IAEA SAFETY GUIDES

no50-SG-QA5 (Rev.1)IAEA SAFETY GUIDES

Quality Assurance During Commissioning and Operation of Nuclear Power Plants

A Safety Guide

This publication is no longer valid Please see http://www-ns.iaea.org/standards/

CATEGORIES OF IAEA SAFETY SERIES

From 1978 onwards the various publications in the Safety Series are divided intofour 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 of 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 of 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.


QUALITY ASSURANCE DURING COMMISSIONING

AND OPERATION OF NUCLEAR POWER PLANTS

A Safety Guide


The following States are Members o f the In ternational A tom ic Energy Agency:

AFGHANISTANALBANIAALGERIAARGENTINAAUSTRALIAAUSTRIABANGLADESHBELGIUMBOLIVIABRAZILBULGARIABURMABYELORUSSIAN SOVIET

SOCIALIST REPUBLIC CAMEROON CANADA CHILE CHINA COLOMBIA COSTA RICA COTE D’IVOIRE CUBA CYPRUSCZECHOSLOVAKIA DEMOCRATIC KAMPUCHEA DEMOCRATIC PEOPLE’S

REPUB LIC OF KOREA DENMARKDOMINICAN REPUBLICECUADOREGYPTEL SALVADORETHIOPIAFINLANDFRANCEGABONGERMAN DEMOCRATIC REPUBLIC GERMANY, FEDERAL REPUBLIC OF GHANA GREECE

GUATEMALAHAITIHOLY SEEHUNGARYICELANDINDIAINDONESIAIRAN, ISLAMIC REPUBLIC OFIRAQIRELANDISRAELITALYJAMAICAJAPANJORDANKENYAKOREA, REPUBLIC OF KUWAIT LEBANON LIBERIALIBYAN ARAB JAMAHIRIYALIECHTENSTEINLUXEMBOURGMADAGASCARMALAYSIAMALIMAURITIUSMEXICOMONACOMONGOLIAMOROCCONAMIBIANETHERLANDSNEW ZEALANDNICARAGUANIGERNIGERIANORWAYPAKISTANPANAMA

PARAGUAYPERUPHILIPPINESPOLANDPORTUGALQATARROMANIASAUDI ARABIASENEGALSIERRA LEONESINGAPORESOUTH AFRICASPAINSRI LANKASUDANSWEDENSWITZERLANDSYRIAN ARAB REPUBLICTHAILANDTUNISIATURKEYUGANDAUKRAINIAN SOVIET SOCIALIST

REPUBLIC UNION OF SOVIET SOCIALIST

REPUBLICS UNITED ARAB EMIRATES UNITED KINGDOM OF GREAT

BRITAIN AND NORTHERN IRELAND

UNITED REPUBLIC OF TANZANIA

UNITED STATES OF AMERICA URUGUAY VENEZUELA VIET NAM YUGOSLAVIA ZAIRE ZAMBIA

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

© IAEA, 1986

Permission to reproduce or translate the information contained in this publication may be obtained by writing to the International Atomic Energy Agency, Wagramerstrasse 5, P.O. Box 100, A-1400 Vienna, Austria.

Printed by the IAEA in Austria September 1986


SAFETY SERIES No.50-SG-QA5(Rev.l)

QUALITY ASSURANCE DURING COMMISSIONING

AND OPERATION OF NUCLEAR POWER PLANTS

A Safety Guide

INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA, 1986


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

QUALITY ASSURANCE DURING COMMISSIONING AND OPERATION OF NUCLEAR POWER PLANTS

A SAFETY GUIDE IAEA, VIENNA, 1986

STI/PUB/735 ISBN 92-0-123786-3


FOREWORD by the Director General

The demand for energy is continually growing, both in the developed and the developing countries. Traditional sources of 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 important role in the development of energy programmes throughout the world.

Since its inception the nuclear energy industry has maintained a safety record second to none. Recognizing the importance of this aspect of nuclear power and wishing to ensure the continuation of this record, the International Atomic Energy Agency established a wide-ranging programme to provide the Member States with guidance on the many aspects of safety associated with thermal neutron nuclear power reactors. The programme, at present involving the preparation and publication of about 50 books in the form of Codes of 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 of 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 of 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 of Practice and Safety Guides are recommendations issued by the Agency for use by Member States in the context of 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 of the Codes of 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 written in such a form as would enable a Member State, should it so decide, to make the contents of such documents 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 requirement and a desirable option.

The task of ensuring an adequate and safe supply of energy for coming generations, and thereby contributing to their well-being and standard of life, is a matter 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 of use in this task.

STATEMENT by the Senior Advisory Group

The Agency’s plans for establishing Codes of Practice and Safety Guides for nuclear power plants have been set out in IAEA document GC(XVIII)/526/Mod.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 of power. The present publication is brought out within this framework.

A Senior Advisory Group (SAG), set up by the Director General in September 1974 to implement the programme, selected five topics to be covered by Codes of Practice and drew up a provisional list of subjects for Safety Guides supporting the five Codes. The SAG was entrusted with the task of 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 of experts from Member States, was created for each of the topics covered by the Codes of Practice.


In accordance with the procedure outlined in the above-mentioned IAEA document, the Codes of Practice and Safety Guides, which are based on documentation and experience from various national systems and practices, are first drafted by expert working groups consisting of 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 of both published and unpublished material, such as answers to questionnaires, submitted 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 transmitted to the Director General, who submits them, as and when appropriate, to the Board of Governors for approval before final publication.

The five Codes of Practice cover the following topics:

Governmental organization for the regulation of 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 that 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 methods of implementing specific parts of the relevant Codes of Practice. Methods and solutions varying from those set out in these Guides may be acceptable, if they provide at least comparable assurance that nuclear power plants can be operated without undue risk to the health and safety of the general public and site personnel. Although these Codes of Practice and Safety Guides establish an essential basis for safety, they may not be sufficient or entirely applicable. 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 of fissile and radioactive materials and of a nuclear power plant as a whole is mentioned where appropriate but is not treated in detail. Non-radiological aspects of industrial safety and environmental protection are not explicitly considered.


When an appendix is included it is considered to be an integral part of the document and to have the same status as that assigned to the main text of the document.

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

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

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

The following publications o f the NUSS programme are referred to in the text o f the present Safety Guide:

NOTE

Safety Series No. 50-C-0 Safety Series No. 50-SG-QA1 Safety Series No. 50-SG-QA2 Safety Series No. 50-SG-QA3 Safety Series No. 50-SG-QA4 Safety Series No. 50-SG-QA6 Safety Series No. 50-SG-QA 7 Safety Series No. 50-SG-QA 10

Safety Series No. 50-SG-01 Safety Series No. 50-SG-02 Safety Series No. 50-SG-04 Safety Series No. 50-SG-06 Safety Series No. 50-SG-07 Safety Series No. 50-C-QA

The titles are given in the List o f NUSS Programme Titles printed at the end o f this Guide, together with information about their publication date. Instructions on how to order them will be found on the last page o f this Guide.


CONTENTS

1. INTRODUCTION.............................................................................................. 11.1. General........................................................................................................ 11.2. Scope.......................................................................................................... 11.3. Responsibility........................................................................................... 2

2. QUALITY ASSURANCE PROGRAMME DURINGCOMMISSIONING............................................................................................ 22.1. Quality assurance programme establishment and documentation.... 2

2.1.1. Commissioning........................................................................... 22.1.2. Organization................................................................................ 32.1.3. Quality assurance programme documentation....................... 4

2.2. Quality assurance programme implementation................................... 42.2.1. General......................................................................................... 42.2.2. Document control...................................................................... 52.2.3. Design control............................................................................. 52.2.4. Commissioning procedures, instructions and drawings........ 62.2.5. Equipment control..................................................................... 62.2.6. Calibration and control of measuring and test equipment... 82.2.7. Housekeeping and cleanliness contro l................................... 82.2.8. Verification by inspection and surveillance, and by

review of commissioning results.............................................. 92.2.9. Non-conformance control........................................................ 112.2.10. Corrective action........................................................................ 112.2.11. Records........................................................................................ 112.2.12. Audits.......................................................................................... 11

3. QUALITY ASSURANCE PROGRAMME DURING OPERATION........... 123.1. Quality assurance programme establishment and documentation.. 12

3.1.1. Operation.................................................................................... 123.1.2. Quality assurance programme................................................. 123.1.3. Quality assurance programme documentation...................... 123.1.4. A dherence.................................................................................. 17

3.2. Organization............................................................................................ 173.2.1. Operating organization.............................................................. 173.2.2. Quality assurance organization................................................ 183.2.3. Training and qualification of personnel................................. 19


3.3. Document control.................................................................................. 193.4. Operation control................................................................................... 203.5. Emergency control................................................................................. 213.6. Procurement contro l.............................................................................. 213.7. Material and equipment contro l.......................................................... 22

3.7.1. Identification and control of material and equipment......... 223.7.2. Material handling and storage.................................................. 223.7.3. Operating status of equipm ent................................................ 223.7.4. Equipment maintenance........................................................... 233.7.5. Equipment modification.......................................................... 243.7.6. Housekeeping and cleanliness control.................................... 24

