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Directory of Certificates of Compliance for Radioactive Materials Packages (NUREG-0383)
Directory of Certificates of Compliance for Radioactive Materials Packages (NUREG-0383)
The purpose of this directory is to make available a convenient source of information on package designs approved by the U.S. Nuclear Regulatory Commission. To assist in identifying packages, an index by Model Number and corresponding Certificate of Compliance Number is included at the front of Volume 2. The report includes all package designs approved prior to the publication date of the directory as of September 2013.
Dry Cask Storage of Nuclear Spent Fuel
Dry Cask Storage of Nuclear Spent Fuel
Cost Estimate for an Away-From-Reactor Generic Interim Storage Facility (GISF) for Spent Nuclear Fuel
Cost Estimate for an Away-From-Reactor Generic Interim Storage Facility (GISF) for Spent Nuclear Fuel
As nuclear power plants began to run out of storage capacity in spent nuclear fuel (SNF) storage pools, many nuclear operating companies added higher density pool storage racks to increase pool capacity. Most nuclear power plant storage pools have been re-racked one or more times. As many spent fuel storage pools were re-racked to the maximum extent possible, nuclear operating companies began to employ interim dry storage technologies to store SNF in certified casks and canister-based systems outside of the storage pool in independent spent fuel storage installations (ISFSIs).
Technical Bases for Extended Dry Storage of Spent Nuclear Fuel
Technical Bases for Extended Dry Storage of Spent Nuclear Fuel
Independent spent fuel storage installations (ISFSIs) are currently licensed for 20 years. However, delays in developing permanent spent fuel disposal capability require continued ISFSI storage beyond the 20-year term. This report provides a technical basis for demonstrating the feasibility of extended spent fuel storage in ISFSIs.
Spent Nuclear Fuel Transportation: An Overview
Spent Nuclear Fuel Transportation: An Overview
Spent nuclear fuel comprises a fraction of the hazardous materials packages shipped annually in the United States. In fact, at the present time, fewer than 100 packages of spent nuclear fuel are shipped annually. At the onset of spent fuel shipments to the proposed Yucca Mountain, Nevada, repository, the U.S. Department of Energy (DOE) expects to ship 400 - 500 spent fuel transport casks per year over the life of the facility.
slides - ISFSI Pad Design Issues
slides - ISFSI Pad Design Issues
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Overview of Vacuum Drying Methods and Factors Affecting the Quantity of Residual Water – Public Version
Overview of Vacuum Drying Methods and Factors Affecting the Quantity of Residual Water – Public Version
NRC initiated a research activity with the Center for Nuclear Waste Regulatory Analyses (CNWRA®) to develop a conceptual test plan for measuring the quantity of residual water remaining in a canister following vacuum drying to the criterion referenced in NUREG–1536. While residual water may be considered as unbound or bound (i.e., physi- or chemisorbed), the focus of this test plan is only the unbound water. This activity consists of the preparation of two technical letter reports. The first is the present report, which describes current industry drying practices and capabilities.
slides - ISFSI Security Rulemaking Update
slides - ISFSI Security Rulemaking Update
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - ISFSI Security Rulemaking Update
slides - ISFSI Security Rulemaking Update
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - Prairie Island ISFSI License Renewal and High Burn Up Fuel Contention
slides - Prairie Island ISFSI License Renewal and High Burn Up Fuel Contention
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
THERMAL PERFORMANCE SENSITIVITY STUDIES IN SUPPORT OF MATERIAL MODELING FOR EXTENDED STORAGE OF USED NUCLEAR FUEL
THERMAL PERFORMANCE SENSITIVITY STUDIES IN SUPPORT OF MATERIAL MODELING FOR EXTENDED STORAGE OF USED NUCLEAR FUEL
The work reported here is an investigation of the sensitivity of component temperatures in a specific storage system, including fuel cladding temperatures, in response to modeling assumptions that differ from design-basis, including age-related changes that could degrade the thermal behavior of the system. Preliminary evaluations of representative horizontal and vertical storage systems at design basis conditions provides general insight into the expected behavior of storage systems over extended periods of time.
DECOMMISSIONING COST ANALYSIS for the CLINTON POWER STATION
DECOMMISSIONING COST ANALYSIS for the CLINTON POWER STATION
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Crystal River Unit 3 -- UPDATED IRRADIATED FUEL MANAGEMENT PROGRAM- 10 CFR 50.54(bb) and SITE-SPECIFIC DECOMMISSIONING COST ESTIMATE FOR THE CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT
Crystal River Unit 3 -- UPDATED IRRADIATED FUEL MANAGEMENT PROGRAM- 10 CFR 50.54(bb) and SITE-SPECIFIC DECOMMISSIONING COST ESTIMATE FOR THE CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT
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Kewaunee Power Station -- Post-Shutdown Decommissioning Activities Report
Kewaunee Power Station -- Post-Shutdown Decommissioning Activities Report
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