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Siting Experience Documents Only
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slides - Operating Experience, Session I, Cask Cranes
slides - Operating Experience, Session I, Cask Cranes
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - Transportation Infrastructure
slides - Transportation Infrastructure
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - Transportation Readiness
slides - Transportation Readiness
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - Vendor Perspective on Spent Fuel Pool Criticality Analysis
slides - Vendor Perspective on Spent Fuel Pool Criticality Analysis
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - Cumulative Impact of Industry and NRC Actions
slides - Cumulative Impact of Industry and NRC Actions
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Slides - Retrievability, Cladding Integrity, and Safety Handling during Storage and Transportation
Slides - Retrievability, Cladding Integrity, and Safety Handling during Storage and Transportation
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - Observations on Key Storage and Transport Technical Issues
slides - Observations on Key Storage and Transport Technical Issues
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste
slides - Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - Transportation Planning Considerations: BRC Report Recommendations and Plans for Implementation
slides - Transportation Planning Considerations: BRC Report Recommendations and Plans for Implementation
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - Transportation Readiness
slides - Transportation Readiness
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - Advancing the Used Fuel Management Agenda
slides - Advancing the Used Fuel Management Agenda
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Flexible Integrated Modular Nuclear Fuel Canister System
Flexible Integrated Modular Nuclear Fuel Canister System
Slides, Spark Presentation
EPRI Review of Geologic Disposal for Used Fuel and High Level Radioactive Waste: Volume IV—Lessons Learned
EPRI Review of Geologic Disposal for Used Fuel and High Level Radioactive Waste: Volume IV—Lessons Learned
The effective termination of the Yucca Mountain program by the U.S. Administration in 2009
has further delayed the construction and operation of a permanent disposal facility for used fuel
and high level radioactive waste (HLW) in the United States. In concert with this decision, the
President directed the Energy Secretary to establish the Blue Ribbon Commission on America’s
Nuclear Future to review and provide recommendations on options for managing used fuel and
Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition (NUREG-75/087)
Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition (NUREG-75/087)
The Standard Review Plan (SRP) is prepared for the guidance of staff reviewers in the Office of Nuclear Reactor Regulation in performing safety reviews of applications to construct or operate nuclear power plants. The principal purpose of the SRP is to assure the quality and uniformity of staff reviews, and to present a well-defined base from which to evaluate proposed changes in the scope and requirements of reviews.
Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants: A Guidance Manual for Users of Standard Technical Specifications (NUREG-0133)
Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants: A Guidance Manual for Users of Standard Technical Specifications (NUREG-0133)
This guidance manual provides the NRC staff methodology for calculating parameters for limiting conditions of operation required in the radiological effluent Technical Specifications for light-water-cooled nuclear power plants. it provides guidance in using the model specifications reported in NUREG-0472 (Revision 1)*, and NUREG-0473 (Revision 1)*, applicable to operating PWR and BWR licensees, and users of the Standard Technical Specifications packages available for various vendor designs.
Recommendations for PWR Storage and Transportation Casks That Use Burnup Credit
Recommendations for PWR Storage and Transportation Casks That Use Burnup Credit
Regulatory Perspective on Potential Fuel Reconfiguration and Its Implication to High Burnup Spent Fuel Storage and Transportation
Regulatory Perspective on Potential Fuel Reconfiguration and Its Implication to High Burnup Spent Fuel Storage and Transportation
The recent experiments conducted by Argonne National Laboratory on high burnup fuel cladding material property show that the ductile to brittle transition temperature of high burnup fuel cladding is dependent on: (1) cladding material, (2) irradiation conditions, and (3) drying-storage histories (stress at maximum temperature) [1]. The experiment results also show that the ductile to brittle temperature increases as the fuel burnup increases.
JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT SECOND NATIONAL REPORT
JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT SECOND NATIONAL REPORT
This report describes the actions taken in Argentina on the safety of spent fuel management
(SF) and on the safety of radioactive waste management, in order to provide evidence of the
fulfillment of its obligations under the Joint Convention. To facilitate the reading and a better
understanding of this report a summary of those parts of the 1st Report that were considered
necessary have been included.
JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT THIRD NATIONAL REPORT
JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT THIRD NATIONAL REPORT
The present National Report describes the actions taken in Argentina on the safety of spent fuel
(SF) management and on the safety of radioactive waste (RW) management, in order to provide
evidence of the fulfilment of the obligations derived from the Joint Convention. To facilitate the
reading and a better understanding, it has been decided to include a summary of those parts of
the two prior National Reports that are considered necessary in order to comply with this
objective.
H12: Project to Establish the Scientific and Technical Basis for HLW Disposal in Japan Project Overview Report
H12: Project to Establish the Scientific and Technical Basis for HLW Disposal in Japan Project Overview Report
As outlined in the overall program for high-level waste (HLW) management in Japan, defined by the Atomic Energy Commission (AEC), HWL separated from spent nuclear fuel during reprocessing will be immobilized in a glass matrix and stored for a period of 30 to 50 years to allow cooling; it will then be disposed of in a stable deep geological formation.
JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT FOURTH NATIONAL REPORT Argentina
JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT FOURTH NATIONAL REPORT Argentina
The structure of the Fourth National Report complies with the Guidelines Regarding the
Form and Structure of National Reports (INFCIRC/604/Rev.1).
Section A describes the scope of the nuclear activity developed in Argentina since 1950
as well as the legal and regulatory framework. It also makes reference to the Strategic
Plan for Radioactive Waste Management (Strategic Plan), which refers to the safety of
Spent Fuel Management and Radioactive Waste Management.
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.
Environmental Permitting Guidance Radioactive Substances Regulation For the Environmental Permitting (England and Wales) Regulations 2010

Environmental Permitting Guidance Radioactive Substances Regulation For the Environmental Permitting (England and Wales) Regulations 2010
This guidance is aimed at helping readers understand the permitting and other requirements specific to Radioactive Substances Regulation (RSR). The RSR regime covers
- more than one European Directive, parts of which are also implemented by other regulatory regimes which, to an extent, complement RSR;
- various Government policies and strategies; and
Underlying Yucca Mountain: The Interplay of Geology and Policy in Nuclear Waste Disposal
Underlying Yucca Mountain: The Interplay of Geology and Policy in Nuclear Waste Disposal
Nuclear waste disposal in the USA is a difficult policy issue infused with
science, technology, and politics. This issue provides an example of the co-production
of scientific knowledge and politics through public policy. The proponents of a
repository site at Yucca Mountain, Nevada, argue that their decision to go ahead
with the site is based on ‘sound science’, but the science they use to uphold their
decision is influenced by politics. In turn, the politics of site selection has been altered