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Basis for radiation protection of the nuclear worker

Description: A description is given of the standards for protection of persons who work in areas that have a potential for radiation exposure. A review is given of the units of radiation exposure and dose equivalent and of the value of the maximum permissible dose limits for occupational exposure. Federal Regulations and Regulatory Guides for radiation protection are discussed. Average occupational equivalent doses experienced in several operations typical of the United States Nuclear Industry are presented… more
Date: January 1, 1982
Creator: Guevara, F.A.
Partner: UNT Libraries Government Documents Department
open access

Demonstration of a computer model for residual radioactive material guidelines, RESRAD

Description: A computer model was developed to calculate residual radioactive material guidelines for the US Department of Energy (DOE). This model, called RESRAD, can be run on IBM or IBM-compatible microcomputer. Seven potential exposure pathways from contaminated soil are analyzed, including external radiation exposure and internal radiation exposure from inhalation and food digestion. The RESRAD code has been applied to several DOE sites to derive soil cleanup guidelines. The experience gained indicates… more
Date: January 1, 1989
Creator: Yu, C.; Yuan, Y. C.; Zielen, A. J.; Wallo III, A. (Argonne National Lab., IL (USA) & USDOE, Washington, DC (USA))
Partner: UNT Libraries Government Documents Department
open access

Environmental compliance considerations for the management of cultural resources

Description: This paper examines three key considerations underlying the programmatic management of cultural resources that may be affected by a large federal project. These considerations are statutory background and the compliance process, cultural resource compliance tasks, and quality assurance. The first consideration addresses the legal requirements and steps that must be met and taken for federal agencies to fulfill their cultural resource compliance responsibilities. The second consideration focuses… more
Date: January 1, 1987
Creator: Curtis, S. A.; Whitfield, S. & McGinnis, K.
Partner: UNT Libraries Government Documents Department
open access

The scale analysis sequence for LWR fuel depletion

Description: The SCALE (Standardized Computer Analyses for Licensing Evaluation) code system is used extensively to perform away-from-reactor safety analysis (particularly criticality safety, shielding, heat transfer analyses) for spent light water reactor (LWR) fuel. Spent fuel characteristics such as radiation sources, heat generation sources, and isotopic concentrations can be computed within SCALE using the SAS2 control module. A significantly enhanced version of the SAS2 control module, which is denote… more
Date: January 1, 1991
Creator: Hermann, O.W. & Parks, C.V.
Partner: UNT Libraries Government Documents Department
open access

Safety Aspects of the IFR Pyroprocess Fuel Cycle

Description: This paper addresses the important safety considerations related to the unique Integral Fast Reactor (IFR) fuel cycle technology, the pyroprocess. Argonne has been developing the IFR since 1984. It is a liquid metal cooled reactor, with a unique metal alloy fuel, and it utilizes a radically new fuel cycle. An existing facility, the Hot Fuel Examination Facility-South (HFEF/S) is being modified and equipped to provide a complete demonstration of the fuel cycle. This paper will concentrate on saf… more
Date: January 1, 1989
Creator: Forrester, R. J.; Lineberry, M. J.; Charak, I.; Tessier, J. H.; Solbrig, C. W. & Gabor, J. D.
Partner: UNT Libraries Government Documents Department
open access

A proposed Regulatory Guide basis for spent fuel decay heat

Description: A proposed revision to Regulatory Guide 3.54, Spent Fuel Heat Generation in an Independent Spent Fuel Storage Installation'' has been developed for the US Nuclear Regulatory Commission. The proposed revision includes a data base of decay heat rates calculated as a function of burnup, specific power, cooling time, initial fuel {sup 235}U enrichment and assembly type (i.e., PWR or BWR). Validation of the calculational method was done by comparison with existing measured decay heat rates. Procedur… more
Date: January 1, 1991
Creator: Hermann, O.W.; Parks, C.V. & Renier, J.P.
Partner: UNT Libraries Government Documents Department
open access

Reliability of leak detection systems in LWRs

Description: In this paper, NRC guidelines for leak detection will be reviewed, current practices described, potential safety-related problems discussed, and potential improvements in leak detection technology (with emphasis on acoustic methods) evaluated.
Date: October 1, 1986
Creator: Kupperman, D.S.
Partner: UNT Libraries Government Documents Department
open access

WHC fire hazards analysis policy

Description: The purpose of this document is to establish the fire protection policy for Westinghouse Hanford Company (WHC) relative to US Department of Energy (DOE) directives for Fire Hazards Analyses (FHAs) and their relationship to facility Safety Analysis Reports (SARs) as promulgated by the DOE Richland Operations Office.
Date: April 1, 1994
Creator: Evans, C. B.
Partner: UNT Libraries Government Documents Department
open access

Plant procedures, principles of information processing, and incorporation of DOE guidelines: A juggling act

Description: Procedure format and style--the manner in which information is organized and visually presented to the procedure user--strongly influence procedure usability, and therefore influence safety and efficiency. The purpose of this paper is to describe recent and on-going efforts at the Rocky Flats Plant (RFP) to enhance plant procedures by applying established principles of human information processing in procedure development, and to educate plant personnel (especially those involved in procedure d… more
Date: June 1, 1993
Creator: Mecherikoff, M. & Caccamise, D. J.
Partner: UNT Libraries Government Documents Department
open access

Implementation of a laboratory information management system for environmental regulatory analyses

