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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

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

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

Nuclear Regulatory Commission Issuances. Volume 45, No. 3

Description: This report includes the issuances received in March 1997. Issuances are from the Commission, the Atomic Safety and Licensing Boards, and the Directors` Decisions. 10 issuances were received: Louisiana Energy Services (2 issuances); Illinois Power Company and Soyland Power Cooperative; Ralph. L. Tetrick; University of Cincinnati; Consumers Power Company; Entergy Operations, Inc.; Georgia Power Company; Westinghouse Electric Corporation; and Wisconsin Electric Power Company. No issuances were received from the the Administrative Law Judges or the Decisions on Petitions for Rulemaking.
Date: March 1, 1997
Partner: UNT Libraries Government Documents Department

Makeup water treatment and auxiliary boiler building structural design description: 4 x 350 MW(t) Modular HTGR [High-Temperature Gas-Cooled Reactor] Plant

Description: The Makeup Water Treatment and Auxiliary Boiler Building (MWABB) is a grade-founded, single-story, steel-framed structure with insulated sheet metal exterior walls and roof decking. It houses the electrically-heated auxiliary boiler and related equipment, and the Raw Water Treatment System. The Makeup Water Treatment and Auxiliary Boiler building is located adjacent to the Maintenance Building in the Energy Conversion Area of the plant.
Date: June 1, 1986
Partner: UNT Libraries Government Documents Department

Systems analysis programs for Hands-on integrated reliability evaluations (SAPHIRE) Version 5.0: Verification and validation (V&V) manual. Volume 9

Description: A verification and validation (V&V) process has been performed for the System Analysis Programs for Hands-on Integrated Reliability Evaluation (SAPHIRE) Version 5.0. SAPHIRE is a set of four computer programs that NRC developed for performing probabilistic risk assessments. They allow an analyst to perform many of the functions necessary to create, quantify, and evaluate the risk associated with a facility or process being analyzed. The programs are Integrated Reliability and Risk Analysis System (IRRAS) System Analysis and Risk Assessment (SARA), Models And Results Database (MAR-D), and Fault tree, Event tree, and Piping and instrumentation diagram (FEP) graphical editor. Intent of this program is to perform a V&V of successive versions of SAPHIRE. Previous efforts have been the V&V of SAPHIRE Version 4.0. The SAPHIRE 5.0 V&V plan is based on the SAPHIRE 4.0 V&V plan with revisions to incorporate lessons learned from the previous effort. Also, the SAPHIRE 5.0 vital and nonvital test procedures are based on the test procedures from SAPHIRE 4.0 with revisions to include the new SAPHIRE 5.0 features as well as to incorporate lessons learned from the previous effort. Most results from the testing were acceptable; however, some discrepancies between expected code operation and actual code operation were identified. Modifications made to SAPHIRE are identified.
Date: March 1, 1995
Creator: Jones, J.L.; Calley, M.B.; Capps, E.L.; Zeigler, S.L.; Galyean, W.J.; Novack, S.D. et al.
Partner: UNT Libraries Government Documents Department

Inspection of Nuclear Power Plant Containment Structures

Description: Safety-related nuclear power plant (NPP) structures are designed to withstand loadings from a number of low-probability external and interval events, such as earthquakes, tornadoes, and loss-of-coolant accidents. Loadings incurred during normal plant operation therefore generally are not significant enough to cause appreciable degradation. However, these structures are susceptible to aging by various processes depending on the operating environment and service conditions. The effects of these processes may accumulate within these structures over time to cause failure under design conditions, or lead to costly repair. In the late 1980s and early 1990s several occurrences of degradation of NPP structures were discovered at various facilities (e.g., corrosion of pressure boundary components, freeze- thaw damage of concrete, and larger than anticipated loss of prestressing force). Despite these degradation occurrences and a trend for an increasing rate of occurrence, in-service inspection of the safety-related structures continued to be performed in a somewhat cursory manner. Starting in 1991, the U.S. Nuclear Regulatory Commission (USNRC) published the first of several new requirements to help ensure that adequate in-service inspection of these structures is performed. Current regulatory in-service inspection requirements are reviewed and a summary of degradation experience presented. Nondestructive examination techniques commonly used to inspect the NPP steel and concrete structures to identify and quantify the amount of damage present are reviewed. Finally, areas where nondestructive evaluation techniques require development (i.e., inaccessible portions of the containment pressure boundary, and thick heavily reinforced concrete sections are discussed.
Date: December 1, 1998
Creator: Graves, H.L.; Naus, D.J. & Norris, W.E.
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

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

Safety survey report EBR-II safety survey, ANL-west health protection, industrial safety and fire protection survey

Description: A safety survey covering the disciplines of Reactor Safety, Nuclear Criticality Safety, Health Protection and Industrial Safety and Fire Protection was conducted at the ANL-West EBR-II FEF Complex during the period January 10-18, 1972. In addition, the entire ANL-West site was surveyed for Health Protection and Industrial Safety and Fire Protection. The survey was conducted by members of the AEC Chicago Operations Office, a member of RDT-HQ and a member of the RDT-ID site office. Eighteen recommendations resulted from the survey, eleven in the area of Industrial Safety and Fire Protection, five in the area of Reactor Safety and two in the area of Nuclear Criticality Safety.
Date: January 10, 1972
Creator: Dunbar, K.A.
Partner: UNT Libraries Government Documents Department

