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No. 50-SG- QA 6IAEA SAFETY GUIDES

Quality Assurance in the Design of Nuclear Power PlantsA Safety Guide

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CATEGORIES OF IAEA SAFETY SERIES

From Safety Series No. 46 onwards the various publications in the series aredivided into fo u r categories, as follows:

(1) IAEA Safety Standards. Publications in this category comprise the Agency’s safety standards as defined in “The Agency’s Safety Standards and Measures” , approved by the Agency’s Board o f Governors on 25 February 1976 and set forth in IAEA docum ent INFCIRC/18/Rev. 1. They are issued under the authority o f the Board o f Governors, and are m andatory for the Agency’s own operations and for Agency-assisted operations. Such standards comprise the Agency’s basic safety standards, the Agency’s specialized regulations and the Agency’s codes o f practice. The covers are distinguished by the wide red band on the lower half.

(2) IAEA Safety Guides. As stated in IAEA docum ent INFCIRC/18/Rev. 1, referred to above, IAEA Safety Guides supplement IAEA Safety Standards and recommend a procedure or procedures that might be followed in implementing them. They are issued under the authority o f the Director General of the Agency. The covers are distinguished by the wide green band on the lower half.

(3) Recommendations. Publications in this category, containing general recom m endations on safety practices, are issued under the authority of the D irector General o f the Agency. The covers are distinguished by the wide brown band on the lower half.

(4) Procedures and Data. Publications in this category contain inform ation on procedures, techniques and criteria pertaining to safety m atters. They are issued under the authority o f the D irector General o f the Agency. The covers are distinguished by the wide blue band on the. lower half.

N o te: The covers o f publications brought o u t within the fram ew ork o f the N U SS (Nuclear Safety Standards) Programme are distinguished by the wide yellow band on the upper half.


QUALITY ASSURANCE IN THE DESIGN

OF NUCLEAR POWER PLANTS

A Safety Guide


The following States are Members of the International Atomic Energy Agency :

A FG H A N ISTA NALBA N IAA LG ER IAA R G E N T IN AA U STR A LIAA U STR IABA NG LA D ESHBELGIUMBO LIV IAB R A ZILBU LG A RIABURMABY ELO RU SSIA N SO V IET

SO C IA LIST REPU BLIC CA NA D A C H ILE COLOM BIA CO STA RICA CUBA CY PRU SCZECH O SLO V A K IA D EM O CRA TIC KAM PUCHEA D EM O CRA TIC PEO PLE’S

REPU BLIC O F K O REA D EN M A RKDOM INICAN REPU BLICECU A D O REG Y PTEL SA L V A D O RET H IO PIAFIN L A N DFR A N C EGABONG ERM A N D EM O CRA TIC REPU BLICG ERM A N Y , FE D E R A L REPU BLIC O FGHANAG R EEC EG U A TEM A LAHAITI

HOLY SEEHU N G A RYICELA N DIN D IAIN D O N ESIAIRA NIR A QIR E L A N DIS R A E LITA LYIV O R Y CO ASTJAM A ICAJAPA NJO R D A NKEN YAK O REA , REPU BLIC O F KUW AIT LEBAN O N L IB E R IALIBYAN A RA B JA M A H IR IY ALIE C H T EN ST EINLU X EM BOU RGM AD A GA SCARM ALAYSIAMALIM A U RITIU SM EXICOM ONACOM ON G OLIAM OROCCON ETH ER L A N D SNEW ZEA LA N DN IC A R A G U AN IG E RN IG E R IANORW AYPAK ISTA NPANAM APA R A G U A YPER U

PH ILIPPIN ESPO LA N DPO RTU G A LQ A T A RROM ANIASAUDI A R A B IASEN EG A LSIE R R A LEO N ESIN G A PO R ESO U TH A FR IC ASPAINSRI LA N KASUDANSWEDENSW ITZERLA N DSY R IA N A RA B R EPU BLICT H A ILA N DT U N ISIATU R K EYU GA N DAU K R A IN IA N SO V IE T SO C IA LIST

REPU BLIC U NION O F SO V IET SO C IA LIST.

REPU BLICS U N IT ED A RAB EM IRA TES U N IT ED KING D OM O F G R E A T

BRITA IN A N D N O R T H E R N IR E L A N D

U N IT ED REPU BLIC O F CA M ERO O N

U N ITED REPU BLIC O F T A N ZA N IA

U N ITED STA TES O F AM ERICA U RUG U AY V EN EZU ELA V IE T NAM Y U G O SLA V IA Z A IR E ZAMBIA

The A gency’s S ta tu te was app roved on 23 O c to b e r 1956 by the C onference on the S ta tu te o f th e IAEA held a t U nited N ations H eadquarters , N ew Y ork ; it en te red in to fo rce on 29 Ju ly 1957. T he H eadquarters o f th e A gency are situ a ted in V ienna. Its p rinc ipal objective is “ to accelerate and enlarge th e c o n tr ib u tio n o f a to m ic energy to peace, hea lth and p ro sperity th ro u g h o u t th e w orld".

© IAEA, 1981

Perm ission to rep roduce o r tran sla te th e in fo rm atio n co n ta in ed in this p u b lica tion m ay be o b ta in ed by w riting to th e In te rn a tio n a l A tom ic Energy A gency, W agram erstrasse 5, P .O . Box 100, A -1400 V ienna , A ustria .

Printed by the IAEA in Austria September 1981


SAFETY SERIES NO. 50-SG-QA6

QUALITY ASSURANCE IN THE DESIGN

OF NUCLEAR POWER PLANTS

A Safety Guide

INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA, 1981


THIS SAFETY GUIDE IS ALSO PUBLISHED IN FRENCH, RUSSIAN AND SPANISH

QUALITY ASSURANCE IN THE DESIGN OF NUCLEAR POWER PLANTS: A SAFETY GUIDE

IAEA, VIENNA, 1981 STI/PUB/605

ISBN 9 2 - 0 - 1 2 3 8 8 1 - 9


FOREWORD by the Director General

The demand for energy is continually growing, both in the developed and the developing countries. Traditional sources o f energy such as oil and gas will probably be exhausted within a few decades, and present world-wide energy demands are already overstraining present capacity. Of the new sources nuclear energy, with its proven technology, is the most significant single reliable source available for closing the energy gap that is likely, according to the experts, to be upon us by the turn o f the century.

During the past 25 years, 19 countries have constructed nuclear power plants. More than 200 power reactors are now in operation, a further 150 are planned, and, in the longer term , nuclear energy is expected to play an increasingly im portant role in the development o f energy programmes throughout the world.

Since its inception the nuclear energy industry has maintained a safety record second to none. Recognizing the importance o f this aspect o f nuclear power and wishing to ensure the continuation o f this record, the International Atomic Energy Agency established a wide-ranging programme to provide the Member States with guidance on the many aspects of. safety associated with thermal neutron nuclear power reactors. The programme, at present involving the preparation and publication o f about 50 books in the form o f Codes o f Practice and Safety Guides, has become known as the NUSS programme (the letters being an acronym for Nuclear Safety Standards). The publications are being produced in the Agency’s Safety Series and each one will be made available in separate English, French, Russian and Spanish versions. They will be revised as necessary in the light o f experience to keep their contents up to date.

