staffing of training and authorization of operating personnel

</) LU9o

> - hLU

SAFETY SERIES No. 50-SG-01 (Rev.1)

<</>

Staffing ofNuclear Power Plants and the Recruitment, Training and Authorization of Operating Personnel

A Safety Guide

A PUBLICATIONWITHIN THE NUSS PROGRAMME

INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, 1991

This publication is no longer valid Please see http://www-ns.iaea.org/standards/

CATEGORIES IN THE IAEA SAFETY SERIES

A new hierarchical categorization scheme has been introduced, according to which the publications in the IAEA Safety Series are grouped as follows:

Safety Fundam entals (silver cover)

Basic objectives, concepts and principles to ensure safety.

Safety S tandards (red cover)

Basic requirements which must be satisfied to ensure safety for particular activities or application areas.

Safety Guides (green cover)

Recommendations, on the basis of international experience, relating to the fulfilment of basic requirements.

Safety Practices (blue cover)

Practical examples and detailed methods which can be used for the application of Safety Standards or Safety Guides.

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.

An additional category, Safety R eports (purple cover), comprises independent reports o f expert groups on safety matters, including the development of new principles, advanced concepts and major issues and events. These reports are issued under the authority of the Director General of the IAEA.

There are other publications of the IAEA which also contain information important to safety, in particular in the Proceedings Series (papers presented at symposia and conferences), the Technical Reports Series (emphasis on technological aspects) and the IAEA-TECDOC Series (information usually in a preliminary form).


STAFFING OF NUCLEAR POWER PLANTS AND THE RECRUITMENT,

TRAINING AND AUTHORIZATION OF OPERATING PERSONNEL

A Safety Guide


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

A F G H A N IS T A N

A L B A N IA

A L G E R IA

A R G E N T IN A

A U S T R A L IA

A U S T R IA

B A N G L A D E S H

B E L G IU M

B O L IV IA

B R A Z IL

B U L G A R IA

B Y E LO R U S S IA N SO V IE T

S O C IA LIS T R E PU BLIC

C A M E R O O N

C A N A D A

C H IL E

C H IN A

C O L O M B IA

CO STA R IC A

C O TE D 'IV O IR E

C U B A

CYPRUS

C Z E C H O S L O V A K IA

D E M O C R A T IC K A M P U C H E A

D E M O C R A T IC PEO PLE’S

R E P U B LIC OF KO REA

D E N M A R K

D O M IN IC A N R EPU BLIC

EC U A D O R

EG YPT

E L S A L V A D O R

E T H IO P IA

F IN L A N D

FR AN C E

G ABO N

G E R M A N Y

G H A N A

G REECE

G U A T E M A L A

H A IT I

H O L Y SEE

H U N G A R Y

IC E L A N D

IN D IA

IN D O N E S IA

IR A N , IS L A M IC R E P U B LIC OF

IR AQ

IR E L A N D

IS R A E L

IT A L Y

J A M A IC A

JAP AN

JO R D A N

K E N Y A

K O R E A , R E P U B LIC OF

K U W A IT

LE B A N O N

L IB E R IA

L IB Y A N A R A B J A M A H IR IY A

LIE C H T E N S T E IN

L U X E M B O U R G

M A D A G A S C A R

M A L A Y S IA

M A L I

M A U R IT IU S

M E X IC O

M O N A C O

M O N G O L IA

M O R O C CO

M Y A N M A R

N A M IB IA

N E T H E R LA N D S

N E W Z E A L A N D

N IC A R A G U A

NIG ER

N IG E R IA

N O R W A Y

P A K IS T A N

P A N A M A

P A R A G U A Y

PERU

PH ILIPP IN ES

P O LA N D

P O R T U G A L

Q A T A R

R O M A N IA

S A U D I A R A B IA

S E N E G A L

SIERRA LE O N E

SING APORE

SO UTH A F R IC A

SPAIN

SRI L A N K A

SU D A N

SW EDEN

S W IT Z E R L A N D

S Y R IA N A R A B R E PU BLIC

T H A IL A N D

T U N IS IA

T U R K E Y

U G A N D A

U K R A IN IA N S O V IE T S O C IA LIS T

RE PU BLIC

U N IO N OF SO V IE T S O C IA LIS T

REPUBLICS

U N IT E D A R A B EM IR A T E S

U N IT E D K IN G D O M OF G R E A T

B R IT A IN A N D N O R T H ER N

IR E L A N D

U N IT E D R E PU BLIC OF

T A N Z A N IA

U N IT E D STATES OF A M E R IC A

U R U G U A Y

V E N E Z U E L A

V IE T N A M

Y U G O S L A V IA

Z A IR E

Z A M B IA

Z IM B A B W E

T he A gency’s S tatute w as approved on 23 O ctober 1956 by the C onference on the Statute o f the IA E A held a t U nited N ations H eadquarters , N ew Y ork; it en tered into force on 29 July 1957. T he H eadquarte rs o f the A gency are situated in V ienna. Its principal objective is “ to accelerate and enlarge the con tribu tion o f a tom ic energy to peace, health and p rosperity th roughout the w o rld ” .

© IA E A , 1991

Perm ission to reproduce o r transla te the inform ation contained in this publication m ay be obtained by w riting to the In ternational A tom ic E nergy A gency, W agram erstrasse 5, P .O . Box 100, A -1400 V ienna, A ustria.

Prin ted by the IA E A in A ustria July 1991


SAFETY SERIES No. 50-SG-01 (Rev. 1)

STAFFING OF NUCLEAR POWER PLANTS AND THE RECRUITMENT,

TRAINING AND AUTHORIZATION OF OPERATING PERSONNEL

A Safety Guide

INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA, 1991


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

STAFFING OF NUCLEAR POWER PLANTS AND THE RECRUITMENT, TRAINING AND AUTHORIZATION OF OPERATING PERSONNEL:

A SAFETY GUIDE IAEA, VIENNA, 1991

STI/PUB/874 ISBN 92-0-123391-4

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 so 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 was developed for land based stationary plants with thermal neutron reactors designed for the production of power but the provisions may be appropriate to a wider range of nuclear applications.

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 international 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.


C O NTEN TS

1. INTRODUCTION ................................................................................................ 9

Background (101-102) ......................................................... .............................. 9Objective (103) .................................................................................. ................... 9Scope (104) ........................................................................................................... 9Structure (105) ..................................................................................................... 10

2. ORGANIZATIONAL PLAN ............................................................................. 10

General (201-208) ............................................................................................... 10Structure (209-210) ............................................................................................ 11Basis of the organizational plan (211-220) .................................................... 12Functions (221-263) ............................................................................................ 14Categories of personnel (264-274) .................................................................. 21

3. RECRUITMENT ................................................................................................... 22

General (301-308) ............................................................................................... 22Professionals (309) ............................................................................................... 24Operators and technicians (310-311) ............................................................... 24Craftsmen (312) .................................................................................................... 24Medical examination (313) ................................................................................. 25

4. TRAINING AND QUALIFICATION ............................................................. 25

General (401-404) ............................................................................................... 25Training system (405-420) ................................................................................. 26Training programmes (421-448) ...................................................................... 29Experience requirements (449-459) ................................................................ 33

5. AUTHORIZATION ............................................................................................. 35

General (501-508) ............................................................................................... 35Positions to be authorized (509-510) ............................................................. 36Basis for authorization (511-513) ................................................................... 36Reauthorization (514-515) ................................................................................. 36

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


ANNEX: NUCLEAR POWER PLANT ORGANIZATIONAL CHARTS ...... 39

CONTRIBUTORS TO DRAFTING AND REVIEW ............................................ 45

LIST OF NUSS PROGRAMME TITLES ............................................................... 49

SELECTION OF PUBLICATIONS RELATING TO THE SAFETY OF NUCLEAR POWER PLANTS .................................................................................... 53

6. RECORDS (601-603) ......................................................................................... 37


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 fundamental definitions used in many NUSS publications are illustrated by the accompanying diagram.

O perational States

States defined under Normal Operation or Anticipated Operational Occurrences.

Norm al O peration

Operation of a nuclear power plant within specified Operational Limits and Conditions including shutdown, power operation, shutting down, starting, maintenance, testing and refuelling.

Anticipated O perational O ccurrences1

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 deviations do not include severe accidents.

1 Examples o f Anticipated Operational Occurrences are loss of normal electric power and faults such as a turbine trip, malfunction of individual items of a normally running plant, failure to function of individual items of 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 (LOCA), etc.

1


Design Basis Accidents

Accident Conditions against which the nuclear power plant is designed according 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 o f 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

Normaloperation

Anticipatedoperational Accidentoccurrences conditions

Severeaccidents

Designbasis

accidents

Accident management

Acceptable Limits

Limits acceptable to the Regulatory Body.

2


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 operational programmes and other applicable documents, and the effectiveness of implementation.

A uthorization

The granting of written permission to perform specified activities.

A uthorized Limits — see Prescribed Limits.

Com m encem ent of O peration

The beginning of initial fuel loading.

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 nonnuclear and nuclear tests.

Com petent A uthority

A national authority designated or otherwise recognized as such by the Member State for a specific purpose (see Regulatory Body).

C onstruction (see footnote 3)

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.

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

3


Decommissioning (see footnote 3)

The process by which a nuclear power plant is permanently taken out of Operation.

Design (see footnote 3)

The process and the result of developing the concept, detailed plans, supporting calculations and specifications for a nuclear power plant and its parts.

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.

Operating Organization

The organization authorized by the Regulatory Body to operate the nuclear power plant.

Operating Personnel

Those members of the Site Personnel who are involved in the operation of the nuclear power plant.

