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Permitting plan for Hanford tanks initiative

Description: This plan describes all the possible permitting actions that could be required to implement the Hanford Tanks Initiative Project (HTI). Since the HTI Project Plan has several decision points where possible future activities could be eliminated, not all permitting actions described will be implemented. The cost and schedule for the permitting actions are included.
Date: February 10, 1997
Creator: Bloom, J. W.
Partner: UNT Libraries Government Documents Department

A process for reducing the licensing burden for new products containing depleted uranium.

Description: This report is intended to provide guidance on the process for petitioning the U.S. Nuclear Regulatory Commission (NRC) to initiate a rulemaking that could reduce the licensing burden for new products containing depleted uranium (DU), which are being investigated by the DU Uses Research and Development (R&D) Program at Oak Ridge National Laboratory (ORNL). The focus is on requirements of the NRC rulemaking process applicable to establishing new exemptions or general licenses for products and devices containing source material. NRC policies and guidance regarding such requirements are described, including a 1965 policy statement on approval of new exemptions for products containing radionuclides (''Federal Register'', Volume 30, page 3462 [30 FR 3462]; March 16, 1965) and Regulatory Guide 6.7, which addresses the contents of environmental reports that support rulemaking petitions seeking exemptions for radionuclide-containing products. Methodologies for calculating radiological and nonradiological impacts on human health (i.e., risks) associated with distributing, using, and disposing of DU-containing products are presented. Also, methodologies for completing assessments of the potential effects of accidents involving new DU-containing products and of product misuse are described. The report recommends that the U.S. Department of Energy formulate a regulatory plan for deployment of DU-containing products in areas that are not already radiologically controlled. Such a plan is needed because deployment of new DU-containing products may be difficult under existing NRC licensing requirements. To provide a basis for the regulatory plan, it is recommended that detailed assessments of the radiological and nonradiological risks of distributing, using, and disposing of DU-containing products be conducted. Such assessments should be initiated as soon as sufficient data are available from the ongoing DU Uses R&D Program at ORNL to support the analyses.
Date: January 6, 2004
Creator: Ranek, N. L.; Kamboj, S.; Hartmann, H. M. & Avci, H.
Partner: UNT Libraries Government Documents Department

National Environmental Policy Act compliance guide. Volume II (reference book)

Description: This document (Volume II of the National Environmental Policy Act Compliance Guide) contains current copies of regulations and guidance from the Council on Environmental Quality, the Department of Energy, the Department of State, and the Environmental Protection Agency, related to compliance with the National Environmental Policy Act of 1969 (NEPA).
Date: September 1, 1994
Partner: UNT Libraries Government Documents Department

Title list of documents made pulicly available, March 1-31, 1997

Description: The Title List of Documents Made Publicly Available is a monthly publication. It describes the information received and published by the U.S. Nuclear Regulatory Commission (NRC). This information includes: (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) non-docketed material received and published by NRC pertinent to its role as a regulatory agency. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index.
Date: May 1, 1997
Creator: Morris, E.B.
Partner: UNT Libraries Government Documents Department

Computer calculations of wire-rope tiedown designs for radioactive materials packages

Description: This Regulatory Compliance Guide (RCG) provides guidance on the use and selection of appropriate wire rope type package tiedowns. It provides an effective way to encourage and to ensure uniform implementation of regulatory requirements applicable to tiedowns. It provides general guidelines for securing packages weighing 5,000 pounds or greater that contain radioactive materials onto legal weight trucks (exclusive of packagings having their own trailer with trunnion type tiedown). This RCG includes a computerized Tiedown Stress Calculation Program (TSCP) which calculates the stresses in the wire-rope tiedowns and specifies appropriate sizes of wire rope and associated hardware parameters (such as turnback length, number of cable clips, etc.).
Date: December 31, 1995
Creator: Shappert, L.B.; Ratledge, J.E.; Moore, R.S. & Dorsey, E.A.
Partner: UNT Libraries Government Documents Department

Evaluation of Modal Combination Methods for Seismic Response Spectrum Analysis

Description: Regulatory Guide 1.92 ''Combining Modal Responses and Spatial Components in Seismic Response Analysis'' was last revised in 1976. The objective of this project was to re-evaluate the current regulatory guidance for combining modal responses in response spectrum analysis, evaluate recent technical developments, and recommend revisions to the regulatory guidance. This paper describes the qualitative evaluation of modal response combination methods.
Date: March 23, 1999
Creator: Chokshi, N.; Kenneally, R.; Morante, R.; Norris, W. & Wang, Y.
Partner: UNT Libraries Government Documents Department

DEVELOPMENT OF HFE SECTIONS OF DG-1145.

