SAFETY SER IES No. 50-C-QA (Rev.

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 CATEGORIES IN THE IAEA SAFETY SERIES

Under the new categorization scheme, the various publications in the IAEA
Safety Series are grouped as follows:

Safety Fundamentals
Publications in this category comprise basic objectives, concepts and principles
to ensure safety. The books have a silver cover.
Safety Standards
Publications in this category establish for particular activities or specific appli­
cation areas basic requirements which in the light of experience and the current state
of technology must be satisfied to ensure adequate safety. The books have a red
cover.
Safety Guides
Publications in this category supplement Safety Standards by giving recom­
mendations relative to the fulfilment of basic requirements and principles on the basis
of international experience. The books have a green cover.
Safety Practices
Publications in this category provide practical examples and detailed methods
regarding procedures and techniques which can be used for the application of Safety
Standards or Safety Guides. The books have a blue cover.
Safety Fundamentals and Safety Standards are issued with the approval of the
IAEA Board of Governors; Safety Guides and Safety Practices are issued under the
authority of the Director General of the IAEA.
There are other publications of the IAEA which also may contain information
important to nuclear safety and radiation protection, in particular books in the
Proceedings Series (containing papers presented at symposia and conferences), the
Technical Reports Series (with emphasis on technological aspects) and the IAEA
TECDOC Series (containing information usually in a preliminary form).
 CODE ON THE SAFETY
OF NUCLEAR POWER PLANTS
QUALITY ASSURANCE
 The following States are Members of the International Atomic Energy Agency:

AFGHANISTAN GUATEMALA PARAGUAY

ALBANIA HAITI PERU
ALGERIA HOLY SEE PHILIPPINES
ARGENTINA HUNGARY POLAND
AUSTRALIA ICELAND PORTUGAL
AUSTRIA INDIA QATAR
BANGLADESH INDONESIA ROMANIA
BELGIUM IRAN, ISLAMIC REPUBLIC OF SAUDI ARABIA
BOLIVIA IRAQ SENEGAL
BRAZIL IRELAND SIERRA LEONE
BULGARIA ISRAEL SINGAPORE
BURMA ITALY SOUTH AFRICA
BYELORUSSIAN SOVIET JAMAICA SPAIN
SOCIALIST REPUBLIC JAPAN SRI LANKA
CAMEROON JORDAN SUDAN
CANADA KENYA SWEDEN
CHILE KOREA, REPUBLIC OF SWITZERLAND
CHINA KUWAIT SYRIAN ARAB REPUBLIC
COLOMBIA LEBANON THAILAND
COSTA RICA LIBERIA TUNISIA
COTE D’IVOIRE LIBYAN ARAB JAMAHIRIYA TURKEY
CUBA LIECHTENSTEIN UGANDA
CYPRUS LUXEMBOURG UKRAINIAN SOVIET SOCIALIST
CZECHOSLOVAKIA MADAGASCAR REPUBLIC
DEMOCRATIC KAMPUCHEA MALAYSIA UNION OF SOVIET SOCIALIST
DEMOCRATIC PEOPLE’S MALI REPUBLICS
REPUBLIC OF KOREA MAURITIUS UNITED ARAB EMIRATES
DENMARK MEXICO UNITED KINGDOM OF GREAT
DOMINICAN REPUBLIC MONACO BRITAIN AND NORTHERN
ECUADOR MONGOLIA IRELAND
EGYPT MOROCCO UNITED REPUBLIC OF
EL SALVADOR NAMIBIA TANZANIA
ETHIOPIA NETHERLANDS UNITED STATES OF AMERICA
FINLAND NEW ZEALAND URUGUAY
FRANCE NICARAGUA VENEZUELA
GABON NIGER VIET NAM
GERMAN DEMOCRATIC REPUBLIC NIGERIA YUGOSLAVIA
GERMANY, FEDERAL REPUBLIC OF NORWAY ZAIRE
GHANA PAKISTAN ZAMBIA
GREECE PANAMA ZIMBABWE

The Agency’ s Statute was approved on 23 October 1956 by the Conference on the Statute o f the
IA E A held at United Nations Headquarters, New York; it entered into force on 29 July 1957. The Head­
quarters o f the Agency are situated in Vienna. Its principal objective is “ to accelerate and enlarge the
contribution o f atomic energy to peace, health and prosperity throughout the world” .

© IA E A , 1988

Permission to reproduce or translate the information contained in this publication may be

obtained by writing to the International Atomic Energy Agency, Wagramerstrasse 5, P .O . Box 100,
A - 1400 Vienna, Austria.

Printed by the IA E A in Austria

August 1988
 SAFETY SERIES No.50-C-QA (Rev. 1)

CODE ON THE SAFETY

OF NUCLEAR POWER PLANTS
QUALITY ASSURANCE

INTERNATIONAL ATOMIC ENERGY AGENCY

VIENNA, 1988
THIS SAFETY SERIES PUBLICATION IS ALSO ISSUED IN
CHINESE, FRENCH, RUSSIAN AND SPANISH

CODE ON THE SAFETY OF NUCLEAR POWER PLANTS:

QUALITY ASSURANCE
IAEA, VIENNA, 1988
STI/PUB/800
ISBN 92-0-123688-3
ISSN 0074-1892
 FOREWORD

by the Director General

Nuclear power is well established and can be expected to become an even more
significant part of the energy programmes of many countries, provided that its safe
use can be ensured and be perceived to be ensured. Although accidents have
occurred, the nuclear power industry has generally maintained a good safety record.
However, improvements are always possible and necessary. Safety is not a static
concept.
The International Atomic Energy Agency, recognizing the importance of the
safety of the industry and desiring to promote an improving safety record, set up a
programme in 1974 to give guidance to its Member States on the many aspects of
the safety of nuclear power reactors. Under this Nuclear Safety Standards (NUSS)
Programme, some 60 Codes and Safety Guides dealing with radiological safety were
published in the IAEA Safety Series between 1978 and 1986. The NUSS Programme
is so far limited to land based stationary plants with thermal neutron reactors
designed for the production of power.
In order to take account of lessons learned since the first publication of the
NUSS Programme was issued, it was decided in 1986 to revise and reissue the Codes
and Safety Guides. During the original development of these publications, as well
as during the revision process, care was taken to ensure that all Member States, in
particular those with active nuclear power programmes, could provide their input.
Several independent reviews took place including a final one by the Nuclear Safety
Standards Advisory Group (NUSSAG). The revised Codes were approved by the
Board of Governors in June 1988. In the revision process new developments in
technology and methods of analysis have been incorporated on the basis of interna­
tional consensus. It is hoped that the revised Codes will be used and that they will
be accepted and respected by Member States as a basis for regulation of the safety
of power reactors within the national legal and regulatory framework.
Any Member State wishing to enter into an agreement with the IAEA for its
assistance in connection with the siting, design, construction, commissioning,
operation or decommissioning of a nuclear power plant will be required to follow
those parts of the Codes and Safety Guides that pertain to the activities to be covered
by the agreement. However, it is recognized that the final decisions and legal
responsibilities in any licensing procedures rest with the Member States.
The Codes and Safety Guides are presented in such a form as to enable a
Member State, should it so desire, to make their contents directly applicable to
activities under its jurisdiction. Therefore, consistent with the accepted practice for
codes and guides, and in accordance with a proposal of the Senior Advisory Group,
‘shall’ and ‘should’ are used to distinguish for the user between strict requirements
and desirable options, respectively.
The five Codes deal with the following topics:
— Governmental organization
— Siting
— Design
— Operation
— Quality assurance.
These five Codes establish the objectives and basic requirements that must be met
to ensure adequate safety in the operation of nuclear power plants.
The Safety Guides are issued to describe to Member States acceptable methods
of implementing particular parts of the relevant Codes. Methods and solutions other
than those set out in these Guides may be acceptable, provided that they give at least
equivalent assurance that nuclear power plants can be operated without undue risk
to the health and safety of the general public and site personnel. Although these
Codes and Safety Guides establish an essential basis for safety, they may require the
incorporation of more detailed requirements in accordance with national practice.
Moreover, there will be special aspects that need to be assessed by experts on a case
by case basis.
These publications are intended for use, as appropriate, by regulatory bodies
and others concerned in Member States. In order to comprehend the contents of any
of them fully, it is essential that the other relevant Codes and Safety Guides be taken
into account. Other safety publications of the IAEA should be consulted as
necessary.
The physical security of fissile and radioactive materials and of nuclear power
plants as a whole is mentioned where appropriate but is not treated in detail.
Non-radiological aspects of industrial safety and environmental protection are also
not explicitly considered.
The requirements and recommendations set forth in the NUSS publications
may not be fully satisfied by older plants. The decision of whether to apply them
to such plants must be made on a case by case basis according to national
circumstances.
 CONTENTS

