no.50-SG-07gnssn.iaea.org/Superseded Safety Standards/Safety... · FOREWORD by the Director General The demand for energy is continually growing, both in the developed and the developing

no.50-SG-07IAEA SAFETY GUIDES

Maintenance of Nuclear Power PlantsA Safety Guide

This publication is no longer valid Please see http://www-ns.iaea.org/standards/

CATEGORIES OF IAEA SAFETY SERIES

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

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

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

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

(4) Procedures and Data. Publications in this category contain information on procedures, techniques and criteria pertaining to safety matters. They are issued under the authority of the Director General of the Agency. The covers are distinguished by the wide blue band on the lower half

Note: The covers o f publications brought out within the framework o f the NUSS (Nuclear Safety Standards) Programme are distinguished by the wide yellow band on the upper half.


MAINTENANCE OF NUCLEAR POWER PLANTS

A Safety Guide


T he follow ing S ta tes are M em bers o f the In te rn a tio n a l A tom ic Energy A gency:

A FG H A N ISTA NA LBA NIAA LG ER IAA R G E N T IN AA U STR A LIAA U STRIABA NG LA D ESHBELGIUMBOLIVIABRA ZILBU LG ARIABURMABY ELO RU SSIA N SO V IET

SO CIA LIST REPU BLIC CANADA CH ILE COLOM BIA COSTA RICA CUBA CYPRUSC ZECH O SLO V A K IA D EM O CRA TIC KAM PUCHEA DEM OCRA TIC PEO PL E’S

REPU BLIC O F K O REA DEN M A RKDOM INICAN REPU BLICECU A DO REG Y PTEL SA LV A D O RETHIO PIAFIN LA N DFRA N CEGABONG ERM AN D EM O CRA TIC REPU BLICG ERM AN Y , F E D E R A L REPU BLIC O FGHANAG REECEG UA TEM A LAHAITI

H OLY SEEHUN G ARYICELA N DIN DIAIN D O N ESIAIRA NIR A QIR EL A N DISR A E LITA LYIV O R Y CO ASTJAM A ICAJAPA NJO R D A NKENYAK O REA , R EPU BLIC O F KUW AIT LEBANON LIBERIALIBYAN A RAB JA M A H IR IY ALIE C H T EN ST EINLU X EM BOU RGM AD A GA SCARM ALAYSIAMALIM AU RITIU SMEXICOM ONACOM ONGOLIAM OROCCON ETH ER L A N D SNEW ZEA LA N DN IC A R A G U AN IG ERN IG ER IANORW AYPAK ISTA NPANAMAPARA G UA YPERU

PHILIPPIN ESPOLAN DPO RTU G A LQ A T A RROM ANIASAUDI A RABIASEN EG A LSIE R R A LEON ESIN G A PO R ESOU TH A FR IC ASPAINSRI LA N KASUDANSWEDENSW ITZERLA N DSY RIA N A RAB REPU BLICTH A ILA N DTU N ISIATU R K E YU GANDAU K R A IN IA N SO V IET SO CIA LIST

REPU BLIC UNION O F SO V IET SO C IA LIST

REPUBLICS U N ITED A RA B EM IRA TES U N IT ED KING D OM O F G R E A T

BRITA IN A ND N O R T H E R N IR EL A N D

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

U N IT ED REPU BLIC O F T A N ZA N IA

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

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

© IA E A , 19 8 2

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

P r in te d by th e IA E A in A u stria O c to b e r 198 2


SAFETY SERIES N o. 50-SG-07

MAINTENANCE OF NUCLEAR POWER PLANTS

A Safety Guide

INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA, 1982


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

MAINTENANCE OF NUCLEAR POWER PLANTS: A SAFETY GUIDE IAEA, VIENNA, 1982

STI/PUB/604 ISBN 9 2 - 0 - 1 2 3 8 8 2 - 7


FOREWORD by the Director General

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

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

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

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

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


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

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

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

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

STATEMENT by the Senior Advisory Group

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

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


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

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

The five Codes of Practice cover the following topics:

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

These five Codes establish the objectives and minimum requirements tha t should be fulfilled to provide adequate safety in the operation of nuclear power plants.

The Safety Guides are issued to describe and make available to Member States acceptable m ethods o f implementing specific parts o f the relevant Codes o f Practice. Methods and solutions varying from those set out in these Guides may be acceptable, if they provide at least comparable assurance that nuclear power plants can be operated w ithout undue risk to the health and safety of the general public and site personnel. Although these Codes o f Practice and Safety Guides establish an essential basis for safety, they may not be sufficient or entirely applicable. Other safety documents published by the Agency should be consulted as necessary.

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

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


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

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

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

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

NOTE

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

Safety Series No. Safety Series No. Safety Series No. Safety Series No. Safety Series No. Safety Series No.

50-SG-D150-SG-D250-SG-0150-SG-0250-SG-0350-SG-04

Safety Series No. Safety Series No. Safety Series No. Safety Series No. Safety Series No. Safety Series No.

50-SG-0550-SG-0950-SG-QA250-SG-QA350-SG-QA550-SG-QA10

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


CONTENTS

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

1.1. General ................................................................................................ 11.2. Scope ................................................................................................ 1

2. MAINTENANCE PROGRAMME ........................................................... 2

2.1. General description ......................................................................... 22.2. Establishing a m aintenance programme .................................... 32.3. Preventive m aintenance schedule ................................................ 32.4. Design liaison .................................................................................. 42.5. Maintenance planning ................................................................... 5

3. ORGANIZATION AND RESPONSIBILITIES FORMAINTENANCE .......................................................................................... 7

3.1. Organizational structure .............................................................. 73.2. Responsibilities .............................................................................. 73.3. Selection and training of maintenance personnel ................... 8

4. ADMINISTRATIVE CONTROLS ............................................................ 9

4.1. Administrative procedures .......................................................... 94.2. Scope o f procedures .................................................................... 104.3. Maintenance instructions .............................................................. 11

5. MAINTENANCE FACILITIES ............................................................ 14

5.1. Workshop facilities ....................................................................... 145.2. Facilities for maintenance on radioactive items .................... 155.3. Decontam ination facilities .......................................................... 155.4. Special facilities ........................................................................... 16

5.4.1. Mock-ups5.4.2. Special equipment and tools5.4.3. Photographic and video records

5.5. Lifting and handling facilities ................................................... 17

6. REPLACEMENTS AND REPAIRS ....................................................... 18

6.1. Remedial maintenance ................................................................... 186.2. Replacing defective items .............................................................. 186.3. Repairing defective items .............................................................. 19


7. MODIFICATIONS ARISING FROM MAINTENANCE ....................... 19

7.1. Types o f modification .................................................................. 197.2. Review requirement ...................................................................... 207.3. Submission of proposals ................................................................ 207.4. Implementation and docum entation ............................................ 21

8. STORES ........................................................................................................ 21

8.1. Organization ...................................................................................... 218.2. Procurement .................................................................................... 228.3. Receipt ................................................................................................ 238.4. Storage ................................................................................................ 248.5. Issue requirements ........................................................................ 25 1

9. RECORDS .................................................................................................. 25

9.1. Generation and collection o f records ........................................... 259.2. Retention of records ..................................................................... 26

10. SURVEILLANCE, REVIEW AND AUDIT PROGRAMME .............. 26

10.1. The need for a programme ........................................................... 2610.2. Surveillance procedures .............................................................. 2710.3. Maintenance review ....................................................................... 2710.4. Audit programmes .......................................................................... 27

ANNEX I. Administrative aspects of maintenance work .......................... 29

DEFINITIONS ....................................................................................................... 35

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

LIST OF NUSS PROGRAMME TITLES


1. INTRODUCTION

1.1. General

1.1.1. Effective m aintenance is essential for safe operation of a nuclear power plant. It not only ensures that the level o f reliability and effectiveness o f all plant structures, systems and com ponents having a bearing on safety remainsin accordance with design assumptions and intent, but also that the safety status of the plant is no t adversely affected after commencement o f operation.

1.1.2. This Safety Guide provides detailed guidance on the provisions of the Code of Practice on Safety in Nuclear Power Plant Operation, Including Commissioning and Decommissioning (IAEA Safety Series No. 50-C-0) on the m aintenance o f structures, systems and components. Like the Code, the Guide forms part of the IAEA’s programme,referred to as the NUSS programme, for establishing Codes o f Practice and Safety Guides relating to nuclear power plants. The List of NUSS Programme Titles appears at the end of this publication.

1.1.3. Nuclear power plant m aintenance requires special attention because of:

(1) Limitations set by requirem ents that a minimum num ber o f components remain operable even when the plant is shut down

(2) Difficulty of access to some plant items even when the plant is shut down, due to radiological protection constraints

(3) Potential radiological hazards to site personnel and the public.

1.2. Scope

1.2.1. This Guide covers the organizational and procedural aspects o f maintenance but does not give detailed technical advice on the m aintenance of particular plant items.

1.2.2. It gives guidance on preventive and remedial measures necessary to ensure that all structures, systems and com ponents im portant to safety are capable of performing as intended.