Description: For the licensing of the current fleet of commercial nuclear power plants (NPPs), the Nuclear Regulatory Commission (NRC) used two key documents, NUREG-0800 and Regulatory Guide (RG) 1.70. RG 1.70 provided guidance to applicants on the contents needed in their Safety Analysis Reports (SARs) submitted as part of their application to construct or operate an NPP. NUREG-0800, the NRC Standard Review Plan (SRP), provides guidance to the NRR staff reviewers on performing their safety reviews of these applications. As part of the preparation for a new wave of improved NPP designs the NRC is in the process of updating the SRP and is also developing a new RG designated as draft RG or DG-1145, ''Combined License Applications for Nuclear Power Plants (LWR Edition).'' This will eventually become RG 1.206 and will take the place of RG 1.70. This will provide guidance for combined license (COL) applicants, as well as for other 10CFR Part 52 variations that are permitted.
Date: March 26, 2007
Creator: HIGGINS,J.C.; OHARA, J.M. & BONGARRA, J.
Partner: UNT Libraries Government Documents Department

Updating the NRC Standard Review Plan - Chapter 8 - Electrical Systems

Description: The Standard Review Plan (SRP) (Reference 2), provides guidance to the regulatory staff of the Nuclear Regulatory Commission (NRC) on performing their safety reviews of applications to construct or operate nuclear power plants, and applications to approve standard designs and sites for nuclear power plants. Chapter 8 of the SRP provides guidance related to the review of station electrical distribution systems described by the applicant in its Design Control Document (DCD) or Safety Analysis Report (SAR). As part of the 2006-2007 SAR update, all sections in this Chapter (8.1, 8.2, 8.3.1, 8.3.2, Appendix 8A, and Appendix 8B) were revised to incorporate new analyses, design approaches, and the lessons learned from the review of the AP 1000 design certification and to assure consistency with the draft Regulatory Guide DG-1145, ''Combined License Applications for Nuclear Power Plants (LWR Edition)''.
Date: June 24, 2007
Creator: Sullivan, K.
Partner: UNT Libraries Government Documents Department

EVALUATION OF MODAL COMBINATION METHODS FOR SEISMIC RESPONSE SPECTRUM ANALYSIS.

Description: Regulatory Guide 1.92 ''Combining Modal Responses and Spatial Components in Seismic Response Analysis'' was last revised in 1976. The objective of this project was to re-evaluate the current regulatory guidance for combining modal responses in response spectrum analysis, evaluate recent technical developments, and recommend revisions to the regulatory guidance. This paper describes the qualitative evaluation of modal response combination methods.
Date: August 15, 1999
Creator: MORANTE,R.
Partner: UNT Libraries Government Documents Department

Applying Current Human Factors Engineering Guidance to Control Room Design

Description: The Westinghouse Savannah River Company, a contractor to the Department of Energy, has compared Revisions 1 and 2 of NUREG-0700-Human System Interface Design Review Guideline, from the United States Nuclear Regulatory Commission Nuclear Regulatory Guide. The comparison has been made with respect to which guidelines remained the same, the guidelines that were reformatted or reworded, additional guidelines, and deleted guidelines. This comparison was made in preparation of revising the previously developed Human Factors Engineering Analysis Tool for automating the review, analysis, and evaluation of human system interface designs. This tool has been described at previous conferences on human factors and the merits and benefits of the tool described. The tool has been successfully applied to over eight facilities at WSRC. This paper describes the methodology and results of the comparison and the plans to enhance the already successful automation tool. The number of criteria in NUREG-0700 increased from approximately 1650 in Revision 1 to almost 2200 in Revision 2. Approximately 1600 criteria remained the same, though they were significantly reorganized; while about 100 were reworded or reformatted to clarify or expand the guidance provided. Around 600 guidelines were added and approximately 70 deleted. The majority of the changes and additions reflect the recent impact that computer technology has had on industrial process control system human system interfaces and control rooms.
Date: January 31, 2005
Creator: LEO, GEARY
Partner: UNT Libraries Government Documents Department