DEFINITIONS .................................................................................................................... 1

1. INTRODUCTION ............................................................................................. 7
General (101-107) ........................................................................................... 7
Scope (108) ........................'............................................................................... 8
Responsibility (109-110) ................................................................................. 8
2. QUALITY ASSURANCE PROGRAMMES ................................................ 9
General (201-209) ........................................................................................... 9
Procedures, instruction and drawings (210-211) ......................................... 10
Management review (212) ............................................................................... 10
3. ORGANIZATION ............................................................................................. 10
Responsibility, authority and communications (301-303) ......................... 10
Organizational interfaces (304) ...................................................................... 12
Staffing and training (305-306) ..................................................................... 12
4. DOCUMENT CONTROL ............................................................................... 12
Document preparation, review and approval (401) ................................... 12
Document release and distribution (402) ..................................................... 13
Document change control (403) ..................................................................... 13
5. DESIGN CONTROL ........................................................................................ 13
General (501-503) ........................................................................................... 13
Design interface control (504) ........................................................................ 14
Design verification (505-506) ........................................................................ 14
Design changes (507) ....................................................................................... 14
6. PROCUREMENT CONTROL ....................................................................... 15
General (601-602) ........................................................................................... 15
Supplier evaluation and selection (603-604) ................................................ 16
Control of purchased items and services (605-607) ................................... 16
7. CONTROL OF ITEMS .................................................................................. 16
Identification and control of materials, parts and components
(701-703) ...................................................................................................... 16
Handling, storage and shipping (704) ........................................................... 17
Maintenance (705) ............................................................................................. 17
8. PROCESS CONTROL (801) ......................................................................... 17
9. INSPECTION AND TEST CONTROL ...................................................... 18
Programme of inspection (901-904) .............................................................. 18
Test programme (905-906) ............................................................................. 18
Calibration and control of measuring andtestequipment (907-908) ......... 19
Indication of inspection, test and operatingstatus (909-910) ..................... 19
10. NON-CONFORMANCE CONTROL .......................................................... 19
General (1001) .................................................................................................. 19
Non-conformance review and disposition(1002) ......................................... 20
11. CORRECTIVE ACTIONS (1101) ................................................................ 20
12. RECORDS ........................................................................................................ 20
Preparation of quality assurance records(1201) ........................................... 20
Collection, storage and preservation of quality assurance records
(1202-1203) ................................................................................................... 21
13. AUDITS ........................... .................................................................................. 21
General (1301) .................................................................................................... 21
Scheduling (1302) ............................................................................................. 22
LIST OF PARTICIPANTS ....................................................................................... 23
LIST OF NUSS PROGRAMME TITLES ............................................................ 27
SELECTION OF IAEA PUBLICATIONS RELATING TO THE
SAFETY OF NUCLEAR POWER PLANTS .................................................. 31
 DEFINITIONS

The definitions below are intended for use in the NUSS programme and may
not necessarily conform to definitions adopted elsewhere for international use.

The relationships between the following eight definitions used in many

NUSS publications are illustrated by the accompanying diagram.

Operational States

States defined under Normal Operation or Anticipated Operational

Occurrences.
Normal Operation

Operation of a nuclear power plant within specified operational limits and

conditions including shutdown, power operation, shutting down, starting, main­
tenance, testing and refuelling.
Anticipated Operational Occurrences1

All operational processes deviating from Normal Operation which are

expected to occur once or several times during the operating life of the plant and
which, in view of appropriate design provisions, do not cause any significant damage
to items important to Safety nor lead to Accident Conditions.
Accident (or Accident State)
A state defined under Accident Conditions or Severe Accidents.
Accident Conditions

Deviations2 from Operational States in which the releases of radioactive

materials are kept to acceptable limits by appropriate design features. These devia­
tions do not include Severe Accidents.

1 Examples o f Anticipated Operational Occurrences are loss o f normal electric power

and faults such as a turbine trip, malfunction o f individual items o f a normally running plant,
failure to function o f individual items o f control equipment, loss o f power to main coolant
pump.
2 A deviation may be a major fuel failure, a loss o f coolant accident (LO CA), etc.

1
Design Basis Accidents
Accident Conditions against which the nuclear power plant is designed accord­
ing to established design criteria.
Severe Accidents

Nuclear power plant states beyond Accident Conditions including those

causing significant core degradation.
Accident Management

Accident management is the taking of a set of actions

— during the evolution of an event sequence, before the design basis of the plant
is exceeded, or
— during Severe Accidents without core degradation, or
— after core degradation has occurred
to return the plant to a controlled safe state and to mitigate any consequences of the
accident.

Plant states

Operational states Accidents

Anticipated
Normal operational Accident Severe
operation occurrences conditions accidents

Design
basis
accidents

Accident management

2
Approval
Formal consent to a proposal.
Audit
A documented activity performed to determine by investigation, examination
and evaluation of Objective Evidence the adequacy of, and adherence to, established
procedures, instructions, specifications, codes, standards, administrative or opera­
tional programmes and other applicable documents, and the effectiveness of
implementation.
Authorization
The granting of written permission to perform specified activities.
Commissioning3
The process during which nuclear power plant components and systems,
having been constructed, are made operational and verified to be in accordance with
design assumptions and to have met the performance criteria; it includes both non­
nuclear and nuclear tests.
Construction3
The process of manufacturing and assembling the components of a nuclear
power plant, the erection of civil works and structures, the installation of components
and equipment, and the performance of associated tests.
Decommissioning3
The process by which a nuclear power plant is permanently taken out of
Operation.

•3
The terms Siting, Design, Construction, Commissioning, Operation and Decommis­
sioning are used to delineate the six major stages o f the licensing process. Several o f the stages
may coexist; for example, Construction and Commissioning, or Commissioning and
Operation.

