of the judgment criteria of nuclear emergency situations(a) At vicinity of the boundary of a nuclear installation, dose rate of space radiation in a point of 500microSv/h ormore for more than 10 minute or 500microSv/h or more at more than two points simultaneously. (Total dose of
500microSv/h or more by measuring dose of neutrons also, when dose of gamma rays is 5microSv/h or more, but
excluding dose due to thunder.)(b) A release of the radioactive materials with which a radioactivity level after spreading corresponds 500microSv/h ormore near the boundary of a nuclear installation at normal release portions, such as a stack, etc. (a release whichcorresponds 5mSv or more by an event when it is managed by accumulated release).
(c) A space radiation dose rate of 5mSv/h or more, or a release of radioactive materials corresponding to 500microSv/hor more in the place outside a management zone etc. when a fire, explosion, etc. arises.
(d) A space radiation dose rate of 10mSv/h or more, or radioactive materials etc. in the point 1m from thetransportation container when an accident occurred during conveyance outside nuclear installations.
(e) Occurrence of a criticality accident(f) A nuclear reactor cannot be shut down by operations such as pouring of borate in a light water reactor in individual
events based on the characteristics of the nuclear installation.
2) Response to nuclear emergency situations(a) Responses of nuclear operators
Nuclear operators need to carry out emergency response for prevention of occurrence, or expansion of a nuclear
emergency.
(b) Responses of the National Government and local governments
The National Government declares a nuclear emergency situation and at the same time it establishes the Nuclear-- Provisional translation for information only --A3-90

Emergency Response Headquarter. Local governments establish Emergency Response Headquarters and carry out
emergency response. The Joint Council for Nuclear Emergency Response which consists of the local response
headquarter of the National Government, response headquarters of governments of prefecture and municipal, etc. isorganized in the off site center, in order to share information, to perform cooperated emergency response and it isimportant to take proper measures to reduce influence of radiation and not to give unnecessary anxiety and confusion
to residents in the vicinity.
5-2 (Omission)
5-3
Indices for protective measures
Indices for taking protective measures are expressed as the dose (prediction dose) expected to receive for individuals if
certain measures are not taken, or measured values as concentration of radioactive materials in food and drink.
Although a predicted dose will be presumed from the mode of an abnormal situation, the release situation of radioactive
materials or radiations, weather information, SPEEDI network system, etc., information from emergency monitoring etc. are
not necessarily obtained at early times of presumption. Therefore, when the measured values by emergency monitoring are
obtained, it is effective to correct the calculated values by SPEEDI network system etc. one by one based on these values.
(1) Indices of sheltering and evacuation, etc.
Based on "The Radiation Level of Emergency Response on the Extensive Release Incident of Radioactive Materials"(reply of Radiation Council 1967), the indices of sheltering, evacuation, etc. taking into account the efficiency of protective
countermeasures are shown in Table 2.
Table 2 Indices about sheltering and evacuation etc.
Anticipated radiation dose (unit: mSv)
Effective dose by− Equivalent dose of the thyroid
external exposure
gland by radioactive iodine
Contents of protective countermeasures− Equivalent dose of the bone
surface or the lung by uranium− Equivalent dose of the bone
surface or the lung by plutonium
10 to 50
100 to 500
Residents need to do indoor sheltering in own
houses, etc. In that case, air tightness should be attended
by shutting windows, etc.
In the case that the neutrons or gamma rays are
directly released from nuclear installations, residents
need to shelter in concrete building or evacuation whenthe Local Nuclear Emergency Response Headquarterindicates it.
50 or more
500 or more
Residents need to take indoor sheltering to concretebuilding or to be evacuated according to directions.
We decided that a certain width is given to the index of sheltering, evacuations, etc. The reason is that a protective
measures should not be determined by only the dose, but it should be determined in considering the possibility of realizationof countermeasures, a risk of being generated by performing, the influencing population scale and the dose to be reduced, andfor that flexibility is needed for enforcement of protective countermeasures. Moreover, advices or directions about actions ofcircumference residents, etc. performed by emergency response headquarters are expected to be given to unit of certain areaand prediction doses change with places in the area. That is the reason why index has a width.
In addition, it is required to define a certain area and to carry out step by step after considering the scale of an unusual
situation and weather conditions according to the above mentioned index, when a protective countermeasures of indoor
sheltering or sheltering in concrete buildings or evacuation are actually applied.
(2) The indices about ingestion restrictions of food and drink
In addition to iodine, uranium and plutonium in radioactive plumes as radioactive elements related to ingestion
restriction of food and drink, cesium was selected based on the experience of the Chernobyl accident of former USSR.
Indices about ingestion restrictions of food and drink are shown as measured concentration of the radioactive materials in
Table 3 determined from the viewpoint that exposures of these nuclides for residents in the vicinity are reduced.
These Indices further show standard when emergency response headquarters etc. start considerations about theingestion restriction measure of food and drink to be appropriate or not.
Table 3 Indices of ingestion restriction of food and drink
Objects
Radioactive iodine (representative nuclide of mixed nuclides: 131 I)
Drink water
3x102Bq/kg or more
Milk and dairy products
Vegetables (excluding root crop and potato)
2x103Bq/kg or more
Objects
Drink water
Milk and dairy products
Vegetables
Grain
Meat, egg, fish, etc.
-- Provisional translation for information only --Radioactive cesium
2x102Bq/kg or more
5x102Bq/kg or more