3.8. Inspection, surveillance and testing..................................................... 243.8.1. General........................................................................................ 243.8.2. Scheduling.................................................................................. 253.8.3. Inspection and surveillance...................................................... 253.8.4. Surveillance of activities........................................................... 263.8.5. Testing......................................................................................... 263.8.6. Inspection and test procedures and reports.......................... 273.8.7. Calibration and control of measuring and test equipm ent.. 27

3.9. Non-conformance control..................................................................... 283.10. Corrective action.................................................................................... 283.11. Assessments, reviews and audits.......................................................... 29

3.11.1. Assessments............................................................................... 293.11.2. Reviews by plant management............................................... 293.11.3. Independent review.................................................................. 293.11.4. Audits......................................................................................... 30

3.12. Records..................................................................................................... 31

4. QUALITY ASSURANCE PROGRAMME DURINGDECOMMISSIONING...................................................................................... 314.1. General....................................................................................................... 314.2. Scope.......................................................................................................... 32

DEFINITIONS............................................................................................................. 33

LIST OF PARTICIPANTS........................................................................................ 37

LIST OF NUSS PROGRAMME TITLES................................................................ 39


1. INTRODUCTION

1.1. General

The IAEA Code of Practice on Quality Assurance for Safety in Nuclear Power Plants and the IAEA Code of Practice on Safety in Nuclear Power Plant Operation Including Commissioning and Decommissioning (IAEA Safety Series Nos 50-C-QA and 50-C-0), hereinafter respectively referred to as the Quality Assurance Code and the Operation Code, contain requirements for quality assurance and administrative control during the commissioning, operation and decommissioning of a nuclear power plant. This Safety Guide supplements those requirements, provides recommendations and describes practices to implement the appropriate requirements of the two Codes.

This Revision of the Safety Guide 50-QA-5 replaces the version published in 1981 and provides more detailed guidance on quality assurance requirements during the commissioning and operation of thermal nuclear power plants.

In addition, the information specific to commissioning is presented in a separate section (Section 2) as far as practicable for ease of reference by the personnel performing commissioning activities. It should be recognized, however, that the commissioning and operation stages coexist and that many of the quality assurance provisions for operation which are set out in Section 3 are applicable during commissioning and shall be followed where appropriate.

The broad term ‘quality assurance’, as it applies to the operation of nuclear power plants, includes all those planned and systematic actions necessary to assure plant operation in accordance with specified requirements. These actions are carried out both by the personnel who perform the work, and by individuals or groups who are assigned the task of verifying the completeness and adequacy of the work. Administrative activities intended to assure quality are formalized parts of the administrative controls pertinent to good management practice.

Management systems, associated procedures, and an organizational structure shall be established, and any necessary approvals shall be obtained, before the start of activities. Provisions shall be made for an orderly transition of control from the design and construction to the commissioning and operation. The detailed programme for decommissioning shall be established prior to transition from operation of the plant to decommissioning.

1.2. Scope

This Guide provides requirements and recommendations for the establishment and implementation of a quality assurance programme for activities important to safety during the commissioning, operation and decommissioning phases of a nuclear power plant. It applies to activities such as: the commissioning, inspecting,

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testing, operating, refuelling, maintaining, repairing, modifying and eventually shutting down and decommissioning of nuclear power plants. It applies also to associated activities related to safety, such as radiation protection, environmental monitoring, handling of radioactive wastes, responses to emergencies and physical security.

1.3. Responsibility

The organization having overall responsibility for the nuclear power plant shall be responsible for the establishment and implementation of the quality assurance programme during plant commissioning, operation and decommissioning. This organization may delegate to other organizations all or part of the work associated with the programme, but shall retain the responsibility for the effectiveness of the overall programme, without prejudice to the contractors’ obligations and/or legal responsibilities.

2. QUALITY ASSURANCE PROGRAMME DURING COMMISSIONING

2.1. Quality assurance programme establishment and documentation

2.1.1. Commissioning

Before a nuclear power plant is put into commercial operation, commissioning is performed to demonstrate the functional adequacy of plant components, systems and structures and to eliminate deficiencies found during this phase. For activities related to commissioning it is intended that this Safety Guide shall be used in conjunction with the Safety Guide on Commissioning Procedures for Nuclear Power Plants (IAEA Safety Series No. 50-SG-04).

Procedures shall ensure that prerequisite steps for equipment testing, such as completion of necessary construction, prior testing, safety precautions, and measures to preserve equipment status have been or will be performed prior to commencement of the appropriate phase of the pre-operational test. Annex I of Safety Series No. 50-SG-04 provides a detailed list of commissioning tests to be given consideration.

A quality assurance programme shall be applied to the commissioning of all systems and equipment important to safety. The quality assurance programme provides means of establishing controls over commissioning activities; its purpose

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is to provide confidence that commissioning is performed according to established requirements.

2.1.2. Organization

The organizational structure, functional responsibilities, levels of authority, and lines of internal and external communication for management, direction and execution of commissioning activities shall be clearly defined and documented.An individual shall be identified as responsible for controlling and co-ordinating the overall performance of commissioning activities.

Procedures shall be established whereby the commissioning group, i.e. the group responsible for execution of the overall commissioning activities, is clearly designated. This group may consist of several teams with delegated tasks to execute specific commissioning activities and with authority to operate the necessary devices and systems. For each of these activities persons with authority to execute and document the work shall be identified.

Verification of effective implementation of the quality assurance programme for commissioning shall be carried out by persons not directly responsible for commissioning activities.

2.1.2.1. Organizational interfaces

Where more than one organization is involved in commissioning activities, the responsibility of each organization involved shall be clearly established and documented. Procedures shall be established for the identification, review, approval, release, distribution and revision of documents that cross organizational boundaries.

2.1.2.2. Transfer of responsibilities

Measures shall be established for the documented transfer of components and systems and the related records from the construction group to the commissioning group and for indicating the change of status of such components and systems. Commissioning personnel shall review the documentation provided by the constructor and any deficiencies should be identified and resolved. When it has been decided that the transfer can be accomplished, the components and systems shall be jointly checked by representatives of the construction and commissioning groups and the turnover records signed to indicate the formal transfer of responsibilities.

Similarly, a documented transfer of components and systems and related records from the commissioning group to the operating group shall be undertaken. After satisfactory completion of the commissioning programme, a documented transfer of the whole plant shall be undertaken. The operating group shall satisfy itself that the systems transferred comply with specified design, performance and safety requirements and shall formally accept responsibility for the transferred components and systems and related records.

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To satisfy itself that the components and systems are ready for transfer, the operating group should:

(1) Check all components and systems for: proper identification, completion of commissioning tests and inspections, cleanness, lubrication, positioning of switches and valves, calibration of instruments, proper status of safety devices, etc.;

(2) Verify that all required commissioning documentation has been completed;

(3) Verify that all deficiencies or open items have been resolved.

2.1.3. Quality assurance programme documentation

The quality assurance programme should be outlined in a programme description and shall be documented in programmatic and work oriented procedures and instructions as specified in the Safety Guide on Establishing the Quality Assurance Programme for a Nuclear Power Plant Project (IAEA Safety Series No. 50-SG-QA1). The programmatic procedures shall address all the applicable quality assurance requirements specified in the Quality Assurance Code. Work oriented procedures and instructions shall document both the commissioning activities and the verifications associated with specific commissioning activities.

2.2. Quality assurance programme implementation

2.2.1. General

Implementation of the quality assurance programme for those activities occurring during commissioning that are comparable in nature to activities during other phases of the nuclear power project such as construction and operation is dealt with in the following Guides:

(1) Quality Assurance During Site Construction of Nuclear Power Plants (IAEA Safety Series No. 50-SG-QA4)

(2) Quality Assurance in the Manufacture of Items for Nuclear Power Plants (IAEA Safety Series No. 50-SG-QA8)

(3) Quality Assurance in the Procurement of Items and Services for Nuclear Power Plants (IAEA Safety Series No. 50-SG-QA3)

Implementation of the quality assurance programme during commissioning shall include all requirements applicable during operation as specified in Section 3 of this Guide.

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2.2.2. Document control

Documents essential to the performance and verification of commissioning shall be controlled. Measures shall be established for their identification, review, approval, issuance, distribution and revision. These measures shall ensure that:

(1) Documents, including changes and revisions, are:(i) reviewed for adequacy and approved for release by authorized

personnel;(ii) distributed for use at the location where the prescribed activity

is to be performed and where the document is required for reference;

(2) The latest authorized documents are used;(3) Obsolete documents are identified as such and promptly removed

from use;(4) Distribution lists are kept up to date;(5) Records permitting the identification of changes and revisions are

maintained.The individuals or organizational units responsible for preparing, reviewing,

approving and issuing documents and all changes and revisions shall be identified.

2.2.3. Design control

Commissioning shall assure to the extent feasible the adequacy of the plant design to meet design performance specifications. The question of changes to the design specification or system modification, including computer software, is considered in the Safety Guide on Quality Assurance in the Design of Nuclear Power Plants (IAEA Safety Series No. 50-SG-QA6).

