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Glass strategy: Hanford’s enhanced waste glass program
The mission of the Department of Energy’s Office of River Protection (ORP) is to complete the safe cleanup of waste resulting from decades of nuclear weapons development. One of the most technologically challenging responsibilities is the safe disposition of approximately 56 million gallons of radioactive waste historically stored in 177 tanks at the Hanford Site in Washington state.
ORP has a clear incentive to reduce the overall mission duration and cost. One pathway is to develop and deploy innovative technical solutions that can advance baseline flow sheets toward higher efficiency operations while reducing identified risks without compromising safety. Vitrification is the baseline process that will convert both high-level and low-level radioactive waste at Hanford into a stable glass waste form for long-term storage and disposal.
Although vitrification is a mature technology, there are key areas where technology can further reduce operational risks, advance baseline processes to maximize waste throughput, and provide the underpinning to enhance operational flexibility; all steps in reducing mission duration and cost.
Sunil D. Weerakkody
Nuclear Technology | Volume 186 | Number 2 | May 2014 | Pages 139-144
Technical Paper | Reactor Safety | doi.org/10.13182/NT13-39
Articles are hosted by Taylor and Francis Online.
Until the late 1990s, inspection and enforcement practices at the U.S. Nuclear Regulatory Commission (NRC) were minimally influenced by probabilistic risk assessment (PRA) results. In the late 1990s, the NRC noted various shortcomings of the licensee assessment process [commonly known as the systematic assessment of licensee performance (SALP)] established in 1980. For example, the SALP process was found to lack focus on the most safety important issues and was subjective. The resulting new reactor oversight process is a risk-informed performance-based framework that uses PRA insights. Consequently, the NRC set up a significance determination process (SDP) that would rely on the risk significance of performance deficiencies of the licensees. The SDP assesses contributions from both internal events and external events using the best available information. Over the last two to three decades, the NRC has completed the development of high-quality PRA models that are capable of assessing risks due to internal events. Several recent regulatory actions, some of which were prompted by the events at Fukushima, have provided the impetus for the NRC and the licensees to enhance the methods and information related to assessing risks associated with external events such as earthquakes and floods. This paper describes the current status on how the NRC staff uses the best available information to assess risk associated with external events and notes a plethora of regulatory actions that may provide inertia for the development of high-quality models for external events. The paper then points to past trends on how the regulatory actions in the fire PRA area contributed to significant advancements in fire PRA technology and points to tangible evidence on how the same trend has begun in the area of seismic- and flood-related risk assessments.