The task envisaged in this programme is a considerable and taxing one, entailing numerous meetings for drafting, reviewing, amending, consolidating and approving the documents. The Agency wishes to thank all those Member States that have so generously provided experts and material, and those many individuals, named in the published Lists o f Participants, who have given their time and efforts to help in implementing the programme. Sincere gratitude is also expressed to the international organizations that have participated in the work.

The Codes o f Practice and Safety Guides are recommendations issued by the Agency for use by Member States in the context o f their own nuclear safety requirements. A Member State wishing to enter into an agreement with the Agency for the Agency’s assistance in connection with the siting, construction,


commissioning, operation or decommissioning o f a nuclear power plant will be required to follow those parts o f the Codes o f Practice and Safety Guides that pertain to the activities covered by the agreement. However, it is recognized that the final decisions and legal responsibilities in any licensing procedures always rest with the Member State.

The NUSS publications presuppose a single national framework within which the various parties, such as the regulatory body, the applicant/licensee and the supplier or manufacturer, perform their tasks. Where more than one Member State is involved, however, it is understood that certain modifications to the procedures described may be necessary in accordance with national practice and with the relevant agreements concluded between the States and between the various organizations concerned.

The Codes and Guides are w ritten in such a form as would enable a Member State, should it so decide, to make the contents o f such docum ents directly applicable to activities under its jurisdiction. Therefore, consistent with accepted practice for codes and guides, and in accordance with a proposal o f the Senior Advisory Group, “ shall” and “ should” are used to distinguish for the potential user between a firm requirement and a desirable option.

The task of ensuring an adequate and safe supply of energy for coming generations, and thereby contributing to their well-being and standard o f life, is a m atter o f concern to us all. It is hoped that the publication presented here, together with the others being produced under the aegis of the NUSS programme, will be o f use in this task.

STATEMENT by the Senior Advisory Group

The Agency’s plans for establishing Codes of Practice and Safety Guides for nuclear power plants have been set out in IAEA document GC(XVIII)/526/M od. 1. The programme, referred to as the NUSS programme, deals with radiological safety and is at present limited to land-based stationary plants with therm al neutron reactors designed for the production of power. The present publication is brought out within this framework.

A Senior Advisory Group (SAG), set up by the Director General in September 1974 to implement the programme, selected five topics to be covered by Codes of Practice and drew up a provisional list o f subjects for Safety Guides supporting the five Codes. The SAG was entrusted with the task o f supervising, reviewing and advising on the project at all stages and approving draft documents for onward transmission to the Director General. One Technical Review Com m ittee (TRC), composed o f experts from Member States, was created for each o f the topics covered by the Codes o f Practice.


In accordance with the procedure outlined in the above-mentioned IAEA docum ent, the Codes of Practice and Safety Guides, which are based on docum entation and experience from various national systems and practices, are first drafted by expert worjting groups consisting o f two or three experts from Member States together with Agency staff members. They are then reviewed and revised by the appropriate TRC. In this undertaking use is made o f both published and unpublished material, such as answers to questionnaires, subm itted by Member States.

The draft documents, as revised by the TRCs, are placed before the SAG. A fter acceptance by the SAG, English, French, Russian and Spanish versions are sent to Member States for comments. When' changes and additions have been made by the TRCs in the light o f these comments, and after further review by the SAG, the drafts are transm itted to the Director General, who submits them, as and when appropriate, to the Board o f Governors for approval before final publication.

The five Codes o f Practice cover the following topics:

Governmental organization for the regulation of nuclear power plantsSafety in nuclear power plant sitingDesign for safety o f nuclear power plantsSafety in nuclear power plant operationQuality assurance for safety in nuclear power plants.

These five Codes establish the objectives and minimum requirements that should be fulfilled to provide adequate safety in the operation o f nuclear power plants.

The Safety Guides are issued to describe and make available to Member States acceptable m ethods of implementing specific parts of the relevant Codes o f Practice. Methods and solutions varying from those set out in these Guides may be acceptable, if they provide at least comparable 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 of Practice and Safety Guides establish an essential basis for safety, they may not be sufficient or entirely applicable. O ther safety documents published by the Agency should be consulted as necessary.

In some cases, in response to particular circumstances, additional requirements may need to be met. Moreover, there will be special aspects which have to be assessed by experts on a case-by-case basis.

Physical security o f fissile and radioactive materials and o f a nuclear power plant as a whole is mentioned where appropriate but is not treated in detail. Non-radiological aspects o f industrial safety and environmental protection are not explicitly considered.


When an appendix is included it is considered to be an integral part o f the docum ent and to have the same status as that assigned to the main tex t o f the document.

On the other hand annexes, footnotes, lists o f participants and bibliographies are only included to provide inform ation or practical examples that might be helpful to the user. Lists o f additional bibliographical material may in some cases be available at the Agency.

A list of relevant definitions appears in each book.These publications are intended for use, as appropriate, by regulatory bodies

and others concerned in Member States. To fully comprehend their contents, it is essential that the o ther relevant Codes o f Practice and Safety Guides be taken into account.

NO TE

The follow ing publications o f the N U SS programme are referred to in the te x t o f the present Safety Guide:

Safety Series No. 50-SG-D1 Safety Series No. 50-C-QA Safety Series No. 50-SG-QA2 Safety Series No. 50-SG-QA10

The titles are given in the Provisional L ist o f N U SS Programme Titles printed at the end o f this Guide, together with information about their publication date. Instructions on how to order them will be fo u n d on the last page o f this Guide.


CONTENTS

1. INTRODUCTION ............................................................................................... 1

1.1. Scope ............................................................................................................ 11.2. Responsibility .............................................................................................. 2

2. QUALITY ASSURANCE PROGRAMME REQUIREMENTS .................. 2

3. DESIGN INPUT REQUIREMENTS ............................................................. 4

3.1. General ....................................................................................................... 43.2. Responsibilities and requirem ents ....................................................... 43.3. Checking and approval .......................................................................... 4

4. DESIGN PROCESS PLANNING AND PERFORMANCE ....................... 4

4.1. General ....................................................................................................... 44.2. Design analyses ................................................................................ ;....... 54.3. Drawings ....................................................................................................... 54.4. Specifications and other design docum ents ......................................... 6

5. DESIGN INTERFACE CONTROL .................................................................. 6

5.1. General ....................................................................................................... 65.2. Interface control during design process .............................................. 7

5.2.1. External5.2.2. Internal

6. COMMUNICATION BETWEEN DESIGN ORGANIZATION ANDOTHER ORGANIZATIONS .......................................................................... 8

7. DESIGN VERIFICATION ................................................................................ 9

7.1. Design reviews .............................................................................................. 107.2. Alternative calculations ........................................................................... 117.3. Qualification testing ............................................................................... 11

8. DOCUMENT CONTROL ................................................................................. 12

8.1. Document preparation, review and approval .................................... 138.2. Document release and distribution ....................................................... 138.3. Document change control ...................................................................... 13


9. CONTROL OF DESIGN CHANGES ........................................................... 13

10. CORRECTIVE ACTION ................................................................................... 14

11. QUALITY ASSURANCE RECORDS ........................................................... 15

12. AUDITS ................................................................................................................ 15

ANNEX I. Typical areas where procedures for design quality assuranceshould be developed ............................................................................... 17

ANNEX II. Typical design inputs .......................................................................... 18

DEFINITIONS ............................................................................................................ 21

LIST OF PARTICIPANTS ......................................................................................... 25

PROVISIONAL LIST OF NUSS PROGRAMME TITLES ............................... 29


1. INTRODUCTION

The IAEA Code of Practice on Quality Assurance for Safety in Nuclear Power Plants (IAEA Safety Series No. 50-C-QA), hereinafter referred to as the Code, established requirem ents and recom m endations for control of the design of nuclear power plant items which are im portant to safety.