1.2.3. The Guide covers the organizational and administrative requirem ents for establishing and implementing preventive m aintenance schedules, repairing defective plant items, providing m aintenance facilities and equipm ent, procuring stores and spare parts, selecting and training m aintenance personnel, reviewing and controlling plant m odifications arising from maintenance, and for generating, collecting and retaining m aintenance records.

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1.2.4. Maintenance shall be subject to quality assurance in all aspects im portant to safety. Because quality assurance has been dealt with in detail in o ther Safety Guides, it is only included here in specific instances where emphasis is required.

1.2.5. Maintenance is considered to include functional and performance testing of plant, surveillance and in-service inspection, where these are necessary either to support other m aintenance activities or to ensure continuing capability of structures, systems and com ponents im portant to safety to perform their intended functions. This applies no m atter whether functional and performance testing, surveillance and in-service inspection are carried out by m aintenanceor o ther personnel. These activities are, however, covered in other Guides (the Safety Guide on In-service Inspection for Nuclear Power Plants, IAEA Safety Series No. 50-SG-02 and the Safety Guide on Surveillance of Items Im portant to ̂Safety in Nuclear Power Plants, No. 50-SG-08). Reference should be made to these docum ents and to the programmes based on them to avoid gaps in the overall m aintenance programme.

2. MAINTENANCE PROGRAMME

2.1. General description

2.1.1. The m aintenance programme covers all preventive and remedial measures both administrative and technical, necessary to perform m aintenance activities satisfactorily. The range of activities includes servicing, overhaul, repair and replacement of parts and, as appropriate, testing, calibration and inspection (including in-service inspection). It may also include modifications to structures, systems and components.

2.1.2. The operating organization is responsible for establishing a programme for preventive and remedial m aintenance that will achieve design performance throughout the operational life of the plant. The operating organization may delegate to o ther organizations the work of establishing and implementing the maintenance programme or any part thereof, but it shall retain overall responsibility for such work delegated.

2.1.3. The operating organization shall, however, ensure that a m aintenance organization is established tha t includes all the administrative, technical and supervisory functions needed in mobilizing and supervising on-site and off-site maintenance resources. Plant management shall remain responsible for on-site maintenance.

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2.2. Establishing a m aintenance programme

2.2.1. Because the design and design objectives of nuclear power plants have a strong influence on the m aintenance programme, its development should be initiated sufficiently early in the design phase. The requirem ents of the maintenance programme should be similarly reflected in the final design and construction details of the plant. To accomplish this, the operating organization should arrange for personnel with m aintenance experience to consult regularly with the design organization.

2.2.2. The m aintenance programme shall be established at such a time that it can be implemented as necessary to cope w ith the following:

(1) Plant systems as they are put into operation, and(2) Plant items that are already installed, but awaiting system completion.

In addition to defining responsibilities for m aintenance during the operating phase, the operating organization should also define in writing the responsibility for maintaining plant items during construction and commissioning.

2.2.3. The operating organization should collect timely and sufficient information on maintenance needs from designers, manufacturers, and from other operating organizations. It should also ensure that the programme is based on good maintenance practice.

2.2.4. As early as possible during construction, but not later than the commissioning stage of the plant, a site m aintenance group as defined in subsection 3.1.3 should already be established to carry out plant m aintenance(see Safety Guide on Commissioning Procedures for Nuclear Power Plants, IAEA Safety Series No. 50-SG-04).

2.3. Preventive m aintenance schedule

2.3.1. Preventive maintenance entails pre-planned routine testing, inspection, servicing and overhaul of structures, systems and components. Its purpose is to detect incipient failures and to assure the continuing capability of the plant to perform its intended functions. These pre-planned activities shall be specified in a preventive m aintenance schedule.

2.3.2. Items im portant to safety shall be included in the preventive m aintenance schedule. The operating organization shall review, as appropriate, the lists of structures, systems and com ponents in order to ensure that items im portant to safety have been properly identified and classified and to ensure that the

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applicable requirements of the regulatory body have been met; guidance on identification and classification of structures, systems and components is provided in the Safety Guide on Safety Functions and Component Classification for BWR, PWR and PTR, IAEA Safety Series No. 50-SG-D1.

Design bases, design description documents, specifications, the safety report and regulatory requirements shall also be used to identify items important to safety. Consideration should also be given to the requirements and recommendations of the Safety Guide on Operational Limits and Conditions for Nuclear Power Plants, IAEA Safety Series No. 50-SG-03.

2.3.3. The frequency and extent of preventive maintenance of items included in the preventive maintenance schedule shall be established after taking into consideration (a) the criteria detailed in the Safety Guide 50-SG-D1, (b) the supplier’s recommendations, and (c) the relevant experience of the operating organization. Assumptions concerning the frequency of preventive maintenance that were used to justify the reliability of systems or plant items shall also be taken into account when preparing the preventive maintenance schedule; they shall be reviewed in the light of experience and failure data.

2.3.4. The preventive maintenance schedule shall be reviewed as appropriate during the life of the plant to take into account operating experience and plant modifications.

2.4. Design liaison

2.4.1. The aim of close liaison between the operating and design organizations, mentioned in sub-section 2.2.1, should be to ensure that the final maintenance programme is based on a clear understanding of the design philosophy and plant details, that the plant is designed to facilitate and minimize maintenance, and that any exposure to personnel is kept as low as reasonably achievable (ALARA).

2.4.2. The operating organization should arrange for reviews of the design by its staff experienced in maintenance, who should check for design features that could be changed to ease maintenance, particularly in areas of radiological hazard. The review should cover the following:

(1) Access to plant items(2) Adequacy of handling devices(3) Available space for withdrawal(4) Area available for in situ work(5) Interference with the operation and maintenance of other structures

and systems

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(6) Provision for shielding and access control, both perm anently installed and tem porary

(7) Adequacy of maintenance and storage facilities covered in sections 5 and 8

(8) Adequacy o f active drain facilities and ventilation in areas that may be used for tem porary m aintenance work

(9) Electrical and mechanical isolation devices'(10) Draining and venting facilities on active systems(11) Adequacy o f stocks o f spare parts(12) Provisions for handling and storing either tem porarily or permanently

activated or contam inated items, tools etc., particularly in the controlled areas

(13) Ease of m aintenance,of inspection and of decontam ination of com ponents during operation

(14) Suitability of docum entation.

The operating organization’s previous experience or that o f o ther operating organizations in maintaining equipm ent and plant, should be a factor in selecting plant items.

2.4.3. This close liaison between the operating and design organization should be maintained throughout the life of the nuclear power plant. It is particularly necessary to ensure effective and timely assistance from the design organization when plant faults occur or modifications are required. For this purpose, the operating organization should arrange feedback o f operating experience and reliability data to the design organization.

2. S. Maintenance planning

2.5.1. Because of the complexity of a nuclear power plant, the activities of different units w ithin plant management interface w ith one another in ways that are significant for safety. In addition, the large num ber o f special components to be maintained makes successful allocation o f on-site and off-site resources needed for effective m aintenance a major activity. Maintenance activity has to be planned, therefore, in the context o f overall plant management planning. The m aintenance group should, therefore, work in close consultation w ith other plant management groups.

It is the usual practice for plant management to establish a planning unit to co-ordinate all activities. However, the m aintenance group should carry out its own work scheduling within the overall plan. Planning should also ensure that adequate m aintenance personnel are available on call to provide urgent remedial m aintenance o f items im portant to safety.

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2.5.2. More complex planning is necessary for the timely completion of plant shutdown work, particularly where this involves off-load refuelling.

2.5.3. The organization for m aintenance will vary greatly in different operating organizations, depending partly on the operating organization’s philosophy and practices for operation, but more significantly on the type of reactor and mode of refuelling.

2.5.4. In plants designed for on-load refuelling, the refuelling activity is routine and continual and will usually be performed by operating personnel. Subjectto the operating organization’s policy on the use of off-site resources, the organization for m aintenance in this type of plant can be based on having a sufficient num ber of staff to deal effectively with a relatively even flow of (maintenance work with a minimum of assistance from off-site sources.

2.5.5. In plants designed for off-load refuelling, the refuelling activity is periodic, occurring at intervals that usually vary from twelve to eighteen m onths depending on fuel, core design and load factors during the operating period. Due to the periodic nature o f refuelling in such plants, there will be a large accumulation of preventive, remedial and m odification work scheduled for the refuelling shutdown. Since this accumulated work is all scheduled to be perform ed concurrently with a refuelling period o f limited duration, there will probablybe large peaks in the demand for m aintenance resources. Additional personnel requirements will also be necessary in order to comply with radiological protection requirements w ithout extending outage time. The organization for maintenance should be structured and staffed to respond effectively to these peak requirements. It is expected that, in this case, the on-site organization will require significant supplementary resources from off site.

2.5.6. Advantage should be taken o f any shutdown to undertake maintenance.Where this is a refuelling shutdown, m aintenance work shall no t unduly interfere 4 with refuelling activities. A ppropriate m aintenance schedules should thereforebe readily available in the event o f unplanned as well as planned shutdowns.

2.5.7. Control room personnel shall be informed (e.g. by means o f a work perm it procedure, see sub-section 4.2) of all m aintenance work before it commences, any changes to the plant that it entails, and when the plant has been returned to the responsibility o f the operator. Adequate comm unication shall be maintained between the m aintenance and control room operating personnel during the performance of the work.