Operation (see footnote 3)

All activities performed to achieve the purpose for which the nuclear power plant was constructed, including maintenance, refuelling, in-service inspection and other associated activities.

Operational Limits and Conditions

A set of rules which set forth parameter limits, the functional capability and the performance levels of equipment and personnel approved by the Regulatory Body for safe operation of the nuclear power plant.

Operational Records

Documents, such as instrument charts, certificates, log books, computer printouts and magnetic tapes, made to keep objective history of a nuclear power plant’s Operation.

4


Plant Management

The members of Operating Personnel who have been delegated responsibility and authority by the Operating Organization for directing the Operation of the nuclear power plant.

P rescribed L im its4

Limits established or accepted by the Regulatory Body.

Qualified Person

A person who, having complied with specific requirements and met certain conditions, has been officially designated to discharge specified duties and responsibilities.

Q uality Assurance

All those planned and systematic actions necessary to provide adequate confidence that an item or service will satisfy given requirements for quality.

Regulatory Body

A national authority or a system of authorities designated by a Member State, assisted by technical and other advisory bodies, and having the legal authority for conducting the licensing process, for issuing licences and thereby for regulating nuclear power plant Siting, Design, Construction, Commissioning, Operation and Decommissioning or specified aspects thereof.5

Residual Heat

The sum of the heat originating from radioactive decay and shutdown fission and the heat stored in reactor related structures and in heat transport media.

Safety — see N uclear Safety

4 The term ‘authorized limits’ is sometimes used for this term in IAEA documents.5 This national authority could be either the government itself, or one or more depart

ments o f the government, or a body or bodies specially vested with appropriate legal authority.

5


Safety Limits

Limits on process variables within which the Operation of the nuclear power plant has. been shown to be safe.

Safety Report

A document provided by the applicant or licensee to the Regulatory Body containing information concerning the nuclear power plant, its Design, accident analysis and provisions to minimize the risk to the public and the Site Personnel.

Safety Systems

Systems important to Safety6, provided to assure the safe shutdown of the reactor or the residual heat removal from the core, and/or to limit the consequences of Anticipated Operational Occurrences and Accident Conditions.

Safety System Settings

Those points of actuation of appropriate automatic protective devices which are intended to initiate action to prevent a safety limit from being exceeded and to cope with Anticipated Operational Occurrences and Accident Conditions.

Site

The area containing the plant, defined by a boundary and under effective control of the Plant Management.

Site Personnel

All persons working on the Site, either permanently or temporarily.

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.

Vendor

A design, contracting or manufacturing organization supplying a service, component or plant.

6 See Code 50-C-D (Rev. 1).

6


NOTE ON THE INTERPRETATION OF THE TEXT

When an appendix is included it is considered to be an integral part o f 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... o r . . .” is used.

7


1. INTRODUCTION

BACKGROUND

101. This Safety Guide was prepared as part of the NUSS programme for establishing Codes and Safety Guides relating to nuclear power plants. It supplements Safety Series No. 50-C-0 (Rev. 1) “ Code on the Safety of Nuclear Power Plants: Operation” . The present version of this Guide is a revision which takes into account the developments, particularly in training practices, which have taken place since the first edition appeared in 1979.

102. The safe operation of nuclear power plants requires that the relevant organizational structure be clearly defined and be staffed with competent managers and qualified personnel who have the proper awareness of the technical and administrative requirements for safety and the motivation to adopt a positive attitude to safety culture. This culture derives primarily from a management attitude which results in the promotion and development of a mentality in day to day activities which goes beyond the simple implementation of the best and most accurate procedures and provisions. There must be pervasive safety awareness on the part of those concerned in operation, maintenance, operator training and all related activities. This pervasive safety approach is a key element in safety culture.

OBJECTIVE

103. The objective of this Safety Guide is to outline the various factors to be considered in order to ensure that the operating organization has a sufficient number of qualified and motivated personnel for the operation of nuclear power plants.

SCOPE

104. The Guide covers the organization for a nuclear power plant, the requirements in terms of education and experience for the various members of the operating personnel to be recruited, the recruitment, the training and continuing training programmes, as well as the authorizations for persons whose duties have an immediate bearing on safety.

9


STRUCTURE

105. Section 2 summarizes the functions required for the safe operation of one or more nuclear power plants, and in particular those functions which are generally performed by the site personnel under the authority of the plant management. The personnel is divided into the following broad categories: professionals, operators, technicians and craftsmen. The next section deals with the factors which need to be taken into account in recruitment. The fourth section, concentrates on training systems, training programmes and experience requirements. A systematic approach to training is described and recommended. Essential features in the training programmes of different groups of personnel as well as in the continuing training programmes are described. Typical experience requirments derived from average levels in countries with extensive nuclear programmes are also included. The fifth section deals with authorization and reauthorization by the operating organization and the regulatory body and the last section deals with training records.

2. ORGANIZATIONAL PLAN

GENERAL

201. The operating organization which operates or intends to operate one or more nuclear power plants shall establish an organizational structure to meet the general requirements for the safe and reliable operation of the plants, taking into consideration any particular situation or conditions involved.

202. The operating organization shall be aware of the special emphasis that needs to be placed on safety. Although the operating organization may already have an organizational structure for managing non-nuclear power plants, this special emphasis and the commitment to achieving safety will require more than a simple extension of the earlier organizational structure.

203. This Guide does not deal in detail with the individual functions required to be performed for the safe operation of one or more nuclear power plants. These functions are described in the Code on Operation, in Safety Guide 50-SG-09 and also in Safety Guides 50-SG-02, 50-SG-04, 50-SG-05, 50-SG-06, 50-SG-07, 50-SG- 0 8 , 50-SG-010 and 50-SG-011.

204. The operating organization shall examine the various functions and decide which ones will be performed at the plant site, which off the site but within the operating organization, and which outside the operating organization.

10


205. In addition, the complexity of the planned nuclear power plant, its engineering features, the number of nuclear and other plants already in operation, under construction or planned for construction and the general structure of the operating organization itself shall be considered.

206. On the basis o f these decisions and of all applicable regulatory requirements and national industrial practices, the operating organization shall establish an organizational plan which indicates general policies, lines of responsibility and authority, lines of communication, the duties and numbers of persons needed and their qualification requirements. Both operational and accident states shall be taken into account.

207. The organizational plan shall be established well in advance, so that the required structure (including recruitment and training of personnel) is operational as required for the commissioning phase and in any case before commencement of operation. It shall form the basis for the first recruitment and training programme as well as for all subsequent such programmes.

208. The organizational plan shall be regularly reassessed and if necessary updated to reflect developments in safe operation. In general, the operating organization, including the nuclear power plant itself, shall be staffed with competent managers and personnel having both the proper awareness of the technical and administrative requirements of safety and the motivation to implement safety policies.

STRUCTURE

209. The description of the structure and of the functions to be performed by the individual departments in the operating organization, on and off the site, and by the individual persons in each department, as well as the lines of responsibility, authority and communication, shall be unambiguous and shall leave no space for improvisation in either operational states or accident conditions. In some Member States, this description is required as a part of the quality assurance programme and, as far as the plant organization is concerned, is subject to prior approval by the regulatory body. Functions to be performed by external organizations or consultants shall also be indicated in the description, together with the related lines of communication and authority.

210. The description of the responsibilities of each position forms the basis for the definition of the required qualifications and of the prerequisites for recruiting, training and continuing training of the individual persons. Further guidance may be found in Safety Guide 50-SG-09.

11


BASIS OF THE ORGANIZATIONAL PLAN

211. Functions important to the safe operation of nuclear power plants are performed both on and off the site. Typical off-site functions include: personnel administration, procurement of materials or services, design of significant plant modifications and specialist technical support.

212. These functions performed off the site may have a bearing on safety, and therefore the general principles set forth in paras 201-208 also apply and a specific training programme for the personnel involved should be established. This training programme should be consistent with the appropriate on-site training programme. In the case of other functions having a bearing on safety, such as procurement of materials and services, a suitably established and enforced quality assurance programme, which gives due consideration to the safety related aspects of those activities, may be an effective means of ensuring safety. The quality assurance programme should also contain requirements for the qualification of off-site personnel whose work has influence on nuclear power plant safety. Persons responsible for audits or surveillance of safe operation on behalf of the operating organization shall participate in comprehensive training courses.

213. This Guide covers in particular those functions which are generally performed by the site personnel, under the authority of the plant management. The recommendations set forth in it may also be used as guidance for the training of any off-site personnel performing these functions.

214. Under the authority of the plant manager (see para. 226), the various functions such as operation, maintenance and technical support assigned to the site personnel are performed by distinct groups. These groups are described by different terms, according to local practice (sections, departments, groups); for the purposes of this Guide, they will be called groups.

215. The following functions are covered:

(1) Operation(2) Maintenance(3) Technical support

— Reactor physics and core management— Chemistry— Radiation protection— Surveillance and testing— Planning— Performance and plant engineering— Safety analyses and reviews— Emergency preparedness— Records administration and documentation

12


(4) Quality assurance(5) Security(6) Administration

— Stores— Purchasing, generally of relatively small items

(7) Training(8) Other activities, such as fire fighting and industrial safety.

216. Operations and maintenance are generally performed by two separated and dedicated groups, with the possibility of external reinforcements on particular occasions. The functions listed under the common heading of technical support may be performed by one or more groups (for example one group for radiation protection, or one group for reactor physics and core management). In other cases, some of the technical support functions are performed by operations and/or maintenance groups (for example, surveillance and testing, effluent control and waste management).

217. Some of the technical and/or administrative support functions may be performed off the site.

218. The different solutions adopted by operating organizations have a significant bearing on the size of the site organization. The Annex contains charts illustrating different forms of site organization.

