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Workshop Information

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Title: Workshop Information


1
IAEA 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
  • Workshop Information

IAEA Workshop
City , CountryXX - XX Month, Year
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
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
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 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

5
Basis 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
  • Bilateral contacts

6
The basic process for modification ( including
regulatory inspection (if necessary)).
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
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
Legal Basis of Modification (2/3)
10
Legal 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).

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
Licensing 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.

13
Initiation 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
  • Efficiency Improvements
  • Refurbishments
  • Organisational structure
  • Fuel cycle
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