The general objective of this project was to strengthen capabilities of the Hungarian Atomic Energy Authority (HAEA/NSD, and also its TSOs) whose main function is to regulate activities at the Paks NPP, the main nuclear installation in Hungary.
 
 
More specifically, the objective of the project was to assist the HAEA/NSD and its TSOs in:
 

• Task 1 Evaluation of ageing analyses
   
   
  The general objective of Task 1 was to evaluate the Ageing Management Programme (AMP) of the Paks NPP Unit 3-4 covering the systems, structures and components (SSCs) important to safety.
   
  The evaluation was based on the translated Periodic Safety Review Report (PSR Report) of the Paks NPP and on the regulatory procedures to review the plant life management programme. The Chapters 2 and 4 of the PSR Report of the Paks NPP Unit 3-4 were reviewed by the western consortium. The Periodic Safety Review of Paks NPP was conducted in 1997.
   
  The evaluation covered the methodologies for determining the scope of the AMP as well as the methods and requirements for ageing monitoring and analyses. Both the IAEA Safety Guides and the national ageing management programmes and approaches followed by the utilities in Belgium, Finland and the UK were briefly reviewed and compared to. the Hungarian approach given in the PSR Report and other technical documents.
   
  Some conclusions and recommendations were formulated within Task 1 to develop the PSR reporting and the ageing management programme of the Paks NPP. The recommendations concerned, on the one hand, general issues on the Periodic Safety Review and the Ageing Management Programme and, on the other hand, specific areas such as reactor pressure vessel surveillance and safety assessments, non-destructive inspections, and surveillance of cables and instrumentation and control (I&C).
   
  Based on the review of the PSR Report and on the exchange of technical information in the frame of working meetings, it was concluded that Paks NPP's current AMP is generally in accordance with the accepted international practices and follows the IAEA AMP recommendations.
   
  In the third step, relevant ongoing international projects and programmes relevant to the management of the ageing degradation of NPP SSCs were compiled. Several activities were identified which are focused on a better understanding of ageing degradation mechanisms as well as their prediction, monitoring and mitigation. Further participation in international collaboration was recommended as a way to timely follow new insights on ageing degradation mechanisms and their management by using the broad world-wide operating experience with LWRs and taking advantage of shared international R&D work.
   
   
  Finally, reactor pressure vessel (RPV) service life estimation procedures were discussed in-depth. For this reason, in particular, the RPV service life estimation procedures as practised for VVER- 440/213 NPPs operated in Hungary and Finland as well as for PWRs operated in the UK and Germany were compiled, and the corresponding main features of RPV surveillance programmes and pressurised thermal shock (PTS) calculations were compared, The result can be used as a basis for the further qualification of the RPV service life estimation procedures in the Paks NPP, even though direct comparability of the country-specific procedures is not given in any case since the extant conditions differ.
   
  Based on the activities performed and the results achieved, conclusions and recommendations for the ageing/life management of the Paks NPP were derived and compiled.
   
  More specifically, the task was to review 14 HAEA/NSD regulatory guides and one internal procedure and to prepare recommendations on each document made available. Those recommendations were to form the basis from which common positions were issued on four areas specified by HAEA/NSD: ageing management, equipment qualification, maintenance, licence renewal and an additional common position on an internal procedure on licence renewal. In addition, comments were developed on two specific guidelines: Pressurised Thermal Shock Analysis and Structure Condition Monitoring.
   
   
  The task outcome included conclusions and recommendations that HAEA/NSD should consider when revising their regulatory documents. The conclusions and recommendations address not only formal issues to improve the user friendliness of the guidelines, but also fundamental concepts.
   
   
   
  Beneficiary Organizations Details
  - Hungarian Atomic Energy Authority (HAEA)
  http://www.haea.gov.hu
  Project Aims
  The project main objective was to provide technical advice to the regulatory authorities for assessment of Paks NPP ageing and residual lifetime management programme.
  Project Results
   
  • Enhanced HAEA safety assessment capabilities.
  • Reviewed Paks NPP aging and residual lifetime management programme.

  The budget for this project was: 400 000 euro.
  Further Project Results
  Further information on the project could be sought from the beneficiary organization.