219. In any case, the selected organizational structure shall be described in detail in organizational documents, with particular emphasis on the clear definition of responsibilities, authority, interfaces and lines of communication.

220. The following considerations may influence the determination of the positions and the number of persons in the organizational structure:

(1) The number of persons on each shift shall be sufficient to deal safely at any time with all operational states and accident conditions, with consideration given to the possibility of keeping some persons on call and to the time needed for such persons to reach the site. The possibility of abnormal events occurring out of office hours shall be considered.

(2) The definition of the number of shift teams is generally subject to national and local labour regulations and agreements; however, off-shift time for continuing training purposes should also be provided.

(3) The organizational structure shall be such as to permit at any time the implementation of the duties assigned to the operating organization in the emergency plan, with consideration given to the possibility of keeping some persons on-call and to the time needed for such persons to reach the site.

(4) The location of the plant relative to off-site support organizations shall be taken into account.

13


(5) The number of persons assigned to any given activity important to safety (e.g. instrument technicians) shall be determined allowing for absence due to continuing training, sickness, vacation, etc., and the minimum requirements to meet the plant needs.

(6) The expected turnover rate and time to recruit, train and qualify replacement personnel shall be considered.

(7) The possibility of obtaining qualified off-site company personnel for planned or unplanned replacement or reinforcement shall be considered (e.g. increased maintenance staff during refuelling and general plant overhaul).

FUNCTIONS

221. This section summarizes the functions of the plant management and the other functions required to be performed in order to give guidance in establishing the organizational structure and in defining the qualification and training requirements o f the persons assigned to cover the positions in the organizational structure.

222. This Guide does not enter into the details of each function, since these can be found in the relevant Safety Guides. General guidance may be found in Safety Guide 50-SG-09.

223. Actual organizational structures show significant differences among Member States and operating organizations. Therefore, only basic guidance is given here.

224. All staff members shall have clearly designated positions and shall be fully informed of their duties and responsibilities and the lines of authority and communication.

225. Management personnel, in particular the Plant Manager and the heads of the principal groups as well as the shift supervisors, may have deputies. For these deputies the same basic requirements of education and training should apply, although more limited experience may be acceptable.

Plant Manager

226. The chief executive member of the operating organization on the site is the Plant Manager (sometimes called the Station Superintendent). H e1 is the representative of the licensee on the site and has the overall responsibility for the safe and reliable operation of the plant. In discharging this responsibility he may, depending on

1 Throughout this Guide, the pronouns ‘he’ and ‘him’ should be taken as applying equally to both sexes.

14


the structure of the operating organization, also be responsible for overall coordination of technical support functions, whether performed by site personnel or by personnel from off-site departments or external organizations. He is therefore responsible for the qualification (including adequate initial and continuing training) o f the operating personnel.

227. In cases where functions are wholly or partly outside his direct control, the Plant Manager is still responsible for promoting in a documented manner the satisfactory execution of plant related actions concerning these functions.

228. The Plant Manager is responsible for ensuring that the relevant requirements of both the operating organization and the regulatory body are complied with. In addition, he may be involved in public information activities and in maintaining relationships with local authorities.

229. The operating organization shall delegate all necessary authority and provide the means to implement the requirements in this section (see also Safety Guide 50-SG-09).

Operations

230. The function of operations is to ensure safe and reliable operation of the plant, in accordance with operational limits and conditions, established procedures and good practice (see also Safety Guide 50-SG-09).

231. It must be remembered that the operations personnel are of the ‘direct operator’ type, in the sense that their activity has a direct impact on the behaviour of the reactor and its associated systems and the consequences are immediate. This aspect shall be considered in the selection, training, continuing training and authorization of the personnel concerned.

232. The personnel of the group consists essentially o f the shift teams. The number of shift teams shall be determined in accordance with local conditions. The structure of each team varies according to the type of plant, the number of units, the regulatory requirements and the provisions of the emergency plan.

233. Generally, there are three levels: Head of Operations, Shift Supervisor and operators.

Head o f Operations

234. The Head of Operations is responsible for the direct operation of the plant in accordance with the operational limits and conditions. He ensures compliance with the regulatory requirements such as the safety and radiation protection rules and other instructions and procedures issued by the operating organization to ensure

15


safety. He is also responsible for assessing the adequacy of the training of the personnel in his group and for reporting to the persons responsible for the training any proposal for improvement or corrective actions.

Shift Supervisor

235. The Shift Supervisor is responsible for the supervision of his shift and for the direct operational control of the plant in accordance with operational limits and conditions and with authorized instructions and procedures set out in appropriate documents.

236. In multi-unit power plants, one Shift Supervisor may be responsible for two units, and another person is responsible to him for the operation of each unit. This person may be called a Unit Supervisor.

237. The Shift Supervisor is responsible for the initial assessment of the nature and extent of any unusual occurrence, including any which might result in radioactive release, and subsequently for taking the first steps necessary to minimize the consequences, to ensure safety of personnel and to initiate the actions required by the emergency plan.

238. In some Member States, a Shift Safety Engineer is appointed to give advice or to take over responsibilities in some cases. These responsibilities and the lines of authority shall be clearly established in writing.

239. The Shift Supervisor shall be capable of directing or assuming the duties of the Control Room Operator to ensure the safe operation of the plant if he considers such action necessary.

240. He is also responsible for the authorization within established instructions and procedures to remove from service or restore to service plant systems and/or components, and for the issue of the associated permits to carry out work or tests on such items.

Operators

241. Under the authority of the Shift and/or Unit Supervisor, the Control Room Operators are responsible for the manipulation of controls in the control room in accordance with the relevant operating instructions and procedures. Other operators are responsible for the control of operational activities outside the control room under the general direction of the Control Room Operators and in accordance with the relevant operating instructions and procedures.

242. The number of operators on each shift and their responsibilities should be determined on the basis of the complexity of the plant and degree of automation.

16


Maintenance

243. The maintenance functions (for detailed guidance see Safety Guide 50-SG-07)cover all activities related to maintenance, repair and modifications of the plant. They include:

(1) Preparing a preventive maintenance programme;(2) Preparing maintenance procedures and instructions;(3) Execution of the maintenance work;(4) Keeping records of and evaluating performance data and maintenance

activities;(5) Planning the work, and scheduling and requisitioning tools, materials and

spare parts for the maintenance, repair and modifications of the plant.

244. The Head of Maintenance is responsible for ensuring that all maintenance activities are performed in accordance with the operational limits and conditions, the established procedures and good practices. He is responsible for assessing the adequacy of the training of the personnel in his group and for reporting to those responsible for the training any proposal for improvement or corrective actions.

245. The maintenance is normally subdivided into subgroups such as mechanical, electrical, instruments and controls, maintenance preparation and planning. The heads of these subgroups are responsible to the Head of Maintenance; the foremen of the maintenance teams report to them.

Technical support functions

246. As mentioned in para. 216, the structure provided to perform the technical support functions varies among different operating organizations. In some cases, each of these functions is covered by a separate and dedicated group while in other cases two or more functions are grouped. In what follows, each function is summarized separately.

Reactor physics and core management

247. The reactor physics and core management function involve the activities necessary to ensure safe and economical use of the fuel in the reactor. This includes the prediction and the monitoring of the behaviour of fuel and core components during the fuel cycle, the preparation of refuelling programmes and plans and the performance of tests and experiments. Assistance to operations during normal operation and abnormal occurrences is also included. For detailed Guidance see Safety Guide 50-SG-010.

17


Chemistry

248. The chemistry function provides the necessary chemical and radiochemical assistance to ensure safe operation, the long term integrity of systems and components, as well as control and reduction of radiation levels in working areas. The function includes monitoring, analyses, instructions to operations about chemical processes and evaluation of operating results. In many power plants, the chemical and radiochemical activities may include environmental monitoring, in particular when the chemistry and radiation protection activities are both performed by one group.

Radiation protection

249. The aim of radiation protection is to ensure implementation of the radiation protection programme, as described in Safety Guide 50-SG-05, and to advise the plant management on all related problems. This requires maintaining appropriate records, and monitoring work implementation so that all on-site activities are performed in accordance with the relevant requirements of the regulatory body, the policies of the operating organization and the ALARA principle. The Head of Radiation Protection (sometimes called Station Health Physicist) shall be directly responsible to the Plant Manager, independently of any other on-site group. Safety Guide 50-SG-0 5 includes guidance for the environmental monitoring and effluent release control.

Surveillance and testing

250. Surveillance and testing covers all the activities involved in in-service inspection, surveillance and testing contained in Safety Guides 50-SG-02 and 50-SG-08: monitoring plant parameters and system status, checking and calibrating instrumentation, testing and inspecting structures, systems and components, and evaluating the results of these actions.

Planning

251. Planning covers both long term and day to day planning and co-ordination of the on-site operation and maintenance activities, and in particular those important to safety. Its aim is to achieve maximum availability of systems and components important to safety, especially during complex activities such as refuelling, general overhaul and significant plant modifications.

18


Performance and plant engineering

252. The performance and plant engineering function ensures that all systems and components continue to meet the design requirements for safe and reliable operation. It includes:

(1) Monitoring performance,(2) Identifying causes of poor performance,(3) Recommending and designing modifications,(4) Assessing proposed modifications,(5) Reviewing the operating experience of other plants to assess its applicability,(6) Providing feedback of experience (see Safety Guide-SG-09).

253. The performance and plant engineering staff is sometimes subdivided into groups having responsibilities for systems such as: containment systems; shutdown systems; power control systems; heat removal systems; and emergency power supply systems. Other systems such as electrical supply, electrical output and secondary cooling may be included.

