Category of Content
Siting Experience Documents Only
Publication Date
Subject Matter
Keywords
Criticality Consequence Analysis Involving Intact PWR SNF in a Degraded 21 PWR Assembly Waste Package
Criticality Consequence Analysis Involving Intact PWR SNF in a Degraded 21 PWR Assembly Waste Package
EQ6 Calculations for Chemical Degradation of PWR LEU and PWR MOX Spent Fuel Waste Packages
EQ6 Calculations for Chemical Degradation of PWR LEU and PWR MOX Spent Fuel Waste Packages
Criticality Consequence Calculation Involving Intact PWR MOX SNF in a Degraded 21 PWR Assembly Waste Package
Criticality Consequence Calculation Involving Intact PWR MOX SNF in a Degraded 21 PWR Assembly Waste Package
Intact and Degraded Mode Criticality Calculations for the Codisposal of ATR Spent Nuclear Fuel in a Waste Package
Intact and Degraded Mode Criticality Calculations for the Codisposal of ATR Spent Nuclear Fuel in a Waste Package
Investigation of Nuclide Importance to Functional Requirements Related to Transport and Long-Term Storage of LWR Spent Fuel
Investigation of Nuclide Importance to Functional Requirements Related to Transport and Long-Term Storage of LWR Spent Fuel
OCRWM Bulletin Fall 1995
OCRWM Bulletin Fall 1995
<p>A report from the US Deparement of Energy's Office of Civilian Radioactive Waste Management</p>
<p>Regulatory Drop Tests Planned for a Model Transportation Cask</p>
<p>Implementation Plan for the environmental Impact Statement for a Multi-Purpose Canister System for Management of Civilian and Naval Spent Nuclear Fuel Issued</p>
<p>Nuclear Waste Technical Review Board (NWTRB) Update</p>
<p>The NWTRB</p>
<p>Dry Transfer System Design Under Way</p>
OCRWM Bulletin Spring 1995
OCRWM Bulletin Spring 1995
<p>A newsletter from the Office of Civilian Radioactive Waste Management</p>
<p>Highlights Include....</p>
<p>OCRWM FY 1996 Budget Presented to Congress</p>
<p>Public Responds to Waste Acceptance Issues</p>
<p>Transportation External Coordination Working Group Convenes in North Carolina</p>
<p>OCRWM Completes Draft Public Participation Plan</p>
<p>International Program Update</p>
OCRWM Bulletin Winter 1995
OCRWM Bulletin Winter 1995
<p>A newsletter from the Office of Civilian Radioactive Waste Management</p>
<p>OCRWM Director Briefs US. Nuclear Regulatory Commission .</p>
<p>Notice of Inquiry: Technical Assistance and Training for Safe Transportation of Radioactive Waste</p>
<p>OCRWM Program Plan</p>
<p>Environmental Impact Statement Scoping for the Multi-Purpose Canister-Based System</p>
<p>Nuclear Waste Technical Review Board Update,</p>
<p>Nuclear Wasre Negotiator Update</p>
OCRWM Bulletin Special Edition August 1994
OCRWM Bulletin Special Edition August 1994
<p>MULTI-PURPOSE CANISTER PROCUREMENT: A SIGNIFICANT STEP FOR THE DEPARTMENT OF ENERGY'S CIVILIAN RADIOACTIVE WASTE MANAGEMENT PROGRAM</p>
OCRWM Bulletin Summer 1995
OCRWM Bulletin Summer 1995
<p>A newsletter from the Office of Civilian Radioactive Waste Management</p>
<p>Highlights include...</p>
<p>Westinghouse begins designing multi-purpose canister</p>
<p>DOE accepts General Atomics-9 assembly transportation cask trailer</p>
<p>Final interpretation of nuclear waste acceptance issues published</p>
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.
Burnup Credit — Contribution to the Analysis of the Yankee Rowe Radiochemical Assays
Burnup Credit — Contribution to the Analysis of the Yankee Rowe Radiochemical Assays
This report presents a methodology for validation of the isotopic
contents of spent light water reactor fuel for actinide-only burnup
credit with additional high-quality radiochemistry assay (RCA) data
obtained from the Yankee Rowe pressurized water reactor. The
additional Yankee Rowe RCA data were not included in previous
isotopic validation studies for burnup credit due to the difficulty of
accurately modeling the complex Yankee Rowe fuel assembly design
using the SAS2H one-dimensional sequence of the earlier SCALE
Impacts Associated with Transfer of Spent Nuclear Fuel from Spent Fuel Storage Pools to Dry Storage After Five Years of Cooling
Impacts Associated with Transfer of Spent Nuclear Fuel from Spent Fuel Storage Pools to Dry Storage After Five Years of Cooling
In order to decrease the risk of terrorism, it has been suggested that used nuclear fuel should be
moved to dry storage early, after five years cooling in the spent fuel pool. The Nuclear
Regulatory Commission (NRC) has reviewed this issue and issued a white paper stating that it
did not believe such a measure was justified in light of additional security measures implemented
at nuclear plants and the impacts associated with the early movement of used fuel into dry
Generic Repository Design Concepts and Thermal Analysis (FY11)
Generic Repository Design Concepts and Thermal Analysis (FY11)
Reference concepts for geologic disposal of used nuclear fuel and high-level radioactive waste in
the U.S. are developed, including geologic settings and engineered barriers. Repository thermal
analysis is demonstrated for a range of waste types from projected future, advanced nuclear fuel
cycles. The results show significant differences among geologic media considered (clay/shale,
crystalline rock, salt), and also that waste package size and waste loading must be limited to meet
targeted maximum temperature values.
