1,252 Matching Results

Search Results

Advanced search parameters have been applied.

A Methodology for Evaluation of Inservice Test Intervals for Pumps and Motor Operated Valves

Description: The nuclear industry has begun efforts to reevaluate inservice tests (ISTs) for key components such as pumps and valves. At issue are two important questions--What kinds of tests provide the most meaningful information about component health, and what periodic test intervals are appropriate? In the past, requirements for component testing were prescribed by the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code. The tests and test intervals specified in the Code were generic in nature and test intervals were relatively short. Operating experience has shown, however, that performance and safety improvements and cost savings could be realized by tailoring IST programs to similar components with comparable safety importance and service conditions. In many cases, test intervals may be lengthened, resulting in cost savings for utilities and their customers.
Date: August 1, 1999
Creator: McElhaney, K.L.
Partner: UNT Libraries Government Documents Department

Indexes to Nuclear Regulatory Commission issuances, July--December 1995

Description: Digests and indexes for issuances of the NRC, the Atomic Safety and Licensing Board, the Administrative Law Judges, the Directors` Decisions, and the Decisions on Petitions for Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances. Information elements common to the cases heard and ruled upon are: (1) case name, (2) full text reference, (3) issuance number, (4) issued raised by appellants, (5) legal citations, (6) name of facility and Docket number, (7) subject matter, (8) type of hearing, and (9) type of issuance.
Date: April 1, 1996
Partner: UNT Libraries Government Documents Department

Regulatory and Technical Reports (Abstract Index Journal). Annual compilation for 1995, Volume 20, No. 4

Description: The Nuclear Regulatory Commission`s annual summary of licensed nuclear power reactor data is based primarily on the report of operating data submitted by licensees for each unit for the month of December because that report contains data for the month of December, the year to date (in this case calendar year 1994) and cumulative data, usually from the date of commercial operation. The data is not independently verified, but various computer checks are made. The report is divided into two sections. The first contains summary highlights and the second contains data on each individual unit in commercial operation Section 1 capacity and availability factors are simple arithmetic averages. Section 2 items in the cumulative column are generally as reported by the licensee and notes as to the use of weighted averages and starting dates other than commercial operation are provided.
Date: April 1, 1995
Creator: Sheehan, M.
Partner: UNT Libraries Government Documents Department

Shallow Flaws Under Biaxial Loading Conditions, Part II: Application of a Weibull Stress Analysis of the Cruciform Bend Specimen Using a Hydrostatic Stress Criterion

Description: Cruciform beam fracture mechanics specimensl have been developed in the Heavy Section Steel Technology (HSST) Program at Oak Ridge National Laboratory (ORNL) to introduce a prototypic, far- field, out-of-plane biaxird bending stress component in the test section that approximates the nonlinear biaxial stresses resulting from pressurized-thernxd-shock or pressure-temperature loading of a nuclear reactor pressure vessel (RPV). Matrices of cruciform beam tests were developed to investigate and quantify the effects of temperature, biaxial loading, and specimen size on fracture initiation toughness of two-dimensional (constant depth), shtdlow, surface flaws. Tests were conducted under biaxial load ratios ranging from uniaxial to equibiaxial. These tests demonstrated that biaxial loading can have a pronounced effect on shallow-flaw fracture toughness in the lower transition temperature region for RPV materials. Two and three- parameter Weibull models have been calibrated using a new scheme (developed at the University of Illinois) that maps toughness data from test specimens with distinctly different levels of crack-tip constraint to a small scale yielding (SSY) Weibull stress space. These models, using the new hydrostatic stress criterion in place of the more commonly used maximum principal stress in the kernel of the OW integral definition, have been shown to correlate the experimentally observed biaxiaI effect in cruciform specimens, thereby providing a scaling mechanism between uniaxial and biaxial loading states.
Date: August 1999
Creator: Bass, B. R.; McAfee, W. J. & Williams, P. T.
Partner: UNT Libraries Government Documents Department