Safety analysis and review

254. Examples of activities under the function of safety analysis and review are:

(1) Reviewing the safety related aspects of plant operation;(2) Reviewing malfunctions, failures and precursors to assess their importance to

safety and suggesting actions to both correct adverse situations and improvesafety;

(3) Reviewing proposals for modification (see the Code on Operation) to ascertain that they promote safety;

(4) Reviewing submissions to the regulatory body to ensure their consistency with the safety policy of the operating organization;

(5) Suggesting corrective actions and/or modifications.

255. In many operating organizations, a safety committee is established at each nuclear power plant (and sometimes another committee at a higher level in the headquarters) to perform these safety reviews. The site committee is generally formed by the heads of the principal groups, is chaired by the Plant Manager and can request the co-operation of specialists from the site personnel or from off-site organizations.

Emergency preparedness

256. In order to cope with nuclear emergency situations, an emergency plan is prepared and put in force. The operating organization has a number of duties related

19


to the implementation of such a plan (for detailed guidance see Safety Guide 50-SG-06), in particular to maintain and ensure the preparedness to intervene at any time.

257. The function of ensuring emergency preparedness is performed in different ways according to national regulations and practices and may be assigned to one or more groups in the structure of the operating organization. The duties and the responsibilities of groups and individuals related to emergency preparedness shall be clearly defined in writing.

Records administration and documentation

258. Records administration and documentation ensures the appropriate keeping of all documents relevant to the safe and reliable operation of the plant, including design documents, commissioning documents, documents related to the operational history of the plant, as well as general and specific procedures. Particular care shall be exerted in order that, although all versions of each document are appropriately filed and kept as a reference, only the correct, up to date versions are available to the site personnel for day to day activity. For detailed guidance see Safety Guides 50-SG- QA2 and 50-SG-QA5.

Quality assurance

259. The function of a quality assurance unit is to ensure that an appropriate quality assurance programme is established and effectively executed and to verify that activities have been correctly performed (see the Code 50-C-QA and Safety Guide 50-SG-QA7). The Head of Quality Assurance shall be directly responsible to the Plant Manager.

Security

260. The arrangements for the security function vary according to local regulations and practices. In many plants, it is entrusted to external organizations.

Administration

261. The on-site administration functions do not differ significantly from those performed in a non-nuclear plant; they depend on the normal practice of the operating organization.

262. However, if administration is responsible for the management of the stores and for purchasing materials, parts and components important to safety, the personnel involved shall be properly trained in quality assurance provisions.

20


Training

263. The function of the training organization is the development and implementation of an integral training programme. The training programme covers training of all personnel directly involved in safety related activities. Details of recommendable arrangements and actions are given in Section 4.

CATEGORIES OF PERSONNEL

264. This Guide deals with those aspects o f qualifications and training which are important to the safe operation of nuclear power plants. It does not cover the other qualifications (managerial capabilities, financial, personnel management, etc.) which may be required to fully implement the functions of each position.

265. The following broad categories of personnel are involved: professionals, operators, technicians and craftsmen.

Professionals

266. The professional category shall include personnel who will fill the management positions such as Plant Manager and the operational line down to, and in some instances including, the Shift Supervisors. It shall also include the heads, and their senior assistants, of the maintenance and technical support groups.

267. Persons in this category shall have graduated in engineering or science or have another appropriate educational background, according to the national education system. They may also have attained the required equivalent knowledge through appropriate experience and training.

268. These persons shall have adequate practical experience in keeping with the duties and responsibilities assigned to them. For the senior operational, maintenance and technical positions and for the senior reactor physics and radiation protection positions, it is desirable that they have nuclear related experience. If persons with such experience are not available, staff members with suitable qualifications and experience may be recruited from industrial plants, design groups and nuclear research establishments, and be given appropriate training and practical experience in nuclear power plants.

Operators

269. The operator category includes persons who will operate the reactor controls and equipment. Such persons shall have education appropriate to the performance

21


of their duties at a specific power plant or have the equivalent knowledge gained through experience and training.

270. Persons who will operate the reactor controls and equipment shall have the required competence and experience. It is desirable for this experience to have been gained in responsible operational positions at nuclear or at least conventional power plants.

271. All other operators shall have experience appropriate to their duties and responsibilities.

Technicians

272. The technician category includes instrument technicians, radiation control technicians, chemical laboratory technicians, mechanical, electrical and electronic technicians, and other such specialized personnel.

273. Such persons shall have education appropriate to the performance of their duties at a specific power plant, or have the equivalent knowledge gained through experience and training.

Craftsmen

274. The craftsman category includes welders, fitters, mechanics, electricians, machinists and other skilled craftsmen. Such persons shall have education, experience and training appropriate to their duties.

3. RECRUITMENT

GENERAL

301. Recruitment shall be completed at an adequate time before the commissioning of the nuclear power plant to allow for appropriate training and familiarization with the plant. The number of persons recruited and sent for training should take account of the possibility that some of them will prove to be unsuitable at various stages of the training process. The need to know a foreign language for training in another country should also be considered where appropriate. The decision as to when each position or group of related positions is to be filled is largely dependent on the training required and the duties which the individuals are required to carry out prior to

22


being assigned responsibility for operation. In particular, the following factors should be taken into account:

(1) The time needed to train a person after recruitment in order to gain the qualifications and experience required.

(2) The time taken for the training of any person involved in the training of other personnel.

(3) The training of any person in relation to suppliers’ activities; for example, attachment to suppliers involved in pre-shipment testing or assembly of plant items.

(4) The duties the person is required to perform prior to the date of initial fuel loading. Many of these duties may need to be performed several years before this date and could include:(a) Assistance in the recruitment of other staff;(b) Preparation of commissioning procedures;(c) Pre-operational tests;(d) Preparation of operating and maintenance manuals;(e) Preparation of radiation protection procedures;(f) Specification and selection of equipment for the chemical and health

physics laboratories, for the maintenance and instrumentation shops and for radiation protection, and of spare parts, stores and other supplies;

(g) Commissioning and operation of auxiliary systems;(h) Preparation of an in-service inspection programme.

302. It is desirable that the members of the site personnel participate in design and construction activities in order to acquire a better understanding of the design intents and assumptions, of the safety criteria and of the technical characteristics of the plant.

303. Professionals should participate in design, fabrication and construction activities and maintenance personnel should acquire experience by working with vendors, both at the factories and during construction at the site.

304. Technicians and craftsmen should acquire experience during construction at the site.

305. The operating organization shall ensure continuing training of personnel assigned to the above mentioned pre-operational tasks.

306. The results of the consideration given to the above factors will be influenced by the type and size of the plant, the geographical location of the project in relation to the design and supply organizations, and the manpower resources in the locality.

307. The operating organization should prepare a schedule showing how recruitment, training and continuing training will be planned and implemented. The period covered by this schedule, in the case of the first plant, will begin with the start of

23


construction work. As additional plants are constructed and operated, this period may be reduced.

308. The general features of this schedule for the first plant should be along the lines given in the following paragraphs.

PROFESSIONALS

309. A few senior professionals, including in particular the Plant Manager and his deputy, shall be recruited at the beginning of the recruitment period, since one of their first duties is to plan and carry out further recruitment and training. This group should increase in number with the ongoing training and other pre-operational activities. Particular attention shall be given to an early recruitment of Shift Supervisors and senior operators.

OPERATORS AND TECHNICIANS

310. Relatively early recruitment of operators and technicians is advisable as time will also be needed for training and some of their duties start before the commencement of commissioning. The initial recruitment of these personnel may start about a year later than the recruitment of persons in the professional category, especially if operators and technicians with substantial previous experience are recruited. As junior staff are appointed, they shall be placed in training groups and be given pre- operational duties. The increase in personnel shall be brought about in steps so as to facilitate organized training.

311. An important aspect of training for some of these persons could be working with the construction organization in the checking and initial calibration of instruments and controls and in initial operation of equipment prior to fuel loading. Some individuals may thus be located at the site well before the commencement of operation, and others may be sent to suppliers’ plants to acquire experience with new and complex equipment.

CRAFTSMEN

312. The initial recruitment of the most experienced craftsmen should start about one year after recruitment of those in the operators and technicians category. They may receive specialized training at suppliers’ plants during the assembly and preshipment testing of special equipment, for example diesel or gas turbine sets or large pumps or fuel handling equipment. Personnel should continue to be recruited at a

24


rate commensurate with the length of training they will require and also with the opportunities available to place them into the construction and commissioning work to provide experience with the installed equipment and systems.

MEDICAL EXAMINATION

313. In addition to the provisions established by national regulations and practices relating to industrial medicine, all member of the operating staff whose duties have a bearing on safety shall be examined at the time of recruitment and at appropriate times thereafter to ensure that their health is compatible with the duties and responsibilities assigned to them. The use of aptitudinal tests may be recommended where applicable. Some Member States include a phychological test as well. All site personnel who may be occupationally exposed to radiation at the nuclear power plant shall be subjected to an initial and to periodic medical examinations as appropriate (see Safety Guide 50-SG-05).

4. TRAINING AND QUALIFICATION

GENERAL

401. The operating organization is responsible for the recruitment and training of staff and for the definition of qualifications and competence levels. Only qualified persons shall be entrusted with functions important to safety. These functions and the relative duties and responsibilities shall be clearly indicated in the description of the operating organization (see para. 206). Member States, in general, recognize three broad levels of duty and responsibility: professional, technicians and craftsmen. At each level there is a requirement for an individual to become appropriately qualified by means of:

— basic educational level (e.g. academic qualifications)— previous experience— training and continuing training— medical fitness— authorization, when so required.

402. The responsibility of ensuring that individuals are appropriately qualified and remain so rests with the operating organization. A formal authorization issued by the regulatory body or by another body delegated or authorized by the competent authority may be required before a person is assigned to a designated position as described in Section 5.