The establishment and im plem entation of a quality assurance programme in the design o f nuclear power plants provide confidence tha t all relevant criteria, codes and standards have been adequately incorporated into the design and that the required quality has been achieved.

Like the Code, the present Guide was prepared as part of the IAEA’s programme, referred to as the NIJSS programme, for establishing Codes of Practice and Safety Guides related to land-based stationary therm al neutron power plants.

As used in this Guide, the term “ design” refers to the technical and managem ent process which begins w ith identification of the design input and which leads to and includes the issuance o f a design outpu t docum ent.

The extent to which the individual requirem ents and recom m endations of this Guide apply will depend primarily upon the effect on safety o f an error in service or the m alfunctioning o f an item. O ther factors for consideration-include the following:

(1) The com plexity, uniqueness or novelty o f the item to be designed(2) The degree o f standardization of the item(3) The accessibility of the item, after installation in the plant, for

maintenance, in-service inspection or replacement.

1.1. Scope

This Safety Guide provides the requirem ents and recom m endations related to the establishment and im plem entation o f quality assurance for design o f items for a nuclear power plant.

The requirem ents o f this Guide shall be applied to the extent necessary during all constituent activities of the nuclear power plant project, such as design, m anufacture, construction, commissioning and operations. Its requirem ents and recom m endations shall be im plemented, as appropriate, by the responsible organization or by its designated representatives: by plant designers, architect-engineers or m anufacturers, when involved in performing design activities related to items to be m anufactured; by site constructors, when involved , in field engineering activities; by plant operators and other organizations, when involved in design activities related to plant m odifications or to selection of

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spare or replacement parts; and by design consultants and other technical organizations, when performing any engineering activity that affects the work of o ther design organizations during various stages of nuclear power plant projects.

1.2. Responsibility

The organization having overall responsibility for a nuclear power plant (hereinafter referred to as the responsible organization) shall be responsible for the establishment and im plem entation of the quality assurance programme in the design of items for nuclear power plants. This organization may delegate to other organizations the work of establishing or implementing all or part of the quality assurance programme for design, bu t shall retain responsibility for overall effectiveness, w ithout prejudice to the designers’ obligations and/or legal responsibilities. It is the function o f the responsible organization, or its designated representative, to identify in the design of the plant the structures, systems and components to which the various provisions of this Guide apply and the extent to which they apply. When this identification has been made, it is the function of each contractor organization to ensure that the provisions pertaining to its responsibilities are carried out, and to ensure tha t its suppliers of design-related services carry out the provisions that pertain to their responsibilities.

2. QUALITY ASSURANCE PROGRAMME REQUIREMENTS

A quality assurance programme shall be developed and approved as early in the project as possible and shall be implemented prior to the commencement of any of the design activities to which it applies. Where the to tal plant design is shared among various constituent organizations, the responsible organization shall ensure the preparation of an overall quality assurance programme for design, in order to provide for the necessary co-ordination among the constituent organizations. This overall programme shall delineate the design interfaces betw een the constituent organizations, and between those organizations and the responsible organization. It shall also identify specific task responsibilities o f each organization.

Each constituent programme shall define the internal organizational structure within which the programme is to be im plem ented, and shall delineate the authority and responsibility of the persons and organizations responsible for performing activities such as design process or design verification. Individuals who

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are assigned the responsibility for performing these activities shall be appropriately trained and sufficiently qualified for the specific responsibility to which they are assigned. The responsible organization shall either delineate the training and qualification requirem ents for design personnel assigned to the power plant project, or shall assign to constituent organizations the specific responsibility for accomplishing this delineation, subject to its review and acceptance.

To qualify individuals to perform design activities, one or more of the following criteria may be used:

(1) Educational requirements(2) Experience requirements(3) Completion of prescribed training courses(4) Evaluation of relevant on-the-job performance(5) Possession of a certificate awarded by a recognized technical society

or governmental agency.

The programme shall identify the point at which quality assurance activities are initiated and shall provide the requisite depth o f coverage for the various types of design activities. Different degrees of controls may be assigned to different design activities, depending on their nature. Consequently, a system may be considered which allows for the application of a graded design quality assurance programme. Factors that should be considered in developing the gradation for a specific plant are:

(1) Degree of importance to safety of the items being designed. For further inform ation the reader is referred to the Safety Guide on Safety Functions and Com ponent Classification for BWR, PWR and PTR (IAEA Safety Series No. 50-SG-D1).

(2) Nature o f the design activities performed by the different organizations having design responsibilities (e.g. responsible organization, m anufacturer, architect-engineer, constructor), and the characteristics of the design interfaces between them.

(3) State of the art of the various com ponents, systems and structures (e.g. experimental, developmental or standard design).

(4) Nature of the design phase (e.g. conceptual, preliminary, detailed design or field engineering).

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The programme shall require preparation o f specific procedures for the design process, design verification to ensure tha t activities are carried out in a planned, controlled, orderly and correct manner, and provision o f an acceptable basis for the performance of design audits. Annex I lists typical areas where design quality procedures should be developed.

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3. DESIGN INPUT REQUIREMENTS

3.1. General

Procedures shall be established to ensure that the applicable design inputs and changes thereto are correctly identified, docum ented, approved and controlled. These procedures shall ensure tha t the inputs are specified on a timely basis and that they contain the level o f detail necessary to perm it the activity to be carried out correctly, and to provide a consistent basis for making design decisions, accomplishing verification measures and evaluating changes.

3.2. Responsibilities and requirements

The responsible organization or its designated representative shall be responsible for establishing design inputs and for implementing changes to them. The types o f inputs to be identified shall be determ ined by the area o f responsibilities of the organization performing the design, and shall include as applicable:

(1) Identification of general docum ents (e.g. regulatory requirem ents, engineering codes and standards). When applicable, reference to specific parts o f docum ents should be made.

(2) Specific inputs (e.g. technical data, performance requirements, interface documents).

Examples of design inputs are given in Annex II.