Summary report on the project to develop recommendations on effective linkages between state IRP, facility siting and regional transmission planning in a competitive environment. Final report, May 24, 1994--March 31, 1995

Description: This project, which began on May 1, 1994, was designed to: improve the understanding of the types of linkages (or lack of linkages) between utility-specific IRP, state facility siting, and regional transmission planning given (1) the current level of competition, (2) increased generation competition, and (3) retail competition; identify opportunities to better coordinate utility-specific IRP and state facility siting with regional transmission planning, including better regional market and transmission planning information for utility-specific plans; and improve the understanding of the influence of competition on utility-specific IRP in terms of planning objectives, planning process, plan implementation and plan output, and identify potential changes to utility-specific IRP to allow IRP to meet planning objectives in a competitive environment.
Date: July 1, 1995
Partner: UNT Libraries Government Documents Department

Propped Cantilever Mesh Convergence Study Using Hexahedral Elements

Description: The Task Group on Computational Modelling for Explicit Analyses in the ASME Boiler and Pressure Vessel Code committee was set up in August 2008 to develop a quantitative finite element modelling guidance document for the explicit dynamic analysis of energy-limited events. This guidance document will be referenced in the ASME Boiler and Pressure Vessel Code Section III Division 3 and NRC Regulatory Guide 7.6 as a means by which the quality of a finite element model may be judged. In energy limited events, which the guidance document will address, ductile metallic materials will suffer significant plastic strains to take full advantage of their energy absorption capacity. Accuracy of the analyses in predicting large strains is therefore essential. One of the issues that this guidance document will address is the issue of the quality of a finite element mesh, and in particular, mesh refinement to obtain a convergent solution. That is, for a given structure under a given loading using a given type of element, what is the required mesh density to achieve sufficiently accurate results. One portion of the guidance document will be devoted to a series of element convergence studies that can aid designers in establishing the mesh refinement requirements necessary to achieve accurate results for a variety of different elements types in regions of high plastic strain. These convergence studies will also aid reviewers in evaluating the quality of a finite element model and the apparent accuracy of its results. The first convergence study consists of an elegantly simple problem of a cantilevering beam, simply supported at one end and built in at the other, loaded by a uniformly-distributed load that is ramped up over a finite time to a constant value. Three different loads were defined, with the smallest load to cause stresses that are entirely elastic ...
Date: October 1, 2001
Creator: Tso, Chi-Fung; Molitoris, David; Snow, Spencer & Norman, Alex
Partner: UNT Libraries Government Documents Department

Peer Review of NRC Standardized Plant Analysis Risk Models

Description: The Nuclear Regulatory Commission (NRC) Standardized Plant Analysis Risk (SPAR) Models underwent a Peer Review using ASME PRA standard (Addendum C) as endorsed by NRC in Regulatory Guide (RG) 1.200. The review was performed by a mix of industry probabilistic risk analysis (PRA) experts and NRC PRA experts. Representative SPAR models, one PWR and one BWR, were reviewed against Capability Category I of the ASME PRA standard. Capability Category I was selected as the basis for review due to the specific uses/applications of the SPAR models. The BWR SPAR model was reviewed against 331 ASME PRA Standard Supporting Requirements; however, based on the Capability Category I level of review and the absence of internal flooding and containment performance (LERF) logic only 216 requirements were determined to be applicable. Based on the review, the BWR SPAR model met 139 of the 216 supporting requirements. The review also generated 200 findings or suggestions. Of these 200 findings and suggestions 142 were findings and 58 were suggestions. The PWR SPAR model was also evaluated against the same 331 ASME PRA Standard Supporting Requirements. Of these requirements only 215 were deemed appropriate for the review (for the same reason as noted for the BWR). The PWR review determined that 125 of the 215 supporting requirements met Capability Category I or greater. The review identified 101 findings or suggestions (76 findings and 25 suggestions). These findings or suggestions were developed to identify areas where SPAR models could be enhanced. A process to prioritize and incorporate the findings/suggestions supporting requirements into the SPAR models is being developed. The prioritization process focuses on those findings that will enhance the accuracy, completeness and usability of the SPAR models.
Date: March 1, 2011
Creator: Koonce, Anthony; Knudsen, James & Buell, Robert
Partner: UNT Libraries Government Documents Department