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3. ORGANIZATION AND RESPONSIBILITIES FOR MAINTENANCE

3.1. Organizational structure

3.1.1. The plant management shall establish a m aintenance group on site to implement the m aintenance programme. Responsibility for implementing the programme shall be delegated to an individual, usually designated as m aintenance superintendent. Although the structure of the organization will vary in accordance with national practices and the operating organization’s philosophy, there are common factors that influence the choice of structure.

3.1.2. The organizational structure for m aintenance will depend on the extent to which m aintenance is implemented by the m aintenance group, by a central maintenance departm ent o f the operating organization, by.outside agencies,or by contractors. These sources of m aintenance personnel can be successfully used in combination. But in every case the m aintenance superintendent shall retain primary responsibility for implementing the m aintenance programme.

3.1.3. The m aintenance group may be divided into mechanical, electrical, and control and instrum entation sections. The organizational structure below the section heads will depend mainly on which source or com bination of sources of m aintenance personnel is employed. Examples illustrating two different forms of organizational structures have been given in the Safety Guide on Staffing of Nuclear Power Plants and Recruitm ent, Training and A uthorization of Operating Personnel, IAEA Safety Series No. 50-SG-01. Those examples, however, are no t the only possible alternatives for maintenance: others may be equally recommended. The structure o f the m aintenance group, and its integration with off-site resources, depends heavily on such factors as type o f plant, number of reactors on one site, local availability of suitable manpower, modeof operation of the reactors and regulations governing the em ploym ent of off-site labour. In all cases, plant management shall ensure that sufficient num bers of adequately qualified personnel are available to implement the m aintenance programme.

3.2. Responsibilities

3.2.1. The responsibilities o f the m aintenance group management and supervisory staff shall be defined in writing by plant management. Plant management shall ensure that the m aintenance group works in close co-ordination w ith such groups as operations, health physics, quality assurance, planning, fire protection, work safety and security.

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3.2.2. Because o f the variety of organizational structures previously discussed, it is not practical in this guide to define fully the responsibilities o f the various managerial and supervisory positions. Nevertheless, regardless o f the structure chosen for maintenance, the responsibilities normally include:

(1) Maintenance superintendent: implementing m aintenance in accordance with appropriate legislation, the policy o f the operating organization, the quality assurance programme, and the guidelines issued by plant management; reviewing and optimizing the preventative maintenance schedule; administering remedial m aintenance activities including initiation of plant m odifications where necessary; ensuring availability of adequate m aintenance procedures; administering m aintenance personnel, including training and qualification; ensuring provision of tools and equipm ent; reviewing and approving records; reportingto plant management.

(2) Section heads (in the area of their responsibility): im plem entation o f m aintenance in accordance with the quality assurance programme and the instructions of the m aintenance superintendent; specification and inventory control of spares; preparation o f m aintenance procedures and updating o f the same in the light of experience, e.g. radiation exposure, work m ethods; provision o f adequate supervision o f the work, assistance in adm inistration of m aintenance personnel; planning and allocation o f resources in accordance w ith the overall plan; reporting progress and results to the m aintenance superintendent; review and approval of reports and records.

(3) Supervisors (in the area of work assigned to them): allocation of resources to the various jobs in the daily work plan; observation of progress and quality of work; assurance that procedures are followed; generation, collation and processing of records; report o f work status and progress.

It is the responsibility o f the m aintenance superintendent, section heads and supervisors to take into account the need to keep exposure o f personnel as low as reasonably achievable.

3.3. Selection and training of maintenance personnel

3.3.1. Staffing for the m aintenance group including selection of personnel shall be in accordance w ith the provisions o f the Safety Guide on Staffing of Nuclear Power Plants and Recruitm ent, Training and Authorization o f Operating Personnel, IAEA Safety Series No. 50-SG-01. The provisions in the following sub-sections (3.3.2, 3.3.3 and 3.3.4) also apply to outside personnel as appropriate to the type and duration of their job on site.

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3.3.2. All m aintenance personnel shall be given training in radiological protection safety rules, access control and emergency procedures appropriate to their duties, and they shall be adequately qualified in these areas before being allowed to work in controlled areas. Detailed guidance for training of personnel with respect to radiological protection will be found in the Safety Guide on Radiological Protection during Operation of Nuclear Power Plants, IAEA Safety Series No. 50-SG-05.

For special jobs depending on the nature of the work to be performed, its bearing on the safety o f the plant, the related potential risks and consequent required safety precautions, m aintenance personnel should receive a special briefing appropriate to the job in addition to the above training. Maintenance personnel shall also be appropriately trained and qualified in the quality assurance requirem ents applicable to their duties.

3.3.3. Selected m aintenance supervisors and craftsmen should be given special training, both a t m anufacturer’s works and on site, during construction, fabrication, assembly and testing of particular items im portant to safety. Arrangements should be made for m aintenance personnel to participate in maintenance, inspection and testing during the construction and commissioning stages.

3.3.4. Maintenance craftsmen shall have been trained and shall have initially dem onstrated a satisfactory level of craft skill. Certain crafts, such as welding, require periodic re-qualification to dem onstrate that the individual continues to possess the necessary skills. For this purpose re-training may be necessary. They shall also be trained to understand plant systems and equipm ent appropriate to their job. Each craftsman should be trained in several areas of the plant to provide flexibility in job allocation. This will not only result in more efficient use of manpower but will also enable variations between the radiation exposures of individuals to be minimized.

4. ADMINISTRATIVE CONTROLS

4.1. Administrative procedures

In order to implement the m aintenance programme and achieve the objective o f safe reliable operation, plant management shall establish the required administrative controls. These controls will usually be in the form of administrative procedures, which will also include all administrative controls and requirem ents for carrying out m aintenance on the plant. The development,

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review and approval o f administrative procedures shall be in accordance with the Safety Guide on Quality Assurance during Operation of Nuclear Power Plants, IAEA Safety Series No. 50-SG-QA5.

4.2. Scope of procedures

4.2.1. Administrative procedures for m aintenance shall be sufficiently comprehensive to provide plant m aintenance supervision w ith administrative guidance in all areas of maintenance.

4.2.2. The following is a list of some of the administrative controls and procedures to be taken into account when developing docum ents applicable to maintenance:

(1) General m aintenance work criteria and procedures(2) Generation and control o f procedures(3) Review and revision o f procedures(4) Work order authorization(5) Equipm ent isolation work permit(6) Radiation work perm it(7) Fire hazard control(8) Plant modification control(9) Training and qualification of m aintenance personnel

(10) Material and parts control(11) Lubrication control plan and schedule(12) Housekeeping and cleanliness(13) Personnel radiation m onitoring(14) Equipm ent nom enclature, location and labelling(15) Preventive m aintenance schedule(16) Generation and collection o f records(17) R etention of records(18) Maintenance instruction preparation(19) Shutdown work planning.

Inform ation useful for developing authorizations, perm its and certificates needed in administrative control o f the tasks m entioned in items (4), (5) and(6) is provided in Annex I.

4.2.3. In developing the above procedures, account shall be taken of the interfaces between one m aintenance activity and other activities such as m aintenance on other systems or components, plant operation and radiological protection. In particular, the following aspects shall be explicitly covered:

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(1) Delineation of responsibility between those persons performing maintenance and those persons directly responsible for plant operation. For example, removal from and restoration to service of structures, systems and com ponents shall be authorized by the designated persons in the operating shifts (normally the shift supervisor).

(2) The establishment of a work perm it system controlling the issue and cancellation of appropriate docum entation such as work authorizations, equipm ent isolation work permits, live testing authorizations, limitations of access etc. This includes designation of persons in the operating shift to issue such permits to those responsible for carrying out the work.

(3) The provision of a direct positive indication of equipm ent tha t is not available for operation. This includes tagging where appropriate and any steps to be taken to prevent unintentional restoration to service. Tagging shall not obscure any indication device.

(4) When work is to be undertaken in controlled areas, work planning and control requirements m entioned in the Safety Guide on Radiological Protection during O peration of Nuclear Power Plants, IAEA Safety Series No. 50-SG-05, shall be complied with.

Reference should be made to the Safety Guide on Management of Nuclear Power Plants for Safe Operation, IAEA Safety Series No. 50-SG-09 (will be published in 1984), for further details o f interface activities between maintenance and operation.

4.3. Maintenance instructions

4.3.1. The operating organization shall require plant management to prepare instructions that give detailed directions and controls required for carrying out maintenance. Plant management should delegate the responsibility for preparing these instructions to the m aintenance group. If persons outside the maintenance group prepare the instructions for routine maintenance, they should be subm itted to the m aintenance group for final approval. An administrative procedure shall describe the m ethod, form at and level o f detail required in the maintenance instructions. The preparation of m aintenance instructions shall be in accordance with the Safety Guide on Quality Assurance during Operation of Nuclear Power Plants, IAEA Safety Series No. 50-SG-QA5.

4.3.2. Maintenance that can either affect the performance of items im portant to safety or potentially endangers the health and safety of personnel shall be pre-planned and performed in accordance with written procedures, instructions or drawings appropriate to the circumstances.