Time series analysis of nuclear instrumentation in EBR-II

Description: Results of a time series analysis of the scaler count data from the 3 wide range nuclear detectors in the Experimental Breeder Reactor-II are presented. One of the channels was replaced, and it was desired to determine if there was any statistically significant change (ie, improvement) in the channel`s response after the replacement. Data were collected from all 3 channels for 16-day periods before and after detector replacement. Time series analysis and statistical tests showed that there was no significant change after the detector replacement. Also, there were no statistically significant differences among the 3 channels, either before or after the replacement. Finally, it was determined that errors in the reactivity change inferred from subcritical count monitoring during fuel handling would be on the other of 20-30 cents for single count intervals.
Date: May 1, 1996
Creator: Imel, G.R.
Partner: UNT Libraries Government Documents Department

Electromagnetic Compatibility in Nuclear Power Plants

Description: Electromagnetic compatibility (EMC) has long been a key element of qualification for mission critical instrumentation and control (I&C) systems used by the U.S. military. The potential for disruption of safety-related I&C systems by electromagnetic interference (EMI), radio-frequency interference (RFI), or power surges is also an issue of concern for the nuclear industry. Experimental investigations of the potential vulnerability of advanced safety systems to EMI/RFI, coupled with studies of reported events at nuclear power plants (NPPs) that are attributed to EMI/RFI, confirm the safety significance of EMC for both analog and digital technology. As a result, Oak Ridge National Laboratory has been engaged in the development of the technical basis for guidance that addresses EMC for safety-related I&C systems in NPPs. This research has involved the identification of engineering practices to minimize the potential impact of EMI/RFI and power surges and an evaluation of the ambient electromagnetic environment at NPPs to tailor those practices for use by the nuclear industry. Recommendations for EMC guidance have been derived from these research findings and are summarized in this paper.
Date: August 29, 1999
Creator: Ewing, P.D.; Kercel, S.W.; Korsah, K. & Wood, R.T.
Partner: UNT Libraries Government Documents Department

Planning and conduct of Operational Readiness Reviews (ORR)

Description: The purpose of this standard is to describe acceptable methods and approaches to meet the readiness review requirements of DOE 425.1. Specifically, this standard describes methods and approaches to: (1) Determine the type of readiness review which is appropriate to the specific facility startup; (2) Develop the breadth and depth (scope) of the ORR or RA so as to be consistent with the history, hazards, and complexity of the facility being started up; (3) Develop the procedures and conduct an ORR or RA for startup of a specific activity; (4) Verify that the facility is physically ready to startup; (5) Verify that the managers and operators are prepared to manage and operate the facility in the phase in which it is about to startup; (6) Verify that the necessary infrastructure (procedures, staffing, compliance with DOE Orders, rules, and other requirements, etc.) is in place; and (7) Prepare requests for exemptions from the requirements of DOE 425.1
Date: November 1, 1995
Partner: UNT Libraries Government Documents Department

Enforcement actions: Significant actions resolved material licensees. Quarterly progress report, April 1995--June 1995

Description: This compilation summarizes significant enforcement actions that have been resolved during one quarterly period (April-June 1995) and includes copies of letters, Notices, and Orders sent by the Nuclear Regulatory Commission to material licensees with respect to these enforcement actions. It is anticipated that the information in this publication will be widely disseminated to managers and employees engaged in activities licensed by the NRC, so that actions can be taken to improve safety by avoiding future violations similar to those described in this publication.
Date: August 1, 1995
Partner: UNT Libraries Government Documents Department

Comparison of ASME Code NB-3200 and NB-3600 results for fatigue analysis of B31.1 branch nozzles

Description: Fatigue analyses wre conducted on two reactor coolant system branch nozzles in an operating PWR designed to the B31.1 Code, for which no explicit fatigue analysis was required by the licensing basis. These analyses were performed as part of resolving issues connected with NRC`s Fatigue Action Plan to determine if the cumulative usage factor (CUF) for these nozzles, using the 1992 ASME Code and representative PWR transients, were comparable to nozzles designed and analyzed to the ASME Code. Both NB-3200 and NB-3600 ASME Code methods were used. NB-3200 analyses included the development of finite element models for each nozzle. Although detailed thermal transients were not available for the plant analyzed, representative transients from similar PWRs were applied in each method. CUFs calculated using NB-3200 methods were significantly less than using NB-3600. The paper points out differences in analysis methods and highlights difficulties and unknowns in performing more detailed analyses to reduce conservative assumptions.
Date: June 1, 1996
Creator: Nitzel, M.E.; Ware, A.G. & Morton, D.K.
Partner: UNT Libraries Government Documents Department