3
Design (see footnote 3)
The process and the result of developing the concept, detailed plans, support­
ing calculation and specifications for a nuclear power plant and its parts.
Documentation
Recorded or pictorial information describing, defining, specifying, reporting
or certifying activities, requirements, procedures or results related to Quality
Assurance.
Examination4
An element of Inspection consisting of investigation of materials, components,
supplies, or services, to determine conformance with those specified requirements
which can be determined by such investigation.
Inspection
Actions which by means of Examination, observation or measurement deter­
mine the conformance of materials, parts, components, systems, structures, as well
as processes and procedures, with defined requirements.
Item
A general term covering materials, parts, components, systems or structures
including computer software.
Non-conformance
A deficiency in characteristics, documentation or procedure which renders the
Quality of an Item unacceptable or indeterminate.
Nuclear Safety (or simply Safety)
The achievement of proper operating conditions, prevention of Accidents or
mitigation of accident consequences, resulting in protection of site personnel, the
public and the environment from undue radiation hazards.

4 Examination is usually non-destructive and includes simple physical manipulation,

gauging and measurement.

4
Objective Evidence
Qualitative or quantitative information, record or statement of fact, pertaining
to the Quality of an Item or service, which is based on observation, measurement
or test and which can be verified.
Operation (see footnote 3)
All activities performed to achieve the purpose for which the plant was con­
structed, including maintenance, refuelling, in-service inspection and other
associated activities.
Qualified Person
A person who, having complied with specific requirements and met certain
conditions, has been officially designated to discharge specified duties and
responsibilities.
Quality
The totality of features and characteristics of an Item or service that bear on
its ability to satisfy a defined requirement.
Quality Assurance
All those planned and systematic actions necessary to provide adequate confi­
dence that an Item or service will satisfy given requirements for Quality.
Records
Documents which furnish Objective Evidence of the Quality of Items or
services and of activities affecting Quality.
Responsible Organization
The organization having overall responsibility for the nuclear power plant.
Safety — See Nuclear Safety
Siting (see footnote 3)
The process of selecting a suitable site for a nuclear power plant, including
appropriate assessment and definition of the related design bases.
5
Specification
A written statement of requirements to be satisfied by a product, a service, a
material or process, indicating the procedure by means of which it may be deter­
mined whether the specified requirements are satisfied.
Supplier Evaluation

An appraisal to determine whether or not a management system is capable of

producing an Item or service of a stated Quality, and generating evidence that
supports decisions on acceptability.
Testing

The determination or verification of the capability of an Item to meet specified

requirements by subjecting the Item to a set of physical, chemical, environmental or
operational conditions.
Vendor

A design, contracting or manufacturing organization supplying a service,

component or plant.

Note on the interpretation o f the text

When an appendix is included it is considered to be an integral part of the

document and to have the same status as the main text of the document.
However, annexes, footnotes and bibliographies are only included to provide
additional information or practical examples that might be helpful to the user.
In several cases phrases may use the wording ‘shall consider...’ or ‘shall... as
far as practicable’. In these cases it is essential to give the matter in question careful
attention, and the decision must be made in consideration of the circumstances of
each case. However, the final decision must be rational and justifiable and its
technical grounds must be documented.
Another special use of language is to be noted: “ ‘a’ or ‘b’ ” is used to indicate
that either ‘a’ or ‘b’, but also the combination of both ‘a’ and ‘b’, would fulfil the
requirement. If alternatives are intended to be mutually exclusive, “ either... or... ”
is used.
6
 1. INTRODUCTION

General
101. This Code provides the principles and objectives to be adopted as regards
safety when establishing both a satisfactory overall quality assurance programme for
a nuclear power plant and also separate quality assurance programmes for each of
the constituent areas of activity (e.g. design, manufacturing, construction, commis­
sioning, operation). The principles to be followed in each case, for each type of
programme, are the same.
102. The establishment and implementation of a quality assurance programme for
a nuclear power plant are essential. However, it shall always be recognized that the
basic responsibility for achieving quality in performing a particular task (e.g. in
design, in manufacturing, in commissioning, in operation) rests with those assigned
the task and not with those seeking to ensure by means of verification that it has been
achieved.
103. The quality assurance programme encompasses the activities that are necessary
to achieve the appropriate quality of the respective item or service and the activities
that are necessary for verifying that the required quality is achieved and that objec­
tive evidence is produced to that effect.
104. Quality assurance is an essential aspect of ’good management’. Good manage­
ment contributes to the achievement of quality through thorough analysis of the tasks
to be performed, identification of the skills required, the selection and training of
appropriate personnel, the use of appropriate equipment and procedures, the creation
of a satisfactory environment in which activities can be performed and, as already
noted, a recognition of the responsibility of the individual who is to perform the task.
Briefly stated, a quality assurance programme shall provide for a disciplined
approach to all activities affecting quality, including, where appropriate, verification
that each task has been satisfactorily performed and that necessary corrective actions
have been implemented. It shall also provide for production of documentary evi­
dence to demonstrate that the required quality has been achieved.
105. The manner in which the principles described in this Code are implemented,
both at the overall plant level and at the constituent activity levels, will vary from
country to country and organization to organization. These variations will be due to
such considerations as regulatory requirements, the general organization of industry,
and the degree of sophistication and experience of the technical organizations
involved in providing and operating the nuclear power plant. In any event, the basic
intent of the principles shall be kept in mind at all times and the detailed implementa-
tional procedures shall be arranged accordingly. It is essential, too, that the quality
7
assurance programme be conceived and implemented to ensure sufficient integration
between its technical, managerial and administrative aspects.
106. This Code forms part of the Agency’s programme, referred to as the NUSS
programme, for establishing Codes and Safety Guides relating to land based station­
ary thermal neutron power plants. The Guides listed in Section 5 of the List of NUSS
Programme Titles, printed at the end of this publication, will be of assistance in
implementing the present Code.
107. The quality assurance principles enumerated in this document can be usefully
applied to nuclear facilities other than nuclear power plants.
Scope

108. The Code provides the principles and objectives for the establishment and
implementation of a quality assurance programme during siting, design, manufac­
ture, construction, commissioning, operation and decommissioning of nuclear power
plants. They apply to activities affecting the quality of items and services important
to safety, such as designing, purchasing, fabricating, manufacturing, handling, ship­
ping, storing, cleaning, erecting, installing, testing, commissioning, operating,
inspecting, maintaining, repairing, refuelling, modifying and decommissioning.
They are applicable by all those responsible for the nuclear power plant, by plant
designers, suppliers, architect-engineers, plant constructors, plant operators and
other organizations participating in activities affecting quality.
Responsibility

109. In its responsibility for ensuring the health and safety of the public, the govern­
ment of an IAEA Member State should have established a general, legal framework
for the regulation of nuclear power plants (see the Code 50-C-G (Rev. I)1). Within
this framework should be the requirement that an effective, overall quality assurance
programme be established.
110. The organization having overall responsibility for a nuclear power plant shall
also be responsible for the establishment and implementation of the overall quality
assurance programme for the complete plant. This organization may delegate to
other organizations the work of establishing and implementing all, or a part, of the
programme but shall retain responsibility for the effectiveness of the overall
programme, without prejudice to the contractors’ obligations or legal
responsibilities.

1 Reference to NUSS documents is made by quoting the Safety Series number only.
The titles o f the documents can be found in the list at the end o f the book.