Discussion of Comments from a Peer Review of A Technique for Human Event Anlysis (ATHEANA)

Description: In May of 1998, a technical basis and implementation guidelines document for A Technique for Human Event Analysis (ATHEANA) was issued as a draft report for public comment (NUREG-1624). In conjunction with the release of draft NUREG- 1624, a peer review of the new human reliability analysis method its documentation and the results of an initial test of the method was held over a two-day period in June 1998 in Seattle, Washington. Four internationally known and respected experts in HK4 or probabilistic risk assessment were selected to serve as the peer reviewers. In addition, approximately 20 other individuals with an interest in HRA and ATHEANA also attended the peer and were invited to provide comments. The peer review team was asked to comment on any aspect of the method or the report in which improvements could be made and to discuss its strengths and weaknesses. They were asked to focus on two major aspects: Are the basic premises of ATHEANA on solid ground and is the conceptual basis adequate? Is the ATHEANA implementation process adequate given the description of the intended users in the documentation? The four peer reviewers asked questions and provided oral comments during the peer review meeting and provided written comments approximately two weeks after the completion of the meeting. This paper discusses their major comments.
Date: January 28, 1999
Creator: Bley, D.C.; Cooper, S.E.; Forester, J.A.; Kolaczkowski, A.M.; Ramey-Smith, A, & J., Wreathall
Partner: UNT Libraries Government Documents Department

Helium Storage and Transfer Subsystem design description. Revision

Description: The Helium Storage and Transfer Subsystem (HSTS) consists of two parts. The first consists of nine (9) high pressure storage tanks containing helium at 15.6 MPa (2250 psig). These tanks provide makeup and purge helium at a rate of 1216 kg per y (2680 lb/y) to the various helium users, including circulator bearing seals, analysis packages, and cooling system surge tanks. The second, larger part of the system, provides for the low pressure storage of 6078 kg (13,400 lb) of primary coolant helium in 180 storage tanks at 7.0 MPa (1000 psig). The system serves all four (4) reactor modules. The low pressure storage part of the system receives helium from the discharge of Helium Purification Subsystem (HPS) and is activated during depressurization and pumpup operations only. It is not required to operate continuously. Storage capacity is provided for primary helium coolant from two reactor modules. However, since depressurization and pumpup operations are performed for only one reactor module at a time, two 50% capacity low pressure transfer compressors are provided having a total transfer capacity of 340 am{sup 3}/h (200 acfm) which is sufficient to service one module. High pressure helium is supplied continuously to all the four reactor modules simultaneously from the high pressure storage tanks. These tanks are replaced periodically with fresh tanks.
Date: July 1, 1987
Partner: UNT Libraries Government Documents Department

Security monitoring subsystem design description: 4 x 350 MW(t) Modular HTGR [High-Temperature Gas-Cooled Reactor] Plant

Description: Security Monitoring acquires and processes sensor data for use by security personnel in the performance of their function. Security Monitoring is designed and implemented as a part of an overall security plan which is classified as Safeguards Information under 10CFR73.21.
Date: June 1, 1986
Partner: UNT Libraries Government Documents Department

Standard Review Plan Maintenance Program implementing procedures document

Description: The implementing Procedures Document (IPD) was developed by the Inspection Program Projects Branch, Office of Nuclear Reactor Regulation, with assistance from Pacific Northwest National Laboratory, for the Standard Review Plan Maintenance Program (SRP-MP). The SRP-MP was established to maintain the Standard Review Plan (SRP) on an on-going basis. The IPD provides guidance, including an overall approach and procedures, for SRP-MP tasks. The objective of the IPD is to ensure that modifications to SRP need to reflect current NRC requirements and guidance are identified and that a consistent methodology is used to develop and revise SRP sections.
Date: November 1, 1996
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

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

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

Nuclear Regulatory Commission issuances, Volume 44, No. 4

Description: This report includes the issuances received in October 1996. Issuances are from the Commission, the Atomic Safety and Licensing Boards, and the Directors` Decisions. 15 issuances were received and are abstracted individually in the database: Louisiana Energy Services, U.S. Enrichment Corporation, Yankee Atomic Electric Company, General Public Utilities Nuclear Corporation, James L. Shelton, Juan Guzman, Northern States Power Company, TESTCO Inc., Washington Public Power Supply System, all nuclear plants, Cleveland Electric Illuminating Company, Duke Power Company, Florida Power Corporation, and Northeast Nuclear Energy Company (2 issuances). No issuances were received from the the Administrative Law Judges or the Decisions on Petitions for Rulemaking.
Date: October 1, 1996
Partner: UNT Libraries Government Documents Department

Molten salt reactors - safety options galore

Description: Safety features and attributes of molten salt reactors (MSR) are described. The unique features of fluid fuel reactors of on-line continuous processing and the ability for so-called external cooling result in simple and safe designs with low excess reactivity, low fission product inventory, and small source term. These, in turn, make a criticality accident unlikely and reduce the severity of a loss of coolant to where they are no longer severe accidents. A melt down is not an accident for a reactor that uses molten fuel. The molten salts are stable, non-reactive and efficient heat transfer media that operate at high temperatures at low pressures and are highly compatible with selected structural materials. All these features reduce the accident plethora. Freeze valves can be used for added safety. An ultimate safe reactor (U.S.R) is described with safety features that are passive, inherent and non-tamperable (PINT).
Date: March 1, 1997
Creator: Gat, U. & Dodds, H.L.
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