2.2.3.1. Field changes and modification control

Field modifications and other changes made during commissioning shall be controlled and documented and included either in the original document or as an appendix thereto. Such modifications and changes shall be shown promptly on all documents being used by the commissioning group. These changes shall have been reviewed and approved either by the organization that performed the original review and gave approval or by a group specifically designated by the responsible organization. This review group shall have access to pertinent background information and shall have adequate understanding of the requirements and intent of the design.

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2.2. 4. Commissioning procedures, instructions and drawings

Measures shall be established to ensure that the commissioning, modification, replacement and repair of all systems and components are planned, controlled and performed according to documented procedures, instructions, drawings or checklists.

Annex I of the IAEA Safety Series No. 50-SG-04 provides a detailed list of commissioning tests.

Procedures and instructions shall require that the results of commissioning tests be recorded and evaluated to provide clear indication that the design requirements have been met. Procedures and instructions shall also provide information on how corrective action is to be carried out when design requirements have not been met. The commissioning documentation shall clearly identify the requirements, intent, test objectives, limiting criteria, test conditions and procedures, special equipment, manpower requirements, special precautions and acceptance criteria. For further information on the content and format-of commissioning test procedures and instructions refer to Section 4 of IAEA Safety Series No. 50-SG-04.

2.2.4.1. Review of commissioning test proceduresCommissioning test procedures and instructions shall, prior to use, be reviewed

for adequacy by persons having access to pertinent design and other background information and having adequate understanding of the design requirements and intent of the system equipment being commissioned. Reviewing personnel shall include a representative of the design organization. Changes to commissioning procedures and instructions shall be subject to the same control measures as applied to initial procedures.

2.2.5. Equipment control

2.2.5.1. Configuration identification and control

Measures shall be established to ensure that all equipment and systems important to safety are controlled, maintained and/or modified in accordance with appropriate specifications and procedures. The configuration of equipment for specific tests shall be identified and controlled and, where appropriate, independently verified.

The release of equipment or systems for maintenance and modification during commissioning and their return to commissioning shall be controlled and documented. When equipment is removed from service, independent verification shall be provided to the extent necessary to assure that the proper system was removed. This may be accomplished by physical checking of the appropriate equipment and controls, along with the use of appropriate tags and records or by indirect means

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such as observation of indicators and status lights. Control measures, such as locking and identification by tagging shall be utilized to provide protection of personnel and equipment during maintenance and modification. The status of maintenance and modifications and of any associated inspections and tests performed on equipment and systems shall be recorded. Until objective evidence is available to confirm that specified maintenance, modification, inspection, or testing has been completed satisfactorily, the affected equipment and systems shall be considered to be inoperable. When the maintenance and modification and associated inspections and tests are complete, commissioning personnel shall ensure that normal conditions have been restored.

Commensurate with its importance to safety, restoration of equipment to its normal alignment shall be independently verified by a second qualified person unless all equipment, valves, and switches involved in the activity can be proven to be in their correct alignment by functional testing without adversely affecting the safety of the plant. The person who performs the verification of correct implementation of equipment control measures or proper alignment prior to returning equipment to service shall be qualified to perform such tasks for the particular system involved, and shall possess operating knowledge of the particular system involved and its relationship to plant safety.

2.2.5.2. Equipment maintenanceA maintenance programme, based on supplier recommendations, service

conditions and experience with comparable equipment, shall be applied during commissioning. This programme shall include the procedures and instructions required for maintenance of items of equipment expected to require recurring maintenance.

2.2.5.3. Control of handling and storing of equipment

Handling instructions and procedures shall be provided for material, equipment and instrumentation that may be damaged if handled incorrectly.

Items shall be stored under conditions appropriate to their susceptibility to environmental deterioration and periodically inspected as necessary.

2.2.5.4. Identification and control of material and equipment

Procedures shall be prepared and implemented for the identification and control of material and equipment during receipt, storage, installation and use. These procedures should ensure that identification of these items is maintained by part number, serial number or other appropriate means, either on the item or by records traceable to the items, as required. Further information can be found in Section 7 of the Quality Assurance Code.

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2.2.6. Calibration and control o f measuring and test equipment

Measures shall be implemented to ensure that the following measuring and test equipment used during commissioning are of the proper type, have the proper range, accuracy and precision and are in the proper condition to establish conformance to specified requirements:

— instrumentation for systems important to safety;- gauges, instruments and other equipment used for inspections, examination

and tests (this includes both permanently installed equipment and portableor temporarily installed equipment);

-- portable (derived) standards and laboratory standards used for calibrationof these instruments.The method and interval of calibration shall be defined on the basis of the

type of equipment, its stability and reliability characteristics, the accuracies required and other relevant factors.

All such equipment shall be adjusted, maintained and calibrated against equipment having a known relationship to nationally recognized standards in order to ensure that it is accurate within required limits when it is used for commissioning activities. Where no such national standard exists, the basis for calibration shall be documented.

When deviations beyond prescribed limits are detected during calibration, an evaluation shall be made of the validity of previous measurements and tests and the acceptance of results based on such measurements and tests reassessed.

Records of adjustment, maintenance and calibration shall be maintained and, where possible, equipment shall be suitably marked to indicate its calibration status.

2.2. 7. Housekeeping and cleanliness control

Procedures shall be implemented to establish and maintain the required degree of cleanliness during commissioning activities. These procedures should specify methods such as the following:

(a) Special cleaning(b) Flushing to verify the cleanliness of fluid systems(c) Establishing barriers and covers to maintain established cleanliness levels(d) Maintaining accountability of tools and equipment in the vicinity of

opened systems.Special consideration shall be given to the establishment of measures for mini

mizing the potential contamination of certain portions of plant systems or equipment with foreign materials during commissioning, maintenance or modification activities. Control of access and inspection before closure shall be implemented. Measures shall also be established to ensure the cleanliness of the plant environment.

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2.2.8. Verification by inspection and surveillance, and by review o f commissioning results

2.2.8.1. Responsibilities and functions

Measures shall be established for verifying that commissioning activities are accomplished as specified in commissioning procedures. Verification activities shall be planned and implemented and the acceptability of items and activities shall be documented throughout the commissioning process. Verification shall be performed for each activity where necessary.

The verification method and the acceptance criteria shall be clearly described in the relevant work document. The materials and equipment to be used and the documentation to be completed shall be specified. The individuals or the group responsible for carrying out the verification activities shall be identified. The persons concerned shall have received adequate training and be suitably qualified to carry out the prescribed activities.

2.2.8.2. Receiving inspection

Measures shall be established to:(1) Identify, inspect and, if required, test incoming items as planned;(2) Check the objective evidence provided by the supplier, to confirm

that the items received were fabricated, tested, and inspected prior to shipment, in accordance with the applicable codes, specifications, purchase orders, and/or drawings; and that the documentation requirements of the purchase order for the items have been met;

(3) Verify that the documentation provided by the supplier has been reviewed to ensure that the technical requirements have been met;

(4) Identify conforming and non-conforming items, and, where practical, segregate those which are non-conforming to prevent inadvertent installation or use.

2.2.8.3. Inspections and surveillance of commissioning tests

The verification shall confirm that all relevant parameters meet the acceptance criteria specified in the commissioning programme documentation and that any deficiencies were suitably resolved.

Inspections and confirmatory checking shall be performed and documented to verify compliance with specific test requirements. The following are examples of test requirements which should be verified:

(1) The test prerequisites are in accordance with the approved test procedure;

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(2) Test equipment is of the required type, range and accuracy;(3) Test inputs (flows, currents, pressures, etc.) are within the required

test limits;(4) Personnel and equipment safety requirements are satisfied, in particular

by tagouts and by protection of adjacent equipment;(5) Calibrated test equipment is within its calibration due date and instru

ment serial numbers are recorded in test documentation;(6) The required documentation and reports have been completed;(7) Documentation is approved by authorized individuals.A programme of surveillance shall be implemented to verify conformance

with commissioning procedures. Surveillance of the activities connected with the following shall be performed:

(a) Testing(b) Tracking and resolving test deficiencies(c) Test documentation(d) Document control(e) Control of measuring and test equipment(f) Cleanliness control(g) Field changes and modifications(h) Maintenance during pre-operational testing(i) Personnel qualification (j) Records.

2.2.8.4. Review and confirmation of commissioning records and results

Commissioning records and results shall be reviewed by a responsible group or a person to verify the completeness of the tests performed and confirm that the item or activity to which the records, reports or results apply is satisfactory. This review shall also involve a representative of the design organization.

2.2.8.5. Commissioning status

The commissioning group shall ensure that as soon as the planned verification (inspection, checking, surveillance and records review) is performed, the acceptability of items and activities to which it applies is made known throughout the commissioning process. Suitable control methods such as the use of tags or labels shall be implemented to indicate the commissioning status of items, Only authorized signatures shall indicate final acceptance of items, reports and records. The application and removal of status indicators shall be carried out by authorized personnel.

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2. 2.9. Non-conformance control

Measures shall be established to identify, report, review, dispose, document and otherwise control items and activities that do not conform or are not performed to specified requirements. Detected non-conforming items shall be suitably identified by marking, tagging, or other acceptable methods. Non-conformance reports shall be sufficiently detailed to allow proper review and evaluation and disposition. Individuals responsible for the review shall be identified and shall as appropriate include members of the design organization. All non-conformances shall be resolved before the commissioning activities are considered to be complete.

