Bøger af U S Nuclear Regulatory Commission

Editorial style refers to the choices that writers and editors make to eliminate inconsistencies in their documents. These choices are sometimes difficult because language evolves. In updating this style guide, words related to new technologies posed a special challenge. Is it Email, E-mail, e-mail, or email? The U.S. Government Printing Office standard is e-mail, but this guidance clashes with a trend towards closing hyphenated words. The example shows that the authorities who compile style guides do not always agree. Moreover, each discipline has specific standards.

The contents of this design control quick reference booklet resulted from a collaboration of all four regional offices in support of the agency's focus on knowledge transfer, with staff from various other NRC offices providing valuable comments and suggestions. The principal and contributing authors of this booklet are listed below.

The Interagency Steering Committee on Radiation Standards prepared this annual report for ISCORS members agencies to document ISCORS activities and accomplishments in 2002, and plans for 2003.

Fuses are included in nuclear power plant electrical systems to protect circuits that directly impact plant safety, such as containment integrity protection.

This report, through a question-and-answer format, provides U.S. Nuclear Regulatory Commission staff responses to frequently asked questions on the decommissioning process for commercial, nuclear power reactor

Section 208 of the Energy Reorganization Act of 1974 (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 must report AOs to Congress annually. This report describes those events that the NRC or an Agreement State identified as AOs during fiscal year (FY) 2006.

A U.S. Nuclear Regulatory Commission source and byproduct materials license is required by 10 CFR Part 40 for the Operations of uranium mills and disposal of tailings, wastes produced by the extraction or concentration of source material from ones processed primarily for their source content.

The U.S. Nuclear Regulatory Commission (NRC) regulations in Title 10 of the Code of Federal Regulations (10 CFR) Part 52 include requirements for licensing new nuclear power plants.3 These regulations include the NRC's requirements for early site permit (ESP), design certification, and combined license (COL) applications. The ESP process (10 CFR Part 52, Subpart A, "Early Site Permits") is intended to address and resolve siting-related issues. The design certification process (10 CFR Part 52, Subpart B, "Standard Design Certifications") provides a means for a vendor to obtain NRC certification of a particular reactor design. Finally, the COL process (10 CFR Part 52, Subpart C, "Combined Licenses") allows an applicant to seek authorization to construct and operate a new nuclear power plant. A COL may reference an ESP, a certified design, both, or neither. As part of demonstrating that all applicable NRC requirements are met, a COL applicant referencing an ESP or certified design must demonstrate compliance with any requirements not already resolved as part of the referenced ESP or design certification before the NRC issues that COL.

This report supplements the safety evaluation report (SER), NUREG-0847 (June 1982), Supplement No. 25 (November 2011, Agencywide Documents Access and Management System (ADAMS) Accession No. ML12011A024), with respect to the application filed by the Tennessee Valley Authority (TVA), as applicant and owner, for a license to operate Watts Bar Nuclear Plant (WBN) Unit 2 (Docket No 50-391).

This report summarizes the occupational exposure data that are maintained in the U.S. Nuclear Regulatory Commission's (NRC) Radiation Exposure Information and Reporting System (REIRS). The bulk of the information contained in the report was compiled from the 2010 annual reports submitted by five of the seven categories1 of NRC licensees subject to the reporting requirements of 10 CFR 20.2206. Because there are no geologic repositories for high-level waste currently licensed and no NRC-licensed low-level waste disposal facilities currently in operation, only five categories will be considered in this report. The annual reports submitted by these licensees consist of radiation exposure records for each monitored individual. These records are analyzed for trends and presented in this report in terms of collective dose and the distribution of dose among the monitored individuals.

This technical report is designed to provide guidance to applicants for requests for a sealed source or device safety evaluations and registrations. It also provides the U.S. Nuclear Regulatory Commission (NRC) reviewers of such requests with the information and materials necessary to determine that the products are acceptable for licensing purposes. It provides the applicants and reviewers with information concerning how to file a request, a listing of the applicable regulations and industry standards, policies affecting evaluation and registration, administrative procedures to be followed, information on how to perform the evaluation and write a registration certificate, and the responsibilities of the registration certificate holder.

The complexity of tectonic environments and the limited data available for seismic source and ground motion characterization make the use of a significant level of expert judgment in seismic hazard assessment studies unavoidable. In the mid-90s the Nuclear Regulatory Commission, the U.S. Department of Energy, and the Electric Power Research Institute sponsored a study to develop recommendations for how studies incorporating the use of expert assessments should be conducted in the future. The Senior Seismic Hazard Analysis Committee (SSHAC) developed a structured, multi-level assessment process (the "SSHAC process") described in NUREG/CR-6372 that has since been used for numerous natural hazard studies and is recommended in NRC Regulatory Guide 1.208 for the development of new models to be used in probabilistic seismic hazard analyses.

The purpose of the study was to re-evaluate the resuspension factor parameter used in the screening analysis for demonstration of compliance, used the building occupancy scenario, with the radiological criteria in the license termination rule in 10 CFR 20, Subpart E.

This report describes a nonparametric statistical methodology for the design and analysis of final status decommissioning surveys in support of the final rulemaking on Radiological Criteria for License Termination published by the Nuclear Regulatory Commission in the Federal Register on July 21, 1997.

This report was prepared for the Advisory Committee on Reactor Safeguards as part of the Committee's effort to provide comments and recommendations to the Executive Director for Operation of the U.S. Nuclear Regulatory Commission for use in resolving a differing professional opinion concerning voltage-based alternative criteria for the repair of flaws in stream generator tubes in pressurized water reactors.

CONTENTS:PrefaceIntroduction -- Muriel Mitchell-SmithRegulations and StandardsGeneral and Biological RisksRadioluminous MaterialsMining, Agricultural, and Construction Materials Containing RadioactivityProducts Containing Radioactive SourcesMiscellaneous ProductsPanel Discussion