25


403. For each of the positions in the operating organization having importance to safety, a series of requirements for training and continuing training should be prepared. These requirements vary according to the individual positions, level of responsibility and specific levels of competence required and should be prepared by persons having specific competence in power plant operation and experience in training activities.

404. It is the responsibility of the Plant Manager, with reference to each position having importance to safety, to ensure that:

(1) The appropriate qualification requirements are established;(2) The training needs are analysed and an overall training programme is

developed;(3) The proficiency of the trainee at the various stages of the training is reviewed

and verified;(4) The effectiveness of the training is reviewed and verified;(5) The competence acquired is not lost after the final qualification;(6) The competence of the persons occupying each position is periodically checked

and continuing training is provided on a regular basis.

TRAINING SYSTEM

405. A systematic approach is recommended for the analysis, design, development, implementation and evaluation of both initial and continuing training to ensure that all job competence requirements are established and achieved.

406. A separate initial and continuing training programme should be defined and implemented for each group of personnel. The job specific training and qualification programme should be developed to provide and enhance the knowledge, skills and attitudes necessary for the performance of the assigned tasks and functions under all conditions.

407. The training programme for most nuclear power plant positions should include on the job training for ensuring that trainees obtain the required job related knowledge and skills in the actual work environment. Formal on the job training provides hands-on experience and allows the trainee to become familiar with plant routines. However, on the job training does not mean just working in the job/position under the supervision of a qualified individual but also involves the use of learning objectives, qualification guidelines and trainee assessment. This training should be conducted and evaluated in the work environment by qualified, designated individuals.

26


408. A performance based training programme based on an analysis of the responsibilities and tasks of a job should be designed, developed and implemented for each major station work group. The programme should include the following elements:

(1) Identification of all tasks for each work group;(2) Analysis of these tasks in terms of the knowledge, skills and attitudes required

to perform the tasks adequately;(3) Written compilation of learning objectives;(4) Definition of the basic educational and experience requirements and selection

of the trainees;(5) Specification and design of the training programme;(6) Development of training material and equipment;(7) Planning, scheduling and holding of classroom, simulator, special workshop

and on the job training in a structured manner;(8) Verification of the learning results;(9) Validation and improvement of the programmes.

409. The first step is to conduct job and task analysis for safety related jobs/positions and then to identify the training needs. The analysis identifies the knowledge, skills and attitudes required and the results are used to ensure that personnel are competent to perform all predicted tasks and to avoid improper operation.

410. In the development of a training programme, clear objectives should be compiled stating the anticipated performance, conditions and standards. Training activities and methods are subsequently specified.

411. The following training methods are widely used:

(1) Classroom instruction is the most widely adopted training method. Its effectiveness is enhanced by the use of training media such as written material, transparencies, audio, video and computing devices and plant scale models and part-task simulators.

(2) On the job training should be conducted in accordance with prescribed guidelines by incumbents who have been trained to deliver this form of training. Progress should be monitored and assessment carried out by an independent assessor.

(3) Initial and continuing simulator based training for the control room shift team personnel should be conducted on a simulator which is a representative of the power plant control room and has software of sufficient scope to cover normal operation, anticipated operational occurrences and a range of accident conditions.

(4) Laboratory/workshop training is needed to ensure safe working practices. Training mock-ups and models should be provided for activities that have to

27


be carried out quickly and skilfully and that cannot be practised with actual equipment. Training mock-ups should be full scale to the extent possible.

(5) Self-study training can be undertaken at home and at the work place. In all cases the trainees require support from a designated expert.

412. In general, the training shall consist of periods of formal training in the classroom intermixed with intervals of simulator or laboratory/workshop training as well as practical training in the plant.

413. In some Member States central training facilities are available and have proved to be beneficial. The use of overseas training facilities may involve the additional requirement for the trainees to know a particular foreign language and may involve different system and component identifications.

414. Even if off-site training facilities are to be used, a training unit should still be included in the plant organization. This unit should advise the Plant Manager on questions related to training, co-ordinate training activities on the site, ensure proper liaison with the off-site training facilities and collect the appropriate evidence of satisfactory completion of the training and continuing training of individuals.

415. The existence of a full time training staff does not relieve the plant line management from their responsibility to ensure that their staff are adequately trained and qualified. Each supervisor should recognize and provide for training needs of his subordinates. The responsibilities and the authority of training personnel, as distinct from those of line management, should be clearly defined and understood.

416. The personnel in the on-site training unit should be properly trained, in particular on matters concerning the policies of the operating organization, the regulatory requirements and quality assurance practices.

417. The training instructors, on and off the site, should have sufficient technical knowledge in their assigned areas of responsibilility. This means that they should be technically competent and have credibility with the students and other station personnel. In addition, the instructors should be familiar with the basics of adult education and have adequate instructional skills. They should also be given the time necessary to maintain their technical and instructional competence through work experience and continuing training.

418. The training progress shall be assessed and documented. Assessment of trainee performance includes written examinations, oral questioning and performance demonstrations.

419. A combination of written and oral techniques has been found to be the most appropriate for demonstrating knowledge and performance. Assessment of simulator training should utilize prepared checklists to improve objectivity. Assessment should not be regarded as a once-off activity. In some Member States reassessment of

28


individuals at regular intervals is undertaken by instructors and their immediate supervisors.

420. The training programme and training facilities and material shall be periodically reviewed and modified if necessary. The review shall cover the adequacy and effectiveness of the training, with due consideration given to the actual performance of persons in their jobs. It shall also examine training needs, training programmes and training facilities and material necessary to deal with changes to regulations, changes in the facility and lessons learned from industry experience. Such a review should be undertaken by persons other than those directly responsible for the training.

TRAINING PROGRAMMES

General

421. All new employees starting work at nuclear power plants shall be introduced to their work environment in a systematic and consistent manner. General employee training programmes shall give new employees a basic understanding of their responsibilities and of safe work practices.

422. The training programme for professionals, control room operators and senior technicians shall provide a thorough understanding of the basic principles of nuclear technology, nuclear safety and radiation protection, of the design intents and assumptions and of the theoretical basis of the plant activities, together with the necessary on the job training. The programme for other operators and technicians and for craftsmen should have a more practical orientation with explanations of the theoretical and safety related aspects.

423. All persons likely to be occupationally exposed to ionizing radiation, and not only the radiation protection staff, shall receive suitable training in radiation risks and the technical and administrative means required to prevent undue exposure and implement the ALARA principle (see Safety Guide 50-SG-05).

Training for operations personnel

424. Operators shall receive general employee training and overall operational training comparable to that given to those in the professional category.

425. Formal training of operators shall cover areas of technology to the levels necessary for the task to be performed. It shall develop a thorough theoretical and practical knowledge of plant systems, their function, layout and operation. Participation in the pre-operational phase and plant startup provide a valuable opportunity for this training. Emphasis shall be placed on systems having safety significance. The

29


training shall emphasize the importance of maintaining the plant within the operating limits and conditions and the consequences of the violation of these limits.

426. Control room operators should also get extensive experience in plant diagnostics, control manipulations, team work and administrative tasks. Shift supervisors should additionally be trained in supervisory techniques and communication skills. Their training should in general be more broadly based than that of other operators.

427. The training of control room operators should consist of classroom lectures and seminars, on the job training and simulator training. On the job training should be planned and controlled to ensure that all necessary topics are completed during the training period. Simulator exercises should be structured and planned in detail to ensure adequate coverage of relevant topics. The exercises should include preliminary briefings and follow-up critiques.

428. Training at a representative full scope simulator facility is of paramount importance for operators who work in real time with immediate consequences on the plant behaviour and who may be confronted with abnormal situations which have low probability of occurrence and which cannot therefore be enacted in real plant practice. Consideration shall be given to training control room staff as a unit to develop strength in interaction as members of a team.

429. Trainees shall learn routines for normal operation of the plant and the response of the plant to changes that could cause damaging accidents if not counteracted. The programme shall improve the diagnostic skills o f the trainees. Operating procedures for normal operation and anticipated operational occurrences as well as appropriate actions for design basis accidents and, as far as practicable, for severe accidents shall be included in the programme and shall be practised at the simulator, so that the trainees may recognize the negative consequences of errors or violations of the procedures.

430. In addition to general employee training, the field operators shall receive overall operational training commensurate with their duties and responsibilities. All personnel in this category shall have detailed knowledge of the operational features of the plant and hands-on experience. This knowledge shall cover both the control rooms and the plant as a whole.

Training for maintenance personnel

431. Initial training of maintenance staff shall develop knowledge about plant layout and the general features and purposes of plant systems, quality assurance and quality control, maintenance procedures and practices, including surveillance and inspections, and special maintenance skills.

30


432. Training of maintenance staff shall emphasize the potential safety consequences of technical or procedural errors. Past experience of faults and hazards caused by such errors shall be reviewed.

433. Controls should be established to ensure that maintenance personnel are qualified on equipment to which they are assigned to work. This qualification could be based on training given by the component manufacturer, training on equipment mock-ups and on the job training under supervision by experienced staff. Maintenance personnel should have access to training mock-ups and models for training in maintenance activities that have to be carried out quickly and cannot be practised with actual equipment. Wherever maintenance training may be undertaken, its effectiveness remains the responsibility of the Plant Manager. Evaluation of each individual’s skills and knowledge in performing a given maintenance activity should normally precede qualification.

Training for other technical personnel

434. Personnel involved in chemistry, health physics, nuclear engineering or other functions should have qualifications and receive training appropriate to their jobs and responsibilities. Such training should be determined by a systematic approach as described above for operators and maintenance personnel.

