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Conference Spotlight
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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DNFSB spots possible bottleneck in Hanford’s waste vitrification
Workers change out spent 27,000-pound TSCR filter columns and place them on a nearby storage pad during a planned outage in 2023. (Photo: DOE)
While the Department of Energy recently celebrated the beginning of hot commissioning of the Hanford Site’s Waste Treatment and Immobilization Plant (WTP), which has begun immobilizing the site’s radioactive tank waste in glass through vitrification, the Defense Nuclear Facilities Safety Board has reported a possible bottleneck in waste processing. According to the DNFSB, unless current systems run efficiently, the issue could result in the interruption of operations at the WTP’s Low-Activity Waste Facility, where waste vitrification takes place.
During operations, the LAW Facility will process an average of 5,300 gallons of tank waste per day, according to Bechtel, the contractor leading design, construction, and commissioning of the WTP. That waste is piped to the facility after being treated by Hanford’s Tanks Side Cesium Removal (TSCR) system, which filters undissolved solid material and removes cesium from liquid waste.
According to a November 7 activity report by the DNFSB, the TSCR system may not be able to produce waste feed fast enough to keep up with the LAW Facility’s vitrification rate.
Educational Session|Panel|Sponsored by Risk Management
Tuesday, August 11, 2020|12:00–1:30PM EDT
Session Organizer:
Gene Kelly (Exelon)
Track Organizer:
Timothy Crook (MCR Group)
Knowledge Manager:
Robby Christian (INL)
There are substantial benefits and good reasons for incorporating and crediting FLEX equipment in industry PRA models, for all hazard types (not just seismic and external flooding). Reactor safety is improved by allowing operators the flexibility to use FLEX in a variety of scenarios - not just in beyond design basis external event scenarios, which are the subject of the previously issued Mitigation Strategies under Order EA-12-049. The benefits of crediting FLEX - both in procedures and in PRA models, and for risk applications (such as RICT and SDP cases) - outweigh any potential regulatory uncertainties. The NRC’s recent enforcement policy found in Inspection Manual Chapter (IMC) 0609 Appendix A was recently reconsidered for FLEX equipment deficiencies, both in how these are screened, and in how the cases would be quantified (i.e., which hazard models are used) when performing more detailed significance analysis. FLEX component reliabilities and associated deployment actions (HRA) are evolving and being closely studied and evaluated by industry and the NRC. In the meantime, our models should reasonably reflect the as-built/as-operated plant, as required by the ASME Standard and Regulatory Guide 1.200. The option to deploy FLEX strategies is an important defense in depth measure in any/all scenarios when an extended loss of power is present, and is an improvement in reactor safety. It’s acknowledgement in PRA models should not be discouraged or unduly challenged.
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Reference — FLEX Speaker Bios
Session Notes
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