Ageing PSA as a support for effective ageing management

• Autorzy: Berg H. P. , Volkanovski A.
• Języki publikacji: EN

Abstrakty

EN

Because of the growing operational age of nuclear power plants, the ageing management of structures, systems and components used in these plants is gaining an important role. Technical systems are subject to timedependent and operationally caused ageing phenomena with modifications of originally given characteristics and, thus, of relevance in terms of safety. Especially physical ageing is of importance. Therefore, a comprehensive ageing management is required. In the context of an integrated safety management it has to be shown how to integrate the safety related issues of ageing into probabilistic safety assessment (PSA). In particular the question is to be answered whether the effort for the execution of an ageing PSA is justified, in particular if the safety significant effects of ageing can be identified and quantitatively estimated. Method for prioritization of the components in the nuclear power plant considering implication of their ageing on safety of the nuclear power plant is presented. On the basis of an actual report on ageing management in German nuclear power plants and a literature survey, this paper tries to estimate the necessity and value for the introduction of an ageing PSA in Germany.

Słowa kluczowe

EN

ageing; ageing management; probabilistic safety assessment; prioritization; management of activities

• Wydawca: Polskie Towarzystwo Bezpieczeństwa i Niezawodności
• Czasopismo: Journal of Polish Safety and Reliability Association
• Rocznik: 2014
• Tom: Vol. 5, No. 2
• Strony: 1--10
• Opis fizyczny: Bibliogr. 29 poz., tab., wykr.

Twórcy

autor

Berg H. P.

• Bundesamt für Strahlenschutz, Salzgitter, Germany

autor

Volkanovski A.