LAND AND WATER USE CHARACTERISTICS AND HUMAN HEALTH INPUT PARAMETERS FOR USE IN ENVIRONMENTAL DOSIMETRY AND RISK ASSESSMENTS AT THE SAVANNAH RIVER SITE

Description: Operations at the Savannah River Site (SRS) result in releases of small amounts of radioactive materials to the atmosphere and to the Savannah River. For regulatory compliance purposes, potential offsite radiological doses are estimated annually using computer models that follow U.S. Nuclear Regulatory Commission (NRC) Regulatory Guides. Within the regulatory guides, default values are provided for many of the dose model parameters but the use of site-specific values by the applicant is encouraged. A detailed survey of land and water use parameters was conducted in 1991 and is being updated here. These parameters include local characteristics of meat, milk and vegetable production; river recreational activities; and meat, milk and vegetable consumption rates as well as other human usage parameters required in the SRS dosimetry models. In addition, the preferred elemental bioaccumulation factors and transfer factors to be used in human health exposure calculations at SRS are documented. Based on comparisons to the 2009 SRS environmental compliance doses, the following effects are expected in future SRS compliance dose calculations: (1) Aquatic all-pathway maximally exposed individual doses may go up about 10 percent due to changes in the aquatic bioaccumulation factors; (2) Aquatic all-pathway collective doses may go up about 5 percent due to changes in the aquatic bioaccumulation factors that offset the reduction in average individual water consumption rates; (3) Irrigation pathway doses to the maximally exposed individual may go up about 40 percent due to increases in the element-specific transfer factors; (4) Irrigation pathway collective doses may go down about 50 percent due to changes in food productivity and production within the 50-mile radius of SRS; (5) Air pathway doses to the maximally exposed individual may go down about 10 percent due to the changes in food productivity in the SRS area and to the changes in element-specific transfer factors; ...
Date: August 6, 2010
Creator: Jannik, T.; Karapatakis, D.; Lee, P. & Farfan, E.
Partner: UNT Libraries Government Documents Department

Final Site Specific Decommissioning Inspection Report #2 for the University of Washington Research and Test Reactor, Seattle, Washington

Description: During the period of August through November 2006, ORISE performed a comprehensive IV at the University of Washington Research and Test Reactor Facility. The objective of the ORISE IV was to validate the licensee’s final status survey processes and data, and to assure the requirements of the DP and FSSP were met.
Date: March 20, 2007
Creator: Roberts, S. J.
Partner: UNT Libraries Government Documents Department

Comparison Evaluation of the PFP FSAR and NRC Regulatory Guide 3.39 with DOE-STD-3009-94

Description: One of the Plutonium Finishing Plant's (PFP) current Authorization Basis (AB) documents is the Final Safety Analysis Report (FSAR). This FSAR (HNF-SD-CP-SAR-02 1) was prepared to the format and content guidance specified in U.S. Nuclear Regulatory Commission (NRC) Regulatory Guide 3.39, Standard Format and Content of License Applications for Plutonium Processing and Fuel Fabrication Plants (RG 3.39). In April 1992, the US Department of Energy (DOE) issued DOE Order 5480.23 which established the FSAR requirements for DOE nonreactor nuclear facilities. In 1994, DOE issued DOE-STD-3009-94, Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports, which is a format and content guide addressing the preparation of FSARs in accordance with DOE Order 5480.23. During the initial preparation and issuance of the PFP FSAR the format and content guidance contained in NRC Regulatory Guide 3.39 was utilized, since it was the most applicable guidance at the time for the preparation of Safety Analysis Reports for plutonium processing plants. With the adoption of DOE Order 5480.23 and DOE-STD-3009-94, DOE required the preparation of SARs to meet the format and content of those DOE documents. The PFP was granted an exemption to continue with RG 3.39 format for future FSAR revisions. PFP modifications and additions have required PFP FSAR modifications that have typically been prepared to the same NRC Regulatory Guide 3.39 format and content, to provide consistency with the PFP FSAR. This document provides a table comparison between the 3009 and RG 3.39 formats to validate the extent of PFP FSAR compliance with the intent of DOE Order 5480.23 and DOE-STD-3009-94. This evaluation was initially performed on Revisions 1 and 1A of the PFP FSAR. With the preparation of a Revision 2 draft to the FSAR, sections with significant changes were reevaluated for compliance and the tables were updated, ...
Date: July 28, 2000
Creator: OSCARSON, E.E.
Partner: UNT Libraries Government Documents Department

