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