Description: The Savannah River Technology Center created a second instance of its ORACLE based PEN LIMS to support site Environmental Restoration projects. The first instance of the database had been optimized for R&D support and did not implement rigorous sample tracking, verification, and holding times needed to support regulatory commitments. Much of the R&D instance was transferable such as the work control functions for backlog reports, work assignment sheets, and hazard communication support. A major… more
Date: September 7, 1993
Creator: Spencer, W. A.; Aiken, H. B.; Spatz, T. L.; Miles, W. F. & Griffin, J. C.
Partner: UNT Libraries Government Documents Department
open access

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 limit… more
Date: October 1, 2001
Creator: Tso, Chi-Fung; Molitoris, David; Snow, Spencer & Norman, Alex
Partner: UNT Libraries Government Documents Department
open access

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 sp… more
Date: March 1, 2011
Creator: Koonce, Anthony; Knudsen, James & Buell, Robert
Partner: UNT Libraries Government Documents Department
open access

Documented Safety Analysis Addendum for the Neutron Radiography Reactor Facility Core Conversion

Description: The Neutron Radiography Reactor Facility (NRAD) is a Training, Research, Isotope Production, General Atomics (TRIGA) reactor which was installed in the Idaho National Laboratory (INL) Hot Fuels Examination Facility (HFEF) at the Materials and Fuels Complex (MFC) in the mid 1970s. The facility provides researchers the capability to examine both irradiated and non-irradiated materials in support of reactor fuel and components programs through non-destructive neutron radiography examination. The f… more
Date: May 1, 2009
Creator: Christensen, Boyd D.
Partner: UNT Libraries Government Documents Department
open access

On the Correct Application of the 100-40-40 Rule for Combining Responses Due to three Directions of Earthquake Loading

Description: The 100-40-40 rule is often used with the response spectrum analysis method to determine the maximum seismic responses from structural responses resulting from the three spatial earthquake components. This rule has been referenced in several recent Design Certification applications of nuclear power plants, and appears to be gaining in popularity. However, this rule is described differently in ASCE 4-98 and Regulatory Guide 1.92, consequently causing confusion on correct implementation of this r… more
Date: July 18, 2010
Creator: Nie, J.; Morante, R.; Miranda, M. & Braverman, J.
Partner: UNT Libraries Government Documents Department
open access

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… more
Date: March 26, 2007
Creator: Higgins, J. C.; Ohara, J. M. & Bongarra, J.
Partner: UNT Libraries Government Documents Department
open access

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 Rep… more
Date: June 24, 2007
Creator: Sullivan, K.
Partner: UNT Libraries Government Documents Department
open access

Uncertainty and Sensitivity of Alternative Rn-222 Flux Density Models Used in Performance Assessment

Description: Performance assessments for the Area 5 Radioactive Waste Management Site on the Nevada Test Site have used three different mathematical models to estimate Rn-222 flux density. This study describes the performance, uncertainty, and sensitivity of the three models which include the U.S. Nuclear Regulatory Commission Regulatory Guide 3.64 analytical method and two numerical methods. The uncertainty of each model was determined by Monte Carlo simulation using Latin hypercube sampling. The global se… more
Date: June 1, 2007
Creator: Greg J. Shott, Vefa Yucel, Lloyd Desotell Non-Nstec Authors: G. Pyles and Jon Carilli (NNSA)
Partner: UNT Libraries Government Documents Department
open access

Development of a Standard for Verification and Validation of Software Used to Calculate Nuclear System Thermal Fluids Behavior

Description: With the resurgence of nuclear power and increased interest in advanced nuclear reactors as an option to supply abundant energy without the associated greenhouse gas emissions of the more conventional fossil fuel energy sources, there is a need to establish internationally recognized standards for the verification and validation (V&V) of software used to calculate the thermal-hydraulic behavior of advanced reactor designs for both normal operation and hypothetical accident conditions. To addres… more
Date: May 1, 2010
Creator: Schultz, Richard R.; Harvego, Edwin A. & Crane, Ryan L.
Partner: UNT Libraries Government Documents Department
open access

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… more
Date: January 31, 2005
Creator: Leo, Geary
Partner: UNT Libraries Government Documents Department
open access

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
open access

Reactor Accident Analysis Methodology for the Advanced Test Reactor Critical Facility Documented Safety Analysis Upgrade

Description: The regulatory requirement to develop an upgraded safety basis for a DOE Nuclear Facility was realized in January 2001 by issuance of a revision to Title 10 of the Code of Federal Regulations Section 830 (10 CFR 830). Subpart B of 10 CFR 830, ''Safety Basis Requirements,'' requires a contractor responsible for a DOE Hazard Category 1, 2, or 3 nuclear facility to either submit by April 9, 2001 the existing safety basis which already meets the requirements of Subpart B, or to submit by April 10, … more
Date: May 13, 2003
Creator: Sharp, Gregg L. & McCracken, Richard T.
Partner: UNT Libraries Government Documents Department
open access

Requirements, guidance and logic in planning environmental investigations: Approval versus implementation

Description: In today`s litigious society, it is important for both private parties and government to plan and conduct environmental investigations in a scientifically sound manner, documenting the purpose, methods, and results in a consistent fashion throughout the exercise. Planning documents are prepared during the initial phases of environmental investigations. Project objectives, including data quality requirements, specific work to be conducted to fulfill data needs, and operating procedures are speci… more
Date: September 9, 1993
Creator: Brice, D. A.; Meredith, D. V. & Harris, M. Q.
Partner: UNT Libraries Government Documents Department
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