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Routine maintenance activities that require skills normally possessed by qualified personnel may not require detailed step-by-step delineation; they shall nevertheless be subject to general administrative procedural control.

4.3.3. Exceptionally, performance of a particular job with no m aintenance instructions initially available may be authorized. Such authorization should be issued after a proper review by plant management, and with the proviso that m aintenance instructions are w ritten and appropriately reviewed as the job progresses, and the draft of the instruction reviewed and approved on job completion, before the equipm ent is returned to normal service.

4.3.4. In the process o f preparing m aintenance instructions, reference documents should be consulted to determine the technical content. These docum ents should include appropriate drawings, codes, standards, instruction books and manuals provided by the design organization, construction organization, equipm ent supplier and the operating organization.

4.3.5. Inform ation in the instruction should be presented in a logical, step-by- step order. The level o f detail should be such that the individual responsible for the work can follow the instruction w ithout further direction or supervision.

4.3.6. The content and form at for a typical m aintenance instruction should be generally in accordance with the Safety Guide on Quality Assurance during Operation of Nuclear Power Plants, IAEA Safety Series No. 50-SG-QA5. The content should therefore include the following:

(1) Instruction identification: Numbers, letters or com binations of the two that identify each unique instruction as one in the m aintenance series. These shall uniquely identify the instruction in all subsequent programmes, plans and records that refer to it.

(2) Title: A concise description of the subject of the instruction.(3) Purpose: A brief statem ent of the scope of job controlled by the

instruction.(4) Prerequisites: All special conditions of the plant, system or equip

m ent status required prior to commencement of work. Any special training or mock-up practice should be noted.

(5) Lim iting conditions: Any conditions that limit plant operation as a result of carrying out the job, such as load reduction, and operation of standby equipm ent or safety systems. For example, when a system is undergoing maintenance, it shall be considered unavailable for safety purposes unless it can be dem onstrated that the ability of the system to perform its safety function has not been diminished.

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(6) Special precautions: Any special safety instructions such as special radiological protection measures, the need to secure or remove loose items, and any required material control and environmental conditioning.

(7) Special tools and equipm ent: Lists of all special tools, rigging and equipm ent required to perform the job.

(8) References: List of applicable sections of reference docum ents that may need to be consulted, such as base line data, drawings, prints, instruction books, manuals, photographs, mock-ups etc.

(9) Instruction text: A sequential step-by-step listing of work details required for the job and identifying any changes for radiological conditions as work progresses. A t selected steps, craftsmen may be required to sign their names or initials indicating satisfactory completion of the preceding step or steps, either in the instruction or on an attached check sheet.

(10) Inspection witness points: Selected points in the work sequence where quality control verification by a com petent person is to be made. Work may no t proceed past this point until the inspection has been made and docum ented.

(11) Return to service: Actions and checks required to return the equipment or system to an operational condition after certification that the job is complete by the person responsible. Where appropriate, acceptance criteria shall be specified. These include correct reinstatem ent and correct procedural compliance as well as confirm ation of system operability, e.g. valve line-up.

(12) Operational testing: Any post-maintenance operational testing required to prove that the equipm ent is functioning in the intended manner.

Items (11) and (12) are operating functions and may be included either in the m aintenance instruction or in a special interfacing operating instruction.

4.3.7. The form at of m aintenance instructions may vary depending on the purpose of the docum ent and the practices of the operating organization.

4.3.8. It is essential to docum ent a brief but understandable review o f the repairs carried out, explicitly identifying the cause o f failure, the remedial action taken, the com ponent that failed and its mode of failure, the total repair time and the outage time (if different) and, finally, the state of the system after repairs.

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5. MAINTENANCE FACILITIES

5.1. Workshop facilities

5.1.1. The operating organization shall provide adequate workshop facilities with sufficient space and equipm ent to carry out m aintenance effectively; availability and intended use of off-site facilities and the need to deal with radioactive plant items shall be taken into account. On-site workshops shall be provided for mechanical, electrical, control and instrum entation equipment.

5.1.2. Each of the workshops should include the following:

(1) Office area (if no t already provided elsewhere), including facilities (for the processing and storage of records and procedures

(2) Fitting and overhaul area with suitable work benches for disassembly, repair and reassembly of plant items that are intended to be dealt with in the workshop

(3) Secure storage facilities for special tools and testing equipm ent required for maintenance.

5.1.3. On- or off-site facilities should at least include:

(1) Mechanical shops

(i) Space and equipm ent for welding, sheet m etal and plate fabrication, pipefitting and handling o f heavy equipm ent and material

(ii) Machine tools such as lathes, milling machines, shapers, pedestal drills, grinders and presses

(iii) Clean room with lapping, polishing and surface-checking equipment

(2) Electrical shops ^

(i) Test benches with the appropriate power supplies connected(ii) M otor overhaul and test facility

(iii) High voltage test area with controlled access.(iv) Instrum ent and relay testing and calibration facilities(v) Small coil rewind facility

(3) Control and instrumentation shops

(i) Test benches with the necessary electrical, electronic, pneumatic and hydraulic supplies and test equipm ent

(ii) Calibration and testing facilities for instrum ents and controls(iii) Facility for safe fault finding on energized equipm ent

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(4) Other facilities

(i) Facilities for acceptance testing of overhauled/replacement equipment, as necessary

(ii) Preventive m aintenance tools such as vibration analysers, bearing m onitoring tools and non-destructive testing facilities.

5.2. Facilities for maintenance on radioactive items

5.2.1. It may be impractical or impossible to decontam inate some plant items sufficiently to allow them to be maintained in the general workshops.In such cases and also for the m aintenance of irradiated items, special maintenance facilities shall be provided to keep radiation exposure to individuals as low as reasonably achievable and to prevent the spread of contam ination. This may be accomplished by providing specific m aintenance facilities for particular single plant items and providing a workshop,located within the controlled area, for work on radioactive parts that can be brought to it.

5.2.2. Plant management may occasionally find it necessary to supplement the above perm anent arrangements by erecting a tem porary facility around a plant item or a machine tool.

5.2.3. Whichever facility is being provided, the following need consideration:

(1) Access control and changing rooms(2) Ventilation with filtered discharge(3) Treatm ent, handling and disposal of liquid radioactive wastes(4) Treatm ent, handling and disposal o f solid radioactive wastes(5) Radiological equipm ent for m onitoring and protection(6) Shielding and rem ote handling equipm ent(7) Provision for storing radioactive items, with non-conforming items

segregated from conforming items(8) Decontam ination requirements.

5.3. Decontamination facilities

5.3.1. The operating organization shall provide facilities for removing radioactive contam ination from plant items, tools and equipm ent prior to m aintenance or other disposition.

These facilities should include the following features:

(1) Access control and changing rooms(2) Ventilation with filtered discharge(3) Treatm ent, handling and disposal of liquid radioactive wastes

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(4) Treatm ent, handling, storage and disposal o f solid radioactive wastes(5) Radiological equipm ent for monitoring and protection(6) Decontam ination tanks and special equipm ent to deal with the largest

plant item likely to require decontam ination(7) Adequate supplies o f electrical power, steam, ho t water, compressed

air and approved chemical decontam ination agents(8) O ther decontam ination systems such as glass blasting or ultrasonic

techniques.

5.3.2. Experience in operating plants shows that these facilities are frequently inadequate. Changing rooms and decontam ination facilities should therefore be provided to accommodate maximum usage in periods of intensive m aintenance work.

5.4. Special facilities

5.4.1. Mock-ups

In some cases there are maintenance advantages in designing and constructing simulations, mock-ups or models o f particular sections of the plant, either full size or reduced, in areas rem ote from the section of the plant concerned. Such facilities are particularly recommended for:

(1) Rehearsing work to be carried out in high radiation areas or on highly contam inated plant items, particularly for personnel not familiar with the plant or for an unusual or specialized job

(2) Planning procedures, to avoid errors and reduce exposure(3) Gaining experience with tools and protective equipm ent in

simulated working conditions(4) Developing and improving tools and equipm ent(5) Training and qualifying personnel for selected work.

5.4.2. Special equipm ent and tools

In addition to the special equipm ent essential to maintenance, plant management shall provide special equipm ent where it can significantly reduce radiation exposure or improve safety.

Examples of special equipm ent that has proved necessary or helpful are:

(1) Remote-handling manipulators and rem otely operated special purpose tools

(2) Autom atic welding and cutting equipm ent(3) Remotely operated non-destructive testing equipm ent


(4) A utom atic in situ valve seat lapping machine(5) Remote viewing equipm ent such as mirrors, binoculars, telescopes,

periscopes, horoscopes, fibroscopes, closed circuit television and rem otely operated cameras

(6) Communication systems such as direct line telephones, radio and comm unication equipm ent for use when respiratory protection is being worn

(7) Special containers for contam inated items(8) Shielded containers and portable shielding(9) Radiological protection clothing and equipm ent

(10) Material and equipm ent for controlling and containing radioactive contam ination. Examples are plastic sheeting and tents, paper floor covering, suction cleaners and floor cleaning equipm ent

(11) Fixed or rapidly assembled access equipm ent to reduce personnel exposure, such as perm anent ladders or telescopic cradles.

