After the Fukushima Daiichi accident, the U.S. Nuclear Regulatory Commission (NRC) issued 10 CFR 50.54(f), a letter requiring licensees to perform a re-evaluation of seismic hazard and take further actions if it exceeds their design basis. In...
After the Fukushima Daiichi accident, the U.S. Nuclear Regulatory Commission (NRC) issued 10 CFR 50.54(f), a letter requiring licensees to perform a reevaluation of seismic hazard and take further actions if it exceeds their design basis. In...
In response to Nuclear Regulatory Commission (NRC) post-Fukushima (FLEX) requirements, Entergy sought to install a 21,000 gal, mobile frac tank for temporary water storage at their Pilgrim Nuclear Power Station (PNPS). SGH evaluated the...
The Materials & Fuels Complex (MFC) at the Idaho National Laboratory focuses on research and development of nuclear fuels. SGH developed seismic fragilities for the MFC-704 structure (also referred to as the Fuel Manufacturing Facility...
Diablo Canyon Power Plant, in operation since 1985, uses two Westinghouse Pressurized Water Reactor units to produce 18,000 gigawatt-hours of electricity. PG&E retained SGH to support the re-evaluation of their Long Term Seismic...
The Institute of Nuclear Energy Research (INER) of Taiwan retained SGH to support the new Seismic Probabilistic Risk Assessments (SPRAs) of three Nuclear Power Plants (NPP), which each use different reactor designs. The Chinshan NPP is a...
The Department of Energy uses the Advanced Test Reactor (ATR) at Idaho National Laboratory to test nuclear fuel systems and materials. SGH engineers performed the experienced-based seismic qualification of Seismic Category I equipment at the ATR...
The South Texas Project is a twin-reactor facility that produces 2,700 MW of power. To increase the power generating capacity, the plant planned to add two advanced boiling water reactors to the existing pressurized water reactors. ...
The 1,097 MW power plant went into commercial operation in 1971 and consists of a single-unit boiling water reactor. The owner/operator of the Mühleberg Nuclear Power Plant (KKM) needed to submit an updated Level 1 probabilistic safety...
Deep Well No. 4 provides make-up water to the Advanced Test Reactor (ATR) in the event of a seismic-induced loss-of-coolant accident. A new diesel generator system was required to supply backup power to Deep Well No. 4. The associated structures...
A probabilistic methodology to investigate pinching failure of pressurized water reactor (PWR) spent nuclear fuel (SNF) rod cladding is presented. The considered accident scenario is a 9-m SNF transportation cask drop after long-term SNF dry...
After loss of power and reactor cooling capability at the Fukushima Daiichi nuclear power plant due to an extreme seismic event, the U.S. nuclear energy industry developed a diverse, flexible approach to implement the lessons learned, called FLEX...