LAND JUDGING AND PLANT NUTRITION, A PROGRAMMED INSTRUCTION UNIT, REPORT NUMBER 13.

Science.gov (United States)

LONG, GILBERT A.

A UNIT OF PROGRAMED LEARNING MATERIALS WAS PRESENTED ON THE PRINCIPLES AND PROCEDURES OF LAND JUDGING AND PLANT NUTRITION. IN HIS PREPARATION, THE AUTHOR FIRST IDENTIFIED PRINCIPLES AND FACTS NECESSARY FOR EFFECTIVE LAND CLASSIFICATION AND PLANT NUTRITION BY EXAMINING RELEVANT SCIENTIFIC REPORTS. USING THIS INFORMATION, HE THEN FORMED A TEAM OF 16…

Examining work structure in nuclear power plants

International Nuclear Information System (INIS)

Bauman, M.B.; Boulette, M.D.; Van Cott, H.P.

1985-01-01

This paper describes the assessment of the work structure of ten nuclear power plants. Work structure factors are those factors that relate to the way in which work at all levels in a plant is organized, staffed, managed, rewarded, and perceived by plant personnel. Questionnaires given to a cross-section of personnel at the plants were the primary source of data collection. Structured ''critical incident'' interviews were conducted to verify the questionnaire results. The study revealed that a variety of work structure factor problem areas do exist in nuclear power plants. The paper highlights a prioritized set of candidate research themes to be considered in EPRI's Work Structure and Performance Research Program

Exploratory study of the radiation-protection training programs in nuclear power plants

International Nuclear Information System (INIS)

Fields, C.D.

1982-06-01

The objective of the study was to examine current radiation training programs at a sample of utilities operating nuclear reactors and to evaluate employee information on radiation health. The study addressed three elements: (1) employee perceptions and understanding of ionizing radiation; (2) utility trainers-their background, training, and problems; (3) the content, materials, and conduct of training programs; (4) program uniformity and completeness. These areas were examined through visits to utilities, surveys, and employee interviews. The programs reviewed were developed by utility personnel who have backgrounds, for the most part, in health physics but who may have little formal training in adult education. This orientation, coupled with the inherent nature of the subject, has produced training programs that appear to be too technical to achieve the educational job intended. The average nuclear power plant worker does not have the level of sophistication needed to understand some of the information. It became apparent that nuclear power plant workers have concerns that do not necessarily reflect those of the scientific community. Many of these result from misunderstandings about radiation. Unfortunately, the training programs do not always address these unfounded but very real fears

Water Treatment Plant Operation Volume 2. A Field Study Training Program. Revised.

Science.gov (United States)

California State Univ., Sacramento. School of Engineering.

The purpose of this water treatment field study training program is to: (1) develop new qualified water treatment plant operators; (2) expand the abilities of existing operators, permitting better service both to employers and public; and (3) prepare operators for civil service and certification examinations (examinations administered by…

Plant performance monitoring program at Krsko NPP

International Nuclear Information System (INIS)

Bach, B.; Kavsek, D.

2004-01-01

A high level of nuclear safety and plant reliability results from the complex interaction of a good design, operational safety and human performance. This is the reason for establishing a set of operational plant safety performance indicators, to enable monitoring of both plant performance and progress. Performance indicators are also used for setting challenging targets and goals for improvement, to gain additional perspective on performance relative to other plants and to provide an indication of a potential need to adjust priorities and resources to achieve improved overall plant performance. A specific indicator trend over a certain period can provide an early warning to plant management to evaluate the causes behind the observed changes. In addition to monitoring the changes and trends, it is also necessary to compare the indicators with identified targets and goals to evaluate performance strengths and weaknesses. Plant Performance Monitoring Program at Krsko NPP defines and ensures consistent collection, processing, analysis and use of predefined relevant plant operational data, providing a quantitative indication of nuclear power plant performance. When the program was developed, the conceptual framework described in IAEA TECDOC-1141 Operational Safety Performance Indicators for Nuclear Power Plants was used as its basis in order to secure that a reasonable set of quantitative indications of operational safety performance would be established. Safe, conservative, cautious and reliable operation of the Krsko NPP is a common goal for all plant personnel. It is provided by continuous assurance of both health and safety of the public and employees according to the plant policy stated in program MD-1 Notranje usmeritve in cilji NEK, which is the top plant program. Establishing a program of monitoring and assessing operational plant safety performance indicators represents effective safety culture of plant personnel.(author)

Optimal installation program for reprocessing plants

International Nuclear Information System (INIS)

Kubokawa, Toshihiko; Kiyose, Ryohei

1976-01-01

Optimization of the program of installation of reprocessing plants is mathematically formulated as problem of mixed integer programming, which is numerically solved by the branch-and-bound method. A new concept of quasi-penalty is used to obviate the difficulties associated with dual degeneracy. The finiteness of the useful life of the plant is also taken into consideration. It is shown that an analogous formulation is possible for the cases in which the demand forecasts and expected plant lives cannot be predicted with certainty. The scale of the problem is found to have kN binary variables, (k+2)N continuous variables, and (k+3)N constraint conditions, where k is the number of intervals used in the piece-wise linear approximation of a nonlinear objective function, and N the overall duration of the period covered by the installation program. Calculations are made for N=24 yr and k=3, with the assumption that the plant life is 15 yr, the plant scale factor 0.5, and the maximum plant capacity 900 (t/yr). The results are calculated and discussed for four different demand forecasts. The difference of net profit between optimal and non-optimal installation programs is found to be in the range of 50 -- 100 M$. The pay-off matrix is calculated, and the optimal choice of action when the demand cannot be forecast with certainty is determined by applying Bayes' theory. The optimal installation program under such conditions of uncertainty is obtained also with a stochastic mixed integer programming model. (auth.)

Cost effective snubber reduction program for nuclear power plants

International Nuclear Information System (INIS)

Adams, T.M.; Antaki, G.A.; Chang, K.C.

1985-01-01

Due to the stringent seismic requirements imposed on nuclear power plants, piping engineers have resorted to the extensive use of snubbers to support nuclear piping systems. The advantage of snubbers is that they provide dynamic restraint while allowing free thermal growth of the pipe. Unfortunately, as more plants go into operation, utilities have to face the costs of strict in-service inspection requirements and risks of unscheduled or extended plant outages associated with snubber failures. The snubber inspection requirements, defined in plant Technical Specifications, require periodic visual inspections of all snubbers and functional tests of a percentage of the plant snubbers, during refueling outages. For a typical 1000 Mw unit this represents from 50 to several hundred snubbers to be functionally tested at each refueling outage. Should failures occur during testing, the sample size must be further increased. Very quickly the costs and risks of extended shutdowns have led the industry to consider, and in many cases implement, snubber reduction programs. At the same time several changes in seismic design criteria have greatly facilitated the reduction of snubbers, making snubber elimination economically and technically attractive. In this paper we examine the costs and benefits of snubber reduction programs and propose a method for evaluating their cost benefits

Angra nuclear plant - environmental control program

International Nuclear Information System (INIS)

Kircher, E.; Cruz, E.S. da

1989-01-01

The pre-operational studies, that were elaborated before the beginning of Angra I Power Plant operation, are described in particular the environmental radiological safety area till the fuel loading in the core reactor. Several aspects are included, as socio-economic survey, seismological analysis, Meteorological Program, marine biology, water cooling system, exposure measures of natural radiation, marine sediments characterization in the effluent dispersion area and Environmental Radiological Monitoring Program. The main environmental programs developed for the operational phase of the Angra I Plant are also presented, citing some considerations about the Meteorological Program, Marine Biology Control Program, Temperature and Chlorine Control in Piraquara de Fora Bay, Radiological Environmental Monitoring Program, Sanitary Effluent Control Program and Radiological Emergency Program. (C.G.C.). 2 refs

Better Plants Program Overview

Energy Technology Data Exchange (ETDEWEB)

None

2015-09-30

The U.S. Department of Energy’s (DOE’s) Better Buildings, Better Plants Program is a voluntary partnership initiative to drive significant energy efficiency improvement across energy intensive companies and organizations. 157 leading manufacturers and public water and wastewater treatment utilities are partnering with DOE through Better Plants to improve energy efficiency, slash carbon emissions, and cut energy costs.

Tamarisk coalition - native riparian plant materials program

Science.gov (United States)

Stacy Kolegas

2012-01-01

The Tamarisk Coalition (TC), a nonprofit organization dedicated to riparian restoration in the western United States, has created a Native Plant Materials Program to address the identified need for native riparian plant species for use in revegetation efforts on the Colorado Plateau. The specific components of the Native Plant Materials Program include: 1) provide seed...

QA programs in nuclear power plants

International Nuclear Information System (INIS)

Ellingson, A.C.

1976-01-01

As an overview of quality assurance programs in nuclear power plants, the energy picture as it appears today is reviewed. Nuclear power plants and their operations are described and an attempt is made to place in proper perspective the alleged ''threats'' inherent in nuclear power. Finally, the quality assurance programs being used in the nuclear industry are described

Spanish program of advanced Nuclear Power Plants

International Nuclear Information System (INIS)

Marco, M.; Redon, R.

1993-01-01

The energy Spanish Plan is promoting some actions within the area of advanced reactors. Efforts are focussed onto the European Program of Advanced Reactors, the Program of Passive Plants (EPRI), European Fast Reactor Project and the APWR-1000 Program of INI. Electrical sector utilities and industrial partners supported by the Administration have organized an steering committee. The program of Passive Plants includes activities on Qualification, design and detailed engineering (Qualification project, SBWR project of G.E. and AP600 Project of Westinghouse. The european project on advanced plants has the following Spanish contribution: Analysis of alternative Dossier on European requisites (EUR) and Design of an European Reactor (EPR)

Program change management during nuclear power plant decommissioning

International Nuclear Information System (INIS)

Bushart, Sean; Kim, Karen; Naughton, Michael

2011-01-01

Decommissioning a nuclear power plant is a complex project. The project involves the coordination of several different departments and the management of changing plant conditions, programs, and regulations. As certain project Milestones are met, the evolution of such plant programs and regulations can help optimize project execution and cost. This paper will provide information about these Milestones and the plant departments and programs that change throughout a decommissioning project. The initial challenge in the decommissioning of a nuclear plant is the development of a definitive plan for such a complex project. EPRI has published several reports related to decommissioning planning. These earlier reports provided general guidance in formulating a Decommissioning Plan. This Change Management paper will draw from the experience gained in the last decade in decommissioning of nuclear plants. The paper discusses decommissioning in terms of a sequence of major Milestones. The plant programs, associated plans and actions, and staffing are discussed based upon experiences from the following power reactor facilities: Maine Yankee Atomic Power Plant, Yankee Nuclear Power Station, and the Haddam Neck Plant. Significant lessons learned from other sites are also discussed as appropriate. Planning is a crucial ingredient of successful decommissioning projects. The development of a definitive Decommissioning Plan can result in considerable project savings. The decommissioning plants in the U.S. have planned and executed their projects using different strategies based on their unique plant circumstances. However, experience has shown that similar project milestones and actions applied through all of these projects. This allows each plant to learn from the experiences of the preceding projects. As the plant transitions from an operating plant through decommissioning, the reduction and termination of defunct programs and regulations can help optimize all facets of

Quality Assurance Program Plan for the Waste Isolation Pilot Plant Experimental-Waste Characterization Program

International Nuclear Information System (INIS)

1991-01-01

This Quality Assurance Program Plan (QAPP) identifies the quality of data necessary to meet the specific objectives associated with the Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Experimental-Waste Characterization Program (the Program). This experimental-waste characterization program is only one part of the WIPP Test Phase, both in the short- and long-term, to quantify and evaluate the characteristics and behavior of transuranic (TRU) wastes in the repository environment. Other parts include the bin-scale and alcove tests, drum-scale tests, and laboratory experiments. In simplified terms, the purpose of the Program is to provide chemical, physical, and radiochemical data describing the characteristics of the wastes that will be emplaced in the WIPP, while the remaining WIPP Test Phase is directed at examining the behavior of these wastes in the repository environment. 50 refs., 35 figs., 33 tabs

The Susquehanna plant lifetime excellence program

International Nuclear Information System (INIS)

McNamara, R.W.

1988-01-01

This paper discusses how the Susquehanna plant lifetime excellence program (SPLEX) blends many of the objectives of a new managing for excellence program with plant life extension objectives to achieve excellence in the lifetime operation and availability of the two-unit Susquehanna steam electric station. Investments in lifetime excellence improvements will provide near-term, as well as plant life extension, benefits. A high-quality lifetime experience record, together with extensive, periodic technical assessments and cost-benefit analyses, will provide conclusive justification for future extensions of the unit operating licenses

Development of Intelligent Database Program for PSI/ISI Data Management of Nuclear Power Plant

International Nuclear Information System (INIS)

Park, Un Su; Park, Ik Keun; Um, Byong Guk; Park, Yun Won; Kang, Suk Chul

1998-01-01

For an effective and efficient management of large amounts of preservice/inservice inspection(PSI/ISI) data in nuclear power plants, an intelligent Windows 95-based data management program was developed. This program enables the prompt extraction of previously conducted PSI/ISI conditions and results so that the time-consuming data management, painstaking data processing and analysis in the past are avoided. The program extracts, and the associated remedies. Furthermore, additional inspection data and comments can be easily added or deleted for subsequent PSI/ISI operation. Although the initial version of the program was applied to Kori nuclear power plant, this program can be equally applied to other nuclear power plant. And also this program can be used to offer the fundamental data for application of evaluation data related to fracture mechanics analysis(FMA), probabilistic reliability assessment(PRA) of PSI/ISI results, performance demonstration initiative(PDI) and risk-informed ISI based on probability of detection(POD) information of ultrasonic examination. Besides, the program can be further developed as a unique PSI/ISI data management expert system that can be apart of PSI/ISI data management expert system that can be a part of PSI/ISI Total Support System(TSS) for Korean nuclear power plants

Nuclear plant aging research program

International Nuclear Information System (INIS)

Eissenberg, D.M.

1987-01-01

The U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, has established the Nuclear Plant Aging Research (NPAR) program in its Division of Engineering Technology. Principal contractors for this program include Oak Ridge National Laboratory, Brookhaven National Laboratory, Idaho National Engineering Laboratory, and Pacific Northwest Laboratory. The program goals are: to identify and characterize time-dependent degradation (aging) of nuclear plant safety-related electrical and mechanical components which could lead to loss of safety function; to identify and recommend methods for detecting and trending aging effects prior to loss of safety function so that timely maintenance can be implemented; and to recommend maintenance practices for mitigating the effects of aging. Research activities include prioritization of system and component aging in nuclear plants, characterization of aging degradation of specific components including identification of functional indicators useful for trending degradation, and testing of practical methods and devices for measuring the functional indicators. Aging assessments have been completed on electric motors, snubbers, motor-operated valves, and check valves. Testing of trending methods and devices for motor-operated valves and check valves is in progress

Pantex Plant meteorological monitoring program

International Nuclear Information System (INIS)

Snyder, S.F.

1993-07-01

The current meteorological monitoring program of the US Department of Energy's Pantex Plant, Amarillo, Texas, is described in detail. Instrumentation, meteorological data collection and management, and program management are reviewed. In addition, primary contacts are noted for instrumentation, calibration, data processing, and alternative databases. The quality assurance steps implemented during each portion of the meteorological monitoring program are also indicated

Plant Modernization Programs

International Nuclear Information System (INIS)

O'Hara, John

2004-01-01

Most nuclear plants were designed and built from the 1960's through the 1990's. These plants employ predominantly analog instrumentation and control (I and C) technology, and their control rooms are made up of primarily hardwired controls (e.g., switches, knobs and handles) and displays (e.g., gauges, linear scales and indicator lights). Over the past several years, these plants have been modernized with digital I and C and computer-based human-system interfaces (HSIs) such as software-based process controls, touch-screen interfaces and large-screen, overview displays. As these computer based HIS technologies are integrated into control rooms based on conventional technology, hybrid control rooms are created. The paper summarizes lessons learned from the study of plant modernization programs over the past ten years so that they can be used to help improve the modification process. While the research focused on the impact of technology change on human performance, a number of organizational and programmatic issues were observed as well. Eleven lessons learned are presented

Y-12 Plant Decontamination and Decommissioning Program

International Nuclear Information System (INIS)

1992-01-01

The Decontamination and Decommissioning (D and D) Program at the Oak Ridge Y-12 Plant is part of the Environmental Restoration (ER) and Waste Management (WM) Programs (ERWM). The objective of the ER Program is to provide Y-12 the capability to meet applicable environmental regulations through facility development activities and site remedial actions. The WM Program supports the ER program. The D and D Program provides collective management of sites within the Plant which are in need of decontamination and decommissioning efforts, prioritizes those areas in terms of health, safety, and environmental concerns, and implements the appropriate level of remedial action. The D and D Program provides support to identifiable facilities which formerly served one or more of the many Plant functions. Program activities include (1) surveillance and maintenance of facilities awaiting decommissioning; (2) planning safe and orderly facility decommissioning; and (3) implementing a program to accomplish facility disposition in a safe, cost effective, and timely manner. In order to achieve the first objective, a formal plan which documents the surveillance and maintenance needs for each facility has been prepared. This report provides this documentation for the Y-12 facilities currently included in the D and D Program, as well as those planned for future inclusion in the Program, and includes projected resource requirements for the planning period of FY 1993 through FY 2000

Programs to improve plant performance

International Nuclear Information System (INIS)

Felmus, N.L.

1987-01-01

Looking toward the 1990's, we see a period in which our industry will face the challenge of improving the performance of the nuclear plants which are built and operating. The skills and technology are at hand to make good plant performance a reality and we believe the time has come to use them to achieve that end. As reserve margins decline, utilities and their regulators will increasingly seek to tap the unexploited capacity tied up in plants operating below their optimum availability. This paper describes a number of the programs, plant improvements and operations improvements which can yield a significant increase in nuclear plant availability and capacity factor now and into the 1990's. (author)

B Plant cleanout and stabilization program update

International Nuclear Information System (INIS)

Gehrke, J.W.

1994-01-01

The B Plant Cleanout and Stabilization Program Update FY1993 committed to an annual update document. The Cleanout and Stabilization Program (CSP) plan, Reference 1, remains as the best source of detailed discussion of CSP work and continues to be valid. The CSP presented a five year plan that left a number of plant systems operational to support WESF (Waste Encapsulation and Storage Facility) capsule storage. It is now apparent that the transition of B Plant to a long-term surveillance and maintenance mode (LTS and M) will be necessary to complete B Plant deactivation. To accomplish the LTS and M mode for B Plant, WESF will need to be physically isolated to allow stand alone operation for many years beyond the anticipated B Plant deactivation. B Plant has processed large quantities (> 100 megacuries) of cesium-137 and strontium-90. Residual radioactive contamination from this processing is in many forms and locations in B Plant. The plant design incorporates many features for radiological containment and confinement and systems to prevent the exposure of plant personnel and the public to excessive radiation. To minimize or reduce the radiological hazard wherever possible this program includes activities in four areas: Prevent Migration of Contamination; Stabilize Major Radioactive Source Terms; characterize Radioactive Source Terms; and Reduce Radiation Dose Rates. This document will describe work that is need to meet current goals and objectives and work that has changed, been completed, ore redirected. A systems engineering approach to defining this mission was initiated in FY1994 that will also be addressed in this document

Advancements in nuclear plant maintenance programs

International Nuclear Information System (INIS)

Meligi, A.E.; Maras, M.C.