435. Technicians may be assigned to carry out work similar to their own at other plants or with equipment suppliers. Emphasis shall be placed on the development of specific skills, with classroom training limited to essentials. In some cases, laboratories and part-scope simulators may have to be established to impart basic and specific skills.

436. Craftsmen shall receive general employee training and some overall plant training. The main objective shall be to impart and develop the basic and specialized skills required for work on the installed equipment. Methods to achieve this objective could include attaching persons to suppliers of equipment and components and to construction groups. The basic skills could also be developed with the help of part- scope simulators, as appropriate.

Training for supervisory personnel

437. In addition to the training described above it is recognized that technicians and professionals may require additional technical knowledge and skills and also supervisory skills.

438. Managers and supervisors should have mastered their own technical field through basic training and long experience in the nuclear field. They should have a thorough understanding of relevant standards, rules and regulations. They should

31


also have a good overall knowledge of the plant and its systems. Those having responsible positions in the emergency preparedness organization should be specially trained for their emergency duties.

439. Since supervisory personnel will hold leading positions in the plant organization, it is important that they acquire a particular capacity for promoting among their subordinates, mainly by example, the consciousness of the need to consider safety as a primary objectives in all day to day activities.

440. There should be a management development programme to ensure that an adequate number of qualified persons are available to fill any management position, should a need suddenly arise. Training of managers and supervisors, and their potential successors, should include courses and seminars on management and supervisory skills.

Training for emergencies

441. General training shall be provided for all staff members who have assignments under the emergency plan. Supplementary training shall be provided to those staff members who must perform specialized duties required in the event of an accident.

442. Training for accident response and management should be emphasized. Such topics as nuclear safety analysis, applicable codes, standards and regulations, information on evaluated safety margins of the plant, symptom oriented procedures and accident management measures should be covered. The principal results of any probabilistic safety assessment of the plant, showing the importance of plant systems in preventing damage or severe accidents, shall be covered by the training programme.

Continuing training

443. Continuing training is that training necessary to maintain and enhance the competence of nuclear power plant staff in terms of their knowledge, skills and attitudes. It can also include training to improve the career development potential of selected individuals. Continuing training must therefore be regarded as an integral part of the operations of a nuclear power plant. Continuing training based on a systematic approach is essential to ensure that the levels o f qualification and competence are maintained and upgraded when necessary.

444. Continuing training shall be carried out on a regular basis. An annual programme is recommended. Included in the programme should be all groups of personnel whose functions are important to the safe operation of the nuclear power plant.

32


445. All site personnel shall have continuing training in the performance of their duties in an emergency.

446. Persons occupationally exposed to ionizing radiations shall receive periodic training in radiation protection.

447. Operators should undergo formal continuing training on a regular basis and the time needed for this should be taken into account when work schedules are established. Continuing training at a simulator facility is essential and simulator training exercises should be planned annually and systematically. Such exercises should reflect operating experience with emphasis on those situations which do not occur frequently, for example startup, shutdown, special transients and accident conditions. In the case of the maintenance group, refresher training should be given on infrequently performed maintenance activities.

448. The continuing training should include updates on the plant and procedural changes or modifications, operating experience gained in-house and elsewhere in the industry as well as trends in job performance.

EXPERIENCE REQUIREMENTS

G eneral

449. Some guidance is given in this section on the previous experience required of candidates before they are assigned to the various positions in the plant organization. Only general guidance can be given because of the large variety of valid experience possible. The information below is derived from average levels in countries with extensive nuclear programmes.

450. Successful performance in subordinate positions is an acceptable form of experience for head positions. The Plant Manager, and the Heads o f Operations and Maintenance (as well as of Technical Support, if such a comprehensive group is foreseen), require a variety of experience in positions of increasing responsibility. The requirements for these positions and for the Shift Supervisors must include demonstration of leadership ability.

451. On the job training does not always correspond to practical experience. Their equivalence in terms of both duration and effectiveness for qualification purposes should be assessed case by case.

Professionals

452. The Plant Manager shall have experience in several of the key areas of plant activity such as operation, maintenance or technical support. This experience may

33


usually be gained over a period of 10-15 years. He should have also appropriate management experience.

453. The Heads of Operations and Maintenance (and Technical Support, see para. 450) shall have experience in their respective fields of activity sufficient for the development o f specific competence and managing capacity. This experience may usually be gained over a period of 5-8 years, with a minimum of 2-3 years at nuclear power plants, of which 6 months at the specific (or similar) site.

454. Shift Supervisors shall have operational shift experience in a conventional or nuclear power plant, with team and leadership experience. This experience may usually be gained over a period of 4 -6 years, with a minimum of 2-3 years at nuclear power plants, o f which 6 months at the specific (or similar) site.

455. The Head of Radiation Protection and the person responsible for reactor physics shall have had specific experience at comparable facilities. Sufficient experience may usually be gained over a period of 4 -6 years at nuclear facilities, of which 6 months at the specific (or similar) site.

Operators

456. The senior members of this category should have operational shift experience in fossil fuelled or nuclear power plants. Sufficient experience may be gained over a period of 3 -4 years, of which a minimum of 2 years at nuclear power plants, with 3 months at the specific (or similar) site.

457. The other operators shall have experience appropriate to their duties and responsibilities.

Technicians and craftsmen

458. The leading members of this category should have about 2-3 years of practical experience. The other technicians and craftsmen shall have experience appropriate to their duties and responsibilities.

459. Some experience may be gained during construction and commissioning activities.

34


5. AUTHORIZATION

GENERAL

501. The operating organization, in carrying out its responsibilities for safe operation, shall establish procedures by which persons controlling or supervising changes in the operational status of the plant, or with duties having a direct bearing on safety, have to be authorized before they are allowed to perform these duties.

502. These procedures shall provide for an assessment of the capabilities of persons to be authorized. These capabilities shall include a thorough knowledge of the established safety rules and regulations, as well as of the particular nuclear power plant and its safety aspects.

503. Persons occupying positions of the type referred to in para. 501 should hold a formal authorization issued by the regulatory body or by an other body acknowledged by the competent authority. In some Member States a proposal regarding the positions for which personnel must be authorized by the regulatory body has to be submitted to the regulatory body for approval.

504. The term ‘authorization’ will be used below to indicate both the authorization by the operating organization and the formal authorization issued by the regulatory body.

505. In some Member States, the regulatory body requires documented evidence of the qualifications of other persons (not authorized by the regulatory body) whose duties have a significant, though not immediate, bearing on safety.

506. Independently of any formal authorization issued by other bodies, it is the responsibility of the operating organization to ensure the appropriate qualification of all members of site personnel and off-site personnel.

507. The operating organization has the the responsibility for establishing qualification criteria for its own personnel and for contractor personnel who perform activities important to safety. Assurance is required that contractor personnel meet the qualification criteria prior to active involvement in plant maintenance or other support activities.

508. Work on safety related structures, systems or components carried out by contractor personnel shall be monitored by a representative of the operating organization who meets the training and qualification criteria established for such work.

35


P O S IT IO N S T O B E A U T H O R IZ E D

509. As a minimum, the persons who occupy the following positions shall be authorized:

(1) Shift Supervisor (and any person who is designated to take charge of the direct plant or unit operation);

(2) Reactor Operator.

510. In addition, consideration should be given to making it a requirement that persons in designated positions such as the Plant Manager, Heads of Operations and Maintenance and Chiefs in Technical Support (e.g. Chief Health Physicist) be authorized.

BASIS FOR AUTHORIZATION

511. The authorization of persons occupying positions specified in para. 509 which entail direct responsibility for the manipulation of the operational controls in the control room shall be based on a careful evaluation of the individual’s qualifications.

512. Any authorization of persons occupying positions such as those named in para. 510 should be on the basis of the individual’s qualifications, including education, experience, training and personal attributes.

513. Authorization of persons occupying responsible positions other than those indicated in paras 509-510 shall be based on an evaluation of their knowledge and experience in the relevant fields they have to supervise.

REAUTHORIZATION

514. If an authorized individual moves to a different nuclear power plant or to a different position in the same plant for which an authorization is also required, he shall satisfy the specific qualification requirements before he is authorized to assume the new position.

515. Consideration shall be given to the need for periodic reauthorization as well as for reauthorization of individuals who are to resume authorized duties after an extended period of absence from performing the duties of the authorized position. The authorization is generally subject to periodic reviews (2-3 years) of the competence of the authorized person and may be withdrawn or not extended if the required conditions are no more met. Renewal or extension of the authorization shall in any case be subject to a medical examination.

36


6. RECORDS

601. The operating organization shall maintain adequate records of individual training plans, of the performance of the individual trainees and of the authorizations issued.

602. The main purpose of these records is:

(1) To provide evidence to the regulatory body of the qualifications of all persons whose duties have a bearing on safety and of the authorizations, when so required;

(2) To provide information necessary for reviews of the training programme and for corrective actions if necessary.

603. The records shall be collected and kept in accordance with the applicable quality assurance requirements (see Safety Guide 50-SG-QA2).