8
 2. QUALITY ASSURANCE PROGRAMMES

General

201. An overall quality assurance programme shall be established consistent with

the requirement contained in this Code as an integral part of the nuclear power plant
project. The overall programme shall provide for control of the constituent activities
associated with a nuclear power plant, such as siting, design, construction, manufac­
turing, commissioning, operation and decommissioning. The control of each consti­
tuent activity shall also be consistent with this Code.
202. Management in the overall and constituent areas of activity shall provide for
effective implementation of the quality assurance programmes consistent with the
time schedules for accomplishing project activities, including the procurement of
materials for long-delivery-time items. Management of nuclear power plant opera­
tion shall ensure that the quality assurance programme shall be in effect during plant
operation.
203. All programmes shall define the organizational structure within which the
quality assurance activities are to be planned and implemented and shall clearly
delineate the responsibility and authority of the various personnel and organizations
involved.
204. The establishment of the programmes shall include consideration of the techni­
cal aspects of the activities to be performed. The programmes shall contain provi­
sions to ensure identification of, and compliance with, requirements of appropriate
recognized engineering codes, standards, specifications and practices. Quality assur­
ance requirements, besides managerial and administrative aspects of control, should
include provisions that ensure formulation of the technical objectives to be achieved.
205. Items, services and processes to which the quality assurance programmes will
apply shall be identified. Appropriate methods or levels of control and verification
shall be assigned to those items, services and processes. All programmes shall
provide control and verification over activities affecting the quality of the identified
items to an extent consistent with their importance to safety.
206. All programmes shall provide suitable controlled conditions for the accom­
plishment of activities affecting quality. This includes appropriate environmental
conditions, equipment and skills to attain the required quality.
207. All programmes shall provide for training of personnel performing activities
affecting quality.
208. All programmes shall be subject to regular evaluation and updating.
9
209. All programmes shall state the languages used for documentation. Measures
shall be established to ensure that persons performing the quality assurance function
have adequate knowledge of the language in which the documentation is written.
Translations of the documentation shall be reviewed by competent persons. Verifica­
tion of conformance to the original is necessary.2
Procedures, instructions and drawings

210. All programmes shall provide that the activities affecting quality of nuclear
power plants, including activities during the plant operation, are accomplished in
accordance with written procedures, instructions or drawings of a type appropriate
to the circumstances. Instructions, procedures and drawings shall include appropri­
ate quantitative and/or qualitative acceptance criteria for determining that important
activities have been satisfactorily accomplished.
211. Procedures for implementing the quality assurance programmes on a planned
and systematic basis for different phases of the nuclear power project shall be deve­
loped and documented by the organization performing the constituent activities. The
procedures shall be written in a manner suitable for the technical expertise required
of the user. Their content shall be clear and unambiguous. The procedures shall be
periodically reviewed and updated as necessary to ensure adequate coverage of those
activites.
Management review

212. All programmes shall provide for the review at appropriate intervals by the
management of organizations participating in the programme of the status and ade­
quacy of the part of the quality assurance programme for which they have designated
responsibility. Corrective action shall be taken when programme deficiencies are
discovered.

3. ORGANIZATION

Responsibility, authority and communications

301. A documented organizational structure, with clearly defined functional respon­

sibilities, levels of authority and lines of internal and external communication for
2 Acceptable methods for implementing this section o f the Code are included in the
Safety Guides 50-SG-QA3, 50-SG-QA4, 50-SG-QA5 (Rev. 1), 50-SG-QA6, 50-SG-QA8 and
50-SG-QA11.

10
management, direction, and execution of the quality assurance programme shall be
established.3 The organizational structure and functional assignments shall recog­
nize that execution of a quality assurance programme involves both performers and
verifiers and is not the sole domain of a single group. The organization’s structure
and the functional assignments shall be such that:
(a) Attainment of quality objectives is accomplished by those who have been
assigned responsibility for performing the work; this may include examination,
checks and inspections of the work by the individuals performing the work;
(b) When verification of conformance to established requirements is necessary it
is carried out by those who do not have direct responsibility for performing
the work.
302. The authority and duties of persons and organizations responsible for quality
assurance performance and verification shall be delineated in writing. The persons
and organizations performing the quality assurance functions of
(a) ensuring that an appropriate quality assurance programme is established and
effectively executed, and
(b) verifying that activities have been correctly performed
shall have sufficient authority and organizational freedom to: identify quality
problems; initiate, recommend or provide solutions; and, where necessary, initiate
actions to control further processing, delivery or installation or use of an item which
is non-conforming, deficient or unsatisfactory, until proper disposition has been
achieved.
303. Such persons and organizations performing quality assurance functions shall
report to a management of high enough level to ensure that the authority and
organizational freedom required in the previous paragraph, including sufficient
independence from cost and schedule considerations, are provided. Because of the
many variables involved, such as the number of personnel, the type of activity being
performed, and the location or locations where activities are performed, the
organizational structure for executing the quality assurance programme may take
various forms, provided that the persons and organizations assigned the quality
assurance functions have this required authority and organizational freedom.
Irrespective of the organizational structure, the individual or individuals assigned the
responsibility for ensuring effective execution of any portion of the quality assurance
programme at any location where activities affecting quality are being performed
shall have direct access to such levels of management as may be necessary to achieve
effective implementation of the quality assurance programme.

3 For further guidance see Safety Guide 50-SG-QA7.

11
Organizational interfaces
304. Where multiple organizational arrangements exist, the responsibility of each
organization shall be clearly established and interfaces and co-ordination among
organizations ensured by appropriate measures. Provision shall be made for commu­
nication among organizations and organizational groups participating in activities
affecting quality. The communication of essential information shall be by means of
appropriate documentation. The type of documents shall be identified and distribu­
tion shall be controlled.
Staffing and training

305. Plans shall be developed for selecting staff and training personnel to perform
activities affecting quality. Plans shall reflect the schedule of activity so as to allow
adequate time for assigning or selecting, and training, required personnel.
306. All personnel responsible for performing activities affecting quality shall be
qualified on the basis of general education, experience and proficiency required for
performing the specific assigned tasks. Training programmes and procedures shall
be established to ensure that suitable proficiency is achieved and maintained. As
appropriate, the accomplishment and maintenance of proficiency shall be marked by
the issue of a written statement, such as a certificate. Acceptable methods for
implementing this section of the Code are included in the Safety Guide 50-SG-QA7.

4. DOCUMENT CONTROL

Document preparation, review and approval

401. The preparation, review, approval and issue of documents essential to the per­
formance and verification of the work, such as instructions, procedures and draw­
ings, shall be subject to control. The control measures shall include the identification
of all individuals or organizations responsible for preparing, reviewing, approving
and issuing documents related to activities affecting quality. The reviewing and
approving organization or individuals shall have access to pertinent background
information upon which to base the review or approval.
12
Document release and distribution
402. A document release and distribution system shall be established, utilizing up
to date distribution lists. Measures shall be provided for ensuring that those par­
ticipating in an activity are aware of and use appropriate and correct documents for
performing the activity.
Document change control

403. Changes to documents shall be subject to review and approval in accordance

with documented procedures. The reviewing organizations shall have access to perti­
nent background information upon which the approval is based and shall have an ade­
quate understanding of the requirements and intent of the original document.
Changes to documents shall be reviewed and approved either by the same organiza­
tions that performed the original review and approval or by other organizations that
have been specifically designated. Timely information on document revision and its
actual status shall be promptly relayed to all affected persons and organizations to
preclude the use of outdated and inappropriate documents.

5. DESIGN CONTROL

General

501. Control measures shall be established and documented to ensure that applicable
specified design requirements, such as regulatory requirements, design bases, codes
and standards, are correctly translated into specifications, drawings, procedures or
instructions. They shall include provisions to ensure that applicable quality standards
are specified and stated in design documents. Changes and deviations from specified
design requirements and quality standards shall be controlled. Measures shall also
be established for the selection, and for the review for suitability of application, of
any materials, parts, equipment and processes that are essential to the function of the
structure, system or component.
502. Design control measures shall be applied to subjects such as the following:
radiation protection; human factors; fire protection; physics and stress analysis;
thermal, hydraulic, seismic and accident analysis; compatibility of materials; acces­
sibility for in-service inspection, maintenance and repair; and delineation of accep­
tance criteria for inspection and tests.
13
503. Design activities shall be documented to permit adequate evaluation by techni­
cal personnel other than those performing the original design.