Comparison of ISO 9000 and recent software life cycle standards to nuclear regulatory review guidance

Description: Lawrence Livermore National Laboratory is assisting the Nuclear Regulatory Commission with the assessment of certain quality and software life cycle standards to determine whether additional guidance for the U.S. nuclear regulatory context should be derived from the standards. This report describes the nature of the standards and compares the guidance of the standards to that of the recently updated Standard Review Plan.
Date: January 20, 1998
Creator: Preckshot, G.G. & Scott, J.A.
Partner: UNT Libraries Government Documents Department

Nuclear Regulatory Commission Issuances, Volume 44, No. 5

Description: This report includes the issuances received in November 1996. Issuances are from the Commission, the Atomic Safety and Licensing Boards, and the Directors` Decisions. Seven issuances were received and are abstracted individually in the database: Emerick S. McDaniel, U.S. Enrichment Corporation, Sequoyah Fuels Corporation and General Atomics, all power reactor licensees, Florida Power and Light Company, Maine Yankee Atomic Power Company, and Northern States Power Company. No issuances were received from the the Administrative Law Judges or the Decisions on Petitions for Rulemaking.
Date: November 1, 1996
Partner: UNT Libraries Government Documents Department

Licensee contractor and vendor and vendor inspection status report. Quarterly report, July 1995--September 1995

Description: This periodical covers the results of inspections performed by the NRC`s Special Inspection Branch, Vendor Inspection Section, that have been distributed to the inspected organizations during the period from July 1995 through September 1995. Vendors inspected include: (1) Continental Disc Corporation, (2) Divesco, (3) Eaton, (4) General Electric Nuclear Energy, (5) ITT Barton, (6) Liberty Technologies, (7) Mid-South Nuclear, (8) Power Distribution Services, (9) Rosemount, (10) Target-Rock, and (11) Westinghouse Electric.
Date: December 1, 1995
Partner: UNT Libraries Government Documents Department

Licensee contractor and vendor inspection status report. Quarterly progress report, April 1996--June 1996

Description: The federal government and nuclear industry have established a system for the inspection of commercial nuclear facilities to provide for multiple levels of inspection and verification. The Vendor Inspection System (VIS) of the Special Inspection Branch reviews and inspects the quality and suitability of vendor products, licensee-vendor interface, environmental qualification of equipment, and review of equipment problems found during operation and their corrective action. This report contains copies of all vendor inspection reports issued during the calendar year for which it is published.
Date: August 1, 1996
Partner: UNT Libraries Government Documents Department

Aging assessment of Westinghouse PWR and General Electric BWR containment isolation functions

Description: A study was performed to assess the effects of aging on the Containment Isolation (CI) functions of Westinghouse Pressurized Water Reactors and General Electric Boiling Water Reactors. This study is part of the Nuclear Plant Aging Research (NPAR) program, sponsored by the U.S. Nuclear Regulatory Commission. The objectives of this program are to provide an understanding of the aging process and how it affects plant safety so that it can be properly managed. This is one of a number of studies performed under the NPAR program which provide a technical basis for the identification and evaluation of degradation caused by age. Failure data from two national databases, Nuclear Plant Reliability Data System (NPRDS) and Licensee Event Reports (LERs), as well as plant specific data were reviewed and analyzed to understand the effects of aging on the CI functions. This study provided information on the effects of aging on component failure frequency, failure modes, and failure causes. Current inspection, surveillance, and monitoring practices were also reviewed.
Date: March 1996
Creator: Lee, B. S.; Travis, R.; Grove, E. & DiBiasio, A.
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

Piping benchmark problems for the Westinghouse AP600 Standardized Plant

Description: To satisfy the need for verification of the computer programs and modeling techniques that will be used to perform the final piping analyses for the Westinghouse AP600 Standardized Plant, three benchmark problems were developed. The problems are representative piping systems subjected to representative dynamic loads with solutions developed using the methods being proposed for analysis for the AP600 standard design. It will be required that the combined license licensees demonstrate that their solutions to these problems are in agreement with the benchmark problem set.
Date: January 1997
Creator: Bezler, P.; DeGrassi, G.; Braverman, J. & Wang, Y. K.
Partner: UNT Libraries Government Documents Department