1993-01-01

The viability of the nuclear option as a technology choice for present and future electricity generation will be decided primarily on the basis of operating cost to achieve plant performance objectives. In a nuclear plant, performance is judged not only on availability and output rate but also on safety risk and radiation exposure. Operating, cost is essentially made up of the fuel cost and operation and maintenance (O and M) cost. Over the past decade, the industry average nuclear plant performance has improved significantly; however, this improvement was accompanied by rising O and M cost. The net result was that the nuclear option lost its long-standing economic advantage over the coal option, based on the industry average comparison, around 1987 - with the gap narrowing slightly in the last 2 years. In recent times, gas-fired plants have also become a basis for comparison. The electric generation cost comparisons of various fuel options has led to even greater scrutiny of nuclear plant performance, with the poorer performing plants facing the risk of shutdown. While effective O and M programs improve plant performance, present industry data show that there is no direct correlation between the cost of a plant O and M program and its associated performance. There is a significant number of existing tools and techniques in the O and M area that have proved to be successful and have resulted in significant benefits and payback. This paper presents an overview of the nuclear industry efforts to improve the conduct of O and M activities, describes the basic elements of an effective O and M program, and addresses some of the state-of-the-art tools and techniques to enhance maintenance work planning, training, and procedures

Evaluation of Haddam Neck (Connecticut Yankee) Nuclear Power Plant, environmental impact prediction, based on monitoring programs

International Nuclear Information System (INIS)

Gore, K.L.; Thomas, J.M.; Kannberg, L.D.; Mahaffey, J.A.; Waton, D.G.

1976-12-01

A study was undertaken by the U.S. Nuclear Regulatory Commission (NRC) to evaluate the nonradiological environmental data obtained from three nuclear power plants operating for a period of one year or longer. The document presented reports the second of three nuclear power plants to be evaluated in detail by Battelle, Pacific Northwest Laboratories. Haddam Neck (Connecticut Yankee) Nuclear Power Plant nonradiological monitoring data were assessed to determine their effectiveness in the measurement of environmental impacts. Efforts were made to determine if: (1) monitoring programs, as designed, can detect environmental impacts, (2) appropriate statistical analyses were performed and if they were sensitive enough to detect impacts, (3) predicted impacts could be verified by monitoring programs, and (4) monitoring programs satisfied the requirements of the Environmental Technical Specifications. Both preoperational and operational monitoring data were examined to test the usefulness of baseline information in evaluating impacts. This included an examination of the methods used to measure ecological, chemical, and physical parameters, and an assessment of sampling periodicity and sensitivity where appropriate data sets were available. From this type of analysis, deficiencies in both preoperational and operational monitoring programs may be identified and provide a basis for suggested improvement

Preliminary perspectives gaines from individual plant examination of external events (IPEEE) seismic and fire submittal review

International Nuclear Information System (INIS)

Chen, J.T.; Connell, E.; Chokshi, N.

1997-01-01

As a result of the U.S. Nuclear Regulatory Commission (USNRC) initiated Individual plant Examination of External Events (IPEEE) program, every operating nuclear power reactor in the United States has performed an assessment of severe accident due to external events. This paper provides a summary of the preliminary insights gained through the review of 24 IPEEE submittals

Operation of Wastewater Treatment Plants. Volume 1. A Field Study Training Program. Third Edition. Revised.

Science.gov (United States)

California State Univ., Sacramento. Dept. of Civil Engineering.

The purpose of this wastewater treatment field study training program is to: (1) develop new qualified wastewater treatment plant operators; (2) expand the abilities of existing operators, permitting better service both to employers and public; and (3) prepare operators for civil service and certification examinations (examinations administered by…

Status of the Monticello nuclear generating plant lead plant license renewal program

International Nuclear Information System (INIS)

Pickens, T.A.

1992-01-01

In 1988, the Monticello nuclear generating plant was chosen by the US Department of Energy through Sandia National Laboratories and the Electric Power Research Institute to serve as the lead boiling water reactor in the lead plant license renewal program. The purpose of the lead plant license renewal program is to provide insights during the development of and to demonstrate the license renewal regulatory process with the US Nuclear Regulatory Commission (NRC). The work being performed in three phases: (1) preparation of the technical basis for license renewal; (2) development of the technical basis into a formal license renewal application; and (3) review of the application by the NRC. This paper discusses the systems and structures identified as important to license renewal in accordance with 10CFR54 as well as the plant documents and programs that were used in going through the identification process. The systems and structures important to license renewal will then provide insights into how structures and components were identified that are required to be evaluated for aging, the elements of the aging evaluations, and the effective programs used to manage potentially significant aging

Revised inspection program for nuclear power plants

International Nuclear Information System (INIS)

1978-01-01

The United States Nuclear Regulatory Commission (NRC) regulates nuclear power plants to assure adequate protection of the public and the environment from the dangers associated with nuclear materials. NRC fulfills this responsibility through comprehensive safety reviews of nuclear facilities, licensing of organizations that use nuclear materials, and continuing inspection. The NRC inspection program is currently conducted from the five regional offices in or near Philadelphia, Atlanta, Chicago, Dallas and San Francisco. Inspectors travel from the regional offices to nuclear power plants in various phases of construction, test and operation in order to conduct inspections. However, in June 1977 the Commission approved a revision to the inspection program that will include stationing inspectors at selected plants under construction and at all plants in operation. In addition, the revised program provides for appraising the performance of licensees on a national basis and involves more direct measurement and observation by NRC inspectors of work and tests in progress. The program also includes enhanced career management consisting of improved training and career development for inspectors and other professionals. The report was requested in the Conference Report on the NRC Authorization for Appropriations for Fiscal Year 1978. The report provides a discussion of the basis for both the current and revised inspection programs, describes these programs, and shows how the NRC inspection force will be trained and utilized. In addition, the report includes a discussion of the actions that will be taken to assure the objectivity of inspectors

Plant lifetime management and research program

International Nuclear Information System (INIS)

Sakai, K.; Nagayama, M.

1993-01-01

The importance of nuclear power generation has been increasing in Japan. Because the lower generation cost and more stable fuel supply, in comparison with the case of fossil plants, are beneficial to Japan which has scarce natural resources. In addition, nuclear power generation is expected to help reduce carbon dioxide emission which causes global warming. In these circumstances, the safe and stable operations of nuclear power plants are of prime importance, and the frequency of unscheduled shutdown has been kept low in Japan as a result of thorough periodic inspections supported by aging management. This paper covers the development process of the aging management program and related research programs in The Kansai Electric Power Co., Inc. (KEPCO). KEPCO runs 11 nuclear power units (PWR). A Table shows the commencement date of commercial operation and operating hours for each unit. The early plants, such as Mihama-2 Unit, have been operated for more than 100,000 hours and are in the phase of aging management. Accordingly, we have been conducting aging management programs since 1987. in order to identify age-related degradation and work out countermeasures.The aging management programs have ensured safe and stable operation of nuclear power plants. Each result of the lifetime assessment has provided the information which helps establishing maintenance programs. For example, the result of the lifetime assessment has been reflected to the intervals of overhaulings and inspections, and the replacement timing of some components. In the future activities of aging management should be revised and should focus lifetime assessment on components which provoke difficulties in inspections because of high radiation exposure or high inspection cost

Quality assurance program for nuclear power plants

International Nuclear Information System (INIS)

Gamon, T.H.

1976-02-01

The Topical Report presented establishes and provides the basis for the Brown and Root Quality Assurance Program for Nuclear Power Plants from which the Brown and Root Quality Assurance Manual is prepared and implemented. The Quality Assurance Program is implemented by the Brown and Root Power Division during the design, procurement, and construction phases of nuclear power plants. The Brown and Root Quality Assurance Program conforms to the requirements of Nuclear Regulatory Commission Regulation 10 CFR 50, Appendix B; to approved industry standards such as ANSI N45.2 and ''Daughter Standards''; or to equivalent alternatives as indicated in the appropriate sections of the report

Quality assurance program for nuclear power plants

International Nuclear Information System (INIS)

Gamon, T.H.

1976-06-01

This topical report establishes and provides the basis for the Brown and Root Quality Assurance Program for Nuclear Power Plants from which the Brown and Root Quality Assurance Manual is prepared and implemented. The Quality Assurance Program is implemented by the Brown and Root Power Division during the design, procurement, and construction phases of nuclear power plants. The Brown and Root Quality Assurance Program conforms to the requirements of Nuclear Regulatory Commission Regulation 10 CFR 50, Appendix B; to approved industry standards such as ANSI N45.2 and ''Daughter Standards''; or to equivalent alternatives as indicated in the appropriate sections of this report

EPRI nuclear power plant decommissioning technology program

International Nuclear Information System (INIS)

Kim, Karen S.; Bushart, Sean P.; Naughton, Michael; McGrath, Richard

2011-01-01

The Electric Power Research Institute (EPRI) is a non-profit research organization that supports the energy industry. The Nuclear Power Plant Decommissioning Technology Program conducts research and develops technology for the safe and efficient decommissioning of nuclear power plants. (author)

An analysis of the impacts of economic incentive programs on commercial nuclear power plant operations and maintenance costs

International Nuclear Information System (INIS)

Kavanaugh, D.C.; Monroe, W.H.; Wood, R.S.

1996-02-01

Operations and Maintenance (O and M) expenditures by nuclear power plant owner/operators possess a very logical and vital link in considerations relating to plant safety and reliability. Since the determinants of O and M outlays are considerable and varied, the potential linkages to plant safety, both directly and indirectly, can likewise be substantial. One significant issue before the US Nuclear Regulatory Commission is the impact, if any, on O and M spending from state programs that attempt to improve plant operating performance, and how and to what extent these programs may affect plant safety and pose public health risks. The purpose of this study is to examine the role and degree of impacts from state promulgated economic incentive programs (EIPs) on plant O and M spending. A multivariate regression framework is specified, and the model is estimated on industry data over a five-year period, 1986--1990. Explanatory variables for the O and M spending model include plant characteristics, regulatory effects, financial strength factors, replacement power costs, and the performance incentive programs. EIPs are found to have statistically significant effects on plant O and M outlays, albeit small in relation to other factors. Moreover, the results indicate that the relatively financially weaker firms are more sensitive in their O and M spending to the presence of such programs. Formulations for linking spending behavior and EIPs with plant safety performance remains for future analysis

Technical methods for a risk-informed, performance-based fire protection program at nuclear power plants

International Nuclear Information System (INIS)

Dey, M.K.

1998-01-01

This paper presents a technical review and examination of technical methods that are available for developing a risk-informed, performance-based fire protection program at a nuclear plant. The technical methods include ''engineering tools'' for examining the fire dynamics of fire protection problems, reliability techniques for establishing an optimal fire protection surveillance program, fire computer codes for analyzing important fire protection safety parameters, and risk-informed approaches that can range from drawing qualitative insights from risk information to quantifying the risk impact of alternative fire protection approaches. Based on this technical review and examination, it is concluded that methods for modeling fires, and reliability and fire PRA analyses are currently available to support the initial implementation of simple risk-informed, performance-based approaches in fire protection programs. (author)

Technical methods for a risk-informed, performance-based fire protection program at nuclear power plants

International Nuclear Information System (INIS)

Dey, M.K.

2000-01-01

This paper presents a technical review and examination of technical methods that are available for developing a risk-informed, performance-based fire protection program at a nuclear plant. The technical methods include 'engineering tools' for examining the fire dynamics of fire protection problems, reliability techniques for establishing an optimal fire protection surveillance program, fire computer codes for analyzing important fire protection safety parameters, and risk-informed approaches that can range from drawing qualitative insights from risk information to quantifying the risk impact of alternative fire protection approaches. Based on this technical review and examination, it is concluded that methods for modeling fires, and reliability and fire probabilistic risk analyses (PRA) are currently available to support the initial implementation of simple risk-informed, performance-based approaches in fire protection programs. (orig.) [de

Genetic Programming for Medicinal Plant Family Identification System

Directory of Open Access Journals (Sweden)

Indra Laksmana

2014-11-01

Full Text Available Information about medicinal plants that is available in text documents is generally quite easy to access, however, one needs some efforts to use it. This research was aimed at utilizing crucial information taken from a text document to identify the family of several species of medicinal plants using a heuristic approach, i.e. genetic programming. Each of the species has its unique features. The genetic program puts the characteristics or special features of each family into a tree form. There are a number of processes involved in the investigated method, i.e. data acquisition, booleanization, grouping of training and test data, evaluation, and analysis. The genetic program uses a training process to select the best individual, initializes a generate-rule process to create several individuals and then executes a fitness evaluation. The next procedure is a genetic operation process, which consists of tournament selection to choose the best individual based on a fitness value, the crossover operation and the mutation operation. These operations have the purpose of complementing the individual. The best individual acquired is the expected solution, which is a rule for classifying medicinal plants. This process produced three rules, one for each plant family, displaying a feature structure that distinguishes each of the families from each other. The genetic program then used these rules to identify the medicinal plants, achieving an average accuracy of 86.47%.

Hanford Waste Vitrification Plant quality assurance program description: Overview and applications

International Nuclear Information System (INIS)

Caplinger, W.H.

1990-12-01

This document describes the Hanford Waste Vitrification Plant Project Quality Assurance Program. This program is being implemented to ensure the acceptability of high-level radioactive canistered waste forms produced by the Hanford Waste Vitrification Plant for disposal in a licensed federal repository. The Hanford Waste Vitrification Plant Quality Assurance Program is comprised of this Quality Assurance Program Description as well as the associated contractors' quality assurance programs. The objective of this Quality Assurance Program Description is to provide the Hanford Waste Vitrification Plant Project participants with guidance and direction for program implementation while satisfying the US Department of Energy Office of Civilian Radioactive Waste Management needs in repository licensing activities with regard to canistered waste forms. To accomplish this objective, this description will be prepared in three parts: Part 1 - Overview and applications document; Part 2 - Development and qualification of the canistered waste form; Part 3 - Production of canistered waste forms. Part 1 describes the background, strategy, application, and content of the Hanford Waste Vitrification Plant Quality Assurance Program. This Quality Assurance Program Description, when complete, is designed to provide a level of confidence in the integrity of the canistered waste forms. 8 refs

Practical standard for nuclear power plant life management programs: 2007

International Nuclear Information System (INIS)

2006-03-01

The standard specifies the method of implementing nuclear power plant life management programs. The plant life management programs evaluate the integrity of the plant structures, systems and components, assessing if appropriate measures are taken against existing aging phenomena, if there are possibilities of occurrence and development of aging phenomena and if a sufficient level of margin is maintained to assure the integrity throughout the future operating period. The programs also assess the validity of the current maintenance activities, such as trend monitoring, walkdowns, periodic tests and inspections, repair and replacement work for the purpose of preventive maintenance, and utilization of lessons learned from past trouble experience, in order to newly identify maintenance measures. The technical evaluation on aging phenomena is conducted to establish the 10 year maintenance program for nuclear power plants until the plant reaches 30 years of service. The standard was established and issued by the Atomic Energy Society of Japan (AESJ) through the discussion of experts in the associated fields. (T. Tanaka)

Overall quality assurance program requirements for nuclear power plants

International Nuclear Information System (INIS)

1992-09-01

This standard contains the requirements for the owner's overall quality assurance program for a nuclear power plant. This program encompasses all phases of a nuclear power plant life cycle, including site evaluation, design, procurement, manufacturing, construction and installation, commissioning, operation, and decommissioning. It covers the activities associated with specifying, directing, and administering the work to be done during these phases, and the evaluation and integrated of the activities and programs of participants

Mechanized ultrasonic examination of piping systems in nuclear power plants

International Nuclear Information System (INIS)

Edelmann, X.; Pfister, O.; Allidi, F.

1988-01-01

The success of mechanized ultrasonic examination applied on welds in piping systems in nuclear power plants is highly dependent on its careful preparation. From the development of an adequate examination technique to its implementation on site, many problems are to be solved. This is especially the case when dealing with austenitic welds or dissimilar metal welds. In addition to the specific needs for examination technique based on material properties and requirements for minimum flaw size detection, accessibility and radiation aspects have to be considered. A crew of skilled and highly trained examination personnel is required. Experience in various nuclear power plants, - BWR's and PWR's of different designs - has shown, that even difficult examination problems can be successfully solved, provided that there is a good preparation. The necessary step by step proceeding is illustrated by examples concerning mechanized examination. Preservice inspections and in-service inspections with specific requirements, due to the types of flaws to be found or the type of material concerned, are discussed

Nuclear Plant Aging Research (NPAR) program plan

International Nuclear Information System (INIS)

1991-06-01

A comprehensive Nuclear Plant Aging Research (NPAR) Program was implemented by the US NRC office of Nuclear Regulatory Research in 1985 to identify and resolve technical safety issues related to the aging of systems, structures, and components in operating nuclear power plants. This is Revision 2 to the Nuclear Plant Aging Research Program Plant. This planes defines the goals of the program the current status of research, and summarizes utilization of the research results in the regulatory process. The plan also describes major milestones and schedules for coordinating research within the agency and with organizations and institutions outside the agency, both domestic and foreign. Currently the NPAR Program comprises seven major areas: (1) hardware-oriented engineering research involving components and structures; (2) system-oriented aging interaction studies; (3) development of technical bases for license renewal rulemaking; (4) determining risk significance of aging phenomena; (5) development of technical bases for resolving generic safety issues; (6) recommendations for field inspection and maintenance addressing aging concerns; (7) and residual lifetime evaluations of major LWR components and structures. The NPAR technical database comprises approximately 100 NUREG/CR reports by June 1991, plus numerous published papers and proceedings that offer regulators and industry important insights to aging characteristics and aging management of safety-related equipment. Regulatory applications include revisions to and development of regulatory guides and technical specifications; support to resolve generic safety issues; development of codes and standards; evaluation of diagnostic techniques; (e.g., for cables and valves); and technical support for development of the license renewal rule. 80 refs., 25 figs., 10 tabs

Integrated plant-safety assessment, Systematic Evaluation Program: Big Rock Point Plant (Docket No. 50-155)

International Nuclear Information System (INIS)

1983-09-01

The Systematic Evaluation Program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to reconfirm and document their safety. This report documents the review of the Big Rock Point Plant, which is one of ten plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. It also addresses a majority of the pending licensing actions for Big Rock Point, which include TMI Action Plan requirements and implementation criteria for resolved generic issues. Equipment and procedural changes have been identified as a result of the review

Relationship between internal medicine program board examination pass rates, accreditation standards, and program size.