37


NUCLEAR POWER PLANT ORGANIZATIONAL CHARTS

Annex


UNITED KINGDOM

Station Manager

Production Manager Engineering Manager Resources Manager

Operations Maintenance Engineering Technical Health Management Planning Training QAPhysics Services& Emergency Preparedness

Mechanical Electrical C&l Reactor Chemistry Reactor OperationalPhysics Feedback

PlantPerformance

SafetyAnalysis

Administrarion


GERMANY

Power Plant Administration

I I

MechanicalEngineering

MechanicalEngineering(nuclear)

MechanicalEngineering(conventional)

EquipmentMaintenance

Materials,Welding,Testing

PublicRelations

PlantSafety

BuildingSecurity

Production

Power Plant ShiftOperation

Process & Thermal Engineering

TrainingInstruction

ElectricalEngineering

Heavy current Engineering

Instrumentation and Control

ElectricalEngineering & Instrumentation and Control: Operations

1Monitoring

Physics

RadiationProtection

Chemistry


TEOLLISUUDEN VOIMA OY, FINLAND


PENLY, FRANCE(during startup)


UNITED STATES OF AMERICA

i&cManager

Vice President Nuclear Operations

DirectorQuality Assurance

Site Director

General Manager Plant Operations

Outage Operations MaintenancePlanning Manager ManagerManager

Director Nuclear Engineering

Licensing & Site Training TechnicalCompliance Protection Manager Superintendent

Manager Manager

Director Technical Services

Mechanical ElectricalMaintenance MaintenanceSupervisor Supervisor

Radiation ChemistryProtection ManagerManager

OperationsSupervisor


CONTRIBUTORS TO DRAFTING AND REVIEW

During the development phase the following experts participated in one or more of the meetings (1975-1977):

Burkhardt, W.

Burtheret, J.

Davediuk, F.

Feger, M.

Franzen, L.F.

Ganguly, A.K.

Garnett, C.R.

Grier, B.H.

Gronow, W.S.

Haig, R.

Hedgran, A.

Hendrie, J.

Higashi, A.

Hurst, D.

Iansiti, E.

Ikegame, R.

Jarschky, R.

Kaut, W.

Klik, F.

Komarov, E.I.

Council for Mutual Economic Assistance

France

Canada

France

Germany

India

United Kingdom

United States o f America

United Kingdom

Switzerland

Sweden

United States of America

Japan

Canada

International Atomic Energy Agency

Japan

Germany

Commission of the European Communities

Czechoslovakia

World Health Organization

45


Konstantinov, L.V.

Kovalevich, O .M .

Kiiffer, K.

McCubbin, J.

Messiah, A.

Milhoan, J.L.

Minogue, B.

Mongini, L.

Nilson, R.

Nilson, R.

Pele, J.

Philip, G.

Sanchez Gutierrez, J

Sevcfk, A.

Smyth, H.E.

Stadie, K.B.

Sundaram, S.M.

Timm, M.

Uchida, H.

Van Reijen, G.

V61ez, C.

Wachter, K.P.

Wagadarikar, V.K.

46

Union of Soviet Socialist Republics

Switzerland

Canada

France

United States o f America

United States of America


Sweden

International Organization for Standardization



Mexico

Czechoslovakia

Canada

Nuclear Energy Agency of the OECD

India

Germany

Japan


Mexico

Germany

India



Zuber, J.F . Switzerland

During the revision phase the following experts participated in the meetings (1988-1990):

Aro, I. International Atomic Energy Agency

Bertini, A. Italy

Chapman, C. United Kingdom

Endou, T. Japan

Franzen, F. International Atomic Energy Agency

Grauf, E. Germany

Kiss, I. Hungary

Milley, D .C. Canada

Novak, S. International Atomic Energy Agency

Persson, P.-E. Sweden

Recarte, I. Spain

Sebal, P. France

Shankman, S. United States o f America

NUCLEAR SAFETY STANDARDS ADVISORY GROUP (NUSSAG)

Aro, I. International Atomic Energy Agency

Brooks, G. Canada

Denton, H. United States o f America

Dong, Bainian China

Wright, H .A. International Atomic Energy Agency

47


Havel, S.

Herttrich, P.M .

Hohlefelder, W.

Isaev, A.

Ishikawa, M.

Kovalevich, O.M

Laverie, M.

Lee, Sang Hoon

Pele, J.

Reed, J.

Ryder, E.

Sajaroff, P.

Sarma, M .S.R.

Versteeg, J.

Fischer, J.

Czechoslovakia

Germany

Germany


Japan


France

Korea, Republic of


United Kingdom

United Kingdom

Argentina

India

Netherlands


48


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 of nuclear power plants: Governmentalorganization

Safety Guides

50-SG-G1 Qualifications and training of staff of the regulatory bodyfor nuclear power plants

50-SG-G2 Information to be submitted in support of licensingapplications for nuclear power plants

50-SG-G3 Conduct of regulatory review and assessment during thelicensing process for nuclear power plants

50-SG-G4 Inspection and enforcement by the regulatory body fornuclear power plants

50-SG-G6 Preparedness of public authorities for emergencies atnuclear power plants

50-SG-G8 Licences for nuclear power plants: content, format andlegal considerations

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

2. SITING

50-C-S (Rev. 1) Code on safety of nuclear power plants: Siting

Safety Guides

50-SG-S1 (Rev. 1) Earthquakes and associated topics in relation to nuclearpower plant siting

50-SG-S2 Seismic analysis and testing of nuclear power plants

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

50-SG-S4 Site selection and evaluation for nuclear power plantswith respect to population distribution

1988

1979

1979

1980

1980

1982

1982

1984

1988

1991

1979

1980

1980

49


50-SG-S6

50-SG-S7

50-SG-S8

50-SG-S9

50-SG-S 10A

50-SG-S 1 OB

50-SG-S11A

50-SG-S 1 IB

3. DESIGN

50-C-D (Rev. 1)

50-SG-D1

50-SG-D2

50-SG-D3

50-SG-D4

50-SG-D5

50-SG-D6

50-SG-D7

50-SG-D8

50-SG-S5

50-SG-D9

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

Hydrological dispersion of radioactive material in relation to nuclear power plant siting

Nuclear power plant siting: hydrogeological aspects

Safety aspects o f the foundations o f nuclear power plants

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

Extreme meteorological events in nuclear power plant siting, excluding tropical cyclones

Design basis tropical cyclone for nuclear power plants

Code on the safety of nuclear power plants: Design

Safety Guides

Safety functions and component classification for BWR, PWR and PTR

Fire protection in nuclear power plants

Protection system and related features in nuclear power plants

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

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

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

Emergency power systems at nuclear power plants

Safety-related instrumentation and control systems for nuclear power plants

Design aspects o f radiation protection for nuclearpower plants

1985

1984

1986

1984

1983

1983

1981

1984

1988

1979

1979

1980

1980

1982

1981

1982

1984

1985

1981

50


50-SG-D 10 Fuel handling and storage systems in nuclear power plants 1984

50-SG-D 11 General design safety principles for nuclear power plants 1986

50-SG-D 12 Design of the reactor containment systems in nuclear 1985power plants

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

50-SG-D 14 Design for reactor core safety in nuclear power plants 1986

50-P-l Application of the single failure criterion 1990

4. OPERATION

50-C -0 (Rev. 1) Code on the safety of nuclear power plants: Operation 1988

Safety Guides

50-SG-01 (Rev. 1) Staffing o f nuclear power plants and the recruitment, 1991training and authorization of operating personnel

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

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

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

50-SG-05 Radiation protection during operation of nuclear 1983power plants

50-SG -06 Preparedness o f the operating organization (licensee) 1982for emergencies at nuclear power plants

50-SG-07 (Rev. 1) Maintenance o f nuclear power plants 1990

50-SG-08 (Rev. 1) Surveillance of items important to safety in nuclear 1990power plants

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

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

50-SG-011 Operational management o f radioactive effluents and 1986wastes arising in nuclear power plants

5. QUALITY ASSURANCE

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

1988

51


50-SG-QA2 Quality assurance records system for nuclearpower plants

50-SG-QA3 Quality assurance in the procurement of items andservices for nuclear power plants

50-SG-QA4 Quality assurance during site construction of nuclearpower plants

50-SG-QA5 (Rev. 1) Quality assurance during commissioning and 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 manufacture of items for nuclear power plants

Quality assurance auditing for nuclear power plants

Quality assurance in the procurement, design and manufacture of nuclear fuel assemblies

Safety Guides

50-SG-QA1 Establishing of the quality assurance programme for anuclear power plant project

50-SG-QA6

50-SG-QA7

50-SG-QA8

50-SG-QA10

50-SG-QA11

1979

1979

1981

1986

1981

1983

1981

1980

1983

1984

52


SELECTION OF IAEA PUBLICATIONS RELATING TO THE SAFETY OF

NUCLEAR POWER PLANTS

SAFETY SERIES

9 Basic safety standards for radiation protection:1982 edition

49 Radiological surveillance of airborne contaminantsin the working environment

52 Factors relevant to the decommissioning o f land-basednuclear reactor plants

55 Planning for off-site response to radiationaccidents in nuclear facilities

57 Generic models and parameters for assessingthe environmental transfer of radionuclides from routine releases: Exposures of critical groups

67 Assigning a value to transboundary radiation exposure

69 Management of radioactive wastes from nuclearpower plants

72 Principles for establishing intervention levels for the protection of the public in the event o f a nuclear accident or radiological emergency

73 Emergency preparedness exercises for nuclear facilities: Preparation, conduct and evaluation

75-INSAG-1 Summary report on the post-accident review meetingon the Chernobyl accident

75-INSAG-2 Radionuclide source terms from severe accidents tonuclear power plants with light water reactors

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

77 Principles for limiting releases of radioactiveeffluents into the environment

79 Design o f radioactive waste management systemsat nuclear power plants

81 Derived intervention levels for application incontrolling radiation doses to the public in the event o f a nuclear accident or radiological emergency: Principles, procedures and data

1979

1980

1981

1982

1985

1985

1985

1985

1986

1987

1988

1986

1986

1986

1982

53


86 Techniques and decision making in the assessmentof off-site consequences of an accident in a nuclear facility

93 Systems for reporting unusual events in nuclear power plants

94 Response to a radioactive materials release having a transboundary impact

97 Principles and techniques for post-accident assessment and recovery in a contaminated environment of a nuclear facility