3.3. Checking and approval

Design inputs shall be checked and approved, in accordance with established procedures, to preclude the use o f incorrect input data. Special atten tion shall be given to the interfaces between organizations, or between units within organizations, as described in section 5.

4. DESIGN PROCESS PLANNING AND PERFORMANCE

4.1. General

Design activities shall be carried ou t in accordance w ith prescribed procedures.

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Control measures shall be established and docum ented to ensure that applicable specified design inputs (e.g. regulatory requirements, design bases, codes and standards) are correctly translated into specifications, drawings, procedures or instructions. These measures shall include provisions to ensure that quality requirem ents are stated in the design docum ent, applicable quality standards are specified and selection o f the quality standards is reviewed and approved. Any changes and deviations from specified design requirem ents and quality standards shall be controlled. Measures shall also be established to select and review for suitability the applications of any materials, parts, equipm ent and processes that are essential to functioning o f the structure, system or com ponent. Control measures shall, as a minimum, cover all design aspects im portant to safety including such items as: (a) radiation protection; (b) physics, stress, thermal, hydraulic, seismic and accident analyses; (c) com patibility of materials; (d) accessibility and suitability for in-service inspection; (e) maintenance and repair; (f) delineation of acceptance criteria for inspection and tests; and (g) requirem ents related to fabrication, inspection and non-destructive examination.

Documents such as job specifications, work instructions, planning sheets and procedure manuals shall be established and there shall be provisions for control, checking and reviewing by personnel who are experienced in the subject activity.

Design activities shall be docum ented in sufficient detail to perm it verification and auditing as prescribed by this Guide.

4.2. Design analyses

Design analyses shall be perform ed in a planned and systematic m anner and in accordance w ith approved procedures.

Analyses shall be sufficiently detailed as to purpose, m ethod, assumptions, design inputs, references and units tha t a person technically qualified in the subject can review and understand them and verify the adequacy o f the results. Analyses shall be identifiable and be retrievable by subject, originator, reviewer, date, or other data. If a com puter is used, the com puter code shall be checked in an approved and docum ented m anner, prior to its use or application. For each specific analysis which employs com puter codes, the input data shall be checked and the ou tpu t examined to ensure th a t it is compatible w ith the input. Design analysis docum ents shall be legible and shall be in a form suitable for reproduction, filing and retrieving.

4.3. Drawings

Procedures shall be established for preparing, modifying and controlling drawings. Subjects which should be covered by such procedures include:

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(1) Drafting office standards(2) Standardized symbols(3) Identification system(4) Indication o f status(5) Checking m ethods(6) Requirements for review and approval(7) Issuance and distribution(8) Storage and con tro l'o f originals or master copies(9) Revisions, and control o f obsolete documents

(10) As-built drawings(11) Non-compliance w ith drawing requirements.

4.4. Specifications and other design documents

Procedures shall be established for preparation and control of specifications and other design docum ents such as installation instructions, and commissioning and test procedures. Subjects which should be covered by such procedures include:

(1) Form at requirements(2) Identification system (a uniform system for all items)(3) Indication of status(4) Requirements for review and approval(5) Issuance and distribution(6) Storage and control o f originals or master copies(7) Revisions(8) Non-compliance w ith specifications.

5. DESIGN INTERFACE CONTROL

5.1. General

Measures shall be established during the design phase to control external interfaces (those between design organizations) and internal interfaces (those between design units), in order to obtain a comprehensive and homogeneous design.

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5.2. Interface control during design process

5.2.1. External

5.2.1.1. Identification of interfaces

The external interfaces between organizations performing work affecting the quality of design — those organizations providing criteria, designs, specifications and technical direction — shall be identified in writing.

5.2.1.2. Responsibilities

The responsibilities o f each organization shall be defined and docum ented in sufficient detail to cover the preparation, review, approval, issue and distribution of docum ents involving design interfaces. Responsibilities may be set forth in tabular form or on flow charts and should be accompanied by appropriate explanatory text.

5.2.1.3. Lines o f com m unication

Systematic m ethods shall be established for communicating needed design inform ation (including changes as work progresses) across external design interfaces. Documents should identify key personnel in the com m unication channels and their responsibilities for decision-making, resolving problems, providing and reviewing inform ation, and taking other necessary action.

5.2.1.4. D ocum entation

Procedures shall be established to control the flow o f design inform ation between organizations. When design inform ation is transm itted from one organization to another, it shall be docum ented in specifications, drawings or other similar controlled docum ents which are uniquely identified and are issued by authorized persons. Transm ittals shall identify the status of the inform ation provided and, where necessary, identify incom plete items which require further evaluation, review or approval, so tha t appropriate controls may be initiated. The procedures shall provide tha t design interface inform ation be transm itted to affected organizations and tha t any inform ation requested in the transm ittal be furnished to the requester. Docum entation requesting inform ation or action shall be controlled by a system which ensures tha t the response and the request can be related. Whenever design inform ation is initially transm itted orally or by other inform al means, the transm ittal shall be confirmed prom ptly by a controlled docum ent.

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5.2.2. Internal

5.2.2.1. Identification o f interface

Each organization performing design work shall identify its internal interfaces for managing the flow of design inform ation between its units.

5.2.2.2. Responsibilities

For each organizational unit responsibilities shall be defined and docum ented in sufficient detail to cover the preparation, review, approval, issue, distribution and revision of docum ents involving design interfaces.

5.2.2.3. Lines of communication

Systematic m ethods shall be established for communicating needed design inform ation, including changes as work progresses, across internal design interfaces.

5.2.2.4. D ocum entation

Procedures shall be established to control the flow of design inform ation between organizational units. When design inform ation is transm itted from one unit to another, it shall be docum ented in specifications, drawings and other similar controlled documents. Transmittals shall identify the status of the inform ation provided and, where necessary, identify incomplete items which require further evaluation, review or approval, so tha t appropriate controls may be initiated. Whenever design inform ation is initially transm itted orally or by other inform al means, the transm ittal shall be confirmed prom ptly by a controlled document.

6. COMMUNICATION BETWEEN DESIGN ORGANIZATION

AND OTHER ORGANIZATIONS

Procedures shall be established for lines o f communication between the design organization and organizations involved in other phases of the nuclear power plant project, such as procurem ent, manufacturing, site construction, commissioning and operation. The in ten t should be to ensure proper transmission across organizational interfaces o f inform ation bearing on design, and to initiate any necessary action. These lines o f comm unication should also be used by the design organization for feedback o f inform ation about operating


experience with nuclear power plants. Procedures should follow the principles of section 5.2 of this Guide.

7. DESIGN VERIFICATION

Design verification is the process of reviewing, confirming or substantiating the design to ensure tha t it satisfies all design requirem ents, including: input requirem ents (see section 3 of this Guide); planning and perform ance of the design process (see section 4); and interface controls (see section 5). To provide assurance that verification has been adequately accomplished, one or more o f the m ethods specified in this Guide shall be used in a timely manner.

