Reactor physics calculations were initiated to answer several major questions related to the proposed TRISO-coated particle fuel that is to be used in the prismatic Very High Temperature Reactor (VHTR) or the Next Generation Nuclear Plant (NGNP). These preliminary design evaluation calculations help ensure that the upcoming fuel irradiation tests will test appropriate size and type of fuel particles for a future NGNP reactor design. Conclusions from these calculations are expected to confirm and suggest possible modifications to the current particle fuel parameters specified in the evolving Fuel Specification. Calculated results dispel the need for a binary fuel particle system, which is proposed in the General Atomics GT-MHR concept. The GT-MHR binary system is composed of both a fissile and fertile particle with 350-and 500micron kernel diameters, respectively. For the NGNP reactor, a single fissile particle system (single UCO kernel size) can meet the reactivity and power cycle length requirements demanded of the NGNP. At the same time, it will provide substantial programmatic cost savings by eliminating the need for dual particle fabrication process lines and dual fuel particle irradiation tests required of a binary system.

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This report documents the activities and results of the Data Quality Improvement Project, Job Code Number N6145, conducted for the NRC's Division of Risk Analysis (DRA) by the Idaho National Laboratory (INL). The INL has collected, coded, and analyzed commercial reactor operational experience data for nearly two decades. Those efforts have evolved over time, including the associated data quality assurance and control activities. The purpose of this project is to identify the actions needed to ensure that the data that feeds the various programs under the direction of DRA follow the applicable quality assurance guidelines and standards. The activities addressed by this report include Review of data quality guidelines and standards and compilation of a consensus set of standards, guidelines and good practices Review of current data programs, products, and data quality control activities Evaluation of the quality assurance programs applied by the Institute for Nuclear Power Operations to the Equipment Performance and Information Exchange (EPIX) and characterization of EPIX quality Evaluation of current quality assurance activities at the INL against these requirements Creation of a Data Quality Program Plan to address activities to enhance the current data quality assurance processes.