5.4.3. Photographic and video records

During plant construction, the operating organization should ensure that comprehensive photographic and (where appropriate) video records are compiled, particularly o f plant areas that will eventually be inaccessible or subject to high radiation levels.

These visual construction records of as-built conditions should show identification marks and be comprehensively catalogued with descriptive captions. This will ensure that similar photographs and tapes taken during subsequent inspections or m aintenance work can be easily compared and will assist any work planning and personnel familiarization undertaken before starting m aintenance work.

5.5. Lifting and handling facilities

5.5.1. The operating organization shall ensure that adequate facilities, space and clear access are provided in the design of the plant for all plant items that are likely to require removal and transport.

5.5.2. Plant management shall provide suitable portable lifting and transport facilities with clear indications o f lifting capacity. In the selection and use of these facilities, due account shall be taken o f the radiological consequences of failure. Examples of precautions taken include regular exam ination and maintenance of lifting equipm ent, periodic testing and special inspections before major lifting and rigging operations.

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5.5.3. Special consideration should be given to the use of mobile lifting and transport facilities as a possible means of substantially reducing personnel exposure (e.g. filter removing equipment).

6. REPLACEMENTS AND REPAIRS

6.1. Remedial maintenance

6.1.1. The m aintenance group should be capable, with the assistance of outside agencies if necessary, o f restoring the plant to its normal operational capability by remedial m aintenance such as replacem ent or repair of defective plant items.

6.1.2. The need for remedial m aintenance may arise when deficiencies or failures are noticed during plant operation. Anticipating such cases, plant management shall draw up appropriate procedures, e.g. work order authorization and equipm ent isolation work perm it procedures, including how such failures are to be reported to the m aintenance group and how plant items are to be withdrawn from service for remedial maintenance. These procedures should require operating personnel to assign priority to remedial work based on its importance to safety and taking into account prescribed operational limits and conditions.

6.1.3. After any remedial m aintenance is completed, a brief report o f the repairs or replacements carried out should be prepared, identifying the component that failed, its mode of failure, the remedial action taken, the total repair time, the total outage time and the state of the system after the remedial maintenance work.

6.1.4. The m aintenance group shall periodically review the m aintenance records for evidence of incipient or recurring failures. When the need for remedial maintenance is found either during this review or during preventive m aintenance of the plant, the m aintenance group shall initiate remedial m aintenance in accordance with the administrative procedures referred to above. The preventive maintenance programme shall be revised accordingly.

6.2. Replacing defective items

6.2.1. When remedial m aintenance can be m ost conveniently accomplished by substituting a proven identical spare for the defective plant item, it shall be done in accordance with established procedures such as that for issuing work

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order authorizations. A defective plant item not suitable for subsequent repair shall be disposed o f by a docum ented process that prevents re-use. Defective components should not be allowed to accumulate in work areas.

6.2.2. When a defective item has been replaced, suitable functional or performance tests shall be carried out in conjunction with the operating personnel; the tests shall be docum ented and results recorded. The plant item shall be returned to service or standby duty in accordance with established procedures such as that for issuing equipm ent isolation work permits.

6.3. Repairing defective items

6.3.1. Repairing defective items, whether removed from the plant or not, shall be done in accordance with established procedures such as that for issuing equipm ent isolation work permits and work order authorizations as appropriate.

6.3.2. When plant repairs consist of more than merely replacing parts and com ponents by identical spares, a review shall be made as to w hether the repair will involve changes sufficient to require application of the plant modification control procedure described in section 7.

6.3.3. If repairs are made in situ, post-maintenance testing and procedures for returning to service shall be as described in sub-section 6.2.2 above.

6.3.4. Plant items that have been repaired in the workshop shall be inspected and tested to ensure, as far as possible, full return to serviceability. If testing cannot be completed in the workshop, cautionary labels or tags shall be applied to the plant item to warn that testing still has to be completed before re-use. When these post-repair processes are complete, items no t intended for immediate installation should be returned to stores through normal receiving channels.

7. MODIFICATIONS ARISING FROM MAINTENANCE

7.1. Types of modification

Modifications may be necessary to rectify com ponent failures discovered during maintenance, to repair com ponents following failures in operation, to reduce the frequency of faults, to improve maintainability or to incorporate a non-identical replacement plant item. Modifications may include physical changes, changing of set points, and changes to procedures.

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7.2. Review requirem ent

7.2.1. In accordance with quality assurance requirements, the operating organization shall arrange for an independent review of proposed modifications to plant items im portant to safety resulting from maintenance activities. These arrangements shall include a directive requiring the plant management to classify m odifications as m inor or major so that those judged to be major can be subm itted to an independent assessment by qualified persons. The directive shall include criteria for making this judgement. For example, all modifications shall be considered major that, if incorrectly conceived or inadequately executed, could increase the probability or severity of a radiological hazard.

7.2.2. Notwithstanding these general criteria, the operating organization should specify those plant items and systems (such as primary coolant boundary, emergency electrical supplies, reactor protection equipment) that are considered so significant to safety that no modifications to them can be judged minor.

7.2.3. The above-mentioned directive should allow for rapid review and assessment of any proposed modifications that have to be undertaken urgently; nevertheless, such emergency action shall not reduce levels o f safety. In these circumstances, retrospective formal docum entation shall be completed w ithout undue delay.

7.2.4. A suitable procedure, e.g. plant modification control procedure, issued by the plant management, should clearly allocate responsibility for co-ordinating plant modifications, implementing the on-site classification and review process, for liaison with the independent assessment process, for administering controls relating to the im plem entation and docum entation of approved modifications, and for disseminating inform ation to specified bodies.

7.3. Submission of proposals

7.3.1. Proposals for major modifications subm itted by plant management for independent assessment shall comply w ith requirements specified by the operating organization in accordance with quality assurance requirements.The am ount o f inform ation needed will depend on the extent and complexity o f the modification, but as a general guide, submissions should include the following as necessary:

(1) Design description and reason for modification(2) Safety analysis(3) Sketches, drawings and materials list(4) Specifications requirements for parts and materials(5) Applicable codes, standards and safety report section

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(6) Fabrication, installation and test methods(7) Adverse environmental or operating conditions(8) Quality assurance requirements.

7.3.2. The proposal shall include an assessment o f the effect of the modification on radiological hazard during its implementation, and during subsequent commissioning, testing, maintenance, operation and decommissioning of the modified plant. This assessment shall include the effect o f the modified plant item and its associated system on physically adjacent systems and plant items, and interconnected systems such as power supplies.

7.3.3. The proposal should dem onstrate that the modification meets the original system specification or that the new system specification is better.

7.3.4. When so required, the proposed modification shall be subm itted to the regulatory body for approval before implementation.

7.4. Implementation and docum entation

7.4.1. All reviews and assessments shall be documented, and only those modifications that have successfully gone through the appropriate processes shall be approved for im plementation. Implementation of modifications shall be subject to usual m aintenance administrative procedures together w ith any special requirements generated by reviews and assessments.

7.4.2. The above-mentioned directive shall make plant management responsible for recording approval and im plem entation o f modifications, for amending records of plant design, for updating drawings, procedures and instructions and ensuring that spare parts in stores that no longer conform are dealt with either by modification or disposal and replacement. These requirements should be implemented in accordance with steps set out in the plant modification control procedure.

8. STORES

8.1. Organization

8.1.1. The operating organization shall establish suitable organizational units to procure, receive, store and issue materials, spare plant items and components for use with systems im portant to safety. The unit receiving, storing and issuing such items on site should be responsible to the plant management. The procurem ent unit may also be responsible to plant management or located


elsewhere to serve a num ber of power plants; in the la tter case, the operating organization shall ensure that there are w ritten procedures to control the interface between the off-site procurem ent units and plant management. These procedures shall clearly define who has the authority for specifying technical and quality assurance requirements and for selecting suppliers. When that authority is vested off-site, the procedures should require consultation with, and approval by, the plant management. Whatever the organizational structure, provision should be made for plant management to identify items im portant to safety and the procurem ent unit to respond with appropriate quality assurance activities.

8.1.2. The unit for receipt, storage and issue of items im portant to safety shall have its responsibilities defined in writing by plant management. A satisfactory arrangement would be for personnel in charge of the stores to be responsibleto the head o f an on-site procurem ent unit who also should be the officer administering the interface with the off-site procurem ent unit. If plant management considers allocating this responsibility to an adm inistration group, suitable procedures will be necessary to ensure that this group responds to the requirements o f the maintenance group.

8.1.3. The m aintenance group shall be responsible for ensuring it has adequate spares, tools and resources to achieve its objectives; it shall also be responsible for establishing stock levels and authorizing issue and use of spares.

8.2. Procurement

8.2.1. The operating organization should arrange to purchase appropriate quantities of spare plant items and components for systems im portant to safety at the same time as those to be installed on the plant. These spares shall meet the same technical standards and quality assurance requirem ents as the equivalent installed plant items, but with additional requirements for ensuring adequate protection during long-term storage.