Design verification, including checking, shall be perform ed by com petent individuals or groups who did no t perform the original design, bu t who may be from the same organization. They shall have access to all relevant information. This verification may be performed by the originator’s supervisor. However, if the supervisor limited the originator’s flexibility in developing the design, by restrictions such as specifying a single design approach or ruling ou t certain design considerations, the supervisor may perform the verification only if all the following conditions are met:

(1) All other provisions of this Guide concerning verifications are satisfied.

(2) Justification for the supervisor’s having restricted the design approach is specifically docum ented and approved in advance by an appropriate level of management above the supervisor.

(3) Quality assurance surveillance or audits include specific provisions to cover the frequency and check the effectiveness o f supervisors’ verifications.

Alternatively, verification may be perform ed in selected areas o f the design by another organization.

It is im portant to recognize tha t cursory supervisory reviews do not constitute design verification within the meaning o f this Guide.

The extent o f design verification may range from spot checking of drawings, specifications and calculations to detailed checking of every safety-related docum ent, and the formal review and assessment of the system design by specialists no t normally or directly associated w ith the plant project. It may also include qualification testing of equipm ent, if it is determ ined tha t that is the optimum m ethod of verification. In determining the m ethod, or combination of methods, to be utilized in the verification process o f a design for a specific item, com ponent, system or structure, the responsible design organization should consider the importance of the item to safety, the complexity of

9


the design, the degree of standardization, the state of the art, and the similarity with previously proven designs. Where the design of an identical structure, system or com ponent used in a particular plant has been subjected to a verification process in accordance with this Guide, the verification process need no t be duplicated. However, the applicability of standardized or previously proven designs, with respect to meeting pertinent design inputs, shall be verified for each application.

Known problems affecting the standardized design and their effects on other features shall be considered. The original design and associated verification measures shall be docum ented and referenced in the files of all subsequent applications o f that design. Where changes to previously verified designs have been made, design verification shall be required for those changes, including evaluation o f their effects on the overall design.

The results o f design verification efforts shall be sufficiently docum ented to allow for surveillance or auditing of the verification m ethod after it has been completed so as to perm it confirm ation that the process has been properly implemented. Identification of checkers, verifiers and management approvals should be clearly indicated and dated.

Subsections 7.1, 7.2 and 7.3 outline the requirem ents for three verification m ethods (design review, alternative calculation and qualification testing), at least one of which should be identified and used by the responsible design organization and described in detail in the quality assurance verification procedures. If it is necessary to utilize more than one m ethod, each one used shall be described in the responsible design organization’s procedures.

7.1. Design reviews

Design reviews are critical reviews of design docum ents and activities to provide assurance that the ou tput docum ents are correct and satisfactory. The extent may range from review by a single person to multi-group reviews within the responsible design organization; or reviewers may encompass several design organizations, including the responsible organization. The type of design review and the m ethod used on a given plant project shall be delineated in the quality assurance programme for design and in the procedures of the responsible design organization. The depth of review may range from a limited check o f specific design docum ents, and of the design approach and the results obtained, to a detailed check or review of the complete design by technical specialists in a formal meeting. As part o f the review, an examination should be made to ensure that procedures have been followed, that the designated people have participated, tha t the results are adequately docum ented and that necessary changes or corrections to the design are implemented and checked prior to release o f the design documents.

10


In the design review, certain basic questions shall be addressed. These questions, as applicable, are as follows:

(1) Were the design input requirem ents covered in section 3 o f this Guide correctly selected? Examples of typical inputs are listed in Annex II.(It should be noted that the selection o f design inputs may have been independently reviewed prior to the design review activity; if so, this aspect may not have to be reviewed at this time.)

(2) Are the assumptions necessary to perform the design activity adequately described and reasonable?

(3) Was an appropriate design m ethod used, and were designated design standards followed?

(4) Were the design inputs correctly incorporated into the design?(5) Were the design process procedures followed?(6) Is the design ou tpu t reasonable, when it is compared to design inputs?(7) Are the necessary design input and verification requirem ents for

interfacing organizations specified in the design docum ents or in supporting procedures or instructions?

7.2. Alternative calculations

Verification of some types of calculations or analyses may be achieved by comparing the results w ith those obtained by alternative m ethods o f calculation or analysis.

Where alternative calculations are performed to verify the correctness of the original calculation, a review shall also be performed to address the appropriateness of assumptions, design input data used, and the com puter code or other calculation m ethod used.

The alternative m ethod used for comparison may be a simpler or less rigorous approach, e.g. use of a hand calculator to check the com puter code output. Although the simplified or less rigorous m ethod need no t produce exactly the same results as the original calculation or analysis, it m ust provide results which are consistent w ith the original ones.

7.3. Qualification testing

Design verification for some designs or for specific design features can be achieved by suitable qualification testing o f a proto type unit.

Where a test programme is used to verify the adequacy of a specific design feature, it shall include suitable qualification testing of a pro to type unit.Testing shall be perform ed, if possible, under the m ost adverse design conditions for the specific features being verified. Where it cannot be carried out under the most adverse design conditions, it may be performed under other conditions

11


if the results can be extrapolated to the most adverse design conditions and if the adequacy of the specific design feature can be verified. Where it is intended that the test programme confirm the adequacy of the overall design, all pertinent operating modes shall be considered in determining these design conditions. Where the test is intended to verify only a specific design feature, the other features o f the design shall be verified by other means. For example, to verify that an instrum entation cabinet is designed to withstand the vibratory m otion of the specified earthquakes, it may be m ost effective to actually subject the cabinet to shaker tests which correspond to these vibratory motions. The shaker tests will not, however, verify that the circuitry is designed correctly, or that the com ponents in the cabinet will perform their intended function. Other tests or verification means are required to confirm that the remaining design functions are adequately performed by the instrum entation and that those com ponents perform the intended functions for the varying design conditions to which they are subjected.

Qualification testing shall be performed in accordance w ith w ritten test procedures tha t incorporate or reference the requirements and acceptance limits contained in applicable design documents. The test procedures shall include provisions for assuring that prerequisites for the given test have been met, that adequate instrum entation o f the required range and accuracy is available and used and that necessary monitoring is performed. Prerequisites shall include such items as calibrated instrum entation, appropriate equipm ent, trained personnel, condition of test equipm ent and the item to be tested, suitable environmental conditions, and provisions for data acquisition. Test results shall be docum ented, and evaluated by the responsible design organization to assure that test requirements have been satisfied.

If testing indicates that modifications to the item are necessary to obtain acceptable performance, the m odification shall be docum ented, and the item modified and retested or otherwise verified to assure satisfactory performance. When tests are being performed on models or mock-ups, scaling laws shall be established and verified. The test configuration shall be clearly defined and docum ented. The results of model test work shall be subject to error analysis, where applicable, prior to use in final design work.

8. DOCUMENT CONTROL

All design docum ents shall be controlled in accordance with section 4 of the Code. Documented procedures shall be prepared for this purpose and shall ensure tha t all documents, and all changes to them , are reviewed and approved for release by authorized personnel and are properly distributed.