Design interface control

504. External and internal interfaces between organizations and organizational units
performing the designs shall be identified in writing. Responsibility for each organi­
zation and organizational unit shall be defined in sufficient detail to cover the prepa­
ration, review, approval, release, distribution and revision of documents involving
interfaces. Methods shall be established for communicating design information,
including changes, across the design interfaces. The information communication
shall be documented and controlled.

Design verification

505. Design control measures shall provide for verifying the adequacy of design and
design methods, such as by the performance of design reviews, by the use of
alternative calculational methods, or by the performance of a suitable testing
programme. Design verification shall be performed by individuals or groups other
than those who performed the original design. Verification methods to be applied
shall be identified by the design organizations and design verification results shall
be documented to the extent specified.
506. Where a test programme is used to verify the adequacy of a specific design fea­
ture in lieu of other verifying or checking processes, it shall include suitable qualifi­
cation testing of a prototype unit under the most adverse conditions for the specific
design features being verified. Where testing cannot be carried out under the most
adverse design conditions, testing is permissible under other conditions if the results
can be extrapolated to the most adverse design conditions and if they can verify the
adequacy of a specific design feature.

Design changes

507. Documented procedure shall be provided for effecting design changes, includ­
ing field changes. The technical impact of changes shall be carefully considered and
the required actions documented. The changes shall be subject to the same design
control measures as those applied to the original design. Change documents shall be
reviewed and approved by the same affected groups or organizations responsible for
review and approval of the original design documents, unless other organizations are
specifically designated. This designation of alternative organizations shall be condi­
\

tional on their having access to pertinent background information, on their demon-

14
strating competence in the specific design area of concern, and on their having an
adequate understanding of the original design requirements and intent. Information
concerning the changes shall be transmitted to all affected persons and organizations.

6. PROCUREMENT CONTROL

General

601. Measures shall be established and documented to ensure that applicable regula­
tory requirements, design bases, standards, specifications and other requirements
necessary to assure adequate quality are included or referenced in the documents for
procurement of items and services.
602. Procurement requirements for assuring quality shall include, but need not be
limited to, the following, as applicable:
(a) A statement of the scope of the work to be performed by the supplier.
(b) Technical requirements specified by reference to documents such as codes,
standards, regulations, procedures, instructions and specifications, including
revisions thereto that describe the items or services to be performed.
(c) Test, inspection and acceptance requirements, and any special instructions and
requirements related to these.
(d) Provisions for access to supplier facilities and records for the purpose of source
inspection and audit when the need for such inspection and audit has been
determined.
(e) Identification of quality assurance requirements and the elements of the
programme applicable to the items or services procured. Not all suppliers need
to have a quality assurance programme which complies with all the elements
of this Code. To the extent necessary, the procurement documents shall require
contractors or subcontractors to provide a quality assurance programme con­
sistent with the pertinent provisions of the Code.
(f) Identification of documentation required, such as instructions, procedures,
specifications, inspection and test records, and other quality assurance records
to be prepared and submitted for review or approval by the purchaser.
(g) Provisions for controlled distribution, retention, maintenance and disposition
of quality assurance records.
(h) Requirements for reporting and approving disposition of non-conformances.
(i) Provisions for extending applicable requirements of procurement documents to
lower tier subcontractors and suppliers, including purchaser’s access to facili­
ties and records.
(j) Provisions for specifying the timing of the submission of documents.
15
Supplier evaluation and selection
603. A basic consideration in the selection of suppliers shall be the supplier’s evalu­
ated capability to provide items or services in accordance with the requirements of
the procurement documents.
604. Supplier evaluation includes, as appropriate:
(a) The use of historical quality performance data of similar procurement actions;
(b) The use of supplier’s current quality assurance records supported by
documented quantitative or qualitative information that can be objectively
evaluated;
(c) Source evaluation of supplier’s technical capability and quality system;
(d) Evaluation b y selective product samples.

Control of purchased items and services

605. Purchased items and services shall be subject to control to assure the confor­
mance to procurement documents. The control consists of measures such as objective
evidence of quality furnished by the contractors, inspection and audit at the source,
and examination of the items or services upon delivery.
606. If necessary, samples of material as specified shall be retained for a specific
time at an agreed location and controlled to provide means for further examination.
607. Documentary evidence that purchased items and services, including spare and
replacement parts necessary for plant operation, refuelling and maintenance, con­
form to procurement documents shall be available at the nuclear plant site before
installation or use. This evidence shall be sufficient to identify all requirements met
by the purchased items and services. This documentary evidence may take the form
of a written certificate of conformance which identifies the requirements met by the
item or service, provided that the validity of such certifications can be verified.

7. CONTROL OF ITEMS

Identification and control of materials, parts and components

701. Measures shall be established for the identification and control of items,
including partially fabricated assemblies, as required throughout fabrication, erec­
tion, installation and use. These measures ensure that identification of the item is
maintained, throughout fabrication, erection, installation and use, by batch number,
part number, serial number or other appropriate means, either on the item or records
16
traceable to the item, as required. The required documentation shall be available for
items as they proceed through the construction process.
702. Physical identification shall be used to the maximum extent possible. Where
physical identification is either impractical or insufficient, physical separation,
procedural control or other appropriate means shall be employed to maintain identifi­
cation. These identification and control measures shall be designed to prevent the use
anywhere of incorrect or defective material, parts and components.
703. Where identification marking is employed, the marking shall be clear, unam­
biguous and indelible, and shall be applied in such a manner as not to affect the func­
tion of the item. Marking shall not be hidden by surface treatment or coatings, unless
other means of identification are substituted. Where subdivision of items occurs the
original identification shall be maintained for each part.
Handling, storage and shipping

704. Measures shall be established and documented to control handling, storage and
shipping. These shall include cleaning, packing and preservation of material and
equipment in accordance with established instructions, procedures or drawings to
prevent damage, deterioration or loss. When necessary for particular items, special
coverings, special handling equipment and special protective environments shall be
specified and provided and their existence verified.
Maintenance

705. Maintenance of items important to safety shall be performed in a manner to

ensure a quality equivalent to that originally established for these items.

8. PROCESS CONTROL

801. Processes affecting quality such as used in design, construction, fabrication,

testing, commissioning and operation of a power plant shall be controlled in accor­
dance with specified requirements. Where required by applicable codes, standards,
specifications, criteria or other special requirements, measures shall be established
and documented to ensure that processes in which the quality achieved depends on
the performance of the said process but which cannot be verified by means of final
product inspections, such as those used in welding, heat treatment and non­
destructive examination, shall be performed by qualified personnel, using qualified
procedures and equipment in accordance with existing standards. For processes not
17
covered by existing codes, standards, specifications and criteria or where the quality
requirements exceed the requirements of these documents, the necessary qualifica­
tion of personnel, procedures or equipment shall be defined.