A3-91

Objects
Drink water
Milk and dairy products
Vegetables
Grain
Meat, egg, fish, etc.
Objects

Uranium
20Bq/kg or more
1x102Bq/kg or more

Alpha nuclides of plutonium and trans-uranium (sum of radioactivity
concentration of 238Pu, 239Pu, 240Pu, 242Pu, 241Am, 242Cm, 243Cm, 244Cm)

Drink water
Milk and dairy products
Vegetables
Grain
Meat, egg, fish, etc.

1Bq/kg or more
10Bq/kg or more

Chapter 6 Emergency Medical Treatment
6-3 Emergency medical treatment for radiation exposure(1) Initial medical treatment system for radiation exposure1) Initial medical treatment for patients exposed to radiation at nuclear installation
The initial treatment includes first aid for patients, surveillance, screening and measurement of dosage, followed bydecontamination or prevention of further spread of contamination, and transfer of patients to the medical institutions.
2) Initial response for residents taking refuge in shelters etc.
The initial response includes surveillance, screening and measurement of dosage, and collection and filing of
information on evacuation paths and duration of evacuation.
3) Initial medical treatment at medical institutions
Medical institutions in the vicinity of nuclear installations treat patients transferred there from shelters or nuclear
installations, and practice decontamination and emergency treatment.
It should be taken note of that, in emergency, many residents may visit medical institutions or shelters and seek
unnecessary medical treatment out of mental uneasiness.
(2) Subsequent medical treatment system for radiation exposure
After initial medical treatment, patients with residual contamination or with considerable damage are to betransferred to medical institutions for subsequent medical treatment, which includes whole body decontamination by shower,
medical treatment for contaminated wound, and measurement of contamination and dosage. It also includes treatment forpartially or severely exposed patients.
(3) Special medical treatment system for radiation exposure
Following subsequent medical treatment, patients with severe exposure from external or internal radiation are to
be transferred to medical institutions for special medical treatment. Medical institutions attached to national universities arerecommendable for their special interdisciplinary expertise.
Local medical institutions for special medical treatment obtain cooperation from local radiation protection
institutions in measuring dosage and providing radiation protection.
Local medical institutions for special medical treatment, in cooperation with the National Institute ofRadiological Sciences, practice treatment of patients, long term medical check, etc. Local medical institutions for special
medical treatment, together with institutions for initial and subsequent medical treatment, constitute effective local medical
treatment system for radiation exposure, and are responsible for coordination of transfer of patients, technologicalcooperation, etc. among local institutions.
The National Institute of Radiological Science is the central institute of special medical treatment, practices
highly professional decontamination and medical treatment in cooperation with other institutions with high expertise, andgives assistance and advice to other institutions. The National Institute of Radiological Science is one of the local medical
institutions for special medical treatment, also.

-- Provisional translation for information only --A3-92