Title: Workshop Information
1IAEA Training Course on Safety Assessment of NPPs
to Assist Decision Making
Safety Assessment Process. Plant Modification.
Regulatory point of view
Lecturer Lesson II 2_3
IAEA Workshop
City , CountryXX - XX Month, Year
2Basis 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).
3Basis 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.
4Basis 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 RD 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
5Basis Principles of Safety Assessment (4/4)
- EC - TACIS, PHARE-projects (RAM, TSO)
- Participation in work of different groups and
committees.
- OECD-NEA (CNRA, CSNI and subgroups)
- NERS - Network Countries with Small Nuclear
programmes - EC - CONCERT, ENIS-G, NRWG
- VVER Regulators Forum
6The basic process for modification ( including
regulatory inspection (if necessary)).
7Reference material Modifications to Nuclear
Power Plants (IAEA, Safety Guide, No. NS-G-2.3,
Vienna, October 2001). As example Hungarian
approach to NPP modification.
8Legal 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
9Legal Basis of Modification (2/3)
10Legal Basis of Modification (3/3)
Nr. 1.13 Regulatory Procedure for Regulatory
Evaluation (review and assessment) of Licensee
Request (draft). Nr. 1.24 Periodic Reporting
Obligations of NPPs. Nr. 3.10 Methodologies 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).
11Licensing of Modification (1/3)
- 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).
12Licensing of Modification (2/3)
- 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).
- Steps can be drawn together if the issue is
simple - Different requirements according to safety
significance
- Regulatory license is needed only if
- Modified SSC is classified by safety
- Activity is relevant to safety
- 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.
13Initiation of Modification (3/3)
Sources of initiations
Utility/Licensee
- On-Compliences of (new) Regulations
- Safety Upgrading Measures of Periodic Safety
Review - Feedback of Operational Experiences
- Failure statistics
- Repair maintenance reports
- Refurbishments
- Organisational structure
- Fuel cycle