9. INSPECTION AND TEST CONTROL

Programme of inspection

901. To verify conformance to the documented instructions, procedures and draw­

ings a programme for inspection of items and services and the activities affecting
their quality shall be established and executed by or for the organization performing
these activities. Inspections shall be performed for each work operation where
necessary to assure quality. Inspections which are deemed important for safety shall
be performed by individuals other than those performing the activities being
inspected.
902. The programmes shall provide indirect control by monitoring of the processing
methods, equipment and personnel if, for example, inspection of processed items is
impossible or if additional process monitoring is required. Both inspection and
process monitoring shall be provided when control is inadequate without both.
903. Hold-points beyond which work shall not proceed without the approval of a
designated organization, if such inspection or witnessing of the inspection is
required, shall be indicated in appropriate documents. Such approval shall be
documented before the continuation of work beyond the designated hold-point.
904. A programme for required in-service inspection of completed systems, struc­
tures and components shall be planned and executed, and the results shall be evalu­
ated against baseline data.
Test programme

905. A test programme shall be established to ensure the identification, performance

and documentation of all testing required to demonstrate that the structures, systems
and components will perform satisfactorily in service. The test programme shall
cover all required tests, and include, as appropriate, procedure and equipment
qualification tests, prototype qualification tests, proof tests before installation, com­
missioning tests and surveillance tests during the operation stage.
906. Testing shall be performed in accordance with written test procedures which
incorporate the requirements and acceptance limits specified in design documents,
and include provisions for assuring that prerequisites for a given test have been met
18
and that the test is performed under suitable environmental conditions by appropri­
ately trained personnel using properly calibrated instrumentation. Test results shall
be documented and evaluated to assure that test requirements have been satisfied.
Calibration and control of measuring and test equipment

907. Measures shall be established to ensure that tools, gauges, instruments, and
other inspection, measuring and test equipment and devices used in determining con­
formance to acceptance criteria are of the proper range, type, accuracy and
precision.
908. Testing and measuring devices used in activities affecting quality shall be con­
trolled, calibrated and adjusted at specified intervals or before use to maintain
accuracy within necessary limits. When deviations beyond prescribed limits are
detected, an evaluation shall be made of the validity of previous measurements and
tests, and acceptance of tested items reassessed. Controls shall be established to
assure proper handling, storing and use of calibrated equipment.
Indication of inspection, test and operating status

909. Test and inspection status of individual items of the nuclear power plant shall
be identified by the use of markings, stamps, tags, labels, routing cards, inspection
records, physical location or other suitable means that can indicate the acceptability
or non-conformance of items with regard to tests and inspections performed. The
identification of the inspection and test status shall be maintained as necessary
throughout manufacturing, installation and operation of the item to ensure that only
items that have passed the required inspection and test are used, installed or operated.
910. Measures shall also be established for indicating the operating status of systems
and components of the nuclear power plant, such as by tagging valves and switches
to prevent inadvertent operation.

10. NON-CONFORMANCE CONTROL

General

1001. Measures shall also be established to control items which do not conform to
requirements, in order to prevent their inadvertent use or installation. To ensure
control, these non-conforming items shall be identified by marking, by tagging or
19
by physical segregation, where practical. Measures which control further process­
ing, delivery or installation of non-conforming or defective items shall be estab­
lished, documented and implemented.
Non-conformance review and disposition

1002. Non-conforming items shall be reviewed and accepted without modification,

rejected, repaired or reworked in accordance with documented procedures. The
responsibility for review and authority for disposition of non-conformances shall be
defined. Accepted non-conforming items involving a deviation from procurement
requirements shall be reported to the purchaser and, when necessary, to the desig­
nated authority. The description of changes, waiver or deviation that has been
accepted shall be documented to denote the ‘as built’ condition. Repaired and
reworked items shall be reinspected according to applicable procedures.

11. CORRECTIVE ACTIONS

1101. The programme shall provide that appropriate action be taken to ensure that
conditions adverse to quality, such as failures, malfunctions, deficiencies, devia­
tions, defective or incorrect material and equipment, and any other non­
conformances, are identified and corrected. For significant conditions adverse to
quality, the programme shall provide that the cause of such conditions be deter­
mined, and corrective action taken to prevent repetition. The identification of the sig­
nificant conditions adverse to quality, the cause of the conditions and the corrective
actions taken shall be documented and reported to appropriate levels of management.

12. RECORDS

Preparation of quality assurance records

1201. Quality assurance records adequate for use in the management of the quality
assurance programme shall be prepared. Records shall represent objective evidence
of quality and shall include the results of reviews, inspections, tests, audits, monitor­
ing of work performance, materials analyses and power plant operation logs, as well
as closely related data, such as qualifications of personnel, procedures and equip­
ment, repairs required and other appropriate documents. All quality assurance
records shall be legible, complete and identifiable with respect to the item or service
involved.
20
Collection, storage and preservation of quality assurance records
1202. A quality assurance record system shall be established and executed in accor­
dance with written procedures and instructions. The system shall require that suffi­
cient records be maintained to furnish evidence of activities affecting quality and to
describe baseline pre-operational conditions. The system shall provide for identifica­
tion, collection, indexing, filing, storing, maintenance and disposal of records.
Records shall be stored in such a way that they are readily retrievable and maintained
in a suitable environment to minimize deterioration or damage and to prevent loss.
1203. Retention times of quality assurance records and associated test material and
specimens shall be established in writing. In general, records which correctly iden­
tify the ‘as built’ condition of items in the plant shall be maintained by or for the
responsible organization for the useful life of the item from manufacture through
storage, installation and operation. Periods of retention for records other than life­
time records shall be assigned consistent with the type of record involved. Disposal
of records shall be in accordance with written procedures.4

13. AUDITS

General

1301. Measures shall be undertaken to verify the implementation and effectiveness

of the quality assurance programme. As necessary, a system of planned and
documented internal and external audits shall be carried out to verify compliance
with all aspects of the quality assurance programme and to determine the
programme’s effectiveness. The audits shall be performed in accordance with written
procedures or check-lists. The responsible auditing organizations shall select and
assign qualified auditors. They shall be independent of any direct responsibility for
the activities which they audit. In the case of internal audits, the persons having the
direct responsibility for performance of the activities being audited shall not be
involved in the selection of the audit team. The results of audits shall be documented
by the auditors. Deficiencies noted in the audit shall be reviewed and corrected by
the organization having responsibility in the area audited. Follow-up action shall be
taken to verify implementation of the corrective action.

4 For further guidance, see Safety Guide 50-SG-QA2.

21
Scheduling5
1302. Audits shall be scheduled on the basis of the status and importance of the
activity, and shall be conducted when one or more of the following conditions exist:
(a) When a systematic, independent assessment of programme effectiveness is
considered necessary;
(b) When it is necessary to determine the capability of a contractor’s quality assur­
ance programme before awarding a contract or purchase order;
(c) After award of a contract, when sufficient time has elapsed for implementing
the quality assurance programme and it is appropriate to determine that the
organization is adequately performing the functions as defined in the quality
assurance programme, applicable codes and standards and other contract
documents;
(d) When significant changes are made in functional areas of the quality assurance
programme, such as significant reorganization or revisions of procedure;
(e) When it is suspected that the quality of an item or a service is in jeopardy owing
to a deficiency in the quality assurance programme;
(f) When it is necessary to verify implementation of required corrective actions.