12


8.1. Document preparation, review and approval

Personnel and participating organizations shall use proper and current docum ents such as instructions, procedures, drawings and design inputs. Documented procedures for control o f design docum ents and changes thereto, to ensure that current and appropriate docum ents are available for use, shall be prepared. The docum ent control procedure shall provide for:

(1) Identification of all individuals or organizations responsible for preparing, reviewing, approving and issuing docum ents and revisions thereto.

(2) Identification o f the proper docum ents to be used in performing design. This should include title, applicable revisions and date o f issue, orany other relevant inform ation tha t precisely identifies the docum ent.

(3) Co-ordination and control o f interfacing design docum ents (internal and external). These docum ent control procedures shall be agreed to in advance and prepared in sufficient detail to ensure that the required reviews and approvals are accomplished.

(4) Ascertaining that proper docum ents are in fact being used. These procedures should provide assurance tha t the latest docum ents have been received and that obsolete docum ents have been recalled, destroyed or appropriately stamped or identified to prevent their inadvertent use.

8.2. Document release and distribution

A docum ent release and distribution system shall be established, utilizing up-to-date distribution lists.

8.3. Docum ent change control

Docum ent change control shall be in accordance with section 4.3 of the Code.

9. CONTROL OF DESIGN CHANGES

All design changes, including field changes and m anufacturer’s changes (if the m anufacturer also performs design), shall be controlled in accordance w ith section 5.4 o f the Code. When design changes are made, the reasons should

13


be identified. For example, changes may result from:

(1) qualification, pre-operational or operational test results(2) problems during manufacture(3) problems during construction(4) failures of structures, systems or com ponents to m eet functional

requirements(5) disposition of non-conforming items(6) changes in regulatory or other requirements(7) operational experience(8) design improvements.

10. CORRECTIVE ACTION

Deficiencies or errors in the performance of the design process, in the resultant design outpu t documents, or in the design quality assurance p ro - ' gramme shall be docum ented and corrected in a timely manner. The quality assurance programme shall provide for control of further processing o f deficient documents. Where a design outpu t docum ent is shown to be deficient after it has been used for m anufacture or construction of an item, that item shall be considered as non-conforming and disposition shall be made accordingly. Deficiencies may be detected by:

( l ) design verification measures(2) use of design docum ents(3) audits(4) tests(5) actual failure during operation(6) other means.

In addition to correcting a deficiency, corrective action shall also include, for significant or recurring deficiencies, determ ination of their cause, and institution of appropriate changes in the design process, in the verification process, in the quality assurance programme and in procedures, to prevent similar types of deficiencies from recurring. A procedure for detecting, documenting and evaluating such deficiencies shall be w ritten; it shall include provisions for corrective action. This procedure shall also specify provisions for reporting the deficiency and corrective action to appropriate levels of supervision and management. Where corrective actions cannot be immediately completed, the procedure shall also include a requirem ent for follow-up actions by appropriate personnel, to ensure timely resolution and com pletion of the corrective action.

14


11. QUALITY ASSURANCE RECORDS

Measures shall be established for generating, accumulating, filing and storing the design quality assurance records tha t this Guide requires to be generated. These records shall include not only final design docum ents such as drawings and specifications, and revisions thereto, bu t also records of all im portant steps, such as sources of design inputs, and the checking and verification records which support the final design. For further inform ation on records, the reader is referred to the requirem ents and recom m endations contained in the Safety Guide on Quality Assurance Records System for Nuclear Power Plants (IAEA Safety Series No. 50-SG-QA2).

12. AUDITS

Measures shall be established to verify the im plem entation and effectiveness of the quality assurance programme. As necessary, a system of planned and docum ented audits shall be carried out. Further inform ation is included in the requirements and recom m endations of the Safety Guide on Quality Assurance Auditing for Nuclear Power Plants (IAEA Safety Series No. 50-SG-QA10).Audits should be conducted to a depth commensurate w ith the design responsibility o f each organization being audited. Their purpose is to ensure tha t the overall quality assurance programme for design is adequate and is being followed, that the approved procedures of specific design organizations relative to the design process are being carried out, that the verification process and docum ents and records are being implemented, and tha t design outpu t docum ents contain adequate quality requirem ents to be placed on m aterial and equipm ent suppliers and construction contractors. Individuals perform ing audits o f design process and design activities shall no t be those who were responsible for performing work in these areas for the project under audit.

In those cases where the responsible design organization sub-contracts design work to o ther organizations or consultants, it shall conduct audits o f the sub-contractor or consultant. The purpose of these audits is to confirm tha t the quality assurance programme, and in particular the design process procedures and design verification procedures of these organizations, conform to requirem ents of the responsible design organization.

The audit procedures or checklists for quality assurance programmes of design shall, in addition to the requirem ents and recom m endations specified in Safety Guide SG-QA10, include assurance of the following:

(1) Availability of design quality assurance policies, practices, procedures and instructions

15


(2) Delineation o f pertinent design input inform ation(3) Implem entation of design process and of design verification activities(4) Effectiveness o f these procedures in adequately controlling the

design activities and design interfaces(5) Effective control o f design docum ents and changes thereto(6) Incorporation o f quality requirem ents in design docum ents(7) Training and qualification of design personnel.

16


A nnex I

TYPICAL AREAS WHERE PROCEDURES FOR DESIGN QUALITY ASSURANCE

SHOULD BE DEVELOPED

1. Responsibilities of, and interfaces between, organizations and personnel involved in the programme (e.g. the responsible organization, m anufacturer, architect-engineer, constructor, and other contractors).

2. Responsibilities w ithin the design organization.

3. Technical inform ation exchange across external and internal interfaces.

4. Document control, including review, approval, issue, distribution, and revision.

5. Maintenance and retention o f design documents.

6. Management review of status and adequacy of programme.

7. Necessary training o f personnel.

8. Identification o f appropriate design criteria, standards and other design input requirements.

9. Preparation of design documents.

10. Specification o f quality levels, acceptance standards, and record requirements.

11. Selection o f design verification m ethods.

12. Performance o f design verifications.

13. C onduct o f audits of design activities, their reporting and follow-up.

14. Im plem entation o f corrective action.

15. Making experience reports available to design personnel concerned.

16. Control o f design changes.

17


A nnex II

TYPICAL DESIGN INPUTS

1. Basic functions of each structure, system and com ponent.

2. Performance requirem ents such as capacity, rating, system output.

3. Codes, standards, and regulatory requirements. The applicable issue, revision, or addenda should be specified.

4. Design conditions, such as pressure, tem perature, fluid chemistry and voltage.

5. Loads, such as seismic, wind, thermal and dynamic.

6. Environmental conditions anticipated during storage, construction and operation, such as pressure, tem perature, hum idity, corrosiveness, site elevation, wind direction, nuclear radiation, electromagnetic radiation and duration of exposure.

7. Interface requirements, including definition of the functional and physical interfaces involving structures, systems and components.

8. Material requirements, including considerations such as com patibility, electrical insulation properties, protective coating, corrosion resistance and neutron activation properties.