8.2.2. The quantities of initial spares to be purchased in this way should be approved by plant management after consulting with the vendor and taking account of relevant m aintenance experience available to the operating organization. Factors to be considered include the num ber and importance of major plant items that could be subject to serious failure; the special nature of any manufacturing process that would preclude subsequent m anufacture o f a plant item; the uncertainties in future supply o f parts and com ponents currently available; anticipated delivery times; the estimated duration of repairs to a plant item compared with the unavailability time o f the item perm itted by the operational limits and conditions; and the shelf life of the component.

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8.2.3. Procurem ent of plant spares, materials parts and components shall be in accordance with provisions o f the Safety Guide on Quality Assurance in the Procurem ent of Items and Services for Nuclear Power Plants, IAEA Safety Series No. 50-SG-QA3. Deviations from the original specification, however minor, should not be perm itted until the change has been referred to plant management for consideration under the procedure established for plant modifications described in section 7.

8.2.4. It should be the responsibility of the purchasing unit to ensure that materials and items are obtained only from suppliers who are approved in accordance with the requirem ents of the Safety Guide 50-SG-QA3.

8.2.5. Routine re-ordering o f material and plant items already held in store should be initiated automatically according to w ritten procedures, when a predetermined lower stock limit is reached. This limit should be based on the expected or known rate o f use and the anticipated delivery time or shelf life.The purchasing unit shall ensure, by means of documented reviews at the time of re-ordering, that the technical and quality assurance requirements havebeen updated as appropriate and incorporated in routinely generated procurem ent documents.

8.2.6. Procurem ent of m aintenance items not held in store should be initiated by the m aintenance group. This group should be responsible for ensuring, in accordance with an established procedure, that the technical and quality assurance requirements are correctly established and specified to the purchasing unit. It should be the responsibility of the purchasing unit to ensure that these technical and quality assurance requirements are then incorporated into the procurem ent docum ents w ithout change.

8.3. Receipt

8.3.1. The operating organization shall provide adequate facilities for receiving on site all materials, spare parts and components for items im portant to safety.The facilities for receipt should include equipment for safe, convenient handling and sufficient space with appropriate environmental conditions for proper receipt inspection. A separate and secure quarantine area should be provided for tem porary retention of stores no t cleared for final storage or issue.

8.3.2. Plant management shall allocate in writing the responsibility for receiving all stores on site and should issue a special procedure to control the receipt and acceptance process. This procedure should include visual external inspection for transit damage or deterioration and verification of correct packaging and

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identification. Items found incomplete, incorrect or having inadequate docum entation should not be accepted for final storage. The procedure shall also include a requirem ent to label or tag such items until non-conformance is resolved. More detailed guidance on receipt inspections is given in sections 7 and 9 o f the Safety Guide on Quality Assurance for the Procurem ent o f Items and Services for Nuclear Power Plants, IAEA Safety Series No. 50-SG-QA3.

8.3.3. The receipt procedure should also require that items are either accepted and therefore issued or placed in an area allocated to conforming stock, or rejected and therefore sent for tem porary storage as non-conforming items. Satisfactory completion of the receipt procedure shall also require tha t appropriate records be kept in each case.

8.4. Storage

8.4.1. The operating organization shall ensure that storage facilities offer adequate space and provide for secure retention of stores in environmental conditions designed to prevent lowering o f quality through external effects or deterioration. Access and installed handling equipment shall be adequate for the type and size o f items to be stored.

8.4.2. Plant management shall make administrative arrangements to ensure that the storage facility is operated in a m anner that preserves the correct environmental conditions, guards against fire hazard and prevents unauthorized access to stored items. The stored items should be arranged so that regular examination of all stored items may be conveniently accomplished, where necessary, with suitable handling equipment.

8.4.3. The administrative arrangements should include w ritten procedures allocating responsibility for regularly examining stored items and auditing store adm inistration to detect deterioration and unauthorized or unrecorded use of stored items. Particular attention should be paid to the retention of original identification of items during storage.

8.4.4. In the procedure relating to modifications, plant management should include steps to initiate, control and record the modification of spare plant items following m odification to equivalent items installed in the plant.

8.4.5. If the packaging of items incorporates protection against deterioration in storage and it is found necessary to invalidate that protection, for example to modify or inspect the item, then the protective function shall be restored or deterioration prevented by some other equivalent means.

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8.5. Issue requirements

8.5.1. Storage facilities shall provide for convenient and orderly issue of stores. These normally take the form of a counter or barrier through which the issue of stores can take place w ithout contravening arrangements for security and correct environmental conditions.

8.5.2. Stored items shall only be issued by authorized persons in response to w ritten orders presented by persons having authority to receive the stored items. Appropriate records should be generated to docum ent the ultim ate disposition of issued items to facilitate tracing them. The issuing procedures shall require that excess or unused items be returned to stores in accordance with normal receipt practice.

8.5.3. Unless organizational arrangements allow continuous access to the store, e.g. full shift staffing, the procedures should perm it emergency issue of urgently required stored items on the authority of and under the control of the shift supervisor, in a m anner compatible with the normal issuing process.

9. RECORDS

9.1. Generation and collection of records

9.1.1. Appropriate arrangements shall be made for orderly collection of records and production of reports on m aintenance activities. Records and reports are required to provide objective evidence that the m aintenance programme is being implemented fully in accordance with the quality assurance programme. In addition, m aintenance records such as equipm ent history cards and the results of m aintenance work are a necessary input to a continuing review o f m aintenance effectiveness, which should be the responsibility o f the maintenance group. A nother im portant use of m aintenance records is generation of data for reliability studies.

9.1.2. Both purposes can be served by suitable arrangements to generate and collect the same records, but the controlled copy used for quality assurance purposes shall be processed in accordance with the recommendations o f the Safety Guide on Quality Assurance Records System for Nuclear Power Plants, IAEA Safety Series No. 50-SG-QA2.

25


9.1.3. The m aintenance instructions should be designed to facilitate the convenient generation of records. In general, records shall identify the m aintenance and operational personnel concerned and include certification by supervisors or inspectors as appropriate.

9.1.4. A classification system that identifies the plant item and system facilitates feedback o f data to the appropriate bodies and provides data on com ponent reliability.

9.2. R etention of records

9.2.1. The m aintenance organization should be required by an administrative procedure to select records that give a meaningful plant history and to retain them for the life of the plant. O ther records that have only a transitory value should be retained either until they cease to serve the purpose for which they were originally intended or are replaced by later records. An im portant factor in selecting records to be retained is their use in assembling reliability data.

9.2.2. The retention of records required for quality assurance purposes shall be in accordance with the Safety Guide on Quality Assurance Records System for Nuclear Power Plants, IAEA Safety Series No. 50-SG-QA2.

9.2.3. The record should consist of originals, hard copies, microfilms or com puter storage. In all cases, ease of retrievability commensurate with the likely need for consultation and review, and the need to guard against accidental loss shall be taken into account when establishing storage facilities.

10. SURVEILLANCE, REVIEW AND AUDIT PROGRAMME

10.1. The need for a programme

The operating organization shall establish a programme of surveillance, review and audit of m aintenance in order to ensure that the m aintenance programme has been implemented in accordance with the design intent, with regulatory codes and requirements, and with the operating organization’s own procedures and policies. Reference should be made to the Safety Guide on Quality Assurance during Operation of Nuclear Power Plants, IAEA Safety Series No. 50-SG-QA5.

26


10.2. Surveillance procedures

Verification inspection o f maintenance activities shall be carried out by appropriately qualified individuals who do not have direct responsibility for performing the work. The inspector may be a member of the same organizational unit, and a supervisor may serve as the inspector if he did not personally participate in the work. Inspections may be unannounced and should include direct observation of the specific maintenance activity as well as examination of docum entation. Results and findings o f these inspections shall be transm itted to the appropriate m aintenance supervisors for inform ation, and for corrective action if required.

10.3. Maintenance review

10.3.1. The operating organization shall establish a programme for reviewing the maintenance activities. Responsibility for this review programme shall be assigned by the operating organization.

10.3.2. It is suggested that impartiality of the maintenance review be achieved by bringing in various departm ent heads from plant management. Additional expertise may be obtained from off-site personnel.

10.3.3. The review programme should examine the maintenance programme for features such as:

(1) Adequacy of the preventive maintenance schedule and its im plementation

(2) Response to remedial maintenance requirements(3) Satisfactory control of radiation doses(4) Effective use of resources(5) Level of training and experience(6) Adherence to quality assurance requirements(7) Adequacy of procedures and instructions.

10.3.4. The findings of the review programme should be reported periodically to the maintenance group, plant management and selected members of the operating organization.

10.4. Audit programmes

10.4.1. The operating organization shall establish an audit programme for the maintenance activity. These audits shall be performed by qualified personnel who have no direct responsibility for maintenance. The audits will determine

27


w hether or not the m aintenance activity is being conducted in compliance with regulatory requirements and the operating organization’s quality assurance programme.

10.4.2. Audits shall be performed at specified intervals by qualified audit teams and shall cover all areas of the maintenance activity that could affect items im portant to safety. Audit details shall be in accordance with the recommendations contained in the Safety Guide on Quality Assurance Auditing for Nuclear Power Plants, IAEA Safety Series No. 50-SG-QA10. The audit reports should be sent to plant management and selected members o f the operating organization for action or information, as appropriate.