Science.gov (United States)

Falcone, John L; Gonzalo, Jed D

2014-01-19

To determine Internal Medicine residency program compliance with the Accreditation Council for Graduate Medical Education 80% pass-rate standard and the correlation between residency program size and performance on the American Board of Internal Medicine Certifying Examination. Using a cross-sectional study design from 2010-2012 American Board of Internal Medicine Certifying Examination data of all Internal Medicine residency pro-grams, comparisons were made between program pass rates to the Accreditation Council for Graduate Medical Education pass-rate standard. To assess the correlation between program size and performance, a Spearman's rho was calculated. To evaluate program size and its relationship to the pass-rate standard, receiver operative characteristic curves were calculated. Of 372 Internal Medicine residency programs, 276 programs (74%) achieved a pass rate of =80%, surpassing the Accreditation Council for Graduate Medical Education minimum standard. A weak correlation was found between residency program size and pass rate for the three-year period (p=0.19, pInternal Medicine residency programs complied with Accreditation Council for Graduate Medical Education pass-rate standards, a quarter of the programs failed to meet this requirement. Program size is positively but weakly associated with American Board of Internal Medicine Certifying Examination performance, suggesting other unidentified variables significantly contribute to program performance.

Nuclear power plant simulators for operator licensing and training. Part I. The need for plant-reference simulators. Part II. The use of plant-reference simulators

International Nuclear Information System (INIS)

Rankin, W.L.; Bolton, P.A.; Shikiar, R.; Saari, L.M.

1984-05-01

Part I of this report presents technical justification for the use of plant-reference simulators in the licensing and training of nuclear power plant operators and examines alternatives to the use of plant-reference simulators. The technical rationale is based on research on the use of simulators in other industries, psychological learning and testing principles, expert opinion and user opinion. Part II discusses the central considerations in using plant-reference simulators for licensing examination of nuclear power plant operators and for incorporating simulators into nuclear power plant training programs. Recommendations are presented for the administration of simulator examinations in operator licensing that reflect the goal of maximizing both reliability and validity in the examination process. A series of organizational tasks that promote the acceptance, use, and effectiveness of simulator training as part of the onsite training program is delineated

Integrated plant safety assessment. Systematic evaluation program, Big Rock Point Plant (Docket No. 50-155). Final report

International Nuclear Information System (INIS)

1984-05-01

The Systematic Evaluation Program was initiated in February 1977 by the U.S. Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to reconfirm and document their safety. The review provides (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety when the supplement to the Final Integrated Plant Safety Assessment Report has been issued. This report documents the review of the Big Rock Point Plant, which is one of ten plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. It also addresses a majority of the pending licensing actions for Big Rock Point, which include TMI Action Plan requirements and implementation criteria for resolved generic issues. Equipment and procedural changes have been identified as a result of the review

Quality assurance program preparation - review of requirements and plant systems - selection of program levels

International Nuclear Information System (INIS)

Asmuss, G.

1980-01-01

The establishment and implementation for a practicable quality assurance program for a nuclear power plant demands a detailed background in the field of engineering, manufacturing, organization and quality assurance. It will be demonstrated with examples to define and control the achievement of quality related activities during the phases of design, procurement, manufactoring, commissioning and operation. In general the quality assurance program applies to all items, processes and services important to safety of nuclear power plant. The classification for safety related and non-safety related items and services demonstrate the levels of quality assurance requirements. The lecture gives an introduction of QA Program preparation under the following topics: -Basic criteria and international requirements - Interaction of QA activities - Modular and product oriented QA programs - Structuring of organization for the QA program - Identification of the main quality assurance functions and required actions - Quality Assurance Program documentation - Documentation of planning of activities - Control of program documents - Definitions. (orig./RW)

Postirradiation examination of Kori-1 nuclear power plant fuels

International Nuclear Information System (INIS)

Ro, S.G.; Kim, E.K.; Lee, K.S.; Min, D.K.

1994-01-01

Full size fuels discharged from Kori-1 PWR nuclear power plant have been subjected to postirradiation examination. The fuels under investigation were irradiated for one- to four-reactor cycles. Nondestructive examination and dismantling of the fuel assemblies have been conducted in the pool of the postirradiation examination facility (PIEF) of Korea Atomic Energy Research Institue. Subsequently nondestructive and destructive examinations of fuel rods have been performed in the hot cells of the PIEF. An evaluation of fuel burnup behaviors was based on the postirradiation examination data and the nominal design values. The results did not show any evidence of abnormalities in the fuel integrity. (orig.)

Postirradiation examination of Kori-1 nuclear power plant fuels

Science.gov (United States)

Seung-Gy, Ro; Eun-Ka, Kim; Key-Soon, Lee; Duck-Kee, Min

1994-05-01

Full size fuels discharged from Kori-1 PWR nuclear power plant have been subjected to postirradiation examination. The fuels under investigation were irradiated for one- to four-reactor cycles. Nondestructive examination and dismantling of the fuel assemblies have been conducted in the pool of the postirradiation examination facility (PIEF) of Korea Atomic Energy Research Institute. Subsequently nondestructive and destructive examinations of fuel rods have been performed in the hot cells of the PIEF. An evaluation of fuel burnup behaviors was based on the postirradiation examination data and the nominal design values. The results did not show any evidence of abnormalities in the fuel integrity.

ERDA LWR plant technology program: role of government/industry in improving LWR performance

International Nuclear Information System (INIS)

1975-01-01

Information is presented under the following chapter headings: executive summary; LWR plant outages; LWR plant construction delays and cancellations; programs addressing plant outages, construction delays, and cancellations; need for additional programs to remedy continuing problems; criteria for government role in LWR commercialization; and the proposed government program

Examination of Energy Efficiency Increasing Measures in an Automobile Assembly Plant

Directory of Open Access Journals (Sweden)

Fatma ÇANKA KILIÇ

2018-03-01

Full Text Available In this study, energy consumption analysis was performed in a car assembly plant (Body-inWhite (BiW productions, painting processes, chassis and accessory assembly processes. Examined automobile assembly plant has a production capacity of 200,000 vehicles per year by working six days a week and three shifts a day. Highly energy consuming processes are determined. Energy efficiency increasing opportunities in energy consuming systems (paint shop, drying ovens, compressed air, heating and cooling systems and effects of current automotive assembly techniques on energy efficiency are examined. Most of the total energy in the studied plant is consumed in the paint shop. Considering annual energy consumption; paint shop is responsible for the %50 of total electrical energy and %70 of total natural gas consumption. Specific energy consumption of plant is calculated as 853 kWh (SET; 275 kWh for electricity consumption (SETe , and 578 kWh for natural gas (SETdg . By performing determined energy efficiency measures; SET of plant will reduce %1 for the SETe , and %5,7 for SETdg

75 FR 34941 - Review of the Commission's Program Access Rules and Examination of Programming Tying Arrangements

Science.gov (United States)

2010-06-21

... Commission's Program Access Rules and Examination of Programming Tying Arrangements AGENCY: Federal... Program Access Rules and Examination of Programming Tying Arrangements, MB Docket No. 07-198, FCC 10-17... information collection is contained in Sections 4(i), 303(r), and 628 of the Communications Act of 1934, as...

Integrated plant safety assessment: systematic evaluation program. Haddam Neck Plant, Connecticut Yankee Atomic Power Company. Docket No. 50-213

International Nuclear Information System (INIS)

1983-03-01

The Systematic Evaluation Program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to confirm and document their safety. The review provides: (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of Haddam Neck Plant, operated by Connecticut Yankee Atomic Power Company. The Haddam Neck Plant is one of 10 plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review

The integrated in situ testing program for the Waste Isolation Pilot Plant (WIPP)

International Nuclear Information System (INIS)

Matalucci, R.V.

1987-03-01

The US Department of Energy (DOE) is developing the Waste Isolation Pilot Plant (WIPP) Project in southeastern New Mexico as a research and development (R and D) facility for examining the response of bedded (layered) salt to the emplacement of radioactive wastes generated from defense programs. The WIPP Experimental Program consists of a technology development program, including laboratory testing and theoretical analysis activities, and an in situ testing program that is being done 659 m underground at the project site. This experimental program addresses three major technical areas that concern (1) thermal/structural interactions, (2) plugging and sealing, and (3) waste package performance. To ensure that the technical issues involved in these areas are investigated with appropriate emphasis and timing, an in situ testing plan was developed to integrate the many activities and tasks associated with the technical issues of waste disposal. 5 refs., 4 figs

Quality assurance program manual for nuclear power plants. Volume I. Policies

International Nuclear Information System (INIS)

1976-01-01

The Consumers Power Company Quality Assurance Program Manual for Nuclear Power Plants consists of policies and procedures which comply with current NRC regulatory requirements and industry codes and standards in effect during the design, procurement, construction, testing, operation, refueling, maintenance, repair and modification activities associated with nuclear power plants. Specific NRC and industry documents that contain the requirements, including the issue dates in effect, are identified in each nuclear power plant's Safety Analysis Report. The requirements established by these documents form the basis for the Consumer Power Quality Assurance Program, which is implemented to control those structures, systems, components and operational safety actions listed in each nuclear power plant's Quality List (Q-List). As additional and revised requirements are issued by the NRC and professional organizations involved in nuclear activities, they will be reviewed for their impact on this manual, and changes will be made where considered necessary. CP Co 1--Consumers Power Company QA Program Topical Report is Volume I of this manual and contains Quality Assurance Program Policies applicable during all phases of nuclear power plant design, construction and operation

Evaluation of Monticello Nuclear Power Plant, Environmental Impact Prediction, based on monitoring programs

International Nuclear Information System (INIS)

Gore, K.L.; Thomas, J.M.; Kannberg, L.D.; Watson, D.G.

1976-11-01

This report evaluates quantitatively the nonradiological environmental monitoring programs at Monticello Nuclear Generating Plant. The general objective of the study is to assess the effectiveness of monitoring programs in the measurement of environmental impacts. Specific objectives include the following: (1) Assess the validity of environmental impact predictions made in the Environmental Statement by analysis of nonradiological monitoring data; (2) evaluate the general adequacy of environmental monitoring programs for detecting impacts and their responsiveness to Technical Specifications objectives; (3) assess the adequacy of preoperational monitoring programs in providing a sufficient data base for evaluating operational impacts; (4) identify possible impacts that were not predicted in the environmental statement and identify monitoring activities that need to be added, modified or deleted; and (5) assist in identifying environmental impacts, monitoring methods, and measurement problems that need additional research before quantitative predictions can be attempted. Preoperational as well as operational monitoring data were examined to test the usefulness of baseline information in evaluating impacts. This included an examination of the analytical methods used to measure ecological and physical parameters, and an assessment of sampling periodicity and sensitivity where appropriate data were available

Bibliography of the Maryland Power Plant Research Program, fourteenth edition

International Nuclear Information System (INIS)

McLean, R.I.

1993-02-01

The Power Plant Siting Act of 1971 (Sec. 3-303) established the Power Plant Research Program to ensure that demands for electric power would be met in a timely manner at a reasonable cost while assuring that the associated environmental impact would be acceptable. The scope of the Program extends to estimating the impact of proposed new generating facilities, evaluating the acceptability of proposed transmission line routes, assessing the impact of existing generation facilities, and investigating generic issues related to power plant site evaluation and associated environmental and land use considerations. The bibliography is a compilation of all the studies performed for and/or by the Power Plant and Environmental Review Division since its inception

Application of the comet assay in studies of programmed cell death (PCD in plants

Directory of Open Access Journals (Sweden)

Maria Charzyńska

2014-01-01

Full Text Available Programmed cell death (PCD in plants is an intensively investigated process. One of the main characteristics of PCD in both animal and plant organisms is the non-random, internucleosomal fragmentation of nuclear DNA, usually analysed using total DNA gel electrophoresis or TUNEL method. In this paper we present application of the "comet assay" (Single Cell Gel Electrophoresis for detection of nDNA degradation in studies of PCD during plant life cycle. We analyzed three types of tissue: anther tapetum, endosperm and mesophyll which were prepared in different ways to obtain a suspension of viable cells (without cell walls. The comet assay gives a possibility of examination of the nDNA degradation in individual cell. This method is significant for studies of the plant tissue differentiation and senescence especially in the cases when it is not possible to isolate large number of cells at the same developmental stage.

Human factors engineering plan for reviewing nuclear plant modernization programs

International Nuclear Information System (INIS)

O'Hara, John; Higgins, James

2004-12-01

The Swedish Nuclear Power Inspectorate reviews the human factors engineering (HFE) aspects of nuclear power plants (NPPs) involved in the modernization of the plant systems and control rooms. The purpose of a HFE review is to help ensure personnel and public safety by verifying that accepted HFE practices and guidelines are incorporated into the program and nuclear power plant design. Such a review helps to ensure the HFE aspects of an NPP are developed, designed, and evaluated on the basis of a structured top-down system analysis using accepted HFE principles. The review addresses eleven HFE elements: HFE Program Management, Operating Experience Review, Functional Requirements Analysis and Allocation, Task Analysis, Staffing, Human Reliability Analysis, Human-System Interface Design, Procedure Development, Training Program Development, Human Factors Verification and Validation, and Design Implementation

Human factors engineering plan for reviewing nuclear plant modernization programs

Energy Technology Data Exchange (ETDEWEB)

O' Hara, John; Higgins, James [Brookhaven National Laboratory, Upton, NY (United States)

2004-12-01

The Swedish Nuclear Power Inspectorate reviews the human factors engineering (HFE) aspects of nuclear power plants (NPPs) involved in the modernization of the plant systems and control rooms. The purpose of a HFE review is to help ensure personnel and public safety by verifying that accepted HFE practices and guidelines are incorporated into the program and nuclear power plant design. Such a review helps to ensure the HFE aspects of an NPP are developed, designed, and evaluated on the basis of a structured top-down system analysis using accepted HFE principles. The review addresses eleven HFE elements: HFE Program Management, Operating Experience Review, Functional Requirements Analysis and Allocation, Task Analysis, Staffing, Human Reliability Analysis, Human-System Interface Design, Procedure Development, Training Program Development, Human Factors Verification and Validation, and Design Implementation.

Aging research program at the LaCrosse nuclear power plant

International Nuclear Information System (INIS)

DiBenedetto, P.A.; Goller, K.R.; Sideris, T.

1988-01-01

A research program on the time-dependent, environmentally and operationally induced degradation of components, systems and structures---that is aging---is being conducted at the LaCrosse Boiling Water Reactor (LACBWR) nuclear power plant. In the spring of 1987, Dairyland Power Cooperative, the owner/licensee of the LACBWR plant announced that it was permanently shutting down this plant and intended to decommission it. Shortly thereafter, Dairyland entered into an agreement with DiBenedetto Associates (DBA) to be the exclusive agent and manager of the Aging Research Program (ARP). Wyle Laboratories is the primary supporting contractor to DBA in this effort

Procedural and submittal guidance for the individual plant examination of external events (IPEEE) for severe accident vulnerabilities

International Nuclear Information System (INIS)

Chen, J.T.; Chokshi, N.C.; Kenneally, R.M.; Kelly, G.B.; Beckner, W.D.; McCracken, C.; Murphy, A.J.; Reiter, L.; Jeng, D.

1991-06-01

Based on a Policy statement on Severe Accidents, the licensee of each nuclear power plant is requested to perform an individual plant examination. The plant examination systematically looks for vulnerabilities to severe accidents and cost-effective safety improvements that reduce or eliminate the important vulnerabilities. This document presents guidance for performing and reporting the results of the individual plant examination of external events (IPEEE). The guidance for reporting the results of the individual plant examination of internal events (IPE) is presented in NUREG-1335. 53 refs., 1 figs., 2 tabs

A review of electric cable aging effects and monitoring programs for plant license renewal

International Nuclear Information System (INIS)

Lofaro, R.J.

1999-01-01

As commercial nuclear power plants approach the end of their original license period, some utilities are considering the possibility of license renewal. The requirements for applying for license renewal are specified in the License Renewal Rule, which is in Title 10 of the Code of Federal Regulations, Part 54 (10 CFR54). Among the requirements specified in the rule is the performance of an Integrated Plant Assessment (IPA) which identifies and lists structures and components subject to an aging management review. The intent of this requirement is to ensure that aging degradation will not adversely affect plant safety during the license renewal period. The aging management review includes an identification of the aging effects and monitoring programs for components within the scope of the rule. Among the components within the scope are electric cables since they are passive, long-lived components that are not replaced on a periodic basis. This paper examines the aging causes and effects of electric cables, along with the programs that are typically used to ensure that proper aging management practices are in place to monitor and mitigate the effects of aging on electric cables

46 CFR 176.630 - The Alternative Hull Examination (AHE) Program application.

Science.gov (United States)

2010-10-01

... 46 Shipping 7 2010-10-01 2010-10-01 false The Alternative Hull Examination (AHE) Program... PASSENGER VESSELS (UNDER 100 GROSS TONS) INSPECTION AND CERTIFICATION Hull and Tailshaft Examinations § 176.630 The Alternative Hull Examination (AHE) Program application. If your vessel meets the eligibility...

Using systematic aging assessments to improve effectiveness of plant maintenance programs

International Nuclear Information System (INIS)

Watson, P.; Yang, J.X.; Dam, R.F.; Nickerson, J.H.

2003-01-01

Nuclear plant equipment aging assessment studies provided by AECL include life assessments, condition assessments or systematic assessments of maintenance. AECL has developed several tools to apply the results of aging assessment studies to improve the effectiveness of actual plant maintenance programs. The Systematic Assessment of Maintenance and the SYSTMS tool generate maintenance tasks for a system. The System Maintenance Datastore tool assesses the maintenance resources on a system basis, and can thus quantify the savings realized by optimizing the maintenance program. Long term trends in condition-based maintenance due to component aging can be predicted, and resource savings due to optimum timing of component replacement or general plant refurbishment can be quantified. The System based Adaptive Maintenance Process ensures the maintenance program is continually updated to reflect the latest plant equipment condition and maintenance strategy information. (author)

Savannah River Plant Separations Department mixed waste program

International Nuclear Information System (INIS)

Wierzbicki, W.M.

