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• W3211718309 abstract "The protection of public health and safety, and the environment from inadvertent releases of radioactive materials from nuclear power plants relies on the implementation of the defense-in-depth strategy. The term defense-in-depth evolved historically, and thus its application has not always been uniform. The use of the term in the context of the U.S. Nuclear Regulatory Commission (NRC) safety philosophy entails the reliance of a nuclear facility on successive compensatory measures in preventing accidents or mitigating damage caused by malfunctions, accidents, or naturally occurring events. The introduction of probabilistic risk analyses with NUREG-74/014 and subsequent evolution in risk assessment techniques, are leading to the implementation of risk informed regulation to ensure the safety of the public and the environment. Risk informed regulation minimizes the likelihood of overlooking potentially significant accident sequences while limiting unnecessary burdens imposed on licensees. The proposed framework merges fundamental elements of safety regulation: defense-in depth, safety margins and probabilistic risk. It formalizes the relationship between probabilistic risk assessment (PRA) methods and data, and deterministic analyses in a manner consistent with NRC's defense-in-depth philosophy. Succinctly put, the likelihood and consequences of accident scenarios are considered simultaneously and quantified by a plant safety metric. The integration of these fundamental elements into a practically applicable safety framework is consistent with the NRC policy statement on use of probabilistic risk assessment methods and the November 2002 Regulatory Guide on risk informed decisions on plant-specific changes to the licensing basis. Safety information resulting from the application of the framework supersedes traditional safety figures of merit. Safety quantifiers, referred herein as safety indices, expand on the qualifier outcomes that currently accompany fault tree analyses, e.g., OK or core damage (CD) as descriptors of fuel barrier damage state. Ideally, the plant safety metric would quantify the probability of exceeding the safety limits for each defense-in-depth barrier. Because obtaining such probabilities is beyond the state-of-the art, safety indices are conceptualized to be proxies for the probability of exceeding the safety limit for design basis accidents (DBA). A second group of safety indices is associated with beyond-DBA events, and are conceptualized to be proxies for the extent of barrier damage. As will be shown elsewhere, individual safety indices can explicitly account for code uncertainty in deterministic barrier state descriptions. The complete set of safety indices is assembled into a plant safety metric. In the assembly process, the probability of occurrence of all relevant threat events is used to weigh the safety indices and extract additional plant safety figures of merit. Thus, the proposed conceptual framework is consistent with the objectives set forth in the letter on the subject from the Advisory Committee on Reactor Safety (ACRS). The proposed method is comprehensive and spans the space from licensing to severe accidents. It relies on traditional safety concepts that are at the core of current regulatory activities. Conceptually, individual indices as well as the overall plant safety metrics are understandable to stake holders and usable by decision makers. The definition of a barrier state lends itself to applying the proposed approach to trajectories for which the independent variable is not time. For example, the approach can be applied to compare deterministic analyses for different nodalization schemes. The proposed framework is applicable to comparing plant safety states before and after a wide range of design/operating modifications. The framework is sufficiently comprehensive to be sensitive to a broad range of design modifications, changes in operating conditions and regulatory requirements. Such changes include inspection and monitoring schedules. The indices are sensitive to initial and boundary conditions that alter the safety parameter trajectory, such as source term changes, or changes in reactor coolant initial conditions following a power uprate license modification. Life extension impacts the frequency of occurrence of specific transients and will thus be directly reflected in both the plant safety index matrix and the damage state frequency matrix. Increasing fuel cycle length also has an effect on frequencies of occurrence. Foreseeable clad material changes and/or higher burnups change the safety and loss of function limits, and are thus directly reflected in clad temperature and oxidation related safety indices. Moreover, as new phenomena and initiators are either postulated or experienced, the event-scenario list can be expanded to incorporate new threats and thus modify both the plant safety index matrix and the barrier state frequency matrix. It is expected that as experience is gained with the application of the proposed methodology, the number and definition of safety-relevant intervals will evolve. In proposing the current method, the conceptual value of safety indices was of principal importance. The evolution of sets of safety indices that are adequate proxies for probability of exceeding safety limit and extent of barrier damage should be pursued. Such sets would involve assigning weights to individual safety indices to account for differing safety content and interdependencies. One final observation must be made. The small differences in frequency weighted indices and cumulative barrier state frequencies computed in the example exercise reemphasize the importance of accounting for code uncertainty as well as uncertainties in PRA data and models. Work on systematically accounting for code uncertainty in a matter consistent with the proposed framework is currently ongoing." @default.
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• W3211718309 date "2004-07-01" @default.
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• W3211718309 title "A generalized framework for assessment of safety margins in nuclear power plants" @default.
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