2.2.10. Corrective action

The requirements of Section 11 of the Quality Assurance Code shall be applied to the programme. The cause of any significant conditions adverse to quality shall be determined and corrective action taken to prevent their repetition. Individual responsibilities for initiating and implementing corrective actions and performing follow-up reviews shall be identified.

2.2.11. Records

A records system shall be established to collect and maintain:(1) Those documents from the design, manufacturing and construction

phases that are required as prerequisites to commissioning;(2) Commissioning records, including plans, procedures, detailed test

results, deficiencies discovered and actions taken to correct them; and(3) Commissioning quality assurance audit records.A record-retention policy should be established identifying which records

may have a significant bearing on the safe operation of the station and should therefore be retained for the life of the station. This policy should also cover documents that should be retained for a limited time and will identify the dates when they may be discarded. Further information can be found in the Safety Guide on Quality Assurance Records System for Nuclear Power Plants (IAEA Safety Series No. 50-SG-QA2).

2.2.12. Audits

Audits shall be performed to determine the adequacy of, and the adherence to, all aspects of the commissioning quality assurance programme. Owing to the relatively short duration and complexity of commissioning, audits shall be conducted with sufficient frequency to ensure effectiveness in the commissioning quality assurance programme. The audits shall pay particular attention to the

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organizational interfaces and transfer of responsibility which occur between construction and commissioning and operation. Additional information on auditing can be found in the Safety Guide on Quality Assurance Auditing for Nuclear Power Plants (IAEA Safety Series No. 50-SG-QA 10).

3. QUALITY ASSURANCE PROGRAMME DURING OPERATION

3.1. Quality assurance programme establishment and documentation

3.1.1. Operation

The nuclear power plant and its components and systems shall be operated safely and in accordance with their design intent and specified operational limits and conditions. To satisfy this goal, plant operation must be thoroughly planned, documented and controlled. In this regard the requirements for safety in operations are identified in the Operation Code and its associated Safety Guides.

3.1.2. Quality assurance programme

A quality assurance programme for operations shall be established. It shall apply to all items important to safety and to all activities which affect the quality of such items. It shall also apply to activities related to safety such as radiation protection, management of radioactive wastes, environmental monitoring, physical security and response to emergencies.

3.1.3. Quality assurance programme documentation

3.1.3.1. General

The quality assurance programme for plant operation shall be documented in a programme description and in procedures and instructions according to the requirements and recommendations of IAEA Safety Series No. 50-SG-QA 1.

3.1.3.2. Programme description

The quality assurance programme may be documented in a number of different documents. It is not necessary that all such documents be compiled into one master document. However, a summary programme description with an index shall be compiled to identify all documents pertaining to the programme, and to

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relate them to the requirements of appropriate regulations, codes and standards. The quality assurance programme description shall identify items and activities to which the programme applies, and shall define the responsibilities of the various organizational units and groups for programme implementation.

3.1.3.3. Procedures and instructions

Activities important to safety in nuclear power plants shall be prescribed by written procedures or instructions of a type appropriate to the circumstances and shall be carried out in accordance with them. Procedures and instructions shall cover administrative and programmatic, as well as technical, aspects of the programme and shall address separately operational states, accident conditions and emergency situations. They shall be written in such a way as to avoid ambiguity with regard to the required activities.

Measures shall be established for the issuance, dissemination, review and updating of these documents. Where circumstances necessitate issuing procedures or instructions which have short term applicability, specific provisions shall be made for designating the period of applicability and for eventual cancellation of the temporary procedures.

Procedures and instructions dealing with administrative and programmatic aspects should cover such items as:

(1) Security and visitor control(2) Authorities and responsibilities for safe operation and shutdown(3) Authorities and responsibilities of shift supervisor and other leading

operational personnel(4) Equipment control (e.g. locking and tagging)(5) Procedure adherence and method for making temporary changes(6) Procedure review and approval(7) Schedule for surveillance tests and calibration(8) Shift and relief turnover(9) Transfer of authority during emergency conditions

(10) Log entries, record retention and review procedures(11) Access to containment(12) Access to pressure retaining system(13) Access to control room(14) Bypass of safety functions and jumper control(15) Maintenance of minimum shift complement and call-in of personnel(16) Plant fire protection programme(17) Communication system procedures(18) Quality assurance programme implementation procedures(19) In-service inspection (administrative aspects)(20) Housekeeping and cleanliness control(21) Provision of technical support in emergency situations

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(22) Corrective action recommended by reviews and audits(23) Reporting, analysis and dissemination of operating and industry

experience(24) Overtime limitations.Technical procedures or (according to the terminology suggested in IAEA

Safety Series No. 50-SG-QA1), work oriented procedures and/or instructions should deal with such items as:

(a) System and equipment operation(b) Maintenance(c) Radiation protection(d) In-service inspection(e) Refuelling(f) Calibration and tests(g) Emergencies and other significant events(h) Chemistry control(i) Radioactive waste management.

3.1.3.4. Format and content of procedures

Each procedure and instruction shall be sufficiently detailed that a qualified individual can perform the required function without direct supervision, but it need not include a complete description of the system or plant process. The format may vary depending on the purpose of the document and the practices of the operating organization. As appropriate, the following elements shall be included:(1) Title: A title descriptive of the activity, system or unit to which the proce

dure or instruction applies. It shall include an identification number, a revision number or date and an approval status.

(2) Applicability: A clear statement of the purpose for which the procedure or instruction is intended: (e.g. ‘for use during reactor or plant startup’). If the title does not clearly indicate the purpose, a separate statement of applicability, identifying the reasons for'particular operations, shall be provided.

(3) References: References, as necessary for items such as drawings and other design documents, operational limits and conditions, and relevant operating and maintenance procedures. When the sequence of steps requires other tasks to be performed prior to or concurrent with a particular step withinthe procedures, references shall be identified within the body of the procedure.

(4) Prerequisites: Those independent actions or other activities which shall exist, prior to the use of the procedure or instruction. Prerequisites applicable only to certain sections of a procedure or an instruction shall also be identified.If special personnel qualification, special tools or instrumentation are necessary to accomplish the procedure, they shall be specified.

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(5) Precautions: Precautions to alert the individual performing a task to important measures necessary to protect equipment, personnel and the public, or to avoid an abnormal or emergency situation. It may be desirable to identify these in a separate section. Precautionary notes applicable to specific steps in the procedure or instruction shall be included in the main body of the procedure or instruction and identified as such.

(6) Limitations and actions: Limitations on the parameters being controlled and appropriate corrective measures to return them to the normal control band.It may be convenient to specify limitations and set points in a separate section.

(7) Main body: Step-by-step requirements, in the degree of detail necessary for performing a function or task.

(8) Acceptance criteria: Quantitative and/or qualitative acceptance criteria for determining that important activities have been satisfactorily accomplished, including requirements for and methods of verification.

(9) Restoration: Step-by-step requirements, in the degree of detail necessary, for placing the equipment or system in the desired status following completion of the activity covered by the main body of the procedure.

(10) Check-off lists: When complex procedures or instructions are involved, check-off lists may be included as part of the procedure or instruction, or may be attached as appendices.In addition to these ten elements, which apply to all procedures, the follow

ing additional elements apply to event based emergency procedures:(11) Title: The title shall also be descriptive of the emergency for which the pro

cedure is provided.(12) Symptoms: To aid in identifying an emergency, a list of symptoms such as

alarms, operating conditions and probable magnitudes of parameter changes shall be included.

(13) Automatic actions: The automatic actions that will probably occur as a result of the emergency shall be identified.

(14) Immediate operator actions: Steps specifying immediate actions for operation of controls, or for confirmation of automatic actions that are required to stop the degradation of conditions and mitigate their consequences, shall be included.

(15) Subsequent operator actions: Steps needed to return the reactor to a normal condition or to provide for a safe extended shutdown period under abnormal or emergency conditions shall be included.

3.1.3.5. Review, approval and verification

Each procedure and instruction shall be reviewed and approved, prior to initial use, at the appropriate level of the operating organization and, as appropriate,

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the design organization. The frequency of subsequent reviews shall be specified.This will depend on the type and complexity of the activity involved, on the length of time the specific plant has been in operation, and on the experience gained. The applicable procedures and instructions shall be reviewed after any of the following:

(1) An unusual occurrence at the plant, such as an accident, an unexpected transient, a significant operator error or an equipment malfunction;

(2) Occurrences at other nuclear power plants, if relevant information is available;

(3) Any modification to a system;(4) Difficulty encountered in complying with the procedures or instructions.Rules shall be established which require that the review be carried out by

knowledgeable personnel other than the originators and that the approval be given only by individuals authorized to do so.

Each procedure and instruction shall be verified prior to use. Verification |should include review by the supplier of items and services as appropriate. The verification process should also ensure that the steps of the procedure have been evaluated by such means as a walkthrough of the procedure at the actual plant or performance of the procedure on the power plant simulator used to train personnel for that plant. The suitability of plant operating procedures shall be demonstrated to the maximum extent possible during the pre-operational and initial startup test programmes.