Personnel in the maintenance group should occasionally be assigned to audit teams auditing other areas of plant activity. This experience will enhance the individuals’ understanding of quality assurance requirements in their own activities.

28


A nnex I

ADM INISTRATIVE ASPECTS

OF MAINTENANCE WORK

AI-1. General

AI-1.1. This annex is intended to provide inform ation useful for developing authorizations, permits and certificates needed in administrative control to ensure safety in the work area and to prevent maintenance activities from affecting other aspects of safety. It deals specifically with the items listed in sub-section 4.2.2 of this Guide, namely:

Item (4) Work order authorizationsItem (5) Equipm ent isolation work permitsItem (6) Radiation work permits

and it also addresses those aspects of item (7), fire hazard control, and item (8), plant modification control, which are inseparable from the above items.

AI-1.2. These authorizations, permits and certificates generally:

(a) Define the plant item, the type of work to be performed, and the boundaries of the working area in which the activities of plant personnel are authorized.

(b) Confirm that the plant item is either in a safe condition to work on, or conforms to conditions set out in the prerequisites of written procedures appropriate to the authorized work. These conditions should specify any precautions that need to be taken.

(c) Confirm radiological conditions in the work area, note any other possible hazards, and specify any precautions to be taken in order that the authorized work may be carried out.

(d) Confirm that all personnel have been withdrawn from the working area after the authorized work is completed, and the plant item can either be returned to service or remain in a known condition.

(e) Include self-cancellation features by indicating the conditions of validity, e.g. time limits.

AI-1.3. This annex does not relate to controls required to avoid incorrect m aintenance of the plant item. These are covered in section 4.3 (maintenance instructions and procedures) which should be considered together w ith associated quality assurance requirem ents covered in the Safety Guide on Quality Assurance during Operation of Nuclear Power Plants, IAEA Safety Series No. 50-SG-QA5.

29


AI-2. Work order authorization

AI-2.1. Items to be considered in the preparation of work order authorizations are as follows:

(1) Procedures to obtain authorization for undertaking maintenance, repair, replacement or modifications.

(2) Means to ensure work is not undertaken to modify the plant unless the m odification has been authorized according to the approved procedures (see section 7).

(3) Unambiguous identification of plant items on which work is authorized. This requires a clear, unambiguous labelling system, particularly for multiple unit plants.

(4) Description of the work to be undertaken. This may be by reference to the appropriate procedure which describes the scope of work, prerequisites, precautions, post-maintenance testing requirem ents etc., as detailed in sub-section 4.3.6 of this Guide, or by reference to the docum ent describing the approved plant modification.

(5) Procedures to ensure that both the boundaries of the work area and access through them are specified and clearly marked. This includes locking, barring, taping or roping off unauthorized access routes such as doors, windows or manholes, and confirm ation that the specified action has been taken.

(6) Necessity for the person authorizing work to know all other relevant work which is being undertaken on the plant, so that account can be taken of any interface between the work described in the authorizations and the work covered by other authorizations.

(7) Cancellation of authorization:(i) by a person authorized to do so, or

(ii) after expiry of a stated time, or(iii) under other stated conditions (e.g. non-validity o f relevant

radiation work permits, or shift change-over).

AI-3. Equipm ent isolation work permit/

AI-3.1. The following list contains items to be considered in the preparation of equipm ent isolation work permits to ensure a particular plant item is safeto work on or it is otherwise in accordance with the specified prerequisites forthe work to be undertaken. Some of these details may need to be considered in the preparation of work order authorizations, even if isolation of a plant item is not necessary:

(1) Specification of the plant item and the required conditions (earthed, isolated, vented, jum pered etc.) under which authorized work is to be performed.

30


(2) Control of activities tha t may either change radiological conditionsin the work place while work is in progress, or change conditions related to other hazards (e.g. release of steam or gases, pressure build-up).

(3) Establishment of key interlock procedures.(4) Identification o f the state o f plant items by the use of stamps, tags,

labels, routing cards etc.(5) Confirmation of specified actions taken.(6) A uthorization by shift supervisor for any plant item to be taken out

o f service or restored to service, docum entation of the change-over of responsibility from one shift to the next.

(7) Assurance that removal of one or more plant items from servicefor m aintenance conforms with the requirements of plant operational limits and conditions (see the Safety Guide on Operational Limits and Conditions for Nuclear Power Plants, IAEA Safety Series No. 50-SG-03).

(8) Cancellation of perm it by an authorized person:(i) after expiry of a stated time, or

(ii) under other stated conditions, or(iii) by cancellation of work authorization.

AI-4. Radiation work perm it

AI-4.1. The following list contains items to be considered in the preparation o f radiation work permits, (a) to establish the radiological conditions under which authorized work might be undertaken, and (b) to specify the precautions to be taken:

(1) Clearance for a radiological survey to be carried out by a qualified health physicist so that radiation and contam ination levels can be checked and certified before a work permit is issued. This clearance would specify the extent o f the survey to be undertaken, any special conditions and any hazards other than radiological hazards to which the person performing the survey may be exposed.

(2) Identification o f the radiation hazards and the precautions to be taken. This may be done by classifying radiation and contam ination zones (see the Safety Guide on Radiological Protection during Operation o f Nuclear Power Plants, IAEA Safety Series No. 50-SG -05), marking the radiation and contam ination levels in the area where the work is to be undertaken, identifying the boundaries of these zones, confirming that a radiological survey has been carried out, and specifying the access to the area for normal and emergency use. In addition, o ther appropriate precautions, such as provision of equipm ent isolation, may need to be taken.

31


(3) Individual and collective dose limits for the work authorized.(4) Precautions (specified when appropriate by a certified health

physicist) that may need to be taken before, during, or on work completion in a radiation or contam ination zone. These include:

(i) Monitoring requirements and the frequency o f radiological surveys to be performed during the work.

(ii) Types of personal dose meters to be worn, and where they should be worn.

(iii) Shielding, ventilation, decontamination, and waste handling requirements.

(iv) Protective clothing and respiratory equipment.(v) Special precautions, such as specifying a reference level in terms

of a QFE (quartz fibre electrom eter) reading, which shall not be exceeded.

(vi) Hold points to evaluate progress of work in order to establish w hether conditions are acceptable for work to continue to the next phase o f the work programme.

(vii) A utom atic invalidation of permits after a specified time interval.(5) Monitoring o f individual and collective doses and comparison with

relevant limits a t the time of hold points and on work completion.(6) Cancellation o f permit

(i) by a person authorized to do so, or(ii) after expiry o f stated time, or

(iii) if a given reference level is exceeded, or(iv) under other stated conditions (e.g. shift change-over), or(v) by cancellation of work authorization.

AI-5. Covering conventional hazards in work permits

A I-5.1. Safety standards for nuclear plants require careful attention to conventional hazards tha t can exist in work places. For this purpose a designated person should authorize the work taking into account the conditions and precautions against conventional hazards (see the Safety Guide on Fire Protection in Nuclear Power Plants, IAEA Safety Series No. 50-SG-D2). Examples include:

(i) Monitoring the presence o f combustible, toxic and asphyxiating gases and specifying action levels.

(ii) Protection against spark- or flame-producing activities such as welding.(iii) Protection if internal combustion engines, electrical machines, or

combustible materials are to be used.(iv) Ensuring visibility.(v) Protection against hazardous fluids.

(vi) Operating or tripping the ventilation system.

32


(vii) Adjustment of automatic fire extinguishing systems where these may create a hazard in the work place or its access routes.

AI-6. Certification of work completion

AI-6.1. In developing certificates of work completion, the following considerations should be taken into account:

(1) Confirmation from the maintenance engineer that the authorized work has been satisfactorily completed. Provision should be made for this confirmation to be given for deviations from the originally authorized work provided these are in accordance with written procedures that cover approval for such deviations.

(2) Either acceptance by the shift supervisor of the plant item for operation (or as standby in readiness for operation), or acknowledgement of the condition in which it is to be left.

(3) Acceptance of conditions in the work area after it has been vacated.(4) Confirmation that all relevant authorizations and permits have been

cancelled and all copies are so marked.(5) Clear definition of responsibilities for post-maintenance testing. This

includes responsibility for live testing, since tfiis is an interface activity between operations and maintenance personnel. This could, for example, include confirmation by the maintenance engineer that the item is safe for testing under specified conditions.

AI-7. Format and documentation control

AI-7.1. The following list contains items to be considered in the design and layout of authorizations, permits and certificates:

(1) Unambiguous allocation of responsibilities, by the inclusion of features providing, inter alia, a clear indication that the persons issuing, receiving or cancelling a permit (or authorization) are authorized to do so.

(2) Provision of space at appropriate locations for signatures.(3) An unambiguous means of showing the conditions to be observed,

the precautions to be taken and the completion of these actions.This can be achieved using signed check lists.

(4) Routing of copies to be such that the shift supervisor on shift isaware of all relevant work on the plant.

(5) Authenticity of forms and means of documentation control (thename of the operating organization, the nuclear power plant unit, a unique form reference, colours and copy number).

33


I

<

/


DEFINITIONS

The following definitions are intended fo r use in the NU SS programme and may no t necessarily conform to definitions adopted elsewhere fo r international use. They have been selected from those included in the approved Codes o f Practice published under the NUSS programme.