Fitness for duty in the nuclear power industry: Annual summary of program performance reports CY 1994. Volume 5

Description: This report summarizes the data from the semiannual reports on fitness-for-duty programs submitted to the NRC by utilities for two reporting periods: January 1 through June 30, 1994, and July I through December 31, 1994. During 1994, licensees reported that they had conducted 163,241 tests for the presence of illegal drugs and alcohol. Of these tests, 1,372 (.84%) were confirmed positive. Positive test results varied by category of test and category of worker. The majority of positive test results (977) were obtained through pre-access testing. Of tests conducted on workers having access to the protected area, there were 223 positive tests from random testing and 122 positive tests from for-cause testing. Follow-up testing of workers who had previously tested positive resulted in 50 positive tests. For-cause testing resulted in the highest percentage of positive tests; about 16 percent of for-cause tests were positive. This compares with a positive test rate of 1.22 percent of pre-access tests and .28 percent of random tests. The positive test rate for badged workers (including only random, for-cause, and follow-up test results) was .48 percent. Positive test rates also varied by category of worker. When all types of tests are combined (pre-access, random, for-cause, and follow-up testing), short-term contractor personnel had the highest positive test rate at 1.22 percent. Licensee employees and long-term contractors had lower combined positive test rates (.33% and .49%, respectively). Of the substances tested, marijuana was responsible for the highest percentage of positive test results (52.07%), followed by cocaine (24.25%) and alcohol (17.45%).
Date: August 1995
Creator: Westra, C.; Durbin, N. & Field, I.
Partner: UNT Libraries Government Documents Department

U.S. Nuclear Regulatory Commission organization charts and functional statements. Revision 18

Description: This document (NUREG-0325) is the current US NRC organization chart, listing all NRC offices and regions and their components down through the branch level as of July 23, 1995. Functional statements of each position are given, as is the name of the individual holding the position.
Date: July 23, 1995
Partner: UNT Libraries Government Documents Department

US Nuclear Regulatory Commission organization charts and functional statements

Description: This document is the organizational chart for the US NRC. It contains organizational structure and functional statements for the following: (1) the Commission, (2) committees and boards, (3) staff offices, (4) office of the Inspector General, (5) executive director for operations, (6) program offices, and (7) regional offices.
Date: August 19, 1996
Partner: UNT Libraries Government Documents Department

Indexes to Nuclear Regulatory Commission Issuances, January--June 1997

Description: This report indexes the issuances heard and ruled upon from January through June 1997. Issuances are from the Commission, the Atomic Safety and Licensing Boards, the Administrative Law Judges, the Directors` Decisions, and the Decisions on Petitions for Rulemaking. Information provided for each case includes the case name, full test reference, issuance number, issues raised by appellants, legal citations, facility name and docket number, subject matter of issues and/or rulings, type of hearing, and type of issuance. Each issuance is displayed in one or more of five separate formats: (1) case name index, (2) headers and digests, (3) legal citations index, (4) subject index, and (5) facility index.
Date: October 1, 1997
Partner: UNT Libraries Government Documents Department

Codes and standards and other guidance cited in regulatory documents

Description: As part of the U.S. Nuclear Regulatory Commission (NRC) Standard Review Plan Update and Development Program (SRP-UDP), Pacific Northwest National Laboratory developed a listing of industry consensus codes and standards and other government and industry guidance referred to in regulatory documents. The SRP-UDP has been completed and the SRP-Maintenance Program (SRP-MP) is now maintaining this listing. Besides updating previous information, Revision 3 adds approximately 80 citations. This listing identifies the version of the code or standard cited in the regulatory document, the regulatory document, and the current version of the code or standard. It also provides a summary characterization of the nature of the citation. This listing was developed from electronic searches of the Code of Federal Regulations and the NRC`s Bulletins, Information Notices, Circulars, Enforcement Manual, Generic Letters, Inspection Manual, Policy Statements, Regulatory Guides, Standard Technical Specifications and the Standard Review Plan (NUREG-0800).
Date: August 1996
Creator: Nickolaus, J. R. & Bohlander, K .L.
Partner: UNT Libraries Government Documents Department