Changes shall be reviewed and approved by the organizations that performed the original review and approval unless the operating organization designates another qualified organization.

To accommodate the possible need for changes in approved procedures when there is no time for the normal review and approval process, rules shall be established for assigning responsibility for rapid approval of such changes.

3.1.3.6. Temporary procedures and instructions

Temporary procedures and instructions may be issued during the operational phase:

(1) To direct special operations during testing, refuelling, maintenance and modifications;

(2) To provide guidance in unusual situations not within the scope of the normal procedures;

(3) To ensure orderly and uniform operations for short periods when the plant, a system or a component of a system is performing in a manner not covered by existing detailed procedures or when any of these has been modified or extended in such a manner that portions of existing procedures do not apply.

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Temporary procedures and instructions shall specify the period of time and specific plant configuration for which they may be used. These shall be subject to the review and approval processes prescribed in Subsections 3.1.3.5 and 3.11.3 as applicable.

3.1.4. Adherence

Measures shall be established to ensure the use of, and adherence to, procedures and instructions in all activities important to the safety of the plant. For conditions not covered by approved detailed procedures, operations personnel shall be given written instructions to take action so as to protect public health and safety and to minimize injuries to personnel and damage to the facility.

Guidance shall be provided on how procedures and instructions are to be implemented. For example, the tasks shall be identified for which:

(1) The written procedure shall be at hand (e.g. as a hard copy or as video display) and be followed step by step while the task is being performed,

(2) The operator shall have committed the procedural steps to memory,(3) There shall be verification that significant steps have been completed,

and that the responsible persons have initialled or signed the check-lists.The types of procedures and instructions that shall be available and referred

to directly include those developed for extensive or complex jobs where reliance on memory cannot be trusted, e.g. reactor startup, or for tasks which are infrequently performed. Those procedures which shall be committed to memory include, for example, steps to be taken in response to emergency situations.

Copies of all procedures shall be available to appropriate members of the plant staff at their duty stations. If documentation of an action is required, the necessary data shall be recorded as the task is performed.

3.2. Organization

3.2.1. Operating organization

The operating organization shall define the responsibility of the various parts of the organization with respect to the establishment, implementation and verification of the effectiveness of the quality assurance programme. The operating organization shall provide suitably qualified and trained personnel for activities affecting quality during the operation of the plant. Initial incumbents or replacements for members of the on-site operating organization shall have appropriate experience, training and retraining to assure that necessary competence is maintained. Further information related to staffing of nuclear power plants can be

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found in the Safety Guide on Staffing of Nuclear Power Plants and the Recruitment, Training and Authorization of Operating Personnel (IAEA Safety Series No. 50-SG-01).

3.2.1.1. Assignment of responsibility and authority

Measures shall be provided to ensure that responsibilities and authorities are clearly delineated in such areas as:

(1) Plant control responsibilities(2) General authorities and responsibilities of personnel in the operating

organization(3) Transfer of responsibility(4) Control room access(5) Human factors(6) Implementation of emergency plan.

3.2.1.2. Technical support for the on-shift operating staffThe responsible organization shall establish provisions for ensuring that the

shift organization includes, or has available for consultation, persons with professional level expertise in technical areas that are related to the safe operation of the plant.

3.2.2. Quality assurance organization

The persons or organizations responsible for establishing the programme requirements and measuring the overall effectiveness of the programme shall be designated. They shall be sufficiently independent of cost and scheduling considerations when these are opposed to safety considerations and shall have direct access to such level of management as may be necessary to resolve quality assurance concerns and to achieve effective implementation of the quality assurance programme. They shall report regularly on the effectiveness of the programme to the plant manager as well as cognizant corporate management.

The plant manager shall have overall responsibility for the implementation of the plant quality assurance programme. The persons or organizations responsible for verifying that the quality assurance programme is implemented effectively or for assuring that an activity has been correctly performed may report functionally to an off-site organization, or this responsibility can be divided between organizations reporting on site and off site. If this responsibility is divided, the organization reporting off site shall perform independent audits to verify programme compliance, whereas the organization reporting on site shall perform surveillance, inspection and review activities for the purpose of process control and product

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acceptance and to verify that various activities conform to specified requirements, i.e. the quality control function.

Regardless of the organizational structure, persons or organizations responsible for verifying that the quality assurance programme is implemented effectively or for assuring that an activity has been correctly performed shall have sufficient authority and organizational freedom to: identify quality problems; initiate, recommend or provide solutions through designated channels; and verify implementation of solutions.

Verification of effective implementation of the quality assurance programme for operation shall be carried out by persons not directly responsible for the performance of the operating activities.

In those situations where the verification functions are performed by personnel not from the quality assurance organization, the quality assurance organization shall review and concur in the programme and shall perform audits to assure that the verification activities have been properly accomplished.

Further information related to quality assurance organization for operation is included in the Safety Guide on Quality Assurance Organization for Nuclear Power Plants (IAEA Safety Series No. 50-SG-QA7).

3.2.3. Training and qualification o f personnel

Personnel assigned to implement the elements of the quality assurance programme shall have the necessary training, qualifications and competence to perform effectively their assigned tasks. Appropriate qualification and training requirements shall be established as described in IAEA Safety Series No. 50-SG-01 for operating personnel and Safety Series Nos 50-SG-QA7 and 50-SG-QA 10 for quality assurance personnel. Training programmes shall be established, as necessary, to ensure that suitable proficiency of personnel is achieved and maintained to meet established requirements. Records of the relevant qualifications of personnel shall be maintained. An indoctrination programme shall be implemented to ensure that all personnel are aware of their responsibilities and functions as described in the quality assurance programme documentation.

3.3. Document controlDocuments essential to the performance and verification of the work during

the operation shall be controlled. Measures shall be established for their identification, review, approval, issuance, distribution and revision. These measures shall ensure that:

(1) Documents, including changes and revisions, are:(i) reviewed for adequacy and approved for release by authorized

personnel;

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(ii) distributed for use at the location where the prescribed activity is to be performed and where the document is required for reference;

(2) The latest authorized documents are used;(3) Obsolete documents are identified as such and promptly removed from

use;(4) Distribution lists are kept up to date; and(5) Records permitting the identification of changes and revisions are main

tained.The individuals or organizational units responsible for preparing, reviewing,

approving and issuing documents and all changes and revisions shall be identified.

3.4. Operation control

Requirements and recommendations for controlling the operation of nuclear power plants, including maintenance and modifications, are contained in the Operation Code and its associated Safety Guides. In addition, the other Safety Guides in the Quality Assurance series contain requirements and recommendations concerning design, manufacture and construction related activities associated with maintenance and modification. Activities occurring during operation that are comparable in nature to activities occurring during initial plant design and construction are treated in the following Guides:

(1) Quality Assurance During Site Construction of Nuclear Power Plants (IAEA Safety Series No. 50-SG-QA4);

(2) Quality Assurance in the Design of Nuclear Power Plants (IAEA Safety Series No. 50-SG-QA6);

(3) Quality Assurance in the Manufacture of Items for Nuclear Power Plants (IAEA Safety Series No. 50-SG-QA8).

Provisions shall be included in the relevant plant procedures or in special instructions to ensure that there is adequate communication of informationbetween:

(1) Personnel within a shift(2) One operating shift and another(3) Each operating shift and management(4) The operating shift and maintenance and other services(5) On-site and off-site organizations(6) The operating organization and any on-site construction groups(7) The operating organization and the regulatory organization.As appropriate, the information communicated shall outline plant status,

particularly abnormalities, unfinished work and temporary modifications. The relevant procedures and instructions shall specify methods of transferring respon

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sibility between groups (for example, by work permits for release of items for maintenance, testing or inspection), and shall outline methods of obtaining services (for example, radiological, reactor physics or chemistry services).

In addition to operating and maintenance procedures, there shall be procedures for safety related site services such as: fire prevention and control; storage of materials; controls to prevent damage to, contamination of, or the introduction of foreign materials into safety related systems; and disposal of combustible wastes.

3.5. Emergency control

Measures shall be established to identify reference emergency conditions and to develop and implement operating procedures for coping with them. The procedures shall be written so that a trained operator will know the action he should take.

Information related to the identification of emergency conditions and emergency planning and preparedness can be found in the Safety Guide on Preparedness of the Operating Organization (Licensee) for Emergencies at Nuclear Power Plants (IAEA Safety Series No. 50-SG-06).

3.6. Procurement control

Information on the handling of procurement activities during operation can be found in IAEA Safety Series No. 50-SG-QA3.

During the operation phase, the control of procurement activities can be influenced by several factors. For example:

(1) It may not always be possible to purchase replacement items to the same specification and codes that were applied in the purchase of the original item;

(2) It may not be possible to determine what quality requirements were originally specified;

(3) It may not be possible to determine what quality assurance requirements were originally specified.