5 For further guidance, see Safety Guide 50-SG-QA10.

22
 LIST OF PARTICIPANTS
During the development phase the following experts participated in one or more of
the meetings (1974-1977):
WORKING GROUP

The original draft was prepared by the IAEA Panel on Quality Assurance for
Nuclear Power Plants from 28 October to 1 November 1974.
TECHNICAL REVIEW COMMITTEE (TRC) - QUALITY ASSURANCE

Thomas, R .A . (Chairman) Canada

Havel, S. Czechoslovakia

Carrier, C.
Dive, P. France
Vaujour, J.A.
Stobel, W. Germany, Federal Republic o f
Balaramamoorthy, K.
India
Raghavan, R.V.
Maniori, D. Italy
Ando, Y.
Japan
Hattori, S.
Baschek, H. Switzerland
Fowler, J.L.
United Kingdom
Phillips, C .A .C .
Morrison, W .M . United States o f America

Tolley, B. Commission o f the European Communities

Stoddart, D.E. International Organization for
Standardization

SENIOR ADVISORY GROUP (SAG)

Hurst, D. (Chairman) Canada

Klik, F.
Czechoslovakia
Sevcik, A.

23
Clement, B.
France
Messiah, A.
Franzen, L.F. Germany, Federal Republic o f
Ganguly, A.K . India
Uchida, H. Japan
V61ez, C. M exico
Hedgran, A. Sweden
Zuber, J.F. Switzerland
Ostashenko, V.
Union o f Soviet Socialist Republics
Kovalevich, O .M .
Gausden, R .A . United Kingdom

Hendrie, J.
United States o f America
Minogue, B.
Maurer, H.
Commission o f the European Communities
Pel6, J.P.

Burkhardt, W. Council for Mutual Economic Assistance

Nilson, R. International Organization for
Standardization
Stadie, K.B. OECD/Nuclear Energy Agency

IAEA staff members

Konstantinov, L .V . Scientific Co-ordinator
Raisic, N. Scientific Secretary (Quality Assurance)
Iansiti, E. Scientific Secretary (SAG)

During the revision phase the following perts participated in one or more of the
meetings (1987-1988):

WORKING GROUP
Thomas, R. Canada
Dabek, W. Poland
Morrison, W .M . United States o f America

AD HOC ADVISORY GROUP

Goller, K. (Chairman) United States o f America

Harvie, J. Canada

24
Yang, Juntao China
Conte, M.
France
de Mazancourt, R.

Kraut, A.
Germany, Federal Republic o f
Biichler, H.

Bajaj, S.S. India

Dabek, W. Poland
de Munk, P. Netherlands

Jansson, E. Sweden
Isaev, A. Union o f Soviet Socialist Republics

Vinck, W .
Commission o f the European Communities
Goppel, M.

TECHNICAL COMMITTEE
Dabek, W . (Chairman) Poland
Barbier, R. France
Isaev, A. Union o f Soviet Socialist Republics

de Vrey, G .A . Commission o f the European Communities

Kaden, W . FORATOM

NUCLEAR SAFETY STANDARDS ADVISORY GROUP (NUSSAG)

Ryder, E. (Chairman) United Kingdom
Sajaroff, P. Argentina
Brooks, G. Canada
Dong, Bainian China

Havel, S. Czechoslovakia

Laverie, M. France
Hohlefelder, W .
Germany, Federal Republic o f
Gast, K.
Sarma, M .S.R. India

Ishikawa, M. Japan

Versteeg, J. Netherlands
Lee, Sang-Hoon Republic o f Korea
Reisch, F. Sweden

25
Kovalevich, O .M .
Union o f Soviet Socialist Republics
Isaev, A.

W oods, P. United Kingdom

Denton, H.
Hauber, R. United States o f America
Rosztoczy, Z.

Copic, M. Yugoslavia

Pel6, J.P. Commission o f the European Communities

IAEA Staff Members

Almeida, C. Scientific Secretary (Governmental Organization)
Fischer, J. Scientific Secretary (Design, NUSSAG)
Giuliani, P. Scientific Secretary (Siting)

Novak, S. Scientific Secretary (Operation)

Pieroni, N. Scientific Secretary (Quality Assurance)
Karbassioun, A.

26
 LIST OF NUSS PROGRAMME TITLES

It should be noted that some books in the

series may be revised in the near future.
Those that have already been revised are indicated by the
addition o f ‘(Rev. 1 )’ to the number.

1. GOVERNMENTAL ORGANIZATION

50-C-G (Rev. 1) Code on the safety o f nuclear power plants: Governmental 1988
organization

Safety Guides
50-SG-G1 Qualifications and training o f staff o f the regulatory body 1979
for nuclear power plants

50-SG-G2 Information to be submitted in support o f licensing 1979

applications for nuclear power plants

50-SG-G3 Conduct o f regulatory review and assessment during the 1980

licensing process for nuclear power plants

50-SG-G4 Inspection and enforcement by the regulatory body for 1980

nuclear power plants

50-SG-G6 Preparedness o f public authorities for emergencies at 1982

nuclear power plants

50-SG-G8 Licences for nuclear power plants: content, format and 1982
legal considerations

50-SG-G9 Regulations and guides for nuclear power plants 1984

2. SITING

50-C-S (Rev. 1) Code on the safety o f nuclear power plants: Siting 1988

Safety Guides
50-SG-S1 Earthquakes and associated topics in relation to nuclear 1979
power plant siting

50-SG-S2 Seismic analysis and testing o f nuclear power plants 1979

50-SG-S3 Atmospheric dispersion in nuclear power plant siting 1980

50-SG-S4 Site selection and evaluation for nuclear power plants with 1980
respect to population distribution

27
50-SG-S5 External man-induced events in relation to nuclear power 1981
plant siting

50-SG-S6 Hydrological dispersion o f radioactive material in relation 1985

to nuclear power plant siting

50-SG-S7 Nuclear power plant siting: hydrogeological aspects 1984

50-SG-S8 Safety aspects o f the foundations o f nuclear power plants 1986

50-SG-S9 Site survey for nuclear power plants 1984

50-SG-S10A Design basis flood for nuclear power plants on river sites 1983

50-SG-S10B Design basis flood for nuclear power plants on coastal

sites 1983

50-SG-S11A Extreme meteorological events in nuclear power plant 1981

siting, excluding tropical cyclones

50-SG-S11B Design basis tropical cyclone for nuclear power plants 1984

3. DESIGN
50-C-D (Rev. 1) Code on the safety o f nuclear power plants: Design 1988

Safety Guides
50-SG-D1 Safety functions and component classification for 1979
BWR, PWR and PTR

50-SG-D2 Fire protection in nuclear power plants 1979

50-SG-D3 Protection system and related features in nuclear 1980

power plants

50-SG-D4 Protection against internally generated missiles and 1980

their secondary effects in nuclear power plants

50-SG-D5 External man-induced events in relation to nuclear 1982

power plant design

50-SG-D6 Ultimate heat sink and directly associated heat transport 1981
systems for nuclear power plants

50-SG-D7 Emergency power systems at nuclear power plants 1982

50-SG-D8 Safety-related instrumentation and control systems for 1984

nuclear power plants

50-SG-D9 Design aspects o f radiation protection for nuclear 1985

power plants

50-SG-D10 Fuel handling and storage systems in nuclear power 1984

plants

28
50-SG-D11 General design safety principles for nuclear power plants 1986

50-SG-D12 Design o f the reactor containment systems in nuclear 1985

power plants

50-SG-D13 Reactor cooling systems in nuclear power plants 1986

50-SG-D14 Design for reactor core safety in nuclear power plants 1986

4. OPERATION
5 0 -C -0 (Rev. 1) Code on the safety o f nuclear power plants: Operation 1988

Safety Guides
50-SG-01 Staffing o f nuclear power plants and the recruitment, 1979
training and authorization o f operating personnel