1988-01-01

The Department of Energy's (DOE) Savannah River Plant (SRP) generates radioactive and mixed waste as a result of the manufacture of nuclear material for the national defense program. The radioactive portion of the mixed waste and all nonhazardous radioactive wastes would continue to be regulated by DOE under the Atomic Energy Act. The Separations Department is the largest generator of solid radioactive waste at the Savannah River Plant. Over the last three years, the Separations Department has developed and implemented a program to characterize candidate mixed-waste streams. The program consisted of facility personnel interviews, a waste-generation characterization program and waste testing to determine whether a particular waste form was hazardous. The Separations Department changed waste-handling practices and procedures to meet the requirements of the generator standards. For each Separation Department Facility, staging areas were established, inventory and reporting requirements were developed, operating procedures were revised to ensure proper waste handling, and personnel were provided hazardous waste training. To emphasize the importance of the new requirements, a newsletter was developed and issued to all Separations supervisory personnel

Uncertain and multi-objective programming models for crop planting structure optimization

Directory of Open Access Journals (Sweden)

Mo LI,Ping GUO,Liudong ZHANG,Chenglong ZHANG

2016-03-01

Full Text Available Crop planting structure optimization is a significant way to increase agricultural economic benefits and improve agricultural water management. The complexities of fluctuating stream conditions, varying economic profits, and uncertainties and errors in estimated modeling parameters, as well as the complexities among economic, social, natural resources and environmental aspects, have led to the necessity of developing optimization models for crop planting structure which consider uncertainty and multi-objectives elements. In this study, three single-objective programming models under uncertainty for crop planting structure optimization were developed, including an interval linear programming model, an inexact fuzzy chance-constrained programming (IFCCP model and an inexact fuzzy linear programming (IFLP model. Each of the three models takes grayness into account. Moreover, the IFCCP model considers fuzzy uncertainty of parameters/variables and stochastic characteristics of constraints, while the IFLP model takes into account the fuzzy uncertainty of both constraints and objective functions. To satisfy the sustainable development of crop planting structure planning, a fuzzy-optimization-theory-based fuzzy linear multi-objective programming model was developed, which is capable of reflecting both uncertainties and multi-objective. In addition, a multi-objective fractional programming model for crop structure optimization was also developed to quantitatively express the multi-objective in one optimization model with the numerator representing maximum economic benefits and the denominator representing minimum crop planting area allocation. These models better reflect actual situations, considering the uncertainties and multi-objectives of crop planting structure optimization systems. The five models developed were then applied to a real case study in Minqin County, north-west China. The advantages, the applicable conditions and the solution methods

An Examination of a Gender-Separate Advisory Program

Science.gov (United States)

Weilbacher, Gary; Lanier, Jill

2012-01-01

In this qualitative study, the authors examine the advisory program of a Horizon Schools to Watch middle grades school. Horizon Schools to Watch is the Illinois affiliate of the National Forum to Accelerate Middle School Reform national Schools to Watch (STW) program, meaning schools with the STW designation have made significant inroads in…

Early Site Permit Demonstration Program: Plant parameters envelope report

International Nuclear Information System (INIS)

1993-03-01

The Early Site Permit (ESP) Demonstration Program is the nuclear industry's initiative for piloting the early resolution of siting-related issues before the detailed design proceedings of the combined operating license review. The ESP Demonstration Program consists of three phases. The plant parameters envelopes task is part of Phase 1, which addresses the generic review of applicable federal regulations and develops criteria for safety and environmental assessment of potential sites. The plant parameters envelopes identify parameters that characterize the interface between an ALWR design and a potential site, and quantify the interface through values selected from the Utility Requirements Documents, vendor design information, or engineering assessments. When augmented with site-specific information, the plant parameters envelopes provide sufficient information to allow ESPs to be granted based on individual ALWR design information or enveloping design information for the evolutionary, passive, or generic ALWR plants. This document is expected to become a living document when used by future applicants

Interdisciplinary research and training program in the plant sciences

Energy Technology Data Exchange (ETDEWEB)

Wolk, C.P.

1991-01-01

This document is the compiled progress reports from the Interdisciplinary Research and Training Program in the Plant Sciences funded through the MSU-DOE Plant Research Laboratory. Fourteen reports are included, covering topics such as the molecular basis of plant/microbe symbiosis, cell wall proteins and assembly, gene expression, stress responses, growth regulator biosynthesis, interaction between nuclear and organelle genomes, sensory transduction and tropisms, intracellular sorting and membrane trafficking, regulation of lipid metabolism, the molecular basis of disease resistance and plant pathogenesis, developmental biology of Cyanobacteria and hormonal involvement in environmental control of plant growth. 132 refs. (MHB)

TMI-2 information and examination program 1981 annual report

International Nuclear Information System (INIS)

1982-04-01

The Department of Energy's Technical Information and Examination Program at Three Mile Island Unit 2 continued the research and development work begun on the Island in 1979. The work concentrated in seven major areas: instrumentation and electrical components; radiation and environment; off-site core examination; radioactive waste technology development; configuration and document control; waste immobilization; and reactor evaluation. Research and development work associated with the program aims toward communicating applicable information to the nuclear community. The program seeks to assist in resolving specific problems at TMI-2 and to stimulate interest in specific work activities, thus ensuring that the entire nuclear industry avails itself of the maximum amount of information possible

Operations Program Plan for the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

1990-09-01

This document, Revision 4 of the Operations Program Plan, has been developed as the seven-year master plan for operating of the Waste Isolation Pilot Plant (WIPP). Subjects covered include public and technical communications; regulatory and environmental programs; startup engineering; radiation handling, surface operations, and underground operations; waste certification and waste handling; transportation development; geotechnical engineering; experimental operations; engineering program; general maintenance; security program; safety, radiation, and regulatory assurance; quality assurance program; training program; administration activities; management systems program; and decommissioning. 243 refs., 19 figs., 25 tabs. (SM)

Global warming mitigation strategies and programs for power plant developers

International Nuclear Information System (INIS)

Holmes, N.R.

1992-01-01

Power plant developers are increasingly being surprised by regulatory agencies requiring them to mitigate the carbon dioxide(CO 2 ) emissions from their proposed power plants, as part of the plant's operating permit conditions. Since carbon dioxide is not a criteria pollutant with a National Ambient Air Quality Standard, power plant developers are often troubled by this additional regulatory requirement. This presentation will describe the contribution that CO 2 makes to global warming, the role of trees and forests as carbon sequesters or sinks, some non-forestry related and forestry related mitigation programs, including the advantages, disadvantages, and some cost estimates for the forestry related CO 2 mitigation programs. As public concern about global warming continues to escalate, it is almost certain that regulatory agencies will increase their focus on CO 2 mitigation

Near-term benefits of the plant life extension program

International Nuclear Information System (INIS)

Kaushansky, M.M.

1987-01-01

The aging process can be expected to reduce the availability and increase the production costs of nuclear power plants over time. To mitigate this process and recover or enhance plant availability, capacity, thermal efficiency, and maintenance expenditures, the utility must dedicate increased attention and commitment to a comprehensive plant life extension (PLEX) program. Improvements must be justified by balancing the cost of the recommended modifications with the economic value of benefits obtained from its implementation. It is often extremely difficult for utility management to make an optimal selection from among hundreds of proposed projects, most of which are cost-effective. A properly structured PLEX program with an emphasis on near-term benefits should provide the utility with a means of evaluating proposed projects, thus determining the optimum combination for authorization and implementation

Examination history and abnormal thyroid and breast lesions according to residential distance from nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Lim, Young Khi [Dept. of Radiological Science, Gachon University, Incheon (Korea, Republic of)

2016-12-15

Ascertainment bias are common in epidemiologic studies to assess the association between thyroid cancer risk and living near nuclear power plants because many thyroid cancers are diagnosed by chance through health examination. We surveyed the ultra sonography (USG) examination history and conducted thyroid and breast USG in residents living near nuclear power plants. The study population comprised 2,421 residents living near nuclear power plants in Korea. Information on demographic characteristics, including diagnostic examination history, was collected by interview using questionnaires. USG examination was conducted to evaluate the presence of thyroid nodules and breast lesion. Study participants were divided into 3 groups according to the distance of their respective villages from a nuclear power plant. The proportions of USG examination history and prevalence of thyroid nodules and breast lesions were compared between groups. Examination histories of thyroid USG were 23.1%, 13.7%, and 10.5% in men and 31.3%, 26.7%, 18.3% in women in the short, intermediate, and long distance groups, respectively. There were significant inverse associations between thyroid USG history and the distance from nuclear power plants (P for trend=0.001 for men and 0.017 for women). However, there was no association between the distance of villages from nuclear power plants and prevalence of thyroid nodules. Our results suggest that there may be an ascertainment bias in population-based studies examining the harmful effects of NPPs examination and researchers should pay attention to ascertainment bias resulted from differential health examination. Correction for ascertainment bias, active follow-up and examination for all study population to remove differential health examination is needed.

Examination history and abnormal thyroid and breast lesions according to residential distance from nuclear power plants

International Nuclear Information System (INIS)

Lim, Young Khi

2016-01-01

Ascertainment bias are common in epidemiologic studies to assess the association between thyroid cancer risk and living near nuclear power plants because many thyroid cancers are diagnosed by chance through health examination. We surveyed the ultra sonography (USG) examination history and conducted thyroid and breast USG in residents living near nuclear power plants. The study population comprised 2,421 residents living near nuclear power plants in Korea. Information on demographic characteristics, including diagnostic examination history, was collected by interview using questionnaires. USG examination was conducted to evaluate the presence of thyroid nodules and breast lesion. Study participants were divided into 3 groups according to the distance of their respective villages from a nuclear power plant. The proportions of USG examination history and prevalence of thyroid nodules and breast lesions were compared between groups. Examination histories of thyroid USG were 23.1%, 13.7%, and 10.5% in men and 31.3%, 26.7%, 18.3% in women in the short, intermediate, and long distance groups, respectively. There were significant inverse associations between thyroid USG history and the distance from nuclear power plants (P for trend=0.001 for men and 0.017 for women). However, there was no association between the distance of villages from nuclear power plants and prevalence of thyroid nodules. Our results suggest that there may be an ascertainment bias in population-based studies examining the harmful effects of NPPs examination and researchers should pay attention to ascertainment bias resulted from differential health examination. Correction for ascertainment bias, active follow-up and examination for all study population to remove differential health examination is needed

Status of the decommissioning program of the Eurochemic reprocessing plant

International Nuclear Information System (INIS)

Detilleux, E.J.

1976-01-01

Reprocessing operations at the Eurochemic demonstration plant stopped in December 1974, after 8 years of operation. Immediately thereafter, cleaning and decontamination were begun as the first phase of the decommissioning program. The facility and reprocessing program are described to indicate the magnitude of the problem, and the requirements of the local authorities are reviewed. The technical decommissioning program consists of several phases: (1) plant cleaning and rinsing, (2) establishment of the final fissile-material balance, (3) plant decontamination for access to process equipment, (4) equipment dismantling, and (5) conditioning and storage of newly generated wastes. The two first phases have been completed, and the third one is nearing completion. Some dismantling has been performed, including the plutonium dioxide production unit. Waste-conditioning and surface-storage facilities have been built to meet the dismantling requirements. Since reprocessing may be resumed in the future, decontamination has been performed with ''smooth'' reagents to limit corrosion and dismantling has been limited to subfacilities

Cost effective water treatment program in Heavy Water Plant (Manuguru)

International Nuclear Information System (INIS)

Mohapatra, C.; Prasada Rao, G.

2002-01-01

Water treatment technology is in a state of continuous evolution. The increasing urgency to conserve water and reduce pollution has in recent years produced an enormous demand for new chemical treatment programs and technologies. Heavy water plant (Manuguru) uses water as raw material (about 3000 m 3 /hr) and its treatment and management has benefited the plant in a significant way. It is a fact that if the water treatment is not proper, it can result in deposit formation and corrosion of metals, which can finally leads to production losses. Therefore, before selecting treatment program, complying w.r.t. quality requirements, safety and pollution aspects cost effectiveness shall be examined. The areas where significant benefits are derived, are raw water treatment using polyelectrolyte instead of inorganic coagulant (alum), change over of regenerant of cation exchangers from hydrochloric acid to sulfuric acid and in-house development of cooling water treatment formulation. The advantages and cost effectiveness of these treatments are discussed in detail. Further these treatments has helped the plant in achieving zero discharge and indirectly increased cost reduction of final product (heavy water); the dosage of 3 ppm of polyelectrolyte can replace 90 ppm alum at turbidity level of 300 NTU of raw water which has resulted in cost saving of Rs. 15-20 lakhs in a year beside other advantages; the change over of regenerant from HCl to H 2 SO 4 will result in cost saving of at least Rs.1.4 crore a year besides other advantages; the change over to proprietary formulation to in-house formulation in cooling water treatment has resulted in a saving about Rs.11 lakhs a year. To achieve the above objectives in a sustainable way the performance results are being monitored. (author)

IAEA team to report on Kashiwazaki Kariwa Nuclear Power Plant examination

International Nuclear Information System (INIS)

2007-01-01

Full text: The Kashiwazaki Kariwa Nuclear Power Plant in Japan, affected by a strong earthquake on 16 July, shut down safely and damage appears less than expected, a fact finding mission of international nuclear safety experts has concluded. The six member expert team of the International Atomic Energy Agency was dispatched upon the request of the Japanese authorities. The mission report will be issued within a few days. The Director General of the IAEA, Mohamed ElBaradei, said today that he welcomed the cooperation and transparency the team had received from the Japanese authorities. The mission's findings and the Japanese analyses of the event include important lessons learned - both positive and negative - that will be relevant to other nuclear plants worldwide, he said. The team conducted a three day physical examination covering the complex of seven units, as well as analysis of instrument logs and other records from the time of the event. It has concluded that plant safety features performed as required during the earthquake. The team's review of plant operator records and analyses support the Japanese authorities' conclusion that the very small amount of radioactivity released was well below the authorized limits for public health and environmental safety. Damage from the earthquake appears to be limited to those sections of the plant that would not affect the reactor or systems related to reactor safety. Detailed checks and inspections by the operator and Japanese authorities are ongoing. According to the IAEA team, significant work, such as detailed examination of the reactor vessels, cores and fuel elements, has still to be performed. Physical stresses resulting from the earthquake could affect the long term safe operation of some plant components, the team said. Additional engineering analysis of such components would be an important consideration for future examination, to determine whether they should be replaced earlier than otherwise anticipated. The

Regulatory oversight strategy for chemistry program at Canadian nuclear power plants

International Nuclear Information System (INIS)

Kameswaran; Ram

2012-09-01

Chemistry program is one of the essential programs for the safe operation of a nuclear power plant. It helps to ensure the necessary integrity, reliability and availability of plant structures, systems and components important to safety. Additionally, the program plays an important role in asset preservation, limiting radiation exposure and environmental protection. A good chemistry program will minimize corrosion of materials, reduce activation products, minimize of the buildup of radioactive material leading to occupational radiation exposure and it helps limit the release of chemicals and radioactive materials to the environment. The legal basis for the chemistry oversight at Canadian NPPs is established by the Nuclear Safety and Control Act and its associated regulations. It draws on the Canadian Nuclear Safety Commission's regulatory framework and NPP operating license conditions that include applicable standards such as CAN/CSA N286-05 Management System Requirements for Nuclear Power Plants. This paper focuses on the regulatory oversight strategy used in Canada to assess the performance of chemistry program at the nuclear power plants (NPPs) licensed by CNSC. The strategy consists of a combination of inspection and performance monitoring activities. The activities are further supported from information gathered through staff inspections of cross-cutting areas such as maintenance, corrective-action follow-ups, event reviews and safety related performance indicators. (authors)

Human action perspectives based on individual plant examination results

International Nuclear Information System (INIS)

Forester, J.; Thompson, C.; Drouin, M.; Lois, E.

1996-01-01

This paper provides perspectives on human actions gained from reviewing 76 individual plant examination (IPE) submittals. Human actions found to be important in boiling water reactors (BWRs) and in pressurized water reactors (PWRs) are presented and the events most frequently found important are discussed. Since there are numerous factors that can influence the quantification of human error probabilities (HEPs) and introduce significant variability in the resulting HEPs (which in turn can influence which events are found to be important), the variability in HEPs for similar events across IPEs is examined to assess the extent to which variability in results is due to real versus artifactual differences. Finally, similarities and differences in human action observations across BWRs and PWRs are examined

Increase plant safety and reduce cost by implementing risk-informed in-service inspection programs

International Nuclear Information System (INIS)

Billington, A.; Monette, P.

2001-01-01

The idea behind the program is that it is possible to 'inspect less, but inspect better'. In other words, the risk-informed In-Service Inspection (ISI) process is used to improve the effectiveness of examination of piping components, i.e. concentrate inspection resources and enhance inspection strategies on high safety significant locations, and reduce inspection requirements on others. The Westinghouse Owners Group (WOG) risk-informed ISI process has already been applied for full scope (Millstone 3, Surry 1) and limited scope (Beznau, Ringhals 4, Asco, Turkey Point 3). By examining the high safety significant piping segments for the different fluid piping systems, the total piping core damage frequency is reduced. In addition, more than 80% of the risk associated with potential pressure boundary failures is addressed with the WOG risk-informed ISI process, while typically less that 50% of this same risk is addressed by the current inspection programs. The risk-informed ISI processes are used to improve the effectiveness of inspecting safety-significant piping components, to reduce inspection requirements on other piping components, to evaluate improvements to plant availability and enhanced safety measures, including reduction of personnel radiation exposure, and to reduce overall Operation and Maintenance (O and M) costs while maintaining regulatory compliance. A description of the process as well as benefits from past projects is presented, since the methodology is applicable for WWER plant design. (author)

Increase plant safety and reduce cost by implementing risk-informed In-Service Inspection programs

International Nuclear Information System (INIS)

Billington, A.; Monette, P.; Doumont, C.

2000-01-01

The idea behind the program is that it is possible to 'inspect less, but inspect better'. In other words, the risk-informed In-Service Inspection (ISI) process is used to improve the effectiveness of examination of piping components, i.e. concentrate inspection resources and enhance inspection strategies on high safety significant locations, and reduce inspection requirements on others. The Westinghouse Owners Group (WOG) risk-informed ISI process has already been applied for full scope (Millstone 3, Surry 1) and limited scope (Beznau, Ringhals 4, Asco, Turkey Point 3). By examining the high safety significant piping segments for the different fluid piping systems, the total piping core damage frequency is reduced. In addition, more than 80% of the risk associated with potential pressure boundary failures is addressed with the WOG risk-informed ISI process, while typically less than 50% of this same risk is addressed by the current inspection programs. The risk-informed ISI processes are used: to improve the effectiveness of inspecting safety-significant piping components; to reduce inspection requirements on other piping components; to evaluate improvements to plant availability and enhanced safety measures, including reduction of personnel radiation exposure; and to reduce overall Operation and Maintenance (O and M) costs while maintaining regulatory compliance. A description of the process as well as benefits of past projects is presented, since the methodology is applicable for VVER plant design. (author)

The Meteorological Monitoring program at a former nuclear weapons plant

International Nuclear Information System (INIS)

Maxwell, D.R.; Bowen, B.M.

1994-01-01

The purpose of the Meteorological Monitoring program at Rocky Flats Plant (RFP) is to provide meteorological information for use in assessing the transport, and diffusion, and deposition of effluent actually or potentially released into the atmosphere by plant operations. Achievement of this objective aids in protecting health and safety of the public, employees, and environment, and directly supports Emergency Response programs at RFP. Meteorological information supports the design of environmental monitoring networks for impact assessments, environmental surveillance activities, remediation activities, and emergency responses. As the mission of the plant changes from production of nuclear weapons parts to environmental cleanup and economic development, smaller releases resulting from remediation activities become more likely. These possible releases could result from airborne fugitive dust, evaporation from collection ponds, or grass fires

‘I used to be ashamed’. The influence of an educational program on tribal and non-tribal children's knowledge and valuation of wild food plants

NARCIS (Netherlands)

Cruz Garcia, G.S.; Howard, P.L.

2013-01-01

This study examines the influence of an extra-curricular educational program on children's knowledge and cultural valuation of wild food plants, which are an important component of their diets. This program aims to reinforce children's traditional knowledge and values around biological resources in

Examination of a Museum Program for Children with Autism

Science.gov (United States)

Mulligan, Shelley; Rais, Paula; Steele-Driscoll, Jacqueline; Townsend, Samantha

2013-01-01

This study examined the effectiveness of a children's museum program designed to support young children with autism spectrum disorders (ASD) and their families. The program offers specialized materials, financial incentives, an exclusive time, and trained volunteers to increase the comfort level, enjoyment, and learning opportunities of attendees.…

AP: A Critical Examination of the Advanced Placement Program

Science.gov (United States)

Sadler, Philip M.; Sonnert, Gerhard; Tai, Robert; Klopfenstein, Kirstin

2016-01-01

The Advanced Placement (AP) program was created to enhance the experience of gifted students as they transition from high school to college. "AP: A Critical Examination of the Advanced Placement Program," edited by Philip M. Sadler, Gerhard Sonnert, Robert Tai, and Kirstin Klopfenstein (2010, Harvard Education Press), questions the…

Utilization of logistic computer programs in the power plant piping industry

International Nuclear Information System (INIS)

Motzel, E.