In the case of (1) the items shall be purchased to requirements equivalent either to those specified for the original equipment or to those requirements specified by a properly reviewed and approved version of these requirements. In case(2) where the quality requirements for the original item cannot be determined, an engineering evaluation shall be conducted by qualified individuals, and new quality requirements shall be established and documented. Care shall be exercised to specify performance requirements at least equivalent to the original performance requirements. This evaluation shall take into account interfaces and inter- changeability, ensure that safety functions are not adversely affected and that they are in accordance with regulatory or code requirements. In case (3), where it may not be possible to establish clearly the original quality assurance requirements that

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were applied, an engineering evaluation would again be required to determine these requirements. If the original item or part was procured without specifically identified quality assurance requirements, then after a review of the nature and application of the item, it may be appropriate for spare and replacement parts to be similarly procured.

3.7. Material and equipment control

3. 7.1. Identification and control o f material and equipment

Procedures shall be prepared and implemented for the identification and control of material and equipment during receipt, storage, installation and use. These procedures should ensure that identification of these items is maintained by part number, serial number or other appropriate means, either on the item or records traceable to the items, as required. Further information can be found in Section 7 of the Quality Assurance Code.

3. 7.2. Material handling and storage

Procedures shall be prepared and implemented for the handling and storage of materials, parts and components throughout the operation phase of the plant. Handling instructions and procedures shall be provided for all materials, parts and components that may be damaged if handled incorrectly. When special handling tools and equipment are required they shall be inspected and tested at specified times.

Adequate storage facilities shall be provided for storing and protecting materials, parts or components prior to their use. Procedures shall be prepared, as necessary, for preservation, segregation and packaging to be applied during the storage of any items which have a shelf-life or are liable to deterioration in storage through exposure to air, moisture or other environmental factors. Inspections shall be performed periodically to ensure that adequacy of storage areas and quality of items are being maintained as required. Equipment that requires special storage conditions shall be identified and it shall be verified that those conditions are met. Stock-rooms and storage areas shall be controlled to prevent the removal or replacement of material without appropriate documentation and authorization.3.7.3. Operating status o f equipment

The release of equipment or systems for maintenance, modification and testing and their return to service shall be controlled and documented. The responsible operating personnel shall assess the consequences of releasing each item or system to ensure that adequate protection is maintained and determine whether the equipment or system may be released. Control measures, such as locking and

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tagging, shall be utilized to provide for protection of equipment and personnel during maintenance, modification and testing. Control room tags shall be designed and placed in such a way as to prevent obstruction of other instruments, controls or indicating lights. When equipment is removed from service, independent verification shall be provided to the extent necessary to assure that the proper system was removed. This may be accomplished by physical checking of the appropriate equipment and controls, along with the use of appropriate tags and records, or by indirect means such as observation of indicators and status lights. This requirement may be waived if the only way of accomplishing it would result in significant radiation exposure. Reactor operators and the shift supervisor shall be informed of changes in equipment status and the effects of such changes. Equipment and systems in such a controlled state shall be clearly identified.

Temporary modifications, such as temporary bypass lines, electrical jumpers, lifted electrical leads, mechanical blocks, temporary trip settings, and the like, shall be controlled. The status of maintenance and of modifications and any associated inspections and tests performed on equipment and systems shall be recorded. Until suitable evidence is available to confirm that specified maintenance, modification, inspection or testing has been completed satisfactorily, the affected equipment and systems shall be considered to be inoperable. Before returning equipment and systems to service, operating personnel shall ensure that normal conditions are restored and shall document functional acceptability of equipment.

For equipment of importance to safety, restoration to normal alignment shall be independently verified by a second qualified person unless all items, valves, and switches involved in the activity and other operating features which define normal conditions can be proven to be satisfactory or in their correct alignment by functional testing without adversely affecting the safety of the plant. A second exception is where such verification would result in significant radiation exposure. The person who performs the verification of correct implementation of equipment control measures or proper alignment prior to returning equipment to service shall be qualified to perform such tasks for the particular system involved and shall possess operating knowledge of the particular system involved and its relationship to plant safety.

3.7.4. Equipment maintenance

The maintenance programme developed during commissioning shall be implemented to maintain equipment and systems important to safety at the level of quality required for them to adequately perform their intended functions. The programme shall prescribe the frequency and type of maintenance to be performed. This programme shall include the procedures required for maintenance of items of equipment important to safety expected to require recurring maintenance. Approved procedures shall be available for the repair of equipment and systems important to safety before the performance of such repairs. The maintenance programme

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and schedules shall be periodically reviewed and revised as necessary in response to experience gained in achieving and maintaining the required level of equipment performance. The causes of malfunctions shall be promptly determined, evaluated and recorded and appropriate action taken.

The requirements and recommendations related to maintenance are presented in the Safety Guide on Maintenance of Nuclear Power Plants (IAEA Safety Series No. 50-SG-07).

3.7.5. Equipment modification

Modification of equipment and systems shall be planned and performed in accordance with appropriate procedures, instructions or drawings that conform to applicable codes and standards. Design activities associated with modifications of equipment and systems important to safety shall be subject to control in accordance with the requirements and recommendations of IAEA Safety Series No. 50-SG-QA6.3. 7.6. Housekeeping and cleanliness control

Measures shall be established to ensure the cleanliness of the plant. This shall include the control of cleanliness of radiation zones and work areas, fuel storage and waste disposal facilities, etc. Conditions and environments that can affect health and safety shall be identified and instructions shall require that only proper materials, equipment, processes and procedures are utilized.

Requirements for the cleaning of components and systems and for the control of their cleanliness shall be established in order to:

- ensure the removal of deleterious contaminants- minimize recontamination of cleaned surfaces- minimize the cleaning required after installation, repairs or modification.

There shall be close control of tools and other loose items used in the cleaning process to ensure their removal.

The cleanliness of items shall be specified as necessary and methods shall be documented for control of the site area, the plant, as well as materials and equipment being incorporated in the plant, to preserve the requisite quality of the items being installed. Personnel working in controlled zones shall be familiar with the requirements for cleanliness control applicable to the various zones.

3.8. Inspection, surveillance and testing

3.8.1. General

Inspection and testing programmes for operation shall follow the applicable requirements of Sections 4 (Commissioning) and 7 (Maintenance, Testing, Exami-24


nation and Inspection) of the Operation Code and Section 9 (Inspection and Test Control) of the Quality Assurance Code.

3.8.2. Scheduling

Inspection, surveillance and test schedules shall be prepared and their status shall be identified. It is recommended that an overall master schedule be prepared and maintained up to date, reflecting the status of all planned in-plant surveillance, tests and inspections. This schedule shall be reviewed and revised as necessary in response to experience gained during plant operation. Since tests and inspections may have an effect on operating or maintenance programmes, overall and coordinated planning should be carried out. Schedules for inspections and tests should show the earliest and latest dates when they may be carried out. Control shall be established to govern continued operation and to authorize rescheduling of inspections or tests that are not performed in accordance with the original schedule.

3.8.3. Inspection and surveillance

3.8.3.1. Receiving inspection

Measures shall be established to:(1) Identify, inspect and, if required, test incoming items as planned;(2) Check the objective evidence provided by the supplier, to confirm that

the items received were fabricated, tested, and inspected prior to shipment, in accordance with the applicable codes, specifications, purchase orders, and/or drawings and that the documentation requirements of the purchase order for the items have been met;

(3) Verify that the documentation provided by the supplier has been reviewed to ensure that the technical requirements have been met;

(4) Identify conforming and non-conforming items and, where practical, segregate those which are non-conforming to prevent inadvertent installation or use.

3.8.3.2. Inspections of routine operations, maintenance and repairVerification by inspections of activities associated with operation and mainte

nance and of certain technical service activities routinely assigned to the on-site operating organization shall be performed by appropriately qualified individuals other than those who performed the activity. The inspector may be a member of the same organizational unit. A supervisor may serve as the inspector if he did not personally participate in or supervise directly the work activity.

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Operating procedures or other relevant documents shall identify those control room activities requiring confirmatory inspections. These may be performed by utilizing check-off sheets to double check specific operator activities, e.g. startup and shutdown procedures.

Measures shall be established for ensuring that adequate and suitable verifications by inspections, examinations and tests are prescribed and performed to assure the quality of maintenance and repair activities. Verifications should include: monitoring the maintenance and repair activities, in-process inspections at determined hold-points and final inspection and testing as necessary.

3.8.3.3. In-service inspection

During the operating life of a nuclear power plant it is necessary to subject parts of the plant to periodic in-service inspection. The operating organization shall be responsible for the establishment and implementation of the in-service inspection programme. The quality assurance programme for operation shall be applied as appropriate to all activities associated with the establishment and implementation of the in-service inspection programme.

When in-service inspection is provided by an off-site organization, the operating organization shall ensure by surveillance and audit that the inspection is performed in accordance with approved procedures.

