VGB POWERTECH 7 (2021) - International Journal for Generation and Storage of Electricity and Heat

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Digital transformation of the coal sector VGB PowerTech 7 l 2021 UMFANGREICHES KNOW-HOW FÜR DIE BRANCHE WÖRTERBUCH MIT LEXIKONCHARAKTER Dieses Wörterbuch unterstützt bei: • Der Abwicklung von Exportaufträgen, der Auswertung und Anwendung ausländischer, technischer Regelwerke und Dokumentationen sowie bei technischen Übersetzungen • Dampfturbinen, Gasturbinen, Expander, Verdichter, Wasserturbinen und verwandte Technologien Jetzt im Shop bestellen und Wissen sichern! www.vulkan-shop.de Heinz-Peter Schmitz 1. Auflage 2020 Artikelnummer: 35073 Auch als eBook erhältlich. Preis: € 180,- Hochaktuell und top-relevant: Brandneu erschienen! VULKAN VERLAG. FÜR ALLE, DIE MEHR WISSEN WOLLEN. www.vulkan-verlag.de 60
VGB PowerTech 7 l 2021 Equipment selection methodology of seismic probability safety assessment for nuclear power plants Equipment selection methodology of seismic probability safety assessment for nuclear power plants Junghyun Ryu and Moosung Jae Kurzfassung Methodik der Ausrüstungsauswahl für die Sicherheitsbewertung für Erdbeben eines Kernkraftwerks Auf der Grundlage des Modells für die Wahrscheinlichkeitsbewertung der Sicherheit interner Ereignisse (PSA) beträgt die Anzahl der Basisereignisse für Strukturen, Systeme und Komponenten (SSCs), die in der PSA von Kernkraftwerken berücksichtigt werden, im Allgemeinen mehr als 1000. Wenn alle Basisereignisse im Modell der seismischen probabilistischen Sicherheitsbewertung (SPSA) berücksichtigt werden, wird das PSA-Modell übermäßig groß und das Ergebnis ist äußerst kompliziert. Bei der Berechnung der Häufigkeit seismisch bedingter auslösender Ereignisse mit Hilfe der binären Entscheidungsdiagramm-Methode ist die Anzahl der Basisereignisse begrenzt, so dass nicht alle Komponenten berücksichtigt werden können und geeignete Auswahlkriterien erforderlich sind. Um den Fall der Versagensannlyse, die das größte Budget in SPSA erfordert, zu minimieren, ist eine geeignete Auswahl der Komponenten unerlässlich. In diesem Beitrag wird nach einer Untersuchung der in Korea und den Vereinigten Staaten allgemein bei SPSA berücksichtigten Screening-Kriterien eine Methodik zur Auswahl von Ausrüstungen für SPSA vorgeschlagen, die die Bewertungsergebnisse verbessern kann. Die in diesem Beitrag vorgeschlagene Methode zur Auswahl der Komponenten trägt zu einer vernünftigen und realistischen SPSA bei, da sie alle drei Aspekte berücksichtigt, nämlich die probabilistische seismische Gefährdungsanalyse (PSHA), die seismische Fragilitätsanalyse (SFA) und die seismische Anlagenantwortanalyse (PSRA). l Authors Junghyun Ryu Moosung Jae Department of Nuclear Engineering Hanyang University, Seoul, Republic of Korea In general, based on the internal events probability safety assessment (PSA) model, the number of basic events for structures, systems and components (SSCs) considered in the PSA of nuclear power plants is more than 1000. If all basic events are considered in the seismic probabilistic safety assessment (SPSA) model, the PSA model becomes excessively large and the result is extremely complicated. On the other hand, in the case of calculating seismic-induced initiating event frequency using the binary decision diagram method, there is a limitation on the number of basic events, so all equipment cannot be included and proper screening criteria is required. In order to minimize the case for fragility analysis, which requires the largest budget in SPSA, appropriate equipment selection is essential. In this paper, after examining the screening criteria generally considered in SPSA in Korea and the United States, we propose a methodology for selecting equipment for SPSA that can improve the assessment results. In short, the equipment selection methodology proposed in this paper is expected to help with reasonable and realistic SPSA as it considers all three aspects, namely, probabilistic seismic hazard analysis (PSHA), seismic fragility analysis (SFA), and seismic plant response analysis (PSRA). 1. Introduction A typical seismic probability safety assessment (SPSA) requires geological, structural, and systems analysts. In the case of probabilistic seismic hazard analysis (PSHA), geological experts can independently perform the analysis, but structural experts performing seismic fragility analysis (SFA). Probability safety assessment (PSA) model analysts performing system analysis, cannot perform the analysis independently. Only when the analysis is performed through mutual co-operation between the two fields can a reasonable result be achieved. This is a unique characteristic of SPSA. For SPSA, a seismic equipment list (SEL) is first prepared, and reviews of the design, construction installation data, walkdown and system are conducted to analyze structures, systems and components (SSCs) that have little or no effect on the safety of the entire power plant. The final selected SSCs are reflected in the PSA model to perform SPSA. The following are the considerations in selecting a general SEL [1]: –– Identify SSCs that are important to safe shutdown from full-power PRA models. –– Identify SSCs from a review of seismic evaluation performed for the IPEEE (Individual Plant Examination for External Events). –– Identify structures and passive components that are important to the seismic response. –– Identify additional SSCs from a plant walkdown. As can be seen from the above SEL selection criteria, equipment is required systematically for the safe shutdown of a nuclear power plant, and critical equipment vulnerable to earthquakes is selected through seismic response analysis and site surveys. In this paper, we propose the equipment selection methodology that should be essential to SPSA using the characteristics of individual plants and internal events PSA for existing qualitative and ambiguous selection criteria. 2. Practices for seismic equipment selection and screening criteria In this paper, we review the practice of SEL selection and characteristics based on cases applied in Korea and the United States. In Korea, when an SPSA is performed, the SEL is selected in consideration of the general points mentioned in Chapter 1. After preparing the SEL, special screening criteria are set, which will be reviewed in detail here. Quantitative screening means that SSCs, which generally establish and meet appropriate screening criteria that are expected not to affect overall plant safety, are excluded from the SPSA model, and reflect and analyze only equipment and buildings that do not meet the screening criteria of the SPSA model. For example, there are two screening criteria: the first is the specific median accelera- 61
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