9. Mechanical requirements, such as ability to w ithstand vibration, stress, shock and reaction forces.

10. Structural requirements, covering such items as equipm ent foundations and pipe supports.

11. Hydraulic requirements, such as pump net positive suction heads, allowable pressure drops and allowable fluid velocities.

12. Chemistry requirements, including limitations (particularly on reactor coolants), and provisions for sampling.

13. Electrical requirements, such as source of power, voltage, cableway requirements, electrical insulation and m otor requirements.

14. Layout and arrangement requirements.

15. Operational requirements under various conditions, such as plant start-up, normal plant operation, plant shutdown, plant emergency operation, special or infrequent operation, and abnormal or emergency system operation.

18


16. Instrum entation and control requirem ents, including indicating instruments, controls and alarms required for operation, testing, and maintenance. Other requirem ents such as type o f instrum ent, installed spares, range of m easurement and location of indication are also included.

17. Access and administrative control requirem ents for plant security.

18. Redundancy, diversity and separation o f structures, systems and components to meet the reliability requirements.

19. Requirements to ensure tha t structures, systems and com ponents can withstand defined events and accidents.

20. Test requirements, including pre-operational and periodic in-service tests, and the conditions under which they will be performed.

21. Accessibility, maintenance, repair and in-service inspection requirem ents for the plant, including the conditions under which these will be performed.

22. Transportability requirem ents, such as lim itations on size and shipping weight.

23. Handling, storage, cleaning and shipping requirements.

24. Fire prevention and protection requirements.

25. Personnel requirem ents and lim itations, including the.num ber of personnel available for plant operation, m aintenance, testing and inspection, and their qualifications.

26. Safety requirem ents for preventing injury to personnel, including such items as radiation hazards, restricting the use of dangerous materials, escape provisions from enclosures, and grounding of electrical systems.

27. Ergonomic (human factor) considerations, such as man/m achine interface.

28. Radiation exposure limits for plant personnel and the public.

. 29. O ther requirem ents to prevent undue risk to the health and safety o f the public.

19



DEFINITIONS

The follow ing definitions are intended fo r use in the N U SS programme and may no t necessarily conform to definitions adopted elsewhere fo r international use. Item s marked with an asterisk have been taken from the list o f definitions included in the approved Codes o f Practice published under the N U SS programme.

Checking

As related to design, checking is the detailed technical exam ination of a docum ent to make certain tha t it is accurate, and to ensure tha t all the technical design inputs, design bases, and other design criteria have been correctly incorporated.

Design Analyses

All processes which use design inputs and which result in the generation of inform ation necessary for preparation o f design ou tpu t docum ents such as drawings, Specifications, and procedures. Design analyses include calculations.

Design Input

Those criteria, parameters, bases or other requirem ents upon which detailed final design is based.

Design Interface

The boundary between the design-related responsibilities and activities of one organization, group or individual, and another organization, group or individual. It includes bo th the external design interface, which is the boundary between different organizations, and the internal design interface, which is the boundary between design units o f the same organization.

Design O utput

Documents, such as drawings and Specifications, that define technical requirements necessary for m anufacture, installation and operation of structures, systems and components.

Disposition

An action to determine how a departure from specified requirem ents is to be handled or settled.

21


*Documentation

Recorded or pictorial inform ation describing, defining, specifying, reporting or certifying activities, requirements, procedures or results related to Quality Assurance.

*Examination

An element of Inspection consisting of investigation o f materials, components, supplies, or Services, to determine conformance with those specified requirem ents which can be determined by such investigation.1

*Inspection

Quality Control actions which by means of Examination, observation or measurement determine the conformance of materials, parts, components, systems, structures, as well as processes and procedures, with predeterm ined quality requirements.

Item

A general term covering structures, systems, components, parts or materials.

, *Non-conformance

A deficiency in characteristics, docum entation or procedure which renders the quality of an Item unacceptable or indeterm inate.

*Objective Evidence

Qualitative or quantitative inform ation, record or statem ent o f fact, pertaining to the quality o f an item or service, which is based on observation, m easurement or test and which can be verified.

1 Quality Assurance Exam ination is usually non-destructive and includes simple physical m anipulation, gauging and m easurem ent.

2 2


Procurement

The activities perform ed by a purchaser or his designated representative for obtaining an Item or Service, beginning w ith the preparation of specified requirements, and concluding w ith the purchaser’s acceptance o f such Item or Service.

*Quality Assurance

Planned and systematic actions necessary to provide adequate confidence that an Item or facility will perform satisfactorily in service.

*Quality Control

Quality Assurance actions which provide a means to control and measure the characteristics o f an Item , process or facility in accordance w ith established requirements.

* Records

Documents which furnish Objective Evidence of the quality o f Item s and o f activities affecting quality.

Repair

The process of restoring a non-conforming Item to a condition such that the capability o f this Item to function reliably and safely is unimpaired, even though that item still may no t conform to the prior Specification.

Rework

The process by which a non-conforming Item is made to conform to a prior specified requirem ent by com pletion, remachining, reassembling or other corrective means.

Services

The performance by a Supplier of activities such as design, fabrication, Inspection, non-destructive Exam ination, Repair or installation.

23


A w ritten statem ent of requirem ents to be satisfied by a product, a material or a process, indicating the procedure by means o f which it may be determ ined whether the specified requirem ents are satisfied.

Supplier

An individual or organization under contract for furnishing Items or Services. This includes various levels or kinds o f procurem ent, e.g. as undertaken by vendors, sellers, contractors, sub-contractors, fabricators and consultants.

*Testing

The determ ination or verification of the capability o f an Item to meet specified requirem ents by subjecting the Item to a set of physical, chemical, environmental or operational conditions.

* Specification

24


LIST OF PARTICIPANTS

WORKING GROUP

Dates o f meetings: 30 January to 3 February 1978, 24 to 28 April 1978

Consultants

Heilman, S.K

Kakodkar, A.

Laurent, L.

IAEA s ta ff member

Raisic, N. Scientific Secretary (Quality Assurance)

United S tates o f America

India

France

TECHNICAL REVIEW COMMITTEE (TRC) - QUALITY ASSURANCE

Dates of meetings: 24 to 28 April 1978, 2 4 -2 8 September 1979,1 to 5 December 1980

Members and alternates participating in the meetings

Thom as, R.A. (Chairman) M assicotte, M.

Havel, S.K outsk£, J.

Vaujour, J.A.D oucet, Y.StSbel, W.

B alaram am oorthy, K. Kulkarni, P.G.Rao, V.S.G.

Maniori, D.

A ndo, Y.Aikawa, K.Ojiri, Y.Yam anoi, T.Yoneda, Y.

Sandona, E.

Phillips, C.A.G.S utton , L.J.Fowler, J.L.

M orrison, W.M.

Canada

Czechoslovakia

France

G erm any, Federal R epublic of

India

Italy

Japan

Switzerland

U nited Kingdom

U nited States o f America


Participant from international organization

Buyers, R. International Organization for S tandardization

IAEA s ta ff members

Hatle, Z.