NEPA source guide for the Hanford Site. Revision 2

Description: This Source Guide will assist those working with the National Environmental Policy Act of 1969 (NEPA) to become more familiar with the Environmental Assessments (EA) and Environmental Impact Statements (EIS) that apply to specific activities and facilities at the Hanford Site. This document should help answer questions concerning NEPA coverage, history, processes, and the status of many of the buildings and units on and related to the Hanford Site. This document summarizes relevant EAs and EISs by briefly outlining the proposed action of each and the decision made by the US Department of Energy (DOE) or its predecessor agencies, the US Atomic Energy Commission (AEC), and the US Energy Research and Development Administration (ERDA), concerning the proposed action and current status of the buildings and units discussed in the proposed action. If a decision was officially stated by the DOE, as in a Finding Of No Significant Impact (FONSI) or a Record of Decision (ROD), and was located, a summary is provided in the text. Not all federal decisions, such as FONSIs and RODS, can be found in the Federal Register (FR). For example, although significant large-action FONSIs can be found in the FR, some low-interest FONSIs may have been published elsewhere (i.e., local newspapers). The EA and EIS summaries are arranged in numerical order. To assist in locating a particular EA or EIS, the upper right comer of each page lists the number of the summary or summaries discussed on that page. Any draft EA or EIS is followed by a ``D.`` The EAs with nonstandard numbering schemes are located in Chapter 3.
Date: September 27, 1995
Creator: Tifft, S.R.
Partner: UNT Libraries Government Documents Department

ASSESSMENT OF THE RELEVANCE OF DISPLACEMENT BASED DESIGN METHODS/CRITERIA TO NUCLEAR PLANT STRUCTURES.

Description: Revisions to the USNRC Regulatory Guides and Standard Review Plan Sections devoted to earthquake engineering practice are currently in process. The intent is to reflect changes in engineering practice that have evolved in the twenty years that have passed since those criteria were originally published. Additionally, field observations of the effects of the Northridge (1994) and Kobe (1995) earthquakes have inspired some reassessment in the technical community about certain aspects of design practice. In particular, questions have arisen about the effectiveness of basing earthquake resistant designs on resistance to seismic forces and, then evaluating tolerability of the expected displacements. Therefore, a research effort was undertaken to examine the implications for NRC's seismic practice of the move, in the earthquake engineering community, toward using expected displacement rather than force (or stress) as the basis for assessing design adequacy. The results of the NRC sponsored research on this subject are reported in this paper. A slow trend toward the utilization of displacement based methods for design was noted. However, there is a more rapid trend toward the use of displacement based methods for seismic evaluation of existing facilities. A document known as FEMA 273, has been developed and is being used as the basis for the design of modifications to enhance the seismic capability of existing non-nuclear facilities. The research concluded that displacement based methods, such as given in FEMA 273, may be useful for seismic margin studies of existing nuclear power stations. They are unlikely to be useful for the basic design of new stations since nuclear power stations are designed to remain elastic during a seismic event. They could, however, be useful for estimating the margins associated with that design.
Date: August 12, 2001
Creator: HOFMAYER,C.; MILLER,C.; WANG,Y. & COSTELLO,J.
Partner: UNT Libraries Government Documents Department

EMI/RFI and Power Surge Withstand Guidance for the U.S. Nuclear Regulatory Commission