1982-01-01

Starting from the general situation of the power plant piping industry, the utilization of computer programs as well as the specific magnitude of complexity connected with the project realisation, the necessity for using logistic computer programs especially in case of nuclear power plants is explained. The logistic term as well as the logistic data are described. At the example of the nuclear power plant KRB II, Gundremmingen, Block B/C the practical use of such programs is shown. The planning, scheduling and supervision is carried out computer-aided by means of network-technique. The material management, prefabrication, installation including management of certificates for welding and testing activities is planned and controlled by computer programs as well. With the piping systems installed a complete erection work documentation is available which also serves as base for the billing versus the client. The budgeted costs are continuously controlled by means of a cost control program. Summing-up the further development in controlling piping contracts computer-supported is described with regard to software, hardware and the organisation structure. Furthermore the concept of a self-supporting field computer is introduced for the first time. (orig.) [de

Examining the Role of Multicultural Competence in Leadership Program Design

Science.gov (United States)

Wilson, Amy B.

2015-01-01

Research examining the multicultural competence of leadership educators across a variety of institutions demonstrated variance based on leadership program structure, program elements, and the ways in which diversity was addressed in the program. The Multicultural Competence in Student Affairs-Preliminary 2 (MCSA-P2) scale was used to measure…

Bibliography of the Maryland Power Plant Research Program, Thirteenth Edition

International Nuclear Information System (INIS)

McLean, R.I.

1992-02-01

The Power Plant Siting Act of 1971 (Sec. 3-303) established the Power Plant Research Program to insure that demands for electric power would be met in a timely manner at a reasonable cost while assuring that the associated environmental impact would be acceptable. The scope of the Program extends to estimating the impact of proposed new generating facilities, evaluating the acceptability of proposed transmission line routes, assessing the impact of existing generation facilities, and investigating generic issues related to power plant site evaluation and associated environmental and land use considerations. The bibliography is a compilation of all the studies performed for and or by the Power Plant and Environmental Review Division since its inception. Reports published by the Division considered to be of general interest are routinely made available through the National Technical Information Service. Those reports so registered may be identified by the NTIS accession number immediately following the citation in the bibliography

Recent experience in nuclear plant nondestructive examinations

International Nuclear Information System (INIS)

Epps, T.N.

1986-01-01

This paper reviews recent experience in nuclear plant inservice inspection activities including ultrasonic examination of piping materials, personnel qualification, results, and the overall significance to the industry. Several areas of concern to the nuclear power industry have recently been addressed by Southern Company Services' (SCS) Inspection, Testing, and Engineering Department during implementation of preservice and in-service inspection activities in the SCS system. The most significant of these activities is the ultrasonic inspection of Type 304 stainless steel piping for the presence of intergranular stress corrosion cracking (IGSCC). This activity has been in the forefront of boiling water reactor (BWR) in-service inspections for the past several years

50 CFR 23.79 - How may I participate in the Plant Rescue Center Program?

Science.gov (United States)

2010-10-01

... 50 Wildlife and Fisheries 6 2010-10-01 2010-10-01 false How may I participate in the Plant Rescue Center Program? 23.79 Section 23.79 Wildlife and Fisheries UNITED STATES FISH AND WILDLIFE SERVICE... may I participate in the Plant Rescue Center Program? (a) Purpose. We have established the Plant...

Examining the role of shrub expansion and fire in Arctic plant silica cycling

Science.gov (United States)

Carey, J.; Fetcher, N.; Parker, T.; Rocha, A. V.; Tang, J.

2017-12-01

All terrestrial plants accumulate silica (SiO2) to some degree, although the amount varies by species type, functional group, and environmental conditions. Silica improves overall plant fitness, providing protection from a variety of biotic and abiotic stressors. Plant silica uptake serves to retain silica in terrestrial landscapes, influencing silica export rates from terrestrial to marine systems. These export rates are important because silica is often the limiting nutrient for primary production by phytoplankton in coastal waters. Understanding how terrestrial plant processes influence silica export rates to oceanic systems is of interest on the global scale, but nowhere is this issue more important than in the Arctic, where marine diatoms rely on silica for production in large numbers and terrestrial runoff largely influences marine biogeochemistry. Moreover, the rapid rate of change occurring in the Arctic makes understanding plant silica dynamics timely, although knowledge of plant silica cycling in the region is in its infancy. This work specifically examines how shrub expansion, permafrost thaw, and fire regimes influence plant silica behavior in the Alaskan Arctic. We quantified silica accumulation in above and belowground portions of three main tundra types found in the Arctic (wet sedge, moist acidic, moist non-acidic tundra) and scaled these values to estimate how shrub expansion alters plant silica accumulation rates. Results indicate that shrub expansion via warming will increase silica storage in Arctic land plants due to the higher biomass associated with shrub tundra, whereas conversion of tussock to wet sedge tundra via permafrost thaw would produce the opposite effect in the terrestrial plant BSi pool. We also examined silica behavior in plants exposed to fire, finding that post-fire growth results in elevated plant silica uptake. Such changes in the size of the terrestrial vegetation silica reservoir could have direct consequences for the rates

Qualification of quality assurance program audit personnel for nuclear power plants - August 1980

International Nuclear Information System (INIS)

Anon.

1981-01-01

Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, to 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities, establishes overall quality assurance requirements for the design, construction, and operation of safety-related structures, and components of nuclear power plants. Criterion XVIII, Audits, of Appendix B establishes requirements for conducting audits of the quality assurance program. This guide describes a method acceptable to the NRC staff for complying with the Commission's regulations with regard to qualification of quality assurance program audit personnel for nuclear power plants

Handbook for nuclear power plant self-assessment programs. Final report, July 1991

International Nuclear Information System (INIS)

1991-07-01

EPRI has prepared this handbook to help utilities with their Self-Assessment Programs at nuclear power plants. Self-assessments are independent reviews performed by nuclear plant utilities to identify trends in operational activities that are important to safety, and to assess the impact of these trends on plant safety. Activities performed as self-assessments include reviews and evaluations of plant performance and abnormal events, technical evaluations of plant activities to identify potential problem areas, and reviews of other sources of plant design and operating experience for applicability to safety. This handbook is based on information obtained from utilities and includes examples of activities and methods that have proven effective. The handbook includes a summary of NRC requirements, guidelines for self-assessment program planning, descriptions and examples of investigative techniques, and key references that can be consulted for additional information. It can serve as a training guide for plant staff members who are assigned to self-assessment activities. (author)

Examining the Perceptions of Brand Images Regarding Competing MBA Programs

Science.gov (United States)

Hinds, Timothee; Falgoust, Dexter; Thomas, Kerry, Jr.; Budden, Michael C.

2010-01-01

In today's economic environment, it is crucial to create a strong, consistent brand image within a graduate business program. This study examines the perceptions that students at Southeastern Louisiana University hold about its MBA program and the MBA programs of its main competitors. A focus group was conducted to identify competitors and factors…

Oak Ridge Y-12 Plant Biological Monitoring and Abatement Program Plan

Energy Technology Data Exchange (ETDEWEB)

Adams, S.M.; Brandt, C.C.; Christensen, S.W.; Greeley, M.S.JR.; Hill, W.R.; Peterson, M.J.; Ryon, M.G.; Smith, J.G.; Southworth, G.R.; Stewart, A.J.

2000-09-01

The revised Biological Monitoring and Abatement Program (BMAP) for East Fork Poplar Creek (EFPC) at the Oak Ridge Y-12 Plant, as described, will be conducted as required by the National Pollutant Discharge Elimination System permit issued for the Y-12 Plant on April 28, 1995 and became effective July 1, 1995. The basic approach to biological monitoring used in this program was developed by the staff in the Environmental Science Division (ESD) at the Oak Ridge National Laboratory (ORNL) at the request of the Y-12 Plant. The revision to the BMAP plan is based on results of biological monitoring conducted during the period of 1985 to present. Details of the specific procedures used in the current routine monitoring program are provided; experimental designs for future studies are described in less detail. The overall strategy used in developing this plan was, and continues to be, to use the results obtained from each task to define the scope of future monitoring efforts. Such efforts may require more intensive sampling than initially proposed in some areas (e.g., additional bioaccumulation monitoring if results indicate unexpectedly high PCBs or Hg) or a reduction in sampling intensity in others (e.g., reduction in the number of sampling sites when no impact is still observed). The program scope will be re-evaluated annually. By using the results of previous monitoring efforts to define the current program and to guide us in the development of future studies, an effective integrated monitoring program has been developed to assess the impacts of Y-12 Plant operations (past and present) on the biota of EFPC and to document the ecological effects of remedial actions.

77 FR 73056 - Initial Test Programs for Water-Cooled Nuclear Power Plants

Science.gov (United States)

2012-12-07

... Plants AGENCY: Nuclear Regulatory Commission. ACTION: Draft regulatory guide; request for comment... (DG), DG-1259, ``Initial Test Programs for Water-Cooled Nuclear Power Plants.'' This guide describes... (ITPs) for light water cooled nuclear power plants. DATES: Submit comments by January 31, 2013. Comments...

Computer program for afterheat temperature distribution for mobile nuclear power plant

Science.gov (United States)

Parker, W. G.; Vanbibber, L. E.

1972-01-01

ESATA computer program was developed to analyze thermal safety aspects of post-impacted mobile nuclear power plants. Program is written in FORTRAN 4 and designed for IBM 7094/7044 direct coupled system.

The program of reactors and nuclear power plants

International Nuclear Information System (INIS)

Calabrese, Carlos R.

2001-01-01

Into de framework of the program of research reactors and nuclear power plants, the operating Argentine reactors are described. The uses of the research reactors in Argentina are summarized. The reactors installed by Argentina in other countries (Peru, Algeria, Egypt) are briefly described. The CAREM project for the design and construction of an innovator small power reactor (27 MWe) is also described in some detail. The next biennial research and development program for reactor is briefly outlined

Perspectives on plant vulnerabilities ampersand other plant and containment improvements

International Nuclear Information System (INIS)

LaChance, J.; Kolaczkowski, A.; Kahn, J.

1996-01-01

The primary goal of the Individual Plant Examination (IPE) Program was for licensees to identify plant-unique vulnerabilities and actions to address these vulnerabilities. A review of these vulnerabilities and plant improvements that were identified in the IPEs was performed as part of the IPE Insights Program sponsored by the U.S. Nuclear Regulatory Commission (NRC). The purpose of this effort was to characterize the identified vulnerabilities and the impact of suggested plant improvements. No specific definition for open-quotes vulnerabilityclose quotes was provided in NRC Generic Letter 88-20 or in the subsequent NRC IPE submittal guidance documented in NUREG-1335. Thus licensees were left to use their own definitions. Only 20% of the plants explicitly stated that they had vulnerabilities. However, most licensees identified other plant improvements to address issues not explicitly classified as vulnerabilities, but pertaining to areas in which overall plant safety could potentially be increased. The various definitions of open-quotes vulnerabilityclose quotes used by the licensees, explicitly identified vulnerabilities, proposed plant improvements to address these vulnerabilities, and other plant improvements are summarized and discussed

TMI-2 Technical Information and Examination Program. 1982 annual report

International Nuclear Information System (INIS)

1983-04-01

The Department of Energy's Technical Information and Examination Program at Three Mile Island Unit 2 continued the research and development work begun on the island in 1980. The work concentrated in seven major areas: instrumentation and electrical components, radiation and environment, core activities, information and industry coordination, configuration and document control, waste immobilization, and reactor evaluation. The program assists in resolving specific problems at TMI-2 while developing techniques and broadening understanding of accident consequences to improve the overall safety and reliability of nuclear power. The Technical Information and Examination Program aims to communicate applicable information to the nuclear power industry to ensure that the industry can avail itself of the maximum amount of information possible

TMI-2 Technical Information and Examination Program 1983 annual report

International Nuclear Information System (INIS)

Scardena, D.E.

1984-04-01

The Department of Energy's Technical Information and Examination Program at Three Mile Island Unit 2 continued the research and development work begun on the Island in 1980. The work concentrated in six major areas: waste immobilization, reactor evaluation, data acquisition, information and industry coordination, core activities, and EPICOR II and waste research and disposition. The program assists in resolving specific problems at TMI-2 while developing techniques and broadening understanding of accident consequences to improve the overall safety and reliability of nuclear power. The Technical Information and Examination Program aims to communicate applicable information to the nuclear power industry to ensure that the industry can avail itself to the maximum amount of information possible

Integrated plant safety assessment systematic evaluation program. R.E. Ginna Nuclear Power Plant, Rochester Gas and Electric Corporation, Docket No. 50-244

International Nuclear Information System (INIS)

1982-05-01

The Systematic Evaluation Program was initiated in February 1978 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to reconfirm and document their safety. The review provides (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of the R.E. Ginna Nuclear Power Plant (located in Wayne County near Rochester, NY), one of ten plants reviewed under Phase II of this program, and indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review. It is expected that this report will be one of the bases in considering the issuance of a full-term operating license in place of the existing provisional operating license

Aquatic Plant Control Research Program. Volume A-00-1

National Research Council Canada - National Science Library

Kirk, James

2000-01-01

... at the Waterways Experiment Station. It is principally intended to be a forum whereby information pertaining to and resulting from the Corps of Engineers' nationwide Aquatic Plant Control Research Program (APCRP...

78 FR 35330 - Initial Test Programs for Water-Cooled Nuclear Power Plants

Science.gov (United States)

2013-06-12

... Plants AGENCY: Nuclear Regulatory Commission. ACTION: Regulatory guide; issuance. SUMMARY: The U.S... Programs for Water-Cooled Nuclear Power Plants.'' This guide describes the general scope and depth that the... power plants. ADDRESSES: Please refer to Docket ID NRC-2012-0293 about the availability of information...

Use of nondestructive evaluation methods to improve power plant availability

International Nuclear Information System (INIS)

Weber, R.M.

1985-01-01

On an ever-increasing basis, utilities are relying on nondestructive evaluation (NDE) as a management and planning tool. In addition to the conventional ASME Code and Technical Specification-required examinations, progressive utilities are utilizing NDE sampling programs to monitor existing conditions and search for potential situations affecting plant safety and reliability. Improved NDE detection and sizing procedures give management personnel the accurate information needed to make the ''go/no go'' decisions on repair programs which can significantly affect plant availability. As the burden of regulatory-imposed inspection requirements increases, plant personnel are increasingly cognizant that NDE is a significant factor in their plant's outage schedule. Whether an outage is scheduled or forced, NDE becomes part of each plant's program to assure the safety and reliability of its critical components. Knowledge and planning of NDE application is important because of the time expended in examination performance and subsequent data evaluation. Managers who are knowledgeable in NDE application can effectively improve plant availability by scheduling NDE as an integral part of their maintenance programs. Examination results can then be used in making decisions directly affecting availability

Genesis of the Brazilian nuclear power plants program

International Nuclear Information System (INIS)

Syllus, G.; Lepecki, W.

1996-01-01

The genesis of the Brazilian Nuclear Power Program is described by the authors - who participated in the events - from the beginning of the sixties, until the definition and the start of the implementation in 1975 of the Reference Nuclear Power Program. A description is made of the main events, studies and decisions that contributed to the evolution of the Program: the GTRP (Nuclear Power Plant Working Group); the Thorium Group; the Lane Group; the decision about Angra 1; CNEN's analyses about the reactor line and, finally, the creation of CBTN (Nuclear Technology Brazilian Company), which elaborated the studies that resulted in the final definition of the Program and led to the Brazilian German Agreement and the establishment of NUCLEBRAS. (author)

United States Medical Licensing Examination and American Board of Pediatrics Certification Examination Results: Does the Residency Program Contribute to Trainee Achievement.

Science.gov (United States)

Welch, Thomas R; Olson, Brad G; Nelsen, Elizabeth; Beck Dallaghan, Gary L; Kennedy, Gloria A; Botash, Ann

2017-09-01

To determine whether training site or prior examinee performance on the US Medical Licensing Examination (USMLE) step 1 and step 2 might predict pass rates on the American Board of Pediatrics (ABP) certifying examination. Data from graduates of pediatric residency programs completing the ABP certifying examination between 2009 and 2013 were obtained. For each, results of the initial ABP certifying examination were obtained, as well as results on National Board of Medical Examiners (NBME) step 1 and step 2 examinations. Hierarchical linear modeling was used to nest first-time ABP results within training programs to isolate program contribution to ABP results while controlling for USMLE step 1 and step 2 scores. Stepwise linear regression was then used to determine which of these examinations was a better predictor of ABP results. A total of 1110 graduates of 15 programs had complete testing results and were subject to analysis. Mean ABP scores for these programs ranged from 186.13 to 214.32. The hierarchical linear model suggested that the interaction of step 1 and 2 scores predicted ABP performance (F[1,1007.70] = 6.44, P = .011). By conducting a multilevel model by training program, both USMLE step examinations predicted first-time ABP results (b = .002, t = 2.54, P = .011). Linear regression analyses indicated that step 2 results were a better predictor of ABP performance than step 1 or a combination of the two USMLE scores. Performance on the USMLE examinations, especially step 2, predicts performance on the ABP certifying examination. The contribution of training site to ABP performance was statistically significant, though contributed modestly to the effect compared with prior USMLE scores. Copyright © 2017 Elsevier Inc. All rights reserved.

Integrated Plant Safety Assessment: Systematic Evaluation Program. Haddam Neck Plant, Connecticut Yankee Atomic Power Company, Docket No. 50-213. Final report

International Nuclear Information System (INIS)

1983-01-01

The Systematic Evaluation Progam was initiated in February 1977 by the US Nuclear Regulatory Commission review the designs of older operating nuclear reactor plants to confirm and document their safety. The review provides: (1) an assessment of how these plants compare with curent licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of Haddam Neck Plant, operated by Connecticut Yankee Atomic Power Company. The Haddam Neck Plant is one of 10 plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review

Analysis of integrated plant upgrading/life extension programs

International Nuclear Information System (INIS)

McCutchan, D.A.; Massie, H.W. Jr.; McFetridge, R.H.

1988-01-01

A present-worth generating cost model has been developed and used to evaluate the economic value of integrated plant upgrading life extension project in nuclear power plants. This paper shows that integrated plant upgrading programs can be developed in which a mix of near-term availability, power rating, and heat rate improvements can be obtained in combination with life extension. All significant benefits and costs are evaluated from the viewpoint of the utility, as measured in discounted revenue requirement differentials between alternative plans which are equivalent in system generating capacity. The near-term upgrading benefits are shown to enhance the benefit picture substantially. In some cases the net benefit is positive, even if the actual life extension proves to be less than expected

Japanese plant life extension program

International Nuclear Information System (INIS)

Yoshitsugu, M.