50-SG -02 In-service inspection for nuclear power plants 1980

50-SG -03 Operational limits and conditions for nuclear power 1979
plants

50-SG -04 Commissioning procedures for nuclear power plants 1980

50-SG -05 Radiation protection during operation o f nuclear 1983

power plants

50-SG -06 Preparedness o f the operating organization (licensee) 1982

for emergencies at nuclear power plants

50-SG -07 Maintenance o f nuclear power plants 1982

50-SG -08 Surveillance o f items important to safety in nuclear 1982

power plants

50-SG -09 Management o f nuclear power plants for safe operation 1984

50-SG -010 Core management and fuel handling for nuclear 1985
power plants

50-SG-011 Operational management o f radioactive effluents and 1986

wastes arising in nuclear power plants

5. QUALITY ASSURANCE
50-C-QA (Rev. 1) Code on the safety o f nuclear power plants: 1988
Quality assurance

Safety Guides
50-SG-QA1 Establishing o f the quality assurance programme for a 1984
nuclear power plant project

29
50-SG-QA2 Quality assurance records system for nuclear 1979
power plants

50-SG-QA3 Quality assurance in the procurement o f items and 1979

services for nuclear power plants

50-SG-QA4 Quality assurance during site construction o f nuclear 1981

power plants

50-SG-QA5 Quality assurance during commissioning and operation 1986

(Rev. 1) o f nuclear power plants

50-SG-QA6 Quality assurance in the design o f nuclear power plants 1981

50-SG-QA7 Quality assurance organization for nuclear power plants 1983

50-SG-QA8 Quality assurance in the manufacture o f items for 1981

nuclear power plants

50-SG-QA10 Quality assurance auditing for nuclear power plants 1980

50-SG-QA11 Quality assurance in the procurement, design and 1983

manufacture o f nuclear fuel assemblies

30
 SELECTION OF IAEA PUBLICATIONS RELATING
TO THE SAFETY OF
NUCLEAR POWER PLANTS
SAFETY SERIES
9 Basic safety standards for radiation protection: 1982
1982 edition

46 Monitoring o f airborne and liquid radioactive 1978

releases from nuclear facilities to the environment

49 Radiological surveillance o f airborne contaminants 1979

in the working environment

52 Factors relevant to the decommissioning o f land-based 1980

nuclear reactor plants

55 Planning for off-site response to radiation 1981

accidents in nuclear facilities

57 Generic models and parameters for assessing 1982

the environmental transfer o f radionuclides
from routine releases: Exposures o f critical groups

67 Assigning a value to transboundary radiation exposure 1985

69 Management o f radioactive wastes from nuclear 1985

power plants

72 Principles for establishing intervention levels for the 1985

protection o f the public in the event o f a nuclear accident
or radiological emergency (being revised)
73 Emergency preparedness exercises for nuclear 1985
facilities: Preparation, conduct and evaluation

77 Principles for limiting releases o f radioactive 1986

effluents into the environment

79 Design o f radioactive waste management systems 1986

at nuclear power plants

81 Derived intervention levels for application in 1986

in controlling radiation doses to the public in the event o f a
nuclear accident or radiological emergency: Principles,
procedures and data

84 Basic principles for occupational radiation monitoring 1987

86 Techniques and decision making in the assessment 1987

o f off-site consequences o f an accident in a nuclear facility

31
75-INSAG-l Summary report on the post-accident review meeting 1986
on the Chernobyl accident

75-INSAG-2 Radionuclide source terms from severe accidents to 1987

nuclear power plants with light water reactors

75-INSAG-3 Basic safety principles for nuclear power plants 1988

TECHNICAL REPORTS SERIES

155 Thermal discharges at nuclear power stations 1974

163 Neutron irradiation embrittlement o f reactor pressure 1975

vessel steels (being revised)
189 Storage, handling and movement o f fuel and 1979
related components at nuclear power plants

198 Guide to the safe handling o f radioactive wastes at 1980

nuclear power plants

200 Manpower development for nuclear power: 1980

A guidebook

202 Environmental effects o f cooling systems 1980

217 Guidebook on the introduction o f nuclear power 1982

224 Interaction o f grid characteristics with design and 1983

performance o f nuclear power plants: A guidebook

230 Decommissioning o f nuclear facilities: 1983

Decontamination, disassembly and waste management

237 Manual on quality assurance programme auditing 1984

239 Nuclear power plant instrumentation and control: 1984

A guidebook

242 Qualification o f nuclear power plant operations 1984

personnel: A guidebook

249 Decontamination o f nuclear facilities to permit 1985

operation, inspection, maintenance, modification or plant
decommissioning

262 Manual on training, qualification and certification 1986

o f quality assurance personnel

267 Methodology and technology o f decommissioning 1986

nuclear facilities

268 Manual on maintenance o f systems and components 1986

important to safety

32
271 Introducing nuclear power plants into electrical power 1987
systems o f limited capacity: Problems and remedial
measures

274 Design o f off-gas and air cleaning systems at nuclear 1987

power plants

TECDOC SERIES
225 Planning for off-site response to radiation accidents 1980
in nuclear facilities

238 Management o f spent ion-exchange resins from 1981

nuclear power plants

248 Decontamination o f operational nuclear power plants 1981

276 Management o f radioactive waste from nuclear 1983
power plants

294 International experience in the implementation o f 1983

lessons learned from the Three Mile Island accident

303 Manual on the selection o f appropriate quality assurance 1984

programmes for items and services o f a nuclear power plant

308 Survey o f probabilistic methods in safety and risk 1984

assessment for nuclear power plant licensing

332 Safety aspects o f station blackout at nuclear power plants 1985

341 Developments in the preparation o f operating 1985
procedures for emergency conditions at nuclear power
plants

348 Earthquake resistant design o f nuclear facilities with 1985

limited radioactive inventory

355 Comparison o f high efficiency particulate filter testing 1985

methods

377 Safety aspects o f unplanned shutdowns and trips 1986

379 Atmospheric dispersion models for application in 1986
relation to radionuclide releases

387 Combining risk analysis and operating experience 1986

390 Safety assessment o f emergency electric power systems 1986
for nuclear power plants

416 Manual on quality assurance for the survey, evaluation and 1987
confirmation o f nuclear power plant sites

33
424 Identification o f failure sequences sensitive to 1987
human error

425 Simulation of a loss o f coolant accident 1987

443 Experience with simulator training for emergency 1987

conditions

444 Improving nuclear power plant safety through 1987

operator aids

450 Dose assessments in NPP siting 1988

451 Some practical implications of source term 1988

reassessment

PROCEEDINGS SERIES

STI/PUB/566 Current nuclear power plant safety issues 1981

STI/PUB/593 Quality assurance for nuclear power plants 1982

STI/PUB/628 Nuclear power plant control and instrumentation 1983

STI/PUB/645 Reliability o f reactor pressure components 1983

STI/PUB/673 IAE A safety codes and guides (NUSS) in the light of 1985
current safety issues

STI/PUB/700 Source term evaluation for accident conditions 1986

STI/PUB/701 Emergency planning and preparedness for nuclear 1986

facilities

STI/PUB/716 Optimization o f radiation protection 1986

STI/PUB/759 Safety aspects of the ageing and maintenance o f 1988

nuclear power plants

STI/PUB/761 Nuclear power performance and safety 1988

STI/PUB/782 Severe accidents in nuclear power plants 1988

34
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00
CO
IN T E R N A T IO N A L S U B JE C T G R O U P : II
A T O M IC E N E R G Y A G E N C Y Nuclear Safety and Environm ental Protection/Nuclear Safety
V IE N N A , 1988