Description: This paper discusses the regulatory guidance implemented by U.S. NRC for minimizing malfunctions and upsets in safety-related instrumentation and control (I and C) systems in nuclear power plants caused by electromagnetic interference (EMI), radio-frequency interference (RFI), and power surges. The engineering design, installation, and testing practices deemed acceptable to U.S. NRC are described in Regulatory Guide (RG) 1.180, ''Guidelines for Evaluating Electromagnetic and Radio-Frequency in Safety-Related Instrumentation and Control Systems'' (January 2000) and in a Safety Evaluation Report (SER) endorsing EPRI TR-102323, ''Guidelines for Electromagnetic Interference Testing in Power Plants,'' (April 1996). These engineering practices provide a well-established, systematic approach for ensuring electromagnetic compatibility (EMC) and surge withstand capability (SWC).
Date: September 7, 2001
Creator: Ewing, P. D.
Partner: UNT Libraries Government Documents Department

Regulatory and technical reports (abstract index journal): Annual compilation for 1994. Volume 19, Number 4

Description: This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the US Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC`s intention to publish this compilation quarterly and to cumulate it annually. The main citations and abstracts in this compilation are listed in NUREG number order. These precede the following indexes: secondary report number index, personal author index, subject index, NRC originating organization index (staff reports), NRC originating organization index (international agreements), NRC contract sponsor index (contractor reports), contractor index, international organization index, and licensed facility index. A detailed explanation of the entries precedes each index.
Date: March 1, 1995
Partner: UNT Libraries Government Documents Department

Summary of Information Presented at an NRC-Sponsored Low-Power Shutdown Public Workshop, April 27, 1999, Rockville, Maryland

Description: This report summarizes a public workshop that was held on April 27, 1999, in Rockville, Maryland. The workshop was conducted as part of the US Nuclear Regulatory Commission's (NRC) efforts to further develop its understanding of the risks associated with low power and shutdown operations at US nuclear power plants. A sufficient understanding of such risks is required to support decision-making for risk-informed regulation, in particular Regulatory Guide 1.174, and the development of a consensus standard. During the workshop the NRC staff discussed and requested feedback from the public (including representatives of the nuclear industry, state governments, consultants, private industry, and the media) on the risk associated with low-power and shutdown operations.
Date: July 1, 1999
Creator: Wheeler, Timothy A.; Whitehead, Donnie W. & Lois, Erasmia
Partner: UNT Libraries Government Documents Department

Use and Application of the ARCON96 Dispersion Model at the Y-12 Complex

Description: The Atmospheric Relative Concentrations in Building Wakes computer code (ARCON96) was developed for the U.S. Nuclear Regulatory Commission (NRC) to calculate normalized concentrations in plumes from nuclear power plants at control room air intakes in the vicinity of hypothetical accidental releases. ARCON96 implements a straight-line Gaussian dispersion model with dispersion coefficients that are modified to account for low-wind-speed meander and building wake effects. These two modifications to the dispersion coefficients were benchmarked and justified in the ARCON96 code documentation. The code calculates {chi}/Q values (normalized concentrations) consistent with the methodology defined in NRC Regulatory Guide (RG) 1.145, position 3. Based on recent U. S. Department of Energy (DOE) acceptance of NRC RG 1.145, position 3 methodology for performing accident dispersion analyses, BWXT Y-12 L.L.C. evaluated the potential use and application for performing dispersion analyses at the Y-12 Complex. Using site specific meteorology inputs, a generic analysis (assuming ground-level releases) was performed to develop site-wide normalized concentrations for various distances to be used in consequence screening analyses. Additionally, the results were compared to other dispersion analysis models for confirmation of the results.
Date: June 4, 2001
Creator: Walker, D. A.; Lee, D. W. & Miller, R. L.
Partner: UNT Libraries Government Documents Department

Environmental Guidance Regulatory Bulletin

Description: On September 15, 1994, EPA promulgated a Final Rule revising 40 CFR Part 300: the National Oil and Hazardous Substances Pollution Contingency Plan (NCP). NCP establishes a national response system for responding to discharges of oil and releases of hazardous substances. Figures illustrate the roles of the national response system. Response operations, planning and preparation, and designation of federal trustees are discussed, followed by definitions.
Date: July 31, 1995
Partner: UNT Libraries Government Documents Department