Information concerning in-service inspection activities can be found in the Safety Guide on In-Service Inspection for Nuclear Power Plants (IAEA Safety Series No. 50-SG-02).3.8.4. Surveillance o f activities

Measures shall be established for surveillance of operational activities important to safety. This includes monitoring of: plant operation, emergency drills, preventive maintenance, radiation protection, provisions for fire protection, fuel handling, environmental radiation monitoring, radioactive waste handling, packaging and shipping of radioactive material, etc. Surveillance shall also be extended to functional testing, non-destructive examinations associated with in-service inspection, and monitoring of the performance and results of equipment testing required by codes and standards as well as other activities pertinent to the safety of reactor operation. Personnel performing surveillance activities shall document and report deficiencies to plant management.3.8.5. Testing

The test programme shall cover all tests required by the Operation Code including:

(1) Tests during the initial operational phase: (a) to demonstrate the performance of systems that could not be tested prior to operation; (b) to

26


confirm those physical parameters and physical characteristics that need to be known but which could not have been accurately predicted; and(c) to confirm that plant behaviour conforms to applicable safety requirements.

(2) Surveillance (periodic) tests during the operational phase to ensure that failures or substandard performance do not remain undetected and that the required reliability of systems is maintained. The testing programme shall be developed before the components and systems are declared available for service.

(3) Tests during the operational phase to demonstrate satisfactory performance following plant maintenance, modifications or procedural changes.

Additional information on testing can be found in the Safety Guides on Commissioning Procedures for Nuclear Power Plants (IAEA Safety Series No. 50-SG-04), Maintenance of Nuclear Power Plants (IAEA Safety Series No. 50-SG-07), and Surveillance of Items Important to Safety in Nuclear Power Plants (IAEA Safety Series No. 50-SG-08).

3.8.6. Inspection and test procedures and reports

Inspection and test procedures shall be documented and shall conform to the general provisions of Section 3.1.3.4 of this Guide.

Where tests and inspections are to be witnessed, the respective procedure shall identify hold-points in the sequence to permit witnessing. The procedure shall require appropriate approval for the work to continue beyond the designated hold-point.

Test and inspection results shall be documented and evaluated by authorized personnel to ensure that all requirements have been satisfied.

The test and inspection reports shall include a record of the data, as-found conditions, corrective actions performed (if any), as-left conditions, and identification of those performing the tests or inspections.

3.8. 7. Calibration and control o f measuring and test equipment

Measures shall be implemented to ensure that the following measuring and test equipment used during operation are of the proper type, have the proper range, accuracy and precision and are in the proper condition to establish conformance to specified requirements:

— instrumentation for systems important to safety;— gauges, instruments and other equipment used for inspections, examination

and tests (this includes both permanently installed equipment and portableor temporarily installed equipment);

— portable (derived) standards and laboratory standards used for calibration.

27


The method and interval of calibration shall be defined on the basis of the type of equipment, its stability and reliability characteristics, the accuracies required and other relevant factors.

All such equipment shall be adjusted, maintained and calibrated against equipment having a known relationship to nationally recognized standards in order to ensure that it is accurate within required limits when it is used for operation activities. Where no such national standard exists, the basis for calibration shall be documented.

When deviations beyond prescribed limits are detected during calibration, an evaluation shall be made of the validity of previous measurements and tests and the acceptance of results based on such measurements and tests shall be reassessed.

Records of adjustment, maintenance and calibration shall be maintained and, where possible, equipment shall be suitably marked to indicate its calibration status.

3.9. Non-conformance control

Measures shall be established to identify, report, review, dispose of, control and document items and activities that do not conform to or are not performed according to specified requirements. Detected non-conforming items shall be suitably identified by marking, tagging or other acceptable methods. Nonconformance reports shall be sufficiently detailed to allow proper review, evaluation and disposition. Individuals responsible for the review and disposition shall be identified and shall as appropriate include the design organization.

3.10. Corrective action

The requirements of Section 11 of the Quality Assurance Code shall be applied to all aspects of the programme. For significant conditions adverse to quality, the cause shall be determined and corrective action taken to prevent repetition. The individual responsible for implementing corrective actions shall be identified. Information to be reviewed for corrective actions includes suchitems as:

(1) Violations of procedures(2) Non-conformances and equipment failures(3) Programme deficiencies discovered through audit or review(4) Violation of radiation exposure or release limits, or the occurrence of

situations which might lead to such violations(5) Other abnormal occurrences.

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3.11. Assessments, reviews and audits

3.11.1. Assessments

The effectiveness of plant operation shall be assessed by ongoing analyses of the significant factors influencing plant operation. The analyses should cover the following:

(1) Significant operating abnormalities or deviations from expected plant performance

(2) Changes to operating procedures and equipment or equipment tests and experiments

(3) Operating experience and characteristics(4) Equipment repair, adjustment and replacement trends(5) Actions taken to correct or mitigate abnormal occurrences(6) Unanticipated design/operating deficiencies.Trend analyses shall also be conducted on results of non-conformance reports,

routine inspection and verification results and the findings from the in-service inspection and audit programmes.

3.11.2. Reviews by plant management

In order to keep abreast of general plant conditions and to verify that the day to day operating activities are conducted safely and in accordance with applicable administrative controls, the plant management shall ensure that the normal duties of plant supervisory personnel include timely and continuing monitoring of operating activities. This monitoring is considered to be an integral part of the routine supervisory function and is important to the safety of plant operation.

The plant management shall perform formal reviews, periodically and as the situation demands, to evaluate plant operations and documentation, to examine deficiencies, to evaluate corrective actions and to plan future activities. The important elements of the reviews shall be documented.

3.11.3. Independent review

A system of independent review shall be established. This shall use appropriately qualified personnel not directly involved in the day to day operation of the plant to review important activities and changes during operation and to detect trends which might not be apparent to a day to day observer. These personnel shall have access to all information necessary to perform the review.

Items subject to this independent review should include:(1) Significant changes to procedures

29


(2) Proposed plant modifications which involve:— changes in operational limits and conditions— changes in the previously approved design intent— an unreviewed safety question

(3) Reports of abnormal occurrences and significant equipment failures(4) Audit reports(5) Any other matter involving safe operation of the nuclear power plant

which an independent reviewer deems appropriate for consideration, or which is referred to the independent reviewers by the operating organization or other organizational units.

3.11.3.1. Personnel

Personnel assigned responsibility for independent reviews shall be specified, in terms of both number and technical training, and shall collectively have the experience and competence required to review problems in the following areas:

— Nuclear power plant operations— Nuclear engineering— Chemistry and radiochemistry— Metallurgy— Non-destructive testing— Instrumentation and control— Radiological safety— Mechanical engineering— Electrical engineering— Administrative controls and quality assurance practices— Emergency plans and related organization, procedures and equipment— Human engineering— Other appropriate fields associated with the unique characteristics of the

nuclear power plant involved.An individual may possess competence in more than one speciality area.

3.11.4. Audits

A comprehensive system of planned and documented audits shall be carried out to verify the implementation and effectiveness of the quality assurance programme. Audits of selected aspects shall be performed with a frequency related to their safety significance. An audit of all aspects important to safety functions should be completed within a period of two years.

Audits should be performed of the following elements at greater frequencies:(1) The results of actions taken to correct deficiencies that affect nuclear

safety and occur in plant equipment, structures, systems, or method of operation (at least once every six months).

30


(2) The conformance of plant operation to provisions contained within the operational limits and conditions and applicable licence conditions(at least once every twelve months).

(3) The activities, training and qualifications of the plant staff (at least once every twelve months).

Audits shall include, as a minimum, verification of compliance with and effectiveness of implementation of: internal rules; procedures (e.g. procedures for operation, procurement, maintenance, modification, refuelling, surveillance, test, security, radiation exposure control, and the emergency plan); regulations and licence provisions; programmes for training and retraining; qualification and activities of operating staff; corrective actions taken following abnormal occurrences and record keeping. Audits should also determine the adequacy of plant management and of independent technical review activities. Written reports of audits shall be submitted to appropriate levels of management, including those having responsibility in the area audited.

Audits shall be planned, performed and reported in conformance with the provisions of IAEA Safety Series No. 50-SG-QA 10.

3.12. Records

Information on the handling of quality assurance records can be found in IAEA Safety Series No. 50-SG-QA2.

4. QUALITY ASSURANCE PROGRAMME DURING DECOMMISSIONING

4.1. General

The Operation Code requires that decommissioning be conducted in accordance with a planned decommissioning programme in order to ensure safety. The necessary organizational arrangements and decommissioning programme shall be established and shall include all the steps that can be reasonably taken to ensure safety with the minimum of surveillance after decommissioning has been completed. To this end, a decommissioning quality assurance programme shall be established and implemented.

31


4.2. Scope

The quality assurance programme shall cover all items and activities that could lead to undue radiation exposure of plant personnel or members of the public from final plant shutdown to the final stabilized state. The programme shall be suited to the decommissioning process whether it will be dismantling or decontamination or entombment of structures in order that the dispersion of the radiological inventory be prevented. The programme shall also provide measures to detect possible radioactive release and initiate corrective action.

32


DEFINITIONSThe following definitions are intended for use in the NUSS programme and

may not necessarily conform to definitions adopted elsewhere for international use. Items marked with an asterisk have been taken from the list o f definitions included in the approved Codes o f Practice published under the NUSS programme.

*Audit

A documented activity performed to determine by investigation, examination and evaluation of Objective Evidence the adequacy of, and adherence to, established procedures, instructions, Specifications, codes, standards, administrative or operational programmes and other applicable documents, and the effectiveness of implementation.