Audit

A docum ented 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.

Commencement of Operation

The beginning of initial fuel loading.

Commissioning1

The process during which plant com ponents and systems, having been constructed, are made operational and verified to be in accordance w ith design assumptions and to have m et the performance criteria; it includes both nonnuclear and nuclear tests.

C onstruction1

The process of m anufacturing and assembling the com ponents of a Nuclear Power Plant, the erection o f civil works and structures, the installation of com ponents and equipm ent, and the performance of associated tests.

Decommissioning1

The process by which a Nuclear Power Plant is finally taken out o f Operation.

1 The term s Siting, C onstruction, Commissioning, O peration and Decommissioning are used to delineate the five m ajor stages o f the licensing process. Several o f the stages may coexist; for exam ple, C onstruction and Commissioning, or Commissioning and O peration.

35


Items Important to Safety

The items which comprise:

(1) those structures, systems, and components whose malfunction or failure could lead to undue radiation exposure of the Site Personnel or members of the public;2

(2) those structures, systems and components which prevent Anticipated Operational Occurrences from leading to Accident Conditions;

(3) those features which are provided to mitigate the consequences of malfunction or failure of structures, systems or components.

Nuclear Power Plant

A thermal neutron reactor or reactors together with all structures, systems and components necessary for Safety and for the production of power, i.e. heat or electricity.

Operating Organization

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

Operation (see Footnote 1)

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

Plant Management

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

Qualified Person

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

2 This includes successive barriers set up against the release o f radioactivity from nuclear facilities.

36


Quality Assurance

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

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, Construction, Commissioning, Operation and Decommissioning or specific aspects thereof.3

Safety

Protection of all persons from undue radiological hazard.

Safety Report

A docum ent provided by the Applicant or Licensee to the Regulatory Body containing inform ation concerning the Nuclear Power Plant, its design, accident analysis and provisions to minimize the risk to the public and to the Site Personnel.

Siting (see Footnote 1)

The process o f selecting a suitable Site for a Nuclear Power Plant, including appropriate assessment and definition of the related design bases.

3 This national au thority could be either the government itself, o r one or m ore departm ents o f the governm ent, o r a body or bodies specially vested w ith appropriate legal authority .


<

i


LIST OF PARTICIPANTS

WORKING GROUP

Date of meeting: 3 to 14 July 1978

Consultants

Rangarajan, V. India

Sm ith, P.G. United Kingdom

Moore, R.H. United States o f America

IAEA s ta ff m em ber

Wright, H.A. Scientific Secretary (O peration)

TECHNICAL REVIEW COMMITTEE (TRC) - OPERATION

Dates o f meetings: 27 November to 1 December 1978, 24 to 28 September 1979, 1 to 5 December 1980

Members and alternates participating in the meetings

Bertini, A. (Chairman)Novak, S.

B urtheret, J.Capel, R.

Chudziensky, E.H ofm ann, W.

Sundaram, S.M.Rao, M.R.Santanagopalan, S.

Sasaki, S.Higashi, A.

Kuffer, K.

Simons, H.K.

Milhoan, J.L.

Participants from the Working Group

Rangarajan, V.

Sm ith, P.G.

Moore, R.H.

IA E A s ta ff m em ber

Wright, H.A.

Italy

Czechoslovak Socialist Republic

Fiance

Germ any, Federal R epublic of

India

Japan

Switzerland

U nited Kingdom

U nited States o f America

IndiaU nited Kingdom

U nited States o f America

Scientific Secretary (O peration)

39


SENIOR ADVISORY GROUP (SAG)

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

Members and alternates participating in the meetings

Hurst, D. (Chairman) Canada

Argentina

Czechoslovak Socialist Republic

France

Germ any, Federal R epublic of

India

Japan

Mexico

Sweden

Switzerland

Union of Soviet Socialist Republics

United Kingdom

United States o f America

Participants from international organizations

Commission of the E uropean Com m unities

International Organization for Standardization

World Health Organization

Participant from TRC — Operation

Bertini, A. Chairman of TRC — O peration

IAEA s ta ff members

Konstantinov, L.V. Scientific C o-ordinator (NUSS)

Wright, H.A. Scientific Secretary (O peration)

Iansiti, E. Scientific Secretary (SAG)

Vinck, W.Pele, J.-P.

Nilson, R. Becker, K.

Kom arov, E.I.

Beninson, D. Paganini, C.

Beranek, J.

Messiah, A. Clem ent, B.

Franzen, L.F.Dastidar, P.R. Soman, S.D.Suguri, S. Ishizuka, M.Bello, R. Sanchez, J.

Jansson, E. Hedgran, A.Zuber, J.F .

Isaev, A.Kovalevich, O.M.

Gausden, R.A.

Minogue, R.B. Sm ith, R.

40


LIST OF NUSS PROGRAMME TITLES

For the Safety Guides no plans exist to fill the gaps in the sequence o f numbers.

Safety Series No.

Title Publication date of English version

Code o f Practice

50-C-G

Safety Guides

50-SG-G1

1. Governmental organization

Governmental organization for the Published 1978 regulation o f nuclear power plants

Qualifications and training o f staff Published 1979 of the regulatory body for nuclear power plants

50-SG-G2 Information to be submitted in Published 1979support of licensing applications for nuclear power plants

50-SG-G3 Conduct of regulatory review and Published 1980assessment during the licensing process for nuclear power plants

50-SG-G4 Inspection and enforcement by the Published 1980regulatory body for nuclear power plants

50-SG-G6 Preparedness o f public authorities for Published 1982emergencies at nuclear power plants

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

50-SG-G9 Regulations and guides fornuclear power plants

41


Safety Series TitleNo.

Publication dateof English version

Code o f Practice

50-C-S

Safety Guides

50-SG-S1

50-SG-S2

50-SG-S3

50-SG-S4

50-SG-S5

50-SG-S6

50-SG-S7

50-SG-S8

50-SG-S9

50-SG-S10A

50-SG-S10B

42

2. Siting

Safety in nuclear power plant siting Published 1978

Published 1979

Published 1979

Published 1980

Published 1980

Published 1981

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

Nuclear power plant siting: hydrogeological aspects

Safety aspects of the foundations of 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

Earthquakes and associated topics in relation to nuclear power plant siting

Seismic analysis and testing of nuclear power plants

Atmospheric dispersion in nuclear power plant siting

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

External man-induced events in relation to nuclear power plant




50-SG-S11A

50-SG-S11B

50-SG-S12

Code o f Practice

50-C-D

Safety Guides

50-SG-D1

50-SG-D2

50-SG-D3

50-SG-D4

50-SG-D 5

50-SG-D6

Extreme meteorological events in Published 1981nuclear power plant siting, excluding tropical cyclones

Design basis tropical cyclone for nuclear power plants

Radiological protection aspects of nuclear power plant siting

3. Design

Design for safety of nuclear power Published 1978 plants

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 Published 1982relation to nuclear power plant design

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

Published 1979

Published 1979

Published 1980

Published 1980

43




Safety Guides (cont.)

50-SG-D7 Emergency power systems atnuclear power plants

50-SG-D8 Safety-related instrum entationand control systems for nuclear power plants

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

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

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

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

5Q-SG-D13 Reactor cooling systems innuclear power plants

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

Published 1982

4. Operation

Code o f Practice

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

Published 1978

Safety Guides

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

44




50-SG-02

50-SG-03

50-SG-04

I50-SG-05

50-SG-06

50-SG-07

50-SG-08

50-SG-09

50-SG-010

1 50-SG -011

Code o f Practice

50-C-QA

In-service inspection for nuclear power plants

Operational limits and conditions for nuclear power plants

Commissioning procedures for nuclear power plants

Radiological protection during operation o f nuclear power plants

Preparedness o f the operating organization (licensee) for emergencies at nuclear power plants

Maintenance o f nuclear power plants ■ Published 1982

Surveillance of items im portant to safety in nuclear power plants

Management of nuclear power plants for safe operation

Core management, fuel handling and associated services for nuclear power plants

Operational management of radioactive effluents and wastes arising in nuclear power plants

S. Quality assurance

Quality assurance for safety Published 1978in nuclear power plants

Published 1980

Published 1979

Published 1980

Published 1982

45



Publication dateo f English version

Safety Guides

50-SG-QA1

50-SG-QA2

50-SG-QA3

50-SG-QA4

50-SG-QA5

50-SG-QA6

50-SG-QA7

50-SG-QA8

50-SG-QA10

50-SG-QA11

Establishing of the quality assurance programme for a nuclear power plant project

Quality assurance records system

Quality assurance in the procurement of items and services for nuclear power plants

Quality assurance during site construction of nuclear power plants

Quality assurance during operation of nuclear power plants

Quality assurance in the design of nuclear power plants

Quality assurance organization for nuclear power plants

Quality assurance in the 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

Published 1979

Published 1979

Published 1981

Published 1981

Published 1981

Published 1981

Published 1980

46


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no.50-SG-07gnssn.iaea.org/Superseded Safety Standards/Safety... · FOREWORD by the Director General The demand for energy is continually growing, both in the developed and the developing