• Jožef Stefan Institute, Ljubljana, Slovenia

Bibliografia

• [1] Atwood, C. et al. (2006). APSA in risk informed applications, living report, available under: http://safelife.jrc.ec.europa.eu/APSA/results.htm.
• [2] Bejdakic, E., Krauß, M. & Berg, H.P. (2011). Ansätze zur Berücksichtigung von Alterungseffekten in einer Probabilistische Sicherheitsanalyse., Probabilistische Sicherheitsanalysen in der Kerntechnik, PSA in der SÜ – und in Zukunft? Proc. of the Symposium ’11, May 2627, 2011, Heidelberg (in German).
• [3] Bundesamt für Strahlenschutz (1996). Ageing management in nuclear power plants. Proc. of the 4. KT/KTA-Winterseminar, 25. und 26. January 1996 in Salzgitter, BfS-Report KT-13/96, Mai 1996 (in German).
• [4] Canadian Nuclear Safety Commission (CNSC) (2014). Fitness for Service: Aging Management, Regulatory Document REGDOC-2.6.3, March 2014.
• [5] Čepin, M. Analysis of truncation limit in probabilistic safety assessment. Reliability Engineering and System Safety, Vol. 87 (3), 395403.
• [6] Čepin, M. & Volkanovski, A. (2009). Consideration of ageing within probabilistic safety assessment models and results. Kerntechnik, Vol. 74, No. 3, 140-149.
• [7] Commission on Reactor Safety (RSK) (2004). Management of ageing processes at nuclear power plants, RSK Recommendation, July 22, 2004.
• [8] Investigation of ageing effects using probabilistic safety assessment (2010). Proc. of the European Workshop on Probabilistic Safety Assessment organised at Gösgen-Däniken Nuclear Power Plant, Switzerland, 9th & 10th November 2010 edited by Mirela Nitoi, EUR 25102-2011.
• [9] Kančev, D. & Čepin, M. (2011). Ageing within PSA: development of an analytical unavailability model and its application. European Nuclear Young Generation Forum, Prague, May 17-25.
• [10] Kelly, D.L., Rodionov, A. & Klügel, J.U. (2008). Practical issues in component ageing analysis. Proc. of the International Topical Meeting on Probabilistic Safety Assessment, (PSA 2008), “Challenges to PSA during the nuclear renaissance”, Knoxville, Tennessee.
• [11] Krauß, M., Bejdakic, E., Mahlke, J. & Berg, H.P (2011). Ageing PSA: A complement to ageing management in German nuclear power plants?, Proc. of the Nordic PSA Conference – Castle Meeting 2011, September 5-6.
• [12] Nitoi, M. & Pavelescu, M. (2010). Modelling ageing at the level of electrical systems from Cernavoda NPP. Rom. Journ. Phys., Vol. 55, Nos. 1-2, 53-67.
• [13] Nitoi, M. & Rodionov, A. (2008). Qualitative approach for selection of systems, structures and components to be considered in ageing PSA, JRC Scientific and Technical Reports, EUR 23446, European Communities.
• [14] Nitoi, M. & Rodionov, A. (2010). Guideline for selection of systems, structures and components to be considered in ageing PSA, JRC Scientific and Technical Reports, EUR 24503, European Communities.
• [15] Nitoi, M., Turcu, I., Bruynooghe, C. & Pavalescu, M. (2011). Prioritization of components important for safety and sensitive to ageing. Application for TRIGA reactor. Progress in Nuclear Energy, Volume 53, Issue 4, 336-343.
• [16] Nuclear Safety Standards Commission (2010). Ageing-management in nuclear power plants, KTA 1403, November 2010.
• [17] Panel on Public Affairs (APS) - POPA (2013). Renewing licenses for the Nation’s Nuclear Power Plants, December 2013.
• [18] Petkov, G. (2008). Application of implicit and explicit reliability models for incorporating ageing effects, Presentation, June 3, 2008.
• [19] Petkov, G. & Pekov, M. Ageing effects sensitivity analysis by dynamic system reliability methods (GO-FLOW and ATRD), contribution available under: http://safelife.jrc.ec.europa.eu/APSA/documents/ Petkov_doc.pdf.
• [20] Poghosyan, Sh., Amirjanyan, A., Nitoi, M. & Šimić, Z. (2014). Application of ageing PSA model for systems’ risk-informed classification. Proc. ESREL 2013, Safety, Reliability and Risk Analysis: Beyond the Horizon – Steenbergen et al. (Eds), Taylor & Francis Group, 3115-3119.
• [21] Rodionov, A. (2008). PSA as a tool for evaluation of ageing effects on the safety of NPPs. Proc. of the International Topical Meeting on Probabilistic Safety Assessment, (PSA 2008), “Challenges to PSA during the nuclear renaissance”, Knoxville, Tennessee.
• [22] Rodionov, A. (2009). A case study on incorporation of ageing effects into the PSA model, JRC Scientific and Technical Reports, EUR 23930, European Communities.
• [23] Rodionov, A., Kelly, D. & Klügel, J.U. (2009). Guidelines for analysis of data related to ageing of nuclear power plant components and systems. JRC Scientific and Technical Reports, EUR 23954, European Communities.
• [24] U.S. Nuclear Regulatory Commission – NRC (1988). Prioritization of recommended components for further aging research, NUREG/CR5248, PN L-6701, November 1988.
• [25] U.S. Nuclear Regulatory Commission – NRC (1990). Evaluations of core melt frequency effects due to component aging and maintenance, NUREG/CR-5510, SAIC49/1744, June 1990.
• [26] U.S. Nuclear Regulatory Commission – NRC (1992). Approaches for age-dependent probabilistic safety assessments with emphasis on prioritization and sensitivity studies, NUREG/CR5587, SAIC-92/1137, August 1992.
• [27] U.S. Nuclear Regulatory Commission – NRC (2014). Ongoing staff activities to assess regulatory considerations for power reactor subsequent license renewal, SECY-14-0016, January 31, 2014.
• [28] Volkanovski, A. (2010). The method for assessment of ageing based on the results of PSA. Proc. of the International Conference Nuclear Energy for New Europe 2010, September 6 -9, Portoroz, Slovenia, 706.1-706.8.
• [29] Volkanovski, A. (2012). Method for assessment of ageing based on PSA results, Nuclear Engineering and Design, Volume 246, May 2012, 141-146, http://dx.doi.org/10.1016/j.nucengdes.2011.06.03 7.