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IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Workshop Information IAEA Workshop Safety Assessment Process. Plant Modification.

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Presentation on theme: "IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Workshop Information IAEA Workshop Safety Assessment Process. Plant Modification."— Presentation transcript:

1 IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Workshop Information IAEA Workshop Safety Assessment Process. Plant Modification. Regulatory point of view Lecturer Lesson II 2_3 City, Country XX - XX Month, Year

2 IAEA Training Course on Safety Assessment 2 Basis Principles of Safety Assessment (1/4) –Safety Assessment is a basic task of designer, operator and regulator. –It is connected to: Design and licensing of a new facility. Periodic safety review. Modification of an older plant. Continuous evaluation of safety performance of an operating plant. –Reference material: “Safety Assessment and Verification for Nuclear Power Plants” (IAEA, Safety Guide, No. NS- G-1.2, Vienna, Nov. 2001).

3 IAEA Training Course on Safety Assessment 3 Basis Principles of Safety Assessment (2/4) –This presentation concentrates to regulatory safety assessment activities. –Tools applied vary from engineering judgement to use of complicated computer codes depending of the nature of issue and of capabilities of the Regulatory Body. (1)Regulatory Body may employ experts or expert organisations for the evaluation of safety matters arising during its regulatory activities.

4 IAEA Training Course on Safety Assessment 4 Basis Principles of Safety Assessment (3/4) –Role of TSOs in the assessment: Independency in tools and manpower (e.g. Alternative codes, not “contaminated” manpower) Competency - regulatory R&D programme. –International co-operation and information exchange: Use TSOs from abroad. Assistance projects of:  IAEA- methodology (Guidelines) - missions (e.g. IPERS for seismic and PSA) - workshops - training courses - scientific visits

5 IAEA Training Course on Safety Assessment 5 Basis Principles of Safety Assessment (4/4) Participation in work of different groups and committees.  EC- TACIS, PHARE-projects (RAM, TSO)  OECD-NEA (CNRA, CSNI and subgroups)  NERS - Network Countries with Small Nuclear programmes  EC - CONCERT, ENIS-G, NRWG  VVER Regulators Forum Bilateral contacts

6 IAEA Training Course on Safety Assessment 6 The basic process for modification (*: including regulatory inspection (if necessary)). The basic process for modification (*: including regulatory inspection (if necessary)).

7 IAEA Training Course on Safety Assessment 7 Reference material; “Modifications to Nuclear Power Plants” (IAEA, Safety Guide, No. NS-G-2.3, Vienna, October 2001). As example: Hungarian approach to NPP modification.

8 IAEA Training Course on Safety Assessment 8 Legal Basis of Modification (1/3) –Act CXVI of 1996 on Atomic Energy, Section 17. (excerpts). “The following activities fall into the scope of HAEA: a)Nuclear safety licensing required for the siting, construction, enlargement, commissioning, operation, modification, putting out of operation, decommissioning of nuclear facilities;” …… b)“With regard to nuclear equipment, nuclear safety and technical radiation protection licensing and inspection of activities related to the design, manufacture, installation (fitting in) commissioning, operation, modification (repair), imports form abroad, putting out of operation and decommissioning;”

9 IAEA Training Course on Safety Assessment 9 Legal Basis of Modification (2/3) –Government Decree 108/1997 (VI.25) Korm. on the Procedures of HAEA in Nuclear Safety Regulatory Matters, and its Attachments Nuclear Safety Regulations, Volumes 1.-5.) Vol.1. Regulatory Procedures for NPPs. Chapter 4. Licensing of Modifications:  Reason and scope of modifications.  Licensing process and its requirements.  Requirements for contents of submission of license (e.g. Reason and objective of modification, design basis, changes in FSAR, description of equipment/system to be modified, etc.) –Safety Guidelines issued by DG of HAEA (relevant to the subject) Nr.1.5 Licensing Documentation for Modification of Nuclear Power Plant Systems and Components

10 IAEA Training Course on Safety Assessment 10 Legal Basis of Modification (3/3) Nr. 1.13Regulatory Procedure for Regulatory Evaluation (review and assessment) of Licensee Request (draft). Nr. 1.24Periodic Reporting Obligations of NPPs. Nr. 3.10Methodologies for Analysis of Safety Effects of Modifications (draft). –Position/declaration of the Head of the HAEA/NSD on the licensing process of temporary modifications. Additional condition for the case of abnormal (accident or emergency) situation when immediate modification action without regulatory approval is allowed to be taken for the sake of accident prevention or management. (After getting experience enough in its application it will become part of guideline Nr. 1.5).

11 IAEA Training Course on Safety Assessment 11 Licensing of Modification (1/3) –Multistep Process: Modification license of principle or conceptual modification license (analysis for safety effects of modification - technical design). Manufacturing (domestic product) or import (foreign product9 license (features and technical specification of equipment and its components, harmonisation of data, parameters and conditions quantification, QA, etc). Assembly/erection license (execution of the modification on the site without connection to any other (not modified) system, structures and components).

12 IAEA Training Course on Safety Assessment 12 Licensing of Modification (2/3) –Steps can be drawn together if the issue is simple –Different requirements according to safety significance:  Modified SSC is classified by safety  Activity is relevant to safety Modification license (on basis of construction plants, test programme, operational limits and conditions, changes (if any) in conception, commissioning process, (QA). Operational license (for long term operation). Regulatory license is needed only if: Independent expert assessment is required to attach only in safety classes No. 1. And 2. Manufacturing/import license as well as assembly/erection license is not required from Regulatory Body but from Safety Division of the plant in safety class No. 3.

13 IAEA Training Course on Safety Assessment 13 Initiation of Modification (3/3) Sources of initiations Regulatory Body –New Requirements Regulations Safety concerns –Findings of Events Root causes Lessons learned –Results of Regulatory R&D Projects Utility/Licensee –On-Compliences of (new) Regulations –Safety Upgrading Measures of Periodic Safety Review –Feedback of Operational Experiences Failure statistics Repair & maintenance reports –Efficiency Improvements Refurbishments Organisational structure Fuel cycle


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