SENIOR ADVISORY GROUP (SAG)

Dates of meetings: 10 to 14 December 1979, 23 to 27 March 1981

Members or alternates who participated in the meetings

Canada

Argentina

Czechoslovakia

France

G erm any, Federal Republic of

India

Japan

Mexico

Sweden

Switzerland

Union of Soviet Socialist Republics

U nited Kingdom

U nited States o f America

Participants from international organizations

Commission of the European Com m unities

Council for M utual Econom ic Assistance

International Organization for S tandardization

OECD Nuclear Energy Agency

World Health Organization

Vinck, W.

Burkhardt, W.

Nilson, R. Becker, K.

Dari, O.Kom arov, E.I.

H urst, D. (Chairman)

Beninson, D. Paganini, C.

Beranek, J.

Messiah, A.

Franzen, L.F.

Dastidar, P.R. Som an, S.D.

Ishizuka, M.Suguri, S.

Sanchez, J.Bello, R.Hedgran, A.Jansson, E.

Zuber, J.F .

Kovalevich, O.M. Isaev, A.

Gausden, R.A.

Minogue, R.B.Sm ith, R.

26


IAEA s ta ff members

K onstantinov, L.V. Scientific C o-ordinator


Iansiti, E. Scientific Secretary (SAG)



PROVISIONAL LIST OF NUSS PROGRAMME TITLES

Safety Series No.

Provisional title Publication date o f English version

1. Governmental organization

Governmental organization for the regulation o f nuclear power plants

Code o f Practice

50-C-G

Safety Guides

50-SG-G1 Qualifications and training o f staffof the regulatory body for nuclear power plants

50-SG-G2 Inform ation to be subm itted insupport o f licensing applications for nuclear power plants

50-SG-G3 Conduct o f regulatory review andassessment during the licensing process for nuclear power plants

50-SG-G4 Inspection and enforcem ent by theregulatory body for nuclear power plants

50-SG-G6 Preparedness o f public authorities foremergencies at nuclear power plants

50-SG-G8 Licences for nuclear power plants:content, form at and legal considerations

50-SG-G9 Establishment o f regulations andguides by the regulatory body for nuclear power plants; and their purpose

Published 1978

Published 1979

Published 1979

Published 1980

Published 1980

29


Safety Series Provisional titleNo.

Publication dateof English version

Code o f Practice

50-C-S

Safety Guides

50-SG-S1

50-SG-S2

50-SG-S3

50-SG-S4

50-SG-S 5

50-SG-S6

50-SG-S7

50-SG-S9

50-SG-S10A

50-SG-S 1 OB

2. Siting

Safety in nuclear power plant siting Published 1978

Earthquakes and associated topics in relation to nuclear power plant siting

Seismic analysis and testing o f nuclear power plants

Atmospheric dispersion in nuclear power plant siting

Site selection and evaluation for nuclear power plants with respect to population distribution

External man-induced events in relation to nuclear power plant siting

Hydrological dispersion o f radioactive material in relation to nuclear power plant siting

Nuclear power plant siting: hydrogeological aspects

Site survey for nuclear power plants

Design basis flood for nuclear power plants on river sites

Design basis flood for nuclear power plants on coastal sites

Published 1979

Published 1979

Published 1980

Published 1980

Published 1981

30


Safety Series Provisional title Publication dateNo. o f English version

Safety Guides (cont.)

50-SG-S11A Extreme meteorological events innuclear power plant siting, excluding tropical cyclones

50-SG-S1 IB Design basis tropical cyclonefor nuclear power plants

50-SG-S12 Radiological protection aspects o fnuclear power plant siting

3. Design

Code o f Practice

50-C-D Design for safety o f nuclear power plants

Published 1978

Safety Guides

50-SG-D1

50-SG-D2

50-SG-D3

50-SG-D4

50-SG-D5

50-SG-D6

Safety functions and com ponent Published 1979classification for BWR, PWR and PTR

Fire protection in nuclear power Published 1979plants

Protection system, and related Published 1980features in nuclear power plants

Protection against internally Published 1980generated missiles and their secondary effects in nuclear power plants

Man-induced events in relation to nuclear power plant design

Ultimate heat sink and directly Published 1981associated heat transport systems for nuclear power plants

31





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

50-SG-D8 Instrum entation and control o fnuclear power plants

50-SG-D9 Design aspects o f radiologicalprotection for nuclear power plants

50-SG-D10 Fuel handling and storage systemsin nuclear power plants

50-SG-D11 General design safety principlesfor nuclear power plants

50-SG-D12 Design o f the reactor containm entsystem in nuclear power plants

50-SG-D13 • Reactor cooling systems innuclear power plants

50-SG-D14 Design for reactor core safetyin nuclear power plants

4. Operation

Code o f Practice

50-C-0 Safety in nuclear power plant Published 1978operation, including commissioning and decommissioning

Safety Guides

50-SG-01 Staffing o f nuclear power plants Published 1979and recruitm ent, training and authorization o f operating personnel

32





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

50-SG-03 Operational limits and conditionsfor nuclear power plants

50-SG-04 Commissioning procedures fornuclear power plants

50-SG-05 Radiological protection duringoperation o f nuclear power plants

50-SG-06 Preparedness o f the operatingorganization for emergencies at nuclear power plants

50-SG-07 M aintenance o f nuclear power plants

50-SG-08 Surveillance of items im portant tosafety in nuclear power, plants

50-SG-09 Management of nuclear powerplants for safe operation

50-SG-010 Core management, fuel handlingand associated services for nuclear pow er plants

50-SG-011 Operational management o fradioactive effluents and wastes arising in nuclear power plants

Published 1980

Published 1979

Published 1980

5. Quality assurance

Code o f Practice

50-C-QA Quality assurance for safety Published 1978in nuclear power plants

33




Safety Guides

50-SG-QA1

50-SG-QA2

50-SG-QA3

50-SG-QA4

50-SG-QA5

50-SG-QA6

50-SG-QA7

50-SG-QA 8

50-SG-QA 10

50-SG-QA 11

Preparation o f the quality assurance programme for nuclear power plants

Quality assurance records system for nuclear power plants

Quality assurance in the procurem ent o f items and services for nuclear power plants

Quality assurance during site construction of nuclear power plants

Quality assurance during operation of nuclear power plants

Quality assurance in the design of nuclear power plants

Quality assurance organization for nuclear power plants

Quality assurance in the m anufacture of items for nuclear power plants

Quality assurance auditing for nuclear power plants

Quality assurance in the procurem ent, design and m anufacture of nuclear fuel assemblies

Published 1979

Published 1979

Published 1981

Published 1981

Published 1981

Pablished 1981

Published 1980

r-00e*

©00

34


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Division of Publications International Atomic Energy Agency Wagramerstrasse 5, P.O. Box 100, A-1400 Vienna, Austria


INTERNATIO NAL ATOMIC ENERGY AGENCY VIENNA, 1981

SUBJECT GROUP: IINuclear Safety and Environmental Protection/Nuclear Safety PRICE: Austrian Schillings 90,—


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