EPRI Review of Geologic Disposal for Used Fuel and High Level Radioactive Waste: Volume I --The U.S. Site Selection Process Prior to the Nuclear Waste Policy Amendments Act
EPRI Review of Geologic Disposal for Used Fuel and High Level Radioactive Waste: Volume I --The U.S. Site Selection Process Prior to the Nuclear Waste Policy Amendments Act
U.S. efforts to site and construct a deep geologic repository for used fuel and high level radioactive waste (HLW) proceeded in fits and starts over a three decade period from the late 1950s until 1982, when the U.S. Congress enacted the Nuclear Waste Policy Act (NWPA). This legislation codified a national approach for developing a deep geologic repository. Amendment of the NWPA in 1987 resulted in a number of dramatic changes in direction for the U.S. program, most notably the selection of Yucca Mountain as the only site of the three remaining candidates for continued investigation.
Average Burnup and Axial Burnup Profile Measurement for Burnup Credit Application
Average Burnup and Axial Burnup Profile Measurement for Burnup Credit Application
Recommendations Related to Browns Ferry Fire (NUREG-0050)
Recommendations Related to Browns Ferry Fire (NUREG-0050)
On March 22, 1975, a fire was experienced at the Browns Ferry Nuclear Plant near Decatur, Alabama. The Special Review Group was established by the Executive Director for Operations of the Nuclear Regulatory Commission (NRC) soon after the fire to identify the lessons learned from this event and to make recommendations for the future in the light of these lessons. Unless further developments indicate a need to reconvene the Review Group, its task is considered complete with the publication of this report.
Safety Evaluation for Operation of Browns Ferry, Units 1 and 2, Following the March 22, 1975 Fire (NUREG-0061, Initial Report)
Safety Evaluation for Operation of Browns Ferry, Units 1 and 2, Following the March 22, 1975 Fire (NUREG-0061, Initial Report)
On March 22, 1975, a fire at the Browns Ferry Nuclear Plant caused a shutdown of Units 1 and 2. The facility subsequent to the shutdown was found to have incurred substantial damage to power, control, and instrumentation wiring. All three units are presently in the shutdown condition with the fuel removed from the vessels for Units 1 and 2; the Unit 3 reactor is still under construction with operation for that unit scheduled for early 1976.
Report to Congress on Abnormal Occurrences (NUREG-0090)
Report to Congress on Abnormal Occurrences (NUREG-0090)
Section 208 of the Energy Reorganization Act of 1974, as amended (Public Law 93-438), defines an "abnormal occurrence" (AO) as an unscheduled incident or event that the U.S. Nuclear Regulatory Commission (NRC) determines to be significant from the standpoint of public health or safety. The Federal Reports Elimination and Sunset Act of 1995 (Public Law 104-66) requires that the NRC report AOs to Congress annually.
Evolution Of Repository And Waste Package Designs For Yucca Mountain Disposal System For Spent Nuclear Fuel And High-Level Radioactive Waste
Evolution Of Repository And Waste Package Designs For Yucca Mountain Disposal System For Spent Nuclear Fuel And High-Level Radioactive Waste
STANDARD CONTRACT AMENDMENT FOR NEW REACTORS
STANDARD CONTRACT AMENDMENT FOR NEW REACTORS
The following document is a contract amendment to a standard contract between the United States of America, represented by the U.S. Department of Energy, and a corporation organized and existing under the laws of a given state to dispose of Spent Nuclear Fuel (SNF)and/or High-Level Radioactive Waste (HRW).
The Multipurpose Canister Program in Retrospect: Perspective and Issues
The Multipurpose Canister Program in Retrospect: Perspective and Issues
The multipurpose canister (MPC) program represented a major U.S. Department of Energy (DOE) initiative to simplify the management of spent nuclear fuel by enclosing it in a canister acceptable for storage, transport, and disposal. The program was one example of successful interaction between utilities and the DOE. This report documents the history and lessons learned from this substantial effort.
WCS Files License Application with Nuclear Regulatory Commission (NRC) to Operate a Consolidated Interim Storage Facility (CISF) for Used Nuclear Fuel
WCS Files License Application with Nuclear Regulatory Commission (NRC) to Operate a Consolidated Interim Storage Facility (CISF) for Used Nuclear Fuel
WASHINGTON, D.C. (April 28, 2016) – Waste Control Specialists LLC (WCS) submitted an application to the Nuclear Regulatory Commission (NRC) for a license to construct and operate a Consolidated Interim Storage Facility (CISF) for used nuclear fuel. The filing comes after a year of pre-application meetings with NRC and maintains the timeline WCS outlined in February 2015.
The application is being led by WCS, along with its partners AREVA and NAC International, both global industry leaders in the transportation and storage of used nuclear fuel.