98 On-site habitability in the event o f an accident at a nuclear facility:Guidance for assessment and improvement

101 Operational radiation protection: A guide to optimization

103 Provision of operational radiation protection services at nuclear power plants

104 Extension of the principles o f radiation protection to sources of potential exposure

84 Basic principles for occupational radiation monitoring

TECH N ICA L R EPO RTS SERIES

155 Thermal discharges at nuclear power stations

163 Neutron irradiation embrittlement of reactor pressurevessel steels (being revised)

189 Storage, handling and movement of fuel andrelated components at nuclear power plants

198 Guide to the safe handling of radioactive wastes atnuclear power plants

200 Manpower development for nuclear power:A guidebook

202 Environmental effects o f cooling systems

217 Guidebook on the introduction of nuclear power

224 Interaction of grid characteristics with design andperformance of nuclear power plants: A guidebook

230 Decommissioning of nuclear facilities:Decontamination, disassembly and waste management

1987

1990

1989

1989

1989

1990

1990

1990

1974

1975

1979

1980

1980

1980

1982

1983

1987

1983

54


239

242

249

262

267

268

271

274

282

292

294

296

299

300

301

237

306

Nuclear power plant instrumentation and control:A guidebook

Qualification of nuclear power plant operations personnel: A guidebook

Decontamination of nuclear facilities to permit operation, inspection, maintenance, modification or plant decommissioning

Manual on training, qualification and certification of quality assurance personnel

Methodology and technology of decommissioning nuclear facilities

Manual on maintenance of systems and components important to safety

Introducing nuclear power plants into electrical power systems of limited capacity: Problems and remedial measures

Design of off-gas and air cleaning systems at nuclear power plants

Manual on quality assurance for computer software related to the safety of nuclear power plants

Design and operation of off-gas cleaning and ventilation systems in facilities handling low and intermediate level radioactive material

Options for the treatment and solidification of organic radioactive wastes

Regulatory inspection of the implementation of quality assurance programmes: A manual

Review of fuel element developments for water cooled nuclear power reactors

Cleanup of large areas contaminated as a result of a nuclear accident

Manual on quality assurance for installation and commissioning of instrumentation, control and electrical equipment in nuclear power plants

Manual on quality assurance programme auditing

Guidebook on the education and training o f techniciansfor nuclear power

1984

1984

1985

1986

1986

1986

1987

1987

1988

1989

1989

1989

1989

1989

1989

1984

1989

55


307 Management o f abnormal radioactive wastesat nuclear power plants

1989

225

238

248

276

294

303

308

332

341

348

355

377

379

387

390

416

424

IAEA-TECDOC SERIES

Planning for off-site response to radiation accidents in nuclear facilities

Management of spent ion-exchange resins from nuclear power plants

Decontamination of operational nuclear power plants

Management of radioactive waste from nuclear power plants

International experience in the implementation of lessons learned from the Three Mile Island accident

Manual on the selection of appropriate quality assurance programmes for items and services o f a nuclear power plant

Survey of probabilistic methods in safety and risk assessment for nuclear power plant licensing

Safety aspects o f station blackout at nuclear power plants

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

Earthquake resistant design of nuclear facilities with limited radioactive inventory

Comparison of high efficiency particulate filter testing methods

Safety aspects of unplanned shutdowns and trips

Atmospheric dispersion models for application in relation to radionuclide releases

Combining risk analysis and operating experience

Safety assessment of emergency electric power systems for nuclear power plants

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

Identification of failure sequences sensitive to human error

1980

1981

1981

1983

1983

1984

1984

1985

1985

1985

1985

1986

1986

1986

1987

1987

56


443

444

450

451

458

497

498

499

508

510

522

523

525

529

540

542

543

547

425

550

Experience with simulator training for emergency conditions

Improving nuclear power plant safety through operator aids

Dose assessments in NPP siting

Some practical implications of source term reassessment

OSART results

OSART results II

Good practices for improved nuclear power plant performance

Models and data requirements for human reliability analysis

Survey of ranges of component reliability data for use in probabilistic safety assessment

Status of advanced technology and design for water cooled reactors: Heavy water reactors

A probabilistic safety assessment peer review:Case study on the use of probabilistic safety assessment for safety decisions

Probabilistic safety criteria at the safety function/system level

Guidebook on training to establish and maintainthe qualification and competence of nuclear power plantoperations personnel

User requirements for decision support systems used for nuclear power plant accident prevention and mitigation

Safety aspects of nuclear power plant ageing

Use of expert systems in nuclear safety

Procedures for conducting independent peer reviews of probabilistic safety assessment

The use of probabilistic safety assessment in the relicensing of nuclear power plants for extended lifetimes

Simulation o f a loss o f coolant accident

Safety of nuclear installations: Future directions

1987

1987

1988

1988

1988

1989

1989

1989

1989

1989

1989

1989

1989

1989

1990

1990

1990

1990

1987

1990

57


553 Computer codes for level 1 probabilistic safety 1990assessment

561 Reviewing computer capabilities in nuclear power plants 1990

570 OSART mission highlights, 1988-1989

581 Safety implications of computerized process control 1991in nuclear power plants

586 Simulation of a loss o f coolant accident with rupture 1991of the steam generator hot collector

590 Case study on the use of PSA methods: 1991Determining safety importance of systems and componentsat nuclear power plants

591 Case study on the use o f PSA methods: 1991Backfitting decisions

592 Case study on the use o f PSA methods: 1991Human reliability analysis

593 Case study on the use o f probabilistic assessment methods: 1991Station blackout risk at the Millstone Unit 3

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 IAEA safety codes and guides (NUSS) in the light o f 1985current safety issues

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

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

STI/PUB/716 Optimization of radiation protection 1986

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

STI/PUB/761 Nuclear power performance and safety 1988

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

58


STI/PUB/785

STI/PUB/803

STI/PUB/824

STI/PUB/825

STI/PUB/826

STI/PUB/783

Feedback of operational safety experience from nuclear power plants

Regulatory practices and safety standards for nuclear power plants

Fire protection and fire fighting in nuclear installations

Environmental contamination following a major nuclear accident

Recovery operations in the event of a nuclear accident or radiological emergency

Radiation protection in nuclear energy 1988

1989

1989

1989

1990

1990

59


HOW TO ORDER IAEA PUBLICATIONSAn exclusive sales agent for IAEA publications, to whom all orders

and inquiries should be addressed, has been appointed for the following countries:

CANADAUNITED STATES OF AM ERICA UNIPUB, 4611-F Assem bly Drive, Lanham, MD 20706-4391, USA

In the following countries IAEA publications may be purchased from the sales agents or booksellers listed or through major local booksellers. Payment can be made in local currency or with UNESCO coupons.

AR G E N TIN A Comision Nacional de Energfa A tom ica, Avenida del L ibertador 8250, RA-1429 Buenos Aires

A U S T R A LIA Hunter Publications, 58 A Gipps Street, C ollingwood, V ictoria 3066BELGIUM Service Courrier UNESCO, 202, Avenue du Roi, B-1060 Brussels

CHILE Comisi6n Chilena de Energta Nuclear, Venta de Publicaciones, Amunategui 95, Casilla 188-D, Santiago

CHINA IA E A Publications in Chinese:China Nuclear Energy Industry C orporation,Translation Section,P.O. Box 2103, BeijingIA E A Publications other than in Chinese:China National Publications Im port & E xport Corporation, Deutsche Abteilung, P.O. Box 88, Beijing

CZEC HO SLO VAKIA S.N.T.L., Mikulandska 4, CS-11686 Prague 1A lfa , Publishers, Hurbanovo namestie 3, CS-815 89 Bratislava

FRANCE Office International de Docum entation et L ib ra irie ,48 , rue Gay-Lussac, F-75240 Paris Cedex 05

H U N G AR Y Kultura, Hungarian Foreign Trading Company, P.O. Box 149, H-1389 Budapest 62

IN D IA O xford Book and Stationery Co., 17, Park Street, Calcutta-700 016 O xford Book and Stationery Co.,Scindia House, New Delhi-110 001

ISRAEL Heiliger & Co. Ltd.23 Keren Hayesod Street, Jerusalem 94188

ITALY Libreria Scientifica, D ott. Lucio de Biasio "aeiou", Via Meravigli 16, 1-20123 Milan

JAPAN Maruzen Company, L td , P.O. Box 5050,100-31 Tokyo InternationalPAKISTAN Mirza Book Agency, 65, Shahrah Quaid-e-Azam, P.O. Box 729, Lahore 3

POLAND Ars Polona-Ruch, Centrala Handlu Zagranicznego, Krakowskie Przedmiescie 7, PL-00-068 Warsaw

R O M A N IA llex im , PO. Box 136*137, BucharestSOUTH A FR IC A Van Schaik Bookstore (Pty) L td , P.O. Box 724, Pretoria 0001

SPAIN Diaz de Santos, Lagasca 95, E-28006'Madrid Diaz de Santos, Balmes 417, E-08022 Barcelona

SWEDEN AB Fritzes Kungl. Hovbokhandel, Fredsgatan 2, P.O. Box 16356, S-10327 Stockholm

U N ITE D KINGDOM HMSO, Publications Centre, Agency Section, 51 Nine Elms Lane, London SW8 5DR

USSR Mezhdunarodnaya Kniga,Smolenskaya-Sennaya 32*34, Moscow G-200YU G O SLAVIA Jugoslovenska Knjiga,Terazije 27, P.O. Box 36, YU-11001 Belgrade

■ Orders from countries where sales agents have not yet been appointed and requests for information should be addressed directly to:

“ Div's'on °* Publications” ^ it International Atomic Energy Agency° Wagramerstrasse 5, P.O. Box 100, A-1400 Vienna, Austria


INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA, 1991