Disposition

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

♦Documentation

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

*Examination

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

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

1 Quality Assurance Examination is usually non-destructive and includes simple physical manipulation, gauging and measurement.

33


Item

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

*N on-conformance

A deficiency in characteristics, documentation or procedure which renders the quality of an Item unacceptable or indeterminate.

*Objective Evidence

Qualitative or quantitative information, record or statement of fact, pertaining to the quality of an Item or service, which is based on observation, measurement or test and which can be verified.

*Quality Assurance

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

*Quality Control

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

*Records

Documents which furnish Objective Evidence of the quality of Items and of activities affecting quality.

Services

The performance by a Supplier of activities such as design, fabrication, Inspection, non-destructive Examination, repair or installation.

* Specification

A written statement of requirements to be satisfied by a product, a material or a process, indicating the procedure by means of which it may be determined whether the specified requirements are satisfied.

34


Supplier

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

Supplier Evaluation

An appraisal to determine whether or not a management system is capable of producing a product or service of a stated quality, and generating evidence that supports decisions on acceptability.

Surveillance

The act of monitoring or observing to verify whether an item or activity conforms to specified requirements.

Surveillance Testing

Periodic testing to verify that structures, systems and components continue to function or are in a state of readiness to perform their functions.*Testing

The determination or verification of the capability of an Item to meet specified requirements by subjecting the Item to a set of physical, chemical, environmental or operational conditions.

Verification

The act of reviewing, inspecting, testing, checking, auditing or otherwise determining and documenting whether items, processes, services or documents conform to specified requirements.

35



LIST OF PARTICIPANTSWORKING GROUP

Dates of meeting: 13 to 17 August 1984

Consultants

Mullan, J. Canada

Koutsky, J. Czechoslovakia

Eschbach, C. France

Vessely, J.E. United States of America

TECHNICAL REVIEW COMMITTEE (TRC) - QUALITY ASSURANCEDates of meetings: 1 to 5 October 1984, 30 September to 4 October 1985

Members and alternates participating in the meetings

Morrison, W.M. (Chairman) United States of America

Thomas, R.A. Canada

Koutsky, J. Czechoslovakia

Eschbach, C.Fonne, C. FranceVaujour, J.

Balaramamoorthy, K. IndiaRao. V.S.G. n 18

Maniori, D. Italy

Aikawa, K.Ando, Y. .Arii, M. ,apanNaghoshi, H.

Santoma, L. Spain

Fowler, J.L. United KingdomHorne, G.S.

Participant from international organization

Loosemore, K. International Organization for Standardization

IAEA staff members

Raisic, N. Scientific Secretary (Quality Assurance)

Wald, F.

37


SENIOR ADVISORY GROUP (SAG)

Dates of meetings: 5 to 9 November 1984, 9 to 13 December 1985

Members and alternates participating in the meetings

Hurst, D. (Chairman)

Paganini, C.

Kfiz, Z.

Messiah, A.

Buchler, H. Hofmann, W.

Dastidar, P.R.

Suguri, S.

Jansson, E.

Naegelin, R.

Isaev, A.

Gronov, W.S.

Minogue, R.B.

Canada

Argentina

Czechoslovakia

France

Federal Republic of Germany

India

Japan

Sweden

Switzerland

Union of Soviet Socialist Republics

United Kingdom

United States of America

Participants from international organizations

Pele, J.

Becker, K.Nilson, R.

Beraud, G. (Observer)

Haussermann, W.

Commission of the European Communities

International Organization for Standardization

International Union of Producers and Distributors of Electrical Energy (UNIPEDE)

OECD Nuclear Energy Agency

IAEA staff members

Raisic, N.

Iansiti, E.

Scientific Secretary (Quality Assurance)

Scientific Secretary (SAG)

Participants from TRC — Quality Assurance

Morrison, W.

Yaremy, E M.

Chairman of TRC — Quality Assurance

Scientific Secretary (SAG)

38


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

1. Governmental organization

Code o f Practice

50-C-G Governmental organization for theregulation of nuclear power plants

Safety Guides

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

50-SG-G2 Information to be submitted insupport of licensing applications for nuclear power plants

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

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

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

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

50-SG-G9 Regulations and guides for nuclearpower plants

Published 1978

Published 1979

Published 1979

Published 1980

Published 1980

Published 1982

Published 1982

Published 1984

39


Safety Series TitleNo.

Publication dateo f 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-S 8

50-SG-S9 50-SG-S 10A

50-SG-S 1 OB

2. Siting

Safety in nuclear power plant siting Published 1978

Earthquakes and associated topics in relation to nuclear power plant sitingSeismic analysis and testing of nuclear power plantsAtmospheric dispersion in nuclear power plant sitingSite selection and evaluation for nuclear power plants with respect to population distributionExternal man-induced events in relation to nuclear power plant sitingHydrological dispersion of radioactive material in relation to nuclear power plant sitingNuclear power plant siting: hydrogeologic aspectsSafety aspects of the foundations of nuclear power plantsSite survey for nuclear power plantsDesign basis flood for nuclear power plants on river sitesDesign basis flood for nuclear power plants on coastal sites

Published 1979

Published 1979

Published 1980

Published 1980

Published 1981

Published 1985

Published 1984

Published 1984 Published 1983

Published 1983

40




50-SG-S 11A

50-SG-S 1 IB

Code o f Practice

50-C-D

Safety Guides

50-SG-D1

50-SG-D2

50-SG-D3

50-SG-D4

50-SG-D5

50-SG-D6

50-SG-D7

Extreme meteorological events in nuclear power plant siting, excluding tropical cyclonesDesign basis tropical cyclone for nuclear power plants

3. Design

Design for safety of nuclear power plants

Safety functions and component classification for BWR, PWR and PTRFire protection in nuclear power plantsProtection system and related features in nuclear power plantsProtection against internally generated missiles and their secondary effects in nuclear power plantsExternal man-induced events in relation to nuclear power plant designUltimate heat sink and directly associated heat transport systems for nuclear power plantsEmergency power systems at nuclear power plants

Published 1981

Published 1984

Published 1978

Published 1979

Published 1979

Published 1980

Published 1980

Published 1982

Published 1981

Published 1982

41



Publication dateof English version

50-SG-D8

50-SG-D9

50-SG-D10

50-SG-D11

50-SG-D12

50-SG-D13

50-SG-D14

Code o f Practice 50-C-0

Safety Guides 50-SG-01

50-SG-02

50-SG-03

Safety-related instrumentation and control systems for nuclear power plantsDesign aspects of radiation protection for nuclear power plantsFuel handling and storage systems in nuclear power plantsGeneral design safety principles for nuclear power plantsDesign of the reactor containment systems in nuclear power plantsReactor coolant and associated systems in nuclear power plantsDesign for reactor core safety in nuclear power plants

4. Operation

Safety in nuclear power plant operation, including commissioning and decommissioning

Staffing of nuclear power plants and the recruitment, training and authorization of operating personnelIn-service inspection for nuclear power plantsOperational limits and conditions for nuclear power plants

Published 1984

Published 1985

Published 1984

Published 1986

Published 1985

Published 1978

Published 1979

Published 1980

Published 1979

42




50-SG-04

50-SG-05

50-SG-06

50-SG-0750-SG-08

50-SG-09

50-SG-010

50-SG-011

Code o f Practice 50-C-QA

Safety Guides 50-SG-QA 1

50-SG-QA2

Commissioning procedures for nuclear power plantsRadiation protection during operation of nuclear power plantsPreparedness of the operating organization (licensee) for emergencies at nuclear power plantsMaintenance of nuclear power plantsSurveillance of items important to safety in nuclear power plantsManagement of nuclear power plants for safe operationSafety aspectsof core management and fuel handling for nuclear power plantsOperational management of radioactive effluents and wastes arising in nuclear power plants

5. Quality assurance

Quality assurance for safety in nuclear power plants

Establishing the quality assurance programme for a nuclear power plant projectQuality assurance records system for nuclear power plants

Published 1980

Published 1983

Published 1982

Published 1982 Published 1982

Published 1984

Published 1985

Published 1978

Published 1984

Published 1979

43



Publication dateof English version

50-SG-QA3

50-SG-QA4

50-SG-QA5

50-SG-QA6

50-SG-QA7

50-SG-QA8

50-SG-QA10

50-SG-QA11

Quality assurance in the procurement of items and services for nuclear power plantsQuality assurance during site construction of nuclear power plantsQuality assurance during operation of nuclear power plantsQuality assurance in the design of nuclear power plantsQuality assurance organization for nuclear power plantsQuality assurance in the manufacture of items for nuclear power plantsQuality assurance auditing for nuclear power plantsQuality assurance in the procurement, design and manufacture of nuclear fuel assemblies

Published 1979

Published 1981

Published 1981

Published 1981

Published 1983

Published 1981

Published 1980

Published 1983

44


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IN T E R N A T IO N A L S U B J E C T G R O U P : IIA T O M IC E N E R G Y A G E N C Y Nuclear Safety and Environmental Protection/Nuclear SafetyV IE N N A , 1986 P R IC E : Austrian Schillings 140,—
