Assessment Report - Docket 72-1024, U.S. Department of Energy, Dry Transfer System

The U.S. Department of Energy (DOE) submitted to the Nuclear Regulatory Commission (NRC) the Dry Transfer System (DTS) Topical Safety Analysis Report (TSAR) on

Initial Waste Package Probabilistic Criticality Analysis: Multi-Purpose Canister With Disposal Container (TBV)

This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) to provide an assessment of the present waste package design from a criticality risk standpoint. The specific objectives of this initial analysis are to: 1. Establish a process for determining the probability of waste package criticality as a function of time (in terms of a cumulative distribution function, probability distribution function, or expected number of criticalities in a specified time interval) for various waste package concepts;

Preliminary Site Requirements and Considerations for a Monitored Retrievable Storage Facility

In the November 1989 Report to Congress on Reassessment of the Civilian Radioactive Waste Management Program (DOE/RW-0247), the Secretary of Energy announced an initiative for developing a monitored retrievable storage (MRS) facility that is to start spent-fuel acceptance in 1998. This facility, which will be licensed by the U.S. Nuclear Regulatory Commission (NRC), will receive spent fuel from commercial nuclear power plants and provide a limited amount of storage for this

Summary Report of SNF Isotopic Comparisons for the Disposal Criticality Analysis Methodology

The "Summary Report of SNF Isotopic Comparisons for the Disposal Criticality Analysis Methodology" contains a summary of the analyses that compare SNF measured isotopic concentrations (radiochemical assays) to calculated SNF isotop~c concentrations (SAS2H module ·orScale4.3). The results of these analyses are used to support the validation of the isotopic models for spent commercial light water reactor (LWR) fuel.

Screening for Beryllium Disease Among Construction Trade Workers at Department of Energy Nuclear Sites

Background To determine whether current and former construction workers are at significant risk for occupational illnesses from work at the Department of Energy’s (DOE) nuclear weapons facilities, screening programs were undertaken at the Hanford Nuclear Reservation, Oak Ridge Reservation, and the Savannah River Site.

Summary Report of Commercial Reactor Criticality Data for Catawba Unit 1

The "Summary Report of Commercial Reactor Criticality Data for Catawba Unit 1" contains the detailed information necessary to perform commercial reactor criticality (CRC) analyses for the Catawba Unit 1 reactor.

The Siting Record

An Account of the Programs of Federal Agencies and Events That Have Led to the Selection of a Potential Site for a Geologic Repository for High-Level Radioactive Waste

Dry Storage of Used Fuel Transition to Transport

This report provides details of dry storage cask systems and contents in U.S. for commercial light water reactor fuel. Section 2 contains details on the canisters used to store approximately 86% of assemblies in dry storage in the U.S. Transport cask details for bare fuels, dual purpose casks and canister transport casks are included in Section 3. Section 4 details the inventory of those shutdown sites without any operating reactors. Information includes the cask type deployed, transport license and status as well as

Validation Report: Total System Model Version 6.0 Report Generators

This validation report supports the issuance of Version 6.0 of the Total System Model (TSM, BSC 2007a) that is described in the TSM User Manual (UM, BSC 2007b) and the TSM Preprocessor (TSMPP) User Manual (BSC 2007c). This report assumes the reader has detailed, working knowledge of the TSM functions and the Civilian Radioactive Waste Management System (CRWMS) operations. This report is based on an earlier document, Validation Report: Total System Model Version 5.0 Report Generators (BSC 2007d) that supported TSM Version 5.0.

Frequency and Quality of Radiation Monitoring of Construction Workers at Two Gaseous Diffusion Plants

Construction workers were and are considered temporary workers at many construction sites. Since WWII, large numbers of construction workers were employed at US DOE nuclear weapons sites for periods ranging from a few days to over 30 years. These workers performed tasks during new construction and maintenance, repair, renovation, and demolition of existing facilities.

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 - Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste

Presented at the 10th Meeting of the U.S.-Argentina Joint Standing Committee on Nuclear Energy Cooperation, Oak Ridge, Tennessee, August 26, 2013

slides - Transportation Readiness

Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013

Preclosure Criticality Safety Analysis

The means to prevent and control criticality must be addressed as part of the Preclosure Safety Analysis (PCSA) required for compliance with 10 CFR Part 63 [DIRS 180319], where the preclosure period covers the time prior to permanent closure activities. This technical report presents the nuclear criticality safety evaluation that documents the achievement of this objective.

slides - Advancing the Used Fuel Management Agenda

Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013

Federal Policy for the Disposal of Highly Radioactive Wastes from Commercial Nuclear Power Plants

How to dispose of highly radioactive wastes from commercial nuclear power plants is a question that has remained unresolved in the face rapidly changing technological, economic, and political requirements. In the three decades following WWII, two federal agencies -- the Atomic Energy Commission and the Energy Research and Development Administration -- tried unsuccessfully to develop a satisfactory plan for managing high level wastes.

CRC Depletion Calculations for Quad Cities Unit 2

The purpose of this calculation is to document the Quad Cities Unit 2 boiling water reactor (BWR) fuel depletion calculations performed as part of the commercial reactor critical (CRC) evaluation program. The CRC evaluations constitute benchmark calculations that support the development and validation of the neutronics models used for criticality analyses involving commercial spent nuclear fuel in a geologic repository. The revision of this calculation incorporates control blade effects and minor variations in the SAS2H assembly modeling.

Total System Model Version 6.0 Preprocessor Smoothing Algorithm Validation Report

This validation report supports the issuance of Version 6.0 of the Total System Model (TSM BSC-2007a) that is described in the TSM User’s Manual (UM) (BSC-2007b) and the TSM Preprocessor (TSMPP) UM (BSC 2007c). This report assumes the reader has detailed working knowledge of the TSM functions and Civilian Radioactive Waste Management System (CRWMS) operations. This validation was performed in accordance with AP-ENG-006, Total System Model (TSM)- Changes to Configuration Items and Base Case.

An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses--Isotopic Composition Predictions

Taking credit for the reduced reactivity of spent nuclear fuel in criticality analyses is referred to as burnup credit. Criticality safety evaluations employing burnup credit require validation of the depletion and criticality calculation methods and computer codes with available measurement data. To address the issues of burnup credit criticality validation, the U.S. Nuclear Regulatory Commission initiated a project with Oak Ridge National Laboratory to (1) develop and establish

slides - Vendor Perspective on Spent Fuel Pool Criticality Analysis

Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013

CRC Depletion Calculations for Crystal River Unit 3

The purpose of this calculation is to document the Crystal River Unit 3 pressurized water reactor (PWR) fuel depletion calculations performed as part of the commercial reactor critical (CRC) evaluation program. The CRC evaluations support the development and validation of the neutronics models used for criticality analyses involving commercial spent nuclear fuel in a geologic repository.

GAO Storage Study Request - Ltr to Honorable Gene Dodaro from Honorable Fred Upton and John Shimkus

GAO Storage Study Request

DOE Yucca Implementation Letter

Letter from the Congress of the United States House of Representatives, Committee on Energy and Commerce.

CRC Depletion Calculations for McGuire Unit 1

The purpose of this calculation is to document the McGuire Unit 1 pressurized water reactor (PWR) fuel depletion calculations performed as part of the commercial reactor critical (CRC) evaluation program. The CRC evaluations support the development and validation of the neutronics models used for criticality analyses involving commercial spent nuclear fuel in a geologic repository.

Flexible Integrated Modular Nuclear Fuel Canister System

Slides, Spark Presentation