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Performance Testing of Person Passable Openings to Evaluate Accepted Risk

Nuclear Science and Engineering

Rivera, Wayne G.; Sandt, Emily S.

Researchers at Sandia National Laboratories, in conjunction with the Nuclear Energy Institute and Light Water Reactor Sustainability Programs, have conducted testing and analysis to reevaluate and redefine the minimum passible opening size through which a person can effectively pass and navigate. Physical testing with a representative population has been performed on both simple two-dimensional (rectangular and circular cross sections up to 91.4 cm in depth) and more complex three-dimensional (circular cross sections of longer lengths up to 9.1 m and changes in direction) opening configurations. The primary impact of this effort is to define the physical design in which an adversary could successfully pass through a potentially complex opening, as well as to define the designs in which an adversary would not be expected to successfully traverse a complex opening. These data can then be used to support risk-informed decision making.

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EXPLORING VITAL AREA IDENTIFICATION USING SYSTEMS-THEORETIC PROCESS ANALYSIS

Proceedings of the 2021 International Topical Meeting on Probabilistic Safety Assessment and Analysis, PSA 2021

Sandt, Emily S.; Clark, Andrew; Williams, Adam D.; Cohn, Brian C.; Osborn, Douglas M.; Aldemir, Tunc

Vital Area Identification (VAI) is an important element in securing nuclear facilities, including the range of recently proposed advanced reactors (AR). As ARs continue to develop and progress to licensure status, it will be necessary to ensure that safety analysis methods are compatible with the new reactor designs. These reactors tout inherently passive safety systems that drastically reduce the number of active components whose failures need to be considered as basic events in a Level 1 probabilistic risk assessment (PRA). Instead, ARs rely on natural processes for their safety, which may be difficult to capture through the use of fault trees (FTs) and subsequently difficult to determine the effects of lost equipment when completing a traditional VAI analysis. Traditional VAI methodology incorporates FTs from Level 1 PRA as a substantial portion of the effort to identify candidate vital area sets. The outcome of VAI is a selected set of areas deemed vital which must be protected in order to prevent radiological sabotage. An alternative methodology is proposed to inform the VAI process and selection of vital areas: Systems-Theoretic Process Analysis (STPA). STPA is a systems-based, top-down approach which analyzes a system as a hierarchical control structure composed of components (both those that are controlled and their controllers) and controlled actions taken by/acted upon those components. The control structure is then analyzed based on several situational parameters, including a time component, to produce a list of scenarios which may lead to system losses. A case study is presented to demonstrate how STPA can be used to inform VAI for ARs.

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6 Results
6 Results