The PSA analysis of PWR emergency coolant injection availability following SBLOCA

• Autorzy: Borysiewicz M. , Bronowska K. , Kopka P. , Kowal K. , Kwiatkowski T. , Prusiński A. M. , Prusiński P. A. , Siess G.
• Języki publikacji: EN

Abstrakty

EN

The aim of this article is to briefly introduce the probabilistic safety assessment (PSA) of nuclear power plants (NPPs), its scope, main concepts and application to a real case. The results of analysis presented here have been obtained by the Probabilistic Safety Analysis Group (GPSA) at the National Centre for Nuclear Research (NCBJ, Otwock) as a part of the work done for the Polish National Atomic Energy Agency (NAEA). As a reference, NPP Surry Unit 1 (USA), equipped with 800 MWe Westinghouse triple-loop PWR (pressurized water reactor), has been chosen. The emergency coolant injection (ECI) function availability following the small break loss of coolant accident (SBLOCA) was thoroughly analyzed. The approach and data, which were adopted for the selected part of the SBLOCA sequences, were those used in the U.S. NRC Reactor Safety Study (WASH-1400). As a result of this study, the SBLOCA event tree, including ECI systems, i.e. high pressure injection system (HPIS) and auxiliary feedwater system (AFWS) reliability models, was developed and quantified. The probability of each accident sequence was evaluated using Saphire v.8, the PSA software by U.S. NRC. The choice of the software was based on earlier PSA software study. The failure probability of at least one of the considered safety systems – P(FAIL) is equal to 5.76E-3 and the most pessimistic accident branch (unavailability of both HPIS and AFWS) is about 0.05% of P(FAIL). These results were obtained based on assumption that the SBLOCA has occured. The most significant failure components are those corresponding to charging pumps unavailability, loss of electric power and human errors.

Słowa kluczowe

EN

probabilistic safety assessment (PSA); small break LOCA (SBLOCA); emergency coolant injection (ECI); high pressure injection system (HPIS); auxiliary feedwater system (AFWS)

• Wydawca: Institute of Nuclear Chemistry and Technology
• Czasopismo: Nukleonika
• Rocznik: 2013
• Tom: Vol. 58, No. 2
• Strony: 307--316
• Opis fizyczny: Bibliogr. 8 poz., rys.

Twórcy

autor

Borysiewicz M.

autor

Bronowska K.

autor

Kopka P.

autor

Kowal K.

autor

Kwiatkowski T.

autor

Prusiński A. M.

autor

Prusiński P. A.

autor

Siess G.

Bibliografia

• 1. Borysiewicz M (2010) The PSA (Probabilistic Safety Assessment) technique in defining safety regulations for nuclear power plants. IEA POLATOM, Otwock-Świerk, http://ncbj.gov.pl/raporty/
• 2. Borysiewicz M, Potempski S, Prusiński P, Wasiuk A (2010) Evaluation of software for analysing event/fault trees from the nuclear power plant PSA point of view. IEA POLATOM, Otwock-Świerk, http://ncbj.gov.pl/raporty/
• 3. IAEA (1999) Basic safety principles for nuclear power plants. IAEA INSAG-12. International Atomic Energy Agency, Vienna
• 4. IAEA (2010) Development and application of Level-1 Probabilistic Safety Assessment for nuclear power plants. IAEA SSG-3. International Atomic Energy Agency, Vienna
• 5. IAEA (2010) Development and application of Level-2 Probabilistic Safety Assessment for nuclear power plants. IAEA SSG-4. International Atomic Energy Agency, Vienna
• 6. Pershagen B (2009) Light water reactor safety. Pergamon Press, Nyköping
• 7. Regulation of the Polish Council of Ministers of 31 August 2012 on the scope and methods of safety analyses performed before applying for an authorization of a nuclear facility construction, and the scope of the preliminary safety assessment report for the nuclear facility. Dz U (Law Gazette) 2012 no 0 item 1043 (in Polish)
• 8 . US Nuclear Regulatory Commission (1975) Reactor Safety Study – An assessment of accident risks in U S commercial nuclear power plants. U S NRC NUREG 75/014. Washington, DC