1988-01-01

As one of the main items of up-grading light water reactor program in Japan, plant life extension has been recommended by Advisory Committee of Ministry of International trade and Industry and the practical work has begun to be carried out. It is overviewed here. After preliminary works, including investigation on the state of the arts through a entrusted survey work, participation in international meetings and exchange of informations with related organizations, actual work has just started. So-called critical components based on our experience during the past 17 years have been listed up and some experimental works inaugurated as from 1987

Integrated inspection programs at Bruce Heavy Water Plant

Energy Technology Data Exchange (ETDEWEB)

Brown, K C [Ontario Hydro, Tiverton, ON (Canada)

1993-12-31

Quality pressure boundary maintenance and an excellent loss prevention record at Bruce Heavy Water Plant are the results of the Material and Inspection Unit`s five inspection programs. Experienced inspectors are responsible for the integrity of the pressure boundary in their own operating area. Inspectors are part of the Technical Section, and along with unit engineering staff, they provide technical input before, during, and after the job. How these programs are completed, and the results achieved, are discussed. 5 figs., 1 appendix.

Integrated inspection programs at Bruce Heavy Water Plant

International Nuclear Information System (INIS)

Brown, K.C.

1992-01-01

Quality pressure boundary maintenance and an excellent loss prevention record at Bruce Heavy Water Plant are the results of the Material and Inspection Unit's five inspection programs. Experienced inspectors are responsible for the integrity of the pressure boundary in their own operating area. Inspectors are part of the Technical Section, and along with unit engineering staff, they provide technical input before, during, and after the job. How these programs are completed, and the results achieved, are discussed. 5 figs., 1 appendix

Mark II containment lead plant program load evaluation and acceptance criteria

International Nuclear Information System (INIS)

1978-10-01

The report, prepared by the Office of Nuclear Reactor Regulation, addresses the portion of the Mark II owner's program that provides a generic methodology for establishing design basis LOCA and safety relief valve loads for the lead Mark II facilities (Zimmer, Shoreham, and LaSalle), i.e., the lead plant program. The report includes an evaluation of the Mark II owner's load methodology, a description of load methodologies that we find acceptable for use in the individual plant unique assessments, and the basis for the stated conclusions

Examining Dehydration and Hypoxic Stress in Wheat Plants Using a Porous Tube Plant Nutrient Delivery System Developed for Microgravity

Science.gov (United States)

Dreschel, T. W.; Hall, C. R.; Foster, T. E.; Salganic, M.; Warren, L.; Corbett, M.

2005-01-01

The Porous Tube Plant Nutrient Delivery System (PTPNDS) was designed for NASA to grow plants in microgravity of space. The system utilizes a controlled fluid loop to supply nutrients and water to plant roots growing on a ceramic surface moistened by capiflary action. A PTPNDS test bed was developed and utilizing remote sensing systems, spectral analyses procedures, gas-exchange, and fluorescence measurements, we examined differences in plant water status for wheat plants (Triticum aestivum, cv. Perigee) grown in a modified growth chamber during the summers of 2003 and 2004. Some differences in plant performance were detectable in the gas-exchange and fluorescence measurements. For instance, in both years the plants grown with the most available water had the lowest rates of photosynthesis and exhibited higher proportions of non-photochemical quenching particularly under low light levels. In addition, small differences in mean leaf water content between treatments were detected using spectral reflectance analyses.

75 FR 9691 - Review of the Commission's Program Access Rules and Examination of Programming Tying Arrangements

Science.gov (United States)

2010-03-03

... involving programming they own, that impede competition in the video distribution market. See H.R. Rep. No... availability of programming and charging discriminatory prices to non- cable technologies.'' H.R. Rep. No. 102... Access Rules and Examination of Programming Tying Arrangements; Final Rule #0;#0;Federal Register / Vol...

15. international conference on plant growth substances: Program -- Abstracts

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-12-31

Since the 14th Conference in Amsterdam in 1991, progress in plant hormone research and developmental plant biology has been truly astonishing. The five ``classical`` plant hormones, auxin, gibberellin, cytokinin, ethylene, and abscisic acid, have been joined by a number of new signal molecules, e.g., systemin, jasmonic acid, salicylic acid, whose biosynthesis and functions are being understood in ever greater detail. Molecular genetics has opened new vistas in an understanding of transduction pathways that regulate developmental processes in response to hormonal and environmental signals. The program of the 15th Conference includes accounts of this progress and brings together scientists whose work focuses on physiological, biochemical, and chemical aspects of plant growth regulation. This volume contains the abstracts of papers presented at this conference.

TMI-2 core examination plan

International Nuclear Information System (INIS)

Carlson, J.O.

1984-07-01

The role of the Three Mile Island Unit 2 (TMI-2) core examination in the resolution of major nuclear safety issues is delineated in this plan. Relevant data needs are discussed, and approaches for recovering data from the TMI-2 plant are identified. Specific recommendations and justifications are provided for in situ documentation and off-site artifact examination activities. The research and development program is being managed by EG and G Idaho, Inc

Neurolinguistic Programming Examined: Imagery, Sensory Mode, and Communication.

Science.gov (United States)

Fromme, Donald K.; Daniell, Jennifer

1984-01-01

Tested Neurolinguistic Programming (NLP) assumptions by examining intercorrelations among response times of students (N=64) for extracting visual, auditory, and kinesthetic information from alphabetic images. Large positive intercorrelations were obtained, the only outcome not compatible with NLP. Good visualizers were significantly better in…

Growing Plants and Scientists: Fostering Positive Attitudes toward Science among All Participants in an Afterschool Hydroponics Program

Science.gov (United States)

Patchen, Amie K.; Zhang, Lin; Barnett, Michael

2017-06-01

This study examines an out-of-school time program targeting elementary-aged youth from populations that are typically underrepresented in science fields (primarily African-American, Hispanic, and/or English Language Learner participants). The program aimed to foster positive attitudes toward science among youth by engaging them in growing plants hydroponically (in water without soil). Participants' attitudes toward science, including anxiety, desire, and self-concept, were examined through pre-post survey data ( n = 234) over the course of an afterschool program at three separate sites. Data showed that participants' anxiety decreased and desire increased for both male and female participants over the program. Self-concept increased for female participants at all three sites but did not change significantly for male participants. Participants' first language (English or Spanish) was not a factor in attitude outcomes. The primarily positive outcomes suggest that hydroponics can be a useful educational platform for engaging participants in garden-based programming year round, particularly for settings that do not have the physical space or climate to conduct outdoor gardening. Similarities in positive attitude outcomes at the three sites despite differences in format, implementation, and instructor background experience suggest that the program is resilient to variation in context. Understanding which aspects of the program facilitated positive outcomes in the varied contexts could be useful for the design of future programs.

Nuclear Plant Aging Research (NPAR) program plan

International Nuclear Information System (INIS)

1985-07-01

The nuclear plant aging research described in this plan is intended to resolve issues related to the aging and service wear of equipment and systems at commercial reactor facilities and their possible impact on plant safety. Emphasis has been placed on identification and characterization of the mechansims of material and component degradation during service and evaluation of methods of inspection, surveillance, condition monitoring and maintenance as means of mitigating such effects. Specifically the goals of the program are as follows: (1) to identify and characterize aging and service wear effects which, if unchecked, could cause degradation of structures, components, and systems and thereby impair plant safety; (2) to identify methods of inspection, surveillance and monitoring, or of evaluating residual life of structures, components, and systems, which will assure timely detection of significant aging effects prior to loss of safety function; and (3) to evaluate the effectiveness of storage, maintenance, repair and replacement practices in mitigating the rate and extent of degradation caused by aging and service wear

Rockwell International's Critical Mass Laboratory Program at the Rocky Flats Plant

International Nuclear Information System (INIS)

McCarthy, J.D.

1984-01-01

The primary mission of the laboratory is to provide data in support of plant operations. To fulfill this task, the facility has unique capabilities for perfoming general purpose critical mass experiment. The critical mass laboratory performed over 1000 critical measurements, primarily with plutonium metal and uranium metal, oxide and solution; it worked also on the NRC program (high-enriched uranium measurements). Presently the laboratory staff prepares for a series of critical measurements on a poisoned tube tank; the laboratory intends to continue to pursue basic plant support programs in the future

Waste Isolation Pilot Plant transuranic wastes experimental characterization program: executive summary

International Nuclear Information System (INIS)

Molecke, M.A.

1978-11-01

A general overview of the Waste Isolation Pilot Plant transuranic wastes experimental characterization program is presented. Objectives and outstanding concerns of this program are discussed. Characteristics of transuranic wastes are also described. Concerns for the terminal isolation of such wastes in a deep bedded salt facility are divided into two phases, those during the short-term operational phase of the facility, and those potentially occurring in the long-term, after decommissioning of the repository. An inclusive summary covering individual studies, their importance to the Waste Isolation Pilot Plant, investigators, general milestones, and comments are presented

46 CFR 176.650 - Alternative Hull Examination Program options: Divers or underwater ROV.

Science.gov (United States)

2010-10-01

... 46 Shipping 7 2010-10-01 2010-10-01 false Alternative Hull Examination Program options: Divers or...) SMALL PASSENGER VESSELS (UNDER 100 GROSS TONS) INSPECTION AND CERTIFICATION Hull and Tailshaft Examinations § 176.650 Alternative Hull Examination Program options: Divers or underwater ROV. To complete the...

Development of a measure of training program effectiveness for nuclear power plants

International Nuclear Information System (INIS)

Connelly, E.M.; Haas, P.; VanHemel, S.B.; Wreathall, J.

1991-01-01

The approach taken to develop measures of training program effectiveness recognizes that many subject matter experts (SMEs) with varying viewpoints on training effectiveness are working to insure nuclear power plant (NPP) safety. This paper discusses a model as the effectiveness rating strategies of various SMEs whose ratings are important to training; i.e., build a measure of effectiveness (MOE) representing the rating strategy of a sample of those SMEs. A quantitative model of these assessment strategies permits a broad review of them by ll interested parties and provides the basis for building a broadly accepted training program MOE. Major differences in assessment strategies can be examined to determine whether they are appropriate to the different points of view or are in conflict. This paper describes the basic concepts of building effectiveness measures, the methodology used to build the measures, a summary of the measures developed form NRC and industry sources, and an analysis of the differences among SMEs' measures

ESP and NOAH: computer programs for flood-risk analysis of nuclear power plants

International Nuclear Information System (INIS)

Wagner, D.P.; Montague, D.F.; Rooney, J.J.; Fussell, J.B.; Baker, L.S.

1982-06-01

This report describes a computer program package that aids in assessing the impact of floods on risk from nuclear power plants. The package consists of two distinct computer programs: ESP and NOAH. The ESP program improves the efficiency of a flood analysis by screening accident sequences and identifying accident sequences that are potentially significant contributors to risk in the event of a flood. Input to ESP includes accident sequences from an existing risk assessment and flood screening criteria. The NOAH program provides detailed qualitative analysis of the plant systems identified by ESP. NOAH performs a qualitative flood simulation of the fault tree

Detection of programmed cell death in plant embryos.

Science.gov (United States)

Filonova, Lada H; Suárez, María F; Bozhkov, Peter V

2008-01-01

Programmed cell death (PCD) is an integral part of embryogenesis. In plant embryos, PCD functions during terminal differentiation and elimination of the temporary organ, suspensor, as well as during establishment of provascular system. Embryo abortion is another example of embryonic PCD activated at pathological situations and in polyembryonic seeds. Recent studies identified the sequence of cytological events leading to cellular self-destruction in plant embryos. As in most if not all the developmental cell deaths in plants, embryonic PCD is hallmarked by autophagic degradation of the cytoplasm and nuclear disassembly that includes breakdown of the nuclear envelope and DNA fragmentation. The optimized setup of terminal deoxynucleotidyl transferase-mediated dUTP nick end labeling (TUNEL) allows the routine in situ analysis of nuclear DNA fragmentation in plant embryos. This chapter provides step-by-step procedure of how to process embryos for TUNEL and how to combine TUNEL with immunolocalization of the protein of interest.

Three Mile Island Startup program and its contributions to plant performance

International Nuclear Information System (INIS)

Brill, R.A.; Barton, J.J.

1976-01-01

The General Public Utilities Service Corporation Startup Organization provided a specialized group for startup testing, coordination, and management of the Three Mile Island Unit No. 1 nuclear power plant. This organization conducted an extensive test program which contributed to Three Mile Island's high first year plant availability

Oak Ridge Y-12 Plant biological monitoring and abatement program (BMAP) plan

Energy Technology Data Exchange (ETDEWEB)

Adams, S.M.; Brandt, C.C.; Cicerone, D.S. [and others

1998-02-01

The proposed Biological Monitoring and Abatement Program (BMAP) for East Fork Poplar Creek (EFPC) at the Oak Ridge Y-12 Plant, as described, will be conducted for the duration of the National Pollutant Discharge Elimination System permit issued for the Y-12 Plant on April 28, 1995, and which became effective July 1, 1995. The basic approach to biological monitoring used in this program was developed by the staff in the Environmental Sciences Division at the Oak Ridge National Laboratory at the request of Y-12 Plant personnel. The proposed BMAP plan is based on results of biological monitoring conducted since 1985. Details of the specific procedures used in the current routine monitoring program are provided, but experimental designs for future studies are described in less detail. The overall strategy used in developing this plan was, and continues to be, to use the results obtained from each task to define the scope of future monitoring efforts. Such efforts may require more intensive sampling than initially proposed in some areas or a reduction in sampling intensity in others. By using the results of previous monitoring efforts to define the current program and to guide them in the development of future studies, an effective integrated monitoring program has been developed to assess the impacts of the Y-12 Plant operation on the biota of EFPC and to document the ecological effects of remedial actions.

Oak Ridge Y-12 Plant biological monitoring and abatement program (BMAP) plan

International Nuclear Information System (INIS)

Adams, S.M.; Brandt, C.C.; Cicerone, D.S.

1998-02-01

The proposed Biological Monitoring and Abatement Program (BMAP) for East Fork Poplar Creek (EFPC) at the Oak Ridge Y-12 Plant, as described, will be conducted for the duration of the National Pollutant Discharge Elimination System permit issued for the Y-12 Plant on April 28, 1995, and which became effective July 1, 1995. The basic approach to biological monitoring used in this program was developed by the staff in the Environmental Sciences Division at the Oak Ridge National Laboratory at the request of Y-12 Plant personnel. The proposed BMAP plan is based on results of biological monitoring conducted since 1985. Details of the specific procedures used in the current routine monitoring program are provided, but experimental designs for future studies are described in less detail. The overall strategy used in developing this plan was, and continues to be, to use the results obtained from each task to define the scope of future monitoring efforts. Such efforts may require more intensive sampling than initially proposed in some areas or a reduction in sampling intensity in others. By using the results of previous monitoring efforts to define the current program and to guide them in the development of future studies, an effective integrated monitoring program has been developed to assess the impacts of the Y-12 Plant operation on the biota of EFPC and to document the ecological effects of remedial actions

Early Site Permit Demonstration Program: Plant parameters envelope report. Volume 1

Energy Technology Data Exchange (ETDEWEB)

1993-03-01

The Early Site Permit (ESP) Demonstration Program is the nuclear industry`s initiative for piloting the early resolution of siting-related issues before the detailed design proceedings of the combined operating license review. The ESP Demonstration Program consists of three phases. The plant parameters envelopes task is part of Phase 1, which addresses the generic review of applicable federal regulations and develops criteria for safety and environmental assessment of potential sites. The plant parameters envelopes identify parameters that characterize the interface between an ALWR design and a potential site, and quantify the interface through values selected from the Utility Requirements Documents, vendor design information, or engineering assessments. When augmented with site-specific information, the plant parameters envelopes provide sufficient information to allow ESPs to be granted based on individual ALWR design information or enveloping design information for the evolutionary, passive, or generic ALWR plants. This document is expected to become a living document when used by future applicants.

46 CFR 71.50-19 - The Alternative Hull Examination (AHE) Program application.

Science.gov (United States)

2010-10-01

... 46 Shipping 3 2010-10-01 2010-10-01 false The Alternative Hull Examination (AHE) Program...) PASSENGER VESSELS INSPECTION AND CERTIFICATION Drydocking § 71.50-19 The Alternative Hull Examination (AHE... apply to the AHE Program. You must submit an application at least 90 days before the requested hull...

Plant programmed cell death, ethylene and flower senescence

NARCIS (Netherlands)

Woltering, E.J.; Jong, de A.; Hoeberichts, F.A.; Iakimova, E.T.; Kapchina, V.

2005-01-01

Programmed cell death (PCD) applies to cell death that is part of the normal life of multicellular organisms. PCD is found throughout the animal and plant kingdoms; it is an active process in which a cell suicide pathway is activated resulting in controlled disassembly of the cell. Most cases of PCD

Program of social protection for Chornobyl nuclear power plant staff and Slavutich town residents in the aftermath of the plant shutdown

International Nuclear Information System (INIS)

Komarov, V.A.

2001-01-01

In order to solve social issues related to ChNPP shutdown, the Ukrainian Government approved 'Program of Social Protection for Chornobyl Nuclear Power Plant Staff and Slavutich Town Residents in Aftermath of Plant Shutdown' on 29 November 2000. The Program Objective is to ensure social protection and support of well being of ChNPP staff and Slavutich town residents after the plant shutdown. Preserve and develop town infrastructure. Create compensatory jobs; efficiently manage human resources; provide social allowances and guarantees to the ChNPP staff that is being released, and Slavutich town residents

Auditing of quality assurance programs for nuclear power plants - September 1980 - (Rev.1)

International Nuclear Information System (INIS)

Anon.

1981-01-01

Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, to 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities, establishes overall quality assurance requirements for the design, construction, and operation of structures, systems, and components of nuclear power plants important to safety. Criterion XVIII, Audits, of Appendix B to 10 CFR Part 50 establishes requirements for conducting audits of the quality assurance program. This guide describes a method acceptable to the NRC staff for complying with the Commission's regulations with regard to auditing of quality assurance programs for nuclear power plants. The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position

Examination of radioactive contamination in the soil-plant system and their transfer to selected animal tissues

International Nuclear Information System (INIS)

Chibowski, S.; Gladysz, A.

1999-01-01

This paper investigates gamma emitter radioactivity in a system consisting of soil and plants. Some selected sample of tissues of animals fed with the plants from these sites were also measured. In soil and plant samples artificial ( 137 Cs and 134 Cs) and natural (thorium and uranium series) isotopes were detected. Despite the relatively high content of the natural isotopes in plants and their seeds, their accumulation in animal tissues was not detected.The 40 K isotope was transferred in the chain soil-plant-animal in the highest degree. From the group of the natural isotopes, only 212 Pb was detected in examined animal tissue samples. Other natural isotopes were below detection level. In the samples heavy metal content was also examined. In any sample no element concentration was noticed above trade acceptable limit. (author)

Angra nuclear plant - environmental control program; Usina Nuclear de Angra: programa de controle ambiental

Energy Technology Data Exchange (ETDEWEB)

Kircher, E; Cruz, E.S. da [FURNAS, Rio de Janeiro, RJ (Brazil)

1990-12-31

The pre-operational studies, that were elaborated before the beginning of Angra I Power Plant operation, are described in particular the environmental radiological safety area till the fuel loading in the core reactor. Several aspects are included, as socio-economic survey, seismological analysis, Meteorological Program, marine biology, water cooling system, exposure measures of natural radiation, marine sediments characterization in the effluent dispersion area and Environmental Radiological Monitoring Program. The main environmental programs developed for the operational phase of the Angra I Plant are also presented, citing some considerations about the Meteorological Program, Marine Biology Control Program, Temperature and Chlorine Control in Piraquara de Fora Bay, Radiological Environmental Monitoring Program, Sanitary Effluent Control Program and Radiological Emergency Program. (C.G.C.). 2 refs.

Next Generation Nuclear Plant Materials Research and Development Program Plan

Energy Technology Data Exchange (ETDEWEB)

G.O. Hayner; R.L. Bratton; R.N. Wright

2005-09-01

The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Project is envisioned to demonstrate the following: (1) A full-scale prototype VHTR by about 2021; (2) High-temperature Brayton Cycle electric power production at full scale with a focus on economic performance; (3) Nuclear-assisted production of hydrogen (with about 10% of the heat) with a focus on economic performance; and (4) By test, the exceptional safety capabilities of the advanced gas-cooled reactors. Further, the NGNP program will: (1) Obtain a Nuclear Regulatory Commission (NRC) License to construct and operate the NGNP, this process will provide a basis for future performance based, risk-informed licensing; and (2) Support the development, testing, and prototyping of hydrogen infrastructures. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. The NGNP Materials R&D Program includes the following elements: (1) Developing a specific approach, program plan and other project management tools for

Development of computer program for safety of nuclear power plant against tsunami

International Nuclear Information System (INIS)

Jin, S. B.; Choi, K. R.; Lee, S. K.; Cho, Y. S.

2001-01-01

The main objective of this study is the development of a computer program to check the safety of nuclear power plants along the coastline of the Korean Peninsula. The computer program describes the propagation and associated run-up process of tsunamis by solving linear and nonlinear shallow-water equations with finite difference methods. The computer program has been applied to several ideal and simplified problems. Obtained numerical solutions are compared to existing and available solutions and measurements. A very good agreement between numerical solutions and existing measurement is observed. The computer program developed in this study can be to check the safety analysis of nuclear power plants against tsunamis. The program can also be used to study the propagation of tsunamis for a long distance, and associated run-up and run-down process along a shoreline. Furthermore, the computer program can be used to provide the proper design criteria of coastal facilities and structures

Candu Energy's Aging and Obsolescence Program and its Application to Operating Facilities and New Plant Design

International Nuclear Information System (INIS)

Dam, R.; Gold, R.; McCrea, L.

2012-01-01

While plant aging is inevitable, predictable and 'graceful 'aging' behavior can be achieved through the implementation of a comprehensive and integrated Plant Life Management (PLiM) program. Despite organizations like the IAEA and INPO placing more emphasis on equipment reliability, there is still a lack of completely integrated programs in the industry as evidenced by: - Piece-meal, often crisis-driven, implementation comprising many different, partial solutions; - Duplication of effort often seen when different groups work in 'silos'. A strategy which fits with existing plant processes and programs, and which coordinates a broad range of equipment reliability activities is key to achieving the desired results. An example of such a program is the Aging and Obsolescence Program (AOP). AOP follows application of INPO AP-913 guidance for equipment reliability. The program is augmented to include single point vulnerability identification, unified approach to short and long lived components, risk management, spare parts management, and the identification and resolution of obsolescence issues. The systematic nature of the program provides the needed foundation to old and new stations alike. For existing operating stations some of the key uses include outage interval extension, reduced forced outages, and/or outage time reduction, any of which can translate into improving plant performance, competitiveness, and significant dollars saved. Program elements applied to new plant design are commensurate with the industry direction to 'design for reliability', and has allowed Candu Energy to learn and to improve upon what it can offer to operating stations. This paper intends to describe the basic elements of Candu Energy's Aging and Obsolescence Program and will share some of the experience having applied it to existing operating stations, consider applications to support expanding regulatory requirements, and describe the integration into the design of new plants, promoting

Reliability programs for nuclear power plants. Regulatory standard S-98 revision 1

International Nuclear Information System (INIS)

2005-07-01

The purpose of this regulatory standard is to help assure, in accordance with the purpose of the Nuclear Safety and Control Act (NSCA), that a licensee who constructs or operates a nuclear power plant (NPP) develops and implements a reliability program that assures that the systems important to safety at the plant can and will meet their defined design and performance specifications at acceptable levels of reliability throughout the lifetime of the facility. This regulatory standard describes the requirements of a reliability program for a nuclear power plant. The licensee shall implement the requirements described in this regulatory standard when a condition of a licence or other legally enforceable instrument so requires.(author)

OAK RIDGE Y-12 PLANT BIOLOGICAL MONITORING AND ABATEMENT PROGRAM (BMAP) PLAN

Energy Technology Data Exchange (ETDEWEB)

ADAMS, S.M.; BRANDT, C.C.; CHRISTENSEN, S.W.; CICERONE, D.S.; GREELEY, M.S.JR; HILL, W.R.; HUSTON, M.S.; KSZOS, L.A.; MCCARTHY, J.F.; PETERSON, M.J.; RYON, M.G.; SMITH, J.G.; SOUTHWORTH, G.R.; STEWART, A.J.

1998-10-01

The proposed Biological Monitoring and Abatement Program (BMAP) for East Fork Poplar Creek (EFPC) at the Oak Ridge Y-12 Plant, as described, will be conducted for the duration of the National Pollutant Discharge Elimination System permit issued for the Y-12 Plant on April 28, 1995, and which became effective July 1, 1995. The basic approach to biological monitoring used in this program was developed by the staff in the Environmental Sciences Division at the Oak Ridge National Laboratory at the request of Y- 12 Plant personnel. The proposed BMAP plan is based on results of biological monitoring conducted since 1985. Details of the specific procedures used in the current routine monitoring program are provided but experimental designs for future studies are described in less detail. The overall strategy used in developing this plan was, and continues to be, to use the results obtained from each task to define the scope of future monitoring efforts. Such efforts may require more intensive sampling than initially proposed in some areas (e.g., additional toxicity testing if initial results indicate low survival or reproduction) or a reduction in sampling intensity in others (e.g., reduction in the number of sampling sites when no impact is observed). By using the results of previous monitoring efforts to define the current program and to guide us in the development of future studies, an effective integrated monitoring program has been developed to assess the impacts of the Y-12 Plant operation on the biota of EFPC and to document the ecological effects of remedial actions.

An Examination of Program Selection Criteria for Part-Time MBA Students

Science.gov (United States)

Colburn, Michael; Fox, Daniel E.; Westerfelt, Debra Kay

2011-01-01

Prospective graduate students select a graduate program as a result of a multifaceted decision-making process. This study examines the selection criteria that part-time MBA students used in selecting a program at a private university. Further, it analyzes the methods by which the students first learned of the MBA program. The authors posed the…

Concrete Technology program for nuclear power plants

International Nuclear Information System (INIS)

Hassazadeh, M.; Wrangensten, L.

2009-01-01

The nuclear power plants in Sweden and Finland were built during the seventies/eighties and it is planned to extend their service life and increase their production capacity. The challenges are now to assess the condition of the concrete structures; to verify whether or not the structures can withstand the prescribed loads and functions; and verify if the structures can be upgraded in order to fulfil the requirements regarding load bearing and functional capacity. A research program was launched whose priority is condition assessment of the reactor containment. The research includes condition of the pre-stressing reinforcement, reinforcement bars, lining, leakage etc. The conditions are assessed both by destructive and non-destructive test methods. The addressed properties are physical, mechanical, electro-chemical and geometrical. The paper presents the organisation of the program, the co-operating partners, the research program, and the content of the on-going and planned research projects

Hanford Waste Vitrification Plant Quality Assurance Program description for high-level waste form development and qualification

International Nuclear Information System (INIS)

1993-08-01

The Hanford Waste Vitrification Plant Project has been established to convert the high-level radioactive waste associated with nuclear defense production at the Hanford Site into a waste form suitable for disposal in a deep geologic repository. The Hanford Waste Vitrification Plant will mix processed radioactive waste with borosilicate material, then heat the mixture to its melting point (vitrification) to forin a glass-like substance that traps the radionuclides in the glass matrix upon cooling. The Hanford Waste Vitrification Plant Quality Assurance Program has been established to support the mission of the Hanford Waste Vitrification Plant. This Quality Assurance Program Description has been written to document the Hanford Waste Vitrification Plant Quality Assurance Program

Audit program for physical security systems at nuclear power plants

International Nuclear Information System (INIS)

Minichino, C.

1982-01-01

Licensees of nuclear power plants conduct audits of their physical security systems to meet the requirements of 10 CFR 73, Physical Protection of Plants and Materials. Section 73.55, Requirements for physical Protection of Licensed Activities in Nuclear Power Reactors Against Radiological Sabotage, requires that the security programs be reviewed at least every 12 months, that the audit be conducted by individuals independent of both security management and security supervision, and that the audit program review all aspects of the physical security system: hardware, personnel, and operational and maintenance procedures. This report contains information for the Nuclear Regulatory Commission (NRC) and for the licensees of nuclear power reactors who carry out these comprehensive audits. Guidance on the overall management of the audit function includes organizational structure and issues concerning the auditors who perform the review: qualifications, independence, due professional care, and standards. Guidance in the audit program includes purpose and scope of the audit, planning, techniques, post-audit procedures, reporting, and follow-up

46 CFR 115.630 - The Alternative Hull Examination (AHE) Program application.

Science.gov (United States)

2010-10-01

... 46 Shipping 4 2010-10-01 2010-10-01 false The Alternative Hull Examination (AHE) Program... PASSENGERS INSPECTION AND CERTIFICATION Hull and Tailshaft Examinations § 115.630 The Alternative Hull... hull examination date to the Officer in Charge, Marine Inspection (OCMI) who will oversee the survey...

Post-irradiation examination and R and D programs using irradiated fuels at KAERI

International Nuclear Information System (INIS)

Chun, Yong Bum; Min, Duck Kee; Kim, Eun Ka and others

2000-12-01

This report describes the Post-Irradiation Examination(PIE) and R and D programs using irradiated fuels at KAERI. The objectives of post-irradiation examination (PIE) for the PWR irradiated fuels, CANDU fuels, HANARO fuels and test fuel materials are to verify the irradiation performance and their integrity as well as to construct a fuel performance data base. The comprehensive utilization program of the KAERI's post-irradiation examination related nuclear facilities such as Post-Irradiation Examination Facility (PIEF), Irradiated Materials Examination Facility (IMEF) and HANARO is described

Post-irradiation examination and R and D programs using irradiated fuels at KAERI

International Nuclear Information System (INIS)

Chun, Yong Bum; So, Dong Sup; Lee, Byung Doo; Lee, Song Ho; Min, Duck Kee

2001-09-01

This report describes the Post-Irradiation Examination(PIE) and R and D programs using irradiated fuels at KAERI. The objectives of post-irradiation examination (PIE) for the PWR irradiated fuels, CANDU fuels, HANARO fuels and test fuel materials are to verify the irradiation performance and their integrity as well as to construct a fuel performance data base. The comprehensive utilization program of the KAERI's post-irradiation examination related nuclear facilities such as Post-Irradiation Examination Facility (PIEF), Irradiated Materials Examination Facility (IMEF) and HANARO is described

Operating experience review for nuclear power plants in the Systematic Evaluation Program

International Nuclear Information System (INIS)

Mays, G.T.; Harrington, K.H.

1982-01-01

The Systematic Evaluation Program Branch (SEPB) of the Nuclear Regulatory Commission (NRC) is conducting the Systematic Evaluation Program (SEP) whose purpose is to determine the safety margins of the design and operation of the eleven oldest operating commercial nuclear power plants in the United States. This paper describes the methodology and results of the operational experience review portion of the SEP evaluation. SEPB will combine the results from these operational reviews with other safety topic evaluations to perform an integrated assessment of the SEP plants

The examination of Hevea brasiliensis plants produced by in vitro culture and mutagenesis by DNA fingerprinting techniques

International Nuclear Information System (INIS)

Low, F.C.; Atan, S.; Jaafar, H.

1998-01-01

Rubber (Hevea brasiliensis) plants derived from anther and ovule culture as well as gamma-irradiated plants were examined by several DNA marker techniques. These include restriction fragment length polymorphisms (RFLPs), random amplified polymorphic DNA (RAPD), sequence tagged microsatellite sites (STMS), DNA amplification fingerprinting (DAF) and amplified fragment length polymorphisms (AFLPs). Compared to control plants produced by vegetative propagation (cutting and budding), plants produced by in vitro culture appeared to have a reduction in the number of rDNA loci. Two RAPD protocols were compared and found to be similar in amplification of the major DNA bands. After confirmation that the RAPD method adopted was reproducible, the technique was applied to the present studies. Eight out of the 60 primers screened were able to elicit polymorphisms between pooled DNA from in vitro culture plants. Variations in DNA patterns were observed between pooled DNA samples of anther-derived plants as well as between anther-derived and ovule-derived plants. Comparisons of RAPD patterns obtained between anther-derived plants exposed to increasing dosages of gamma-irradiation with non irradiated anther-derived plants revealed distinct DNA polymorphisms. The changes in DNA profiles did not appear to be correlated to the dosage of irradiation. Since somaclonal variation was detected, it was difficult to identify changes which were specifically caused by irradiation. Application of the STMS technique to tag micro satellite sequences (GA) n , (TA) n and (TTA) n in the hydroxymethylglutaryl coenzyme A reductase-1 (hmgr-1) gene failed to detect differences between plants derived from anther and ovule culture. Although restriction endonuclease digestions with methylation sensitive enzymes suggested that four in vitro culture plants examined exhibited similar digestion patterns as the controls, a change in cytosine methylation in one anther-derived plant was detected. Examination of

Air sampling program at the Portsmouth Gaseous Diffusion Plant

International Nuclear Information System (INIS)

Hulett, S.H.

1975-01-01

An extensive air sampling program has been developed at the Portsmouth Gaseous Diffusion Plant for monitoring the concentrations of radioactive aerosols present in the atmosphere on plantsite as well as in the environs. The program is designed to minimize exposures of employees and the environment to airborne radioactive particulates. Five different air sampling systems, utilizing either filtration or impaction, are employed for measuring airborne alpha and beta-gamma activity produced from 235 U and 234 Th, respectively. Two of the systems have particle selection capabilities: a personal sampler with a 10-mm nylon cyclone eliminates most particles larger than about 10 microns in diameter; and an Annular Kinetic Impactor collects particulates greater than 0.4 microns in diameter which have a density greater than 12-15 gm/cm 3 . A Hi-Volume Air Sampler and an Eberline Model AIM-3 Scintillation Air Monitor are used in collecting short-term samples for assessing compliance with ''ceiling'' standards or peak concentration limits. A film-sort aperture IBM card system is utilized for continuous 8-hour samples. This sampling program has proven to be both practical and effective for assuring accurate monitoring of the airborne activity associated with plant operations

TMI-2 accident evaluation program sample acquisition and examination plan. Executive summary

International Nuclear Information System (INIS)

Russell, M.L.; McCardell, R.K.; Broughton, J.M.

1985-12-01

The purpose of the TMI-2 Accident Evaluation Program Sample Acquisition and Examination (TMI-2 AEP SA and E) program is to develop and implement a test and inspection plan that completes the current-condition characterization of (a) the TMI-2 equipment that may have been damaged by the core damage events and (b) the TMI-2 core fission product inventory. The characterization program includes both sample acquisitions and examinations and in-situ measurements. Fission product characterization involves locating the fission products as well as determining their chemical form and determining material association

European passive plant program preliminary safety analyses to support system design

International Nuclear Information System (INIS)

Saiu, Gianfranco; Barucca, Luciana; King, K.J.

1999-01-01

In 1994, a group of European Utilities, together with Westinghouse and its Industrial Partner GENESI (an Italian consortium including ANSALDO and FIAT), initiated a program designated EPP (European Passive Plant) to evaluate Westinghouse Passive Nuclear Plant Technology for application in Europe. In the Phase 1 of the European Passive Plant Program which was completed in 1996, a 1000 MWe passive plant reference design (EP1000) was established which conforms to the European Utility Requirements (EUR) and is expected to meet the European Safety Authorities requirements. Phase 2 of the program was initiated in 1997 with the objective of developing the Nuclear Island design details and performing supporting analyses to start development of Safety Case Report (SCR) for submittal to European Licensing Authorities. The first part of Phase 2, 'Design Definition' phase (Phase 2A) was completed at the end of 1998, the main efforts being design definition of key systems and structures, development of the Nuclear Island layout, and performing preliminary safety analyses to support design efforts. Incorporation of the EUR has been a key design requirement for the EP1000 form the beginning of the program. Detailed design solutions to meet the EUR have been defined and the safety approach has also been developed based on the EUR guidelines. The present paper describes the EP1000 approach to safety analysis and, in particular, to the Design Extension Conditions that, according to the EUR, represent the preferred method for giving consideration to the Complex Sequences and Severe Accidents at the design stage without including them in the design bases conditions. Preliminary results of some DEC analyses and an overview of the probabilistic safety assessment (PSA) are also presented. (author)

46 CFR 115.650 - Alternative Hull Examination (AHE) Program options: Divers or underwater ROV.

Science.gov (United States)

2010-10-01

... 46 Shipping 4 2010-10-01 2010-10-01 false Alternative Hull Examination (AHE) Program options... MORE THAN 49 PASSENGERS INSPECTION AND CERTIFICATION Hull and Tailshaft Examinations § 115.650 Alternative Hull Examination (AHE) Program options: Divers or underwater ROV. To complete your underwater...

Japan's international cooperation programs on seismic safety of nuclear power plants

International Nuclear Information System (INIS)

Sanada, Akira

1997-01-01

MITI is promoting many international cooperation programs on nuclear safety area. The seismic safety of nuclear power plants (NPPs) is a one of most important cooperation areas. Experts from MITI and related organization join the multilateral cooperation programs carried out by international organization such as IAEA, OECD/NEA etc. MITI is also promoting bilateral cooperation programs such as information exchange meetings, training programs and seminars on nuclear safety with several countries. Concerning to the cooperation programs on seismic safety of NPPs such as information exchange and training, MITI shall continue and expand these programs. (J.P.N.)

The computer program system for structural design of nuclear power plants

International Nuclear Information System (INIS)

Aihara, S.; Atsumi, K.; Sasagawa, K.; Satoh, S.

1979-01-01

In recent days, the design method of the Nuclear Power Plant has become more complex than in the past. The Finite Element Method (FEM) applied for analysis of Nuclear Power Plants, especially requires more computer use. The recent computers have made remarkable progress, so that in design work manpower and time necessary for analysis have been reduced considerably. However, instead the arrangement of outputs have increased tremendously. Therefore, a computer program system was developed for performing all of the processes, from data making to output arrangement, and rebar evaluations. This report introduces the computer program system pertaining to the design flow of the Reactor Building. (orig.)

Round Robin Test for Performance Demonstration System of Ultrasound Examination Personnel in Nuclear Power Plants

International Nuclear Information System (INIS)

Kim, Young Ho; Yang, Seung Han; Kim, Yong Sik; Yoon, Byung Sik; Lee, Hee Jong

2005-01-01

Ultrasound testing performance during in-service inspection for the main components of NPPs is strongly affected by each examination person. Therefore, ASME established a more strict qualification requirement in Sec. XI Appendix VIII for the ultrasound testing personnel in nuclear power plants. The Korean Performance Demonstration (KPD) System according to the ASME code for the ultrasonic testing personnel, equipments, and procedures to apply to the Class 1 and 2 piping ultrasound examination of nuclear power plants in Korea was established. And a round robin test was conducted in order to verify the effectiveness of PD method by comparing the examination results from the method of Performance Demonstration (PD) and a traditional ASME code dB-drop method. The round robin test shows that the reliability of the PD method is better than that of the dB-drop method. As a result, application of the PD method to the in-service inspection of the nuclear power plants will improve the performance of ultrasound testing

Next Generation Nuclear Plant Materials Research and Development Program Plan

International Nuclear Information System (INIS)

G.O. Hayner; R.L. Bratton; R.N. Wright

2005-01-01

The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Project is envisioned to demonstrate the following: (1) A full-scale prototype VHTR by about 2021; (2) High-temperature Brayton Cycle electric power production at full scale with a focus on economic performance; (3) Nuclear-assisted production of hydrogen (with about 10% of the heat) with a focus on economic performance; and (4) By test, the exceptional safety capabilities of the advanced gas-cooled reactors. Further, the NGNP program will: (1) Obtain a Nuclear Regulatory Commission (NRC) License to construct and operate the NGNP, this process will provide a basis for future performance based, risk-informed licensing; and (2) Support the development, testing, and prototyping of hydrogen infrastructures. The NGNP Materials Research and Development (R and D) Program is responsible for performing R and D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. The NGNP Materials R and D Program includes the following elements: (1) Developing a specific approach, program plan and other project management

Quality Assurance Program Plan for the Waste Isolation Pilot Plant Experimental-Waste Characterization Program

International Nuclear Information System (INIS)

1991-01-01

This Quality Assurance Program Plan (QAPP) identifies the quality of data necessary to meet the specific objectives associated with the Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Experimental-Waste Characterization Program (the Program). DOE plans to conduct experiments in the WIPP during a Test Phase of approximately 5 years. These experiments will be conducted to reduce the uncertainties associated with the prediction of several processes (e.g., gas generation) that may influence repository performance. The results of the experiments will be used to assess the ability of the WIPP to meet regulatory requirements for the long-term protection of human health and the environment from the disposal of TRU wastes. 37 refs., 25 figs., 18 tabs

Perry Nuclear Power Plant Area/Equipment Temperature Monitoring Program

International Nuclear Information System (INIS)

McGuire, L.L.

1991-01-01

The Perry Nuclear Power Plant Area/Equipment Temperature Monitoring Program serves two purposes. The first is to track temperature trends during normal plant operation in areas where suspected deviations from established environmental profiles exist. This includes the use of Resistance Temperature Detectors, Recorders, and Temperature Dots for evaluation of equipment qualified life for comparison with tested parameters and the established Environmental Design Profile. It also may be used to determine the location and duration of steam leaks for effect on equipment qualified life. The second purpose of this program is to aid HVAC design engineers in determining the source of heat outside anticipated design parameters. Resistance Temperature Detectors, Recorders, and Temperature Dots are also used for this application but the results may include design changes to eliminate the excess heat or provide qualified equipment (cable) to withstand the elevated temperature, splitting of environmental zones to capture accurate temperature parameters, or continued environmental monitoring for evaluation of equipment located in hot spots

CHIT: a cost accounting program for postirradiation examinations of fast breeder reactor materials

International Nuclear Information System (INIS)

Phillips, J.R.; Dowler, K.E.

1975-09-01

CHIT is the Los Alamos Scientific Laboratory's cost accounting computer program for nondestructive and destructive examinations of irradiated fuel pins. The program allows immediate retrieval of fuel pin examination information and provides itemized listings for completed and projected fuel pin examinations, detailed cost accounting summaries for each investigator, fuel pin examinations during a specified time interval, and various subsets of the information. CHIT has been in successful operation for the past two years, providing precise information on cost accounting more efficiently than possible with a manual technique

Status of Pantex Plant Waste Management Project/program control system

International Nuclear Information System (INIS)

Price, Wesley J.; Matthews, William L.

1992-01-01

During a December 1990 Waste Management Program Review held in Albuquerque, New Mexico, the Waste Management and Operational Surety Division (WMOSD) introduced the project control system to be used for the Waste Management (WM) Operations Program. The system was entitled 'TRAC-WM' (Tracking and Control for Waste Management). The stated objective for this system was to establish a frame work for planning, managing, and controlling work within the WM program. As a result Mason and Hanger (the operating contractor at the Pantex Plant) initiated the development of a computerized waste management project tracking system. (author)

Application of plant life management program and experience at NRU

International Nuclear Information System (INIS)

Nickerson, J.; Dam, R.; Arnold, J.; See Hoye, D.

2004-01-01

The National Research Universal (NRU) reactor has seen extensive and excellent service since going into operation in 1957. During that time, significant investments in upgrading and improving the facility have been implemented. Recently, as part of the NRU Licenseability Extension (LE) program, AECL has developed a Plant Life Management (PLiM) program to support planned operation to at least 2012. The objective of the PLiM program is to systematically assess the various aging related degradation mechanisms in order to evaluate both current condition and the potential for further extending service life. Another objective is to identify the associated maintenance, surveillance and inspection strategy for service life extension of important Structures, Systems, and Components (SSCs). The strategy uses approaches that build on AECL's PLiM/PLEx experience at CANDU plants, but also utilizes previous Age Management and refurbishment work performed at NRU. The program is multi-faceted, systematic and integrated, and involves the facility operations organization in the assessment process. The PLiM program has used a number of pilot studies in the initial stages to test out PLiM procedures, gain experience with the various aging assessment techniques and enhance effectiveness of interfaces between the aging assessment team and the facility staff. The aging assessment process begins with the screening and prioritization of the facility SSCs. Selection of the appropriate assessment technique is based on priority and component type. Life and condition assessment techniques used at other plants have been adapted to NRU and performed on important components and structures. For important systems, a combination of condition assessment and systematic maintenance assessment techniques are being used. Detailed PLiM procedures have been developed and are in trial use in pilot studies. These procedures are currently being updated with the experience gained during the pilot studies. In

Next Generation Nuclear Plant Methods Technical Program Plan

Energy Technology Data Exchange (ETDEWEB)

Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

2010-12-01

One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the “highly ranked” phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

Quality control during construction of power plants

International Nuclear Information System (INIS)

Hartstern, R.F.

1982-01-01

This paper traces the background and examines the necessity for a program to control quality during the construction phase of a power plant. It also attempts to point out considerations for making these programs cost effective

Relationship Between Physician Assistant Program Length and Physician Assistant National Certifying Examination Pass Rates.

Science.gov (United States)

Colletti, Thomas P; Salisbury, Helen; Hertelendy, Attila J; Tseng, Tina

2016-03-01

This study was conducted to examine the relationship between physician assistant (PA) educational program length and PA programs' 5-year average Physician Assistant National Certifying Examination (PANCE) first-time pass rates. This was a retrospective correlational study that analyzed previously collected data from a nonprobability purposive sample of accredited PA program Web sites. Master's level PA programs (n = 108) in the United States with published average PANCE scores for 5 consecutive classes were included. Provisional and probationary programs were excluded (n = 4). Study data were not normally distributed per the Kolmogorov-Smirnov test, P = .00. There was no relationship between program length and PANCE pass rates, ρ (108) = -0.04, P = .68. Further analyses examining a possible relationship between program phase length (didactic and clinical) and PANCE pass rates also demonstrated no differences (ρ [107] = -0.05, P = .60 and ρ [107] = 0.02, P = .80, respectively). The results of this study suggest that shorter length PA programs perform similarly to longer programs in preparing students to pass the PANCE. In light of rapid expansion of PA educational programs, educators may want to consider these findings when planning the length of study for new and established programs.

An overview of the US Department of Energy Plant Lifetime Improvement Program

International Nuclear Information System (INIS)

Moonka, A.K.; Harrison, D.L.

1995-01-01

This paper provides a brief summary of the U.S. Department of Energy's (USDOE's) cooperative effort with the nuclear industry to develop technology to manage the effects of material degradation in systems, structures and components (SSCs) that impact plant safety or can significantly improve plant performance/economics and to establish and demonstrate the license renewal process. Also included are efforts to reduce decontamination/decommission costs, and reduce the uncertainty in long-term service-life decision making. During 1995, the Plant Lifetime Improvement (PLIM) Program was renamed the Commercial Operating Light Water Reactor (COLWR) Program activities are focused on sustaining the LWR option for domestic electricity generation by supporting operation of existing LWRs as long as they are safe, efficient, and economical. The status of the key projects is discussed in this paper

Promoting excellence in nuclear power plant training in the United States

International Nuclear Information System (INIS)

Mangin, A.M.

1983-01-01

The Institute of Nuclear Power Operations (INPO) was formed in late 1979 by U.S. nuclear utilities to enhance the operational safety and reliability of their nuclear plants. One of INPO's major functions is to promote excellence in industry training and qualification programs. To accomplish this objective, INPO develops and uses guidelines and evaluation criteria to assist utilities in developing and implementing high quality training and education programs. The training guidelines permit utilities to develop performance-based programs which meet their specific need with minimal duplication of effort. INPO regularly evaluates each utility's training programs and practices in the plant evaluation and accreditation processes using criteria based on the training guidelines. In the accreditation process, INPO examines training programs and training organizations to determine whether they have the potential to produce individuals qualified to perform assigned tasks. During plant evaluations, INPO examines the implementation of the programs and their effectiveness in producing qualified individuals. After each accreditation review and plant evaluation, INPO recommends improvements and follows up to ensure they are made. (author)

Results from the Nuclear Plant Aging Research Program: Their use in inspection activities

International Nuclear Information System (INIS)

Gunther, W.; Taylor, J.

1990-09-01

The US NCR's Nuclear Plant Aging Research (NPAR) Program has determined the susceptibility to aging of components and systems, and the potential for aging to impact plant safety and availability. The NPAR Program also identified methods for detecting and mitigating aging in components. This report describes the NPAR results which can enhance NRC inspection activities. Recommendations are provided for communicating pertinent information to NRC inspectors. These recommendations are based on a detailed assessment of the NRC's Inspection Program, and feedback from resident and regional inspectors as described within. Examples of NPAR report summaries and aging inspection guides for components and systems are included. 13 refs., 3 figs., 4 tabs

Portsmouth Gaseous Diffusion Plant Decontamination and Decommissioning Program surveillance and maintenance plan, FY 1993--2002

International Nuclear Information System (INIS)

Schloesslin, W.

1992-11-01

The Decontamination and Decommissioning (D ampersand D) Program at the Portsmouth Gaseous Diffusion Plant (PORTS) is part of the Environmental Restoration (ER) and Waste Management (WM) Programs (ERWM). The objective of the ER Program is to provide PORTS the capability to meet applicable environmental regulations through facility development activities and site remedial actions. The WM Program supports the ER Program. The D ampersand D Program provides collective management of the sites within the plant which require decontamination and decommissioning, prioritizes those areas in terms of health, safety and environmental concerns, and implements the appropriate level of remedial action. The D ampersand D Program provides support to facilities which formerly served one or more of the many Plant functions. Program activities include (1) surveillance and maintenance of facilities awaiting decommissioning; (2) planning safe and orderly facility decommissioning; and (3) implementing a program to accomplish facility disposition in a safe, cost effective, and timely manner. In order to achieve the first objective, a formal plan which documents the surveillance and maintenance needs for each inactive facility has been prepared. This report provides this documentation for the PORTS facilities currently included in the D ampersand D Program and includes projected resource requirements for the planning period of FY 1993 through FY 2002

Ageing management program of wires for Atucha II Nuclear Power Plant

International Nuclear Information System (INIS)

Zorrilla, J.; Antonaccio, E.; Luraschi, C.; Simionato, E.; Nieto, H.

2012-01-01

Electrical cables constitute one of the most important components of NPP in terms o maintenance, safety and availability of the plant. Due to their large extension (thousands of kilometers) it is impossible to fully replace them and aging management becomes essential for long term operation of NPP. Since Atucha II is under construction there was a good opportunity to establish and implement a holistic cable aging management program from the beginning according to the state of the art in this field. The scope of this program involves safety related cables, including EQ cables and non EQ cables as well. Due to the diversity of the installed cables is impossible to address an aging management program of every single specimen. However it is possible to establish 'cables families' of similar aging behavior based on insulation and jacket material, manufacture, etc Several aging management strategies were set for the different 'cables families'. These strategies include cables deposit in plant, elaboration of procedures of visual and tactile inspection, NDE techniques, etc Currently the aging management program is being implemented covering topic such as: Cable screening and grouping. Review of EQ documentation and conventional qualification information referring to the installed cables. Establishment of base line of condition monitoring techniques. Calibration and set up of test parameters for NDE techniques. Aging mechanism characterization and determination of. Design construction and installation of cable deposit in plant (author)

College and university programs for meeting the needs of educating nuclear power plant personnel

International Nuclear Information System (INIS)

Hajek, B.K.; Miller, D.W.; De Vuono, A.C.

1981-01-01

ANS, INPO, and NRC are considering various recommendations for university courses to be required for all nuclear power plant licensed personnel. This paper discusses these recommendations and compares them with the content and constraints of traditional university academic programs. One solution being pursued by utilities in Ohio is discussed. In this program, courses are being obtained from several different educational institutions for presentation at the power plant site. The program provides sufficient flexibility so that decisions on specific degree options do not have to be made at this time

An international comparison of nuclear plant training programs

International Nuclear Information System (INIS)

Mason, J.H.

1993-01-01

In 1990, I visited four utility companies that own and operate pressurized water reactor (PWR) plants in different countries. The purpose of my visits and associated research was to compare nuclear power plant operator and technician training programs. The companies were: Duke Power Company (DUKE) in the United States, Electricite de France (EDF) in France, Kansai Electric Power Company (KEPCO) in Japan, and RWE Energie AG (RWE) in Germany. The purpose of this paper is to highlight selected aspects of the comparison. First, comparisons of the four subject utilities and four typical nuclear power stations operated by each company, McGuire, Paluel, Ohi, and Biblis, are provided. Then comparisons of new employee demographics and training program specific content are provided. Finally, some general observations are drawn from the comparisons. The comparisons are based on information obtained from documents, interviews, and visits to stations and training centers. However, some interpretation of the information was necessary in order to enable a comparison. For example, categorization of training modules requires judgement, interpretation, and translation. In all cases, the information is intended to be representative or typical, rather than statistically precise

An augmented audit program for assuring radiation safety during radiographic examination operations

International Nuclear Information System (INIS)

Jervey, R.A. Jr.; Papin, P.J.

1993-01-01

Auditing a gamma radiography program is required as part of the authorizing license. Checklists and cursory reviews are the typical approach to addressing program requirements. A more proactive approach is recommended. The audit program described was prepared for a specific set of operating conditions but can be applied to any given program. Improvements in the effectiveness of the radiography safety program can be made with additional examination and emphasis on direct observation of licensed activities

Next Generation Nuclear Plant Research and Development Program Plan

Energy Technology Data Exchange (ETDEWEB)

P. E. MacDonald

2005-01-01

The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission Demonstrate safe and economical nuclearassisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: High temperature gas reactor fuels behavior High temperature materials qualification Design methods development and validation Hydrogen production technologies Energy conversion. The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented in Section 4. The DOE-funded hydrogen

Next Generation Nuclear Plant Research and Development Program Plan

Energy Technology Data Exchange (ETDEWEB)

None

2005-01-01

The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: (1) Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission (2) Demonstrate safe and economical nuclear-assisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: (1) High temperature gas reactor fuels behavior; (2) High temperature materials qualification; (3) Design methods development and validation; (4) Hydrogen production technologies; and (5) Energy conversion. The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented

Reduced program of inspection by induced currents for condenser of Embalse nuclear power plant

International Nuclear Information System (INIS)

Obrutsky, L.; Mendonca, H.

1986-01-01

In this work it's presented a reduced inspection in service program by the technique of induced currents to the turbine condenser of Embalse's Power Plant (Cordoba). The authors based its elaboration on the results obtained in the exam of a small number of tubes and on experience obtained through four inspections in the condensers of Atucha I Power Plant, through mathematical models of oxygen and ammoniac distribution in both Power Plants, and its experimental verification in the case of Atucha I. This program improves the quality of inspection thereby reducing time, equipment and personnel employed. (C.M.) [pt

Examining the Influence of Campus Leadership Programs at a Catholic University

Science.gov (United States)

Whitney, Rich; Meents-DeCaigny, Ellen

2014-01-01

This study uses the socially responsible leadership and leadership efficacy scales in the Multi-Institutional Study of Leadership (MSL) to examine leadership programs at one Catholic campus, and their influence on socially responsible leadership and leadership efficacy. Examining students that identified as involved in 14 campus leadership…

DCD – a novel plant specific domain in proteins involved in development and programmed cell death

Directory of Open Access Journals (Sweden)

Doerks Tobias

2005-07-01

Full Text Available Abstract Background Recognition of microbial pathogens by plants triggers the hypersensitive reaction, a common form of programmed cell death in plants. These dying cells generate signals that activate the plant immune system and alarm the neighboring cells as well as the whole plant to activate defense responses to limit the spread of the pathogen. The molecular mechanisms behind the hypersensitive reaction are largely unknown except for the recognition process of pathogens. We delineate the NRP-gene in soybean, which is specifically induced during this programmed cell death and contains a novel protein domain, which is commonly found in different plant proteins. Results The sequence analysis of the protein, encoded by the NRP-gene from soybean, led to the identification of a novel domain, which we named DCD, because it is found in plant proteins involved in development and cell death. The domain is shared by several proteins in the Arabidopsis and the rice genomes, which otherwise show a different protein architecture. Biological studies indicate a role of these proteins in phytohormone response, embryo development and programmed cell by pathogens or ozone. Conclusion It is tempting to speculate, that the DCD domain mediates signaling in plant development and programmed cell death and could thus be used to identify interacting proteins to gain further molecular insights into these processes.

Brunswick improvement program

International Nuclear Information System (INIS)

Howe, P.W.

1985-01-01

The performance of the twin 790-MW Mark-4 boiling water reactors located at the Brunswick steam electric plant has historically been well below average. The plant experienced low availability, low capacity factors, high US Nuclear Regulatory Commission (NRC) violations, excessive radioactive waste generation, excessive licensee event reports (LERs), an unacceptable industrial safety record, poor SALP ratings, and numerous other deficiencies leading to unacceptable performance. In June 1982 it was determined that certain periodic tests (PT) had never been performed. While one unit was down for a refueling/modification outage, Carolina Power and Light (CP and L) elected to bring the other unit off line and perform an extensive self-examination. As a result, a number of needed improvements covering a wide range of plant activities were identified. CP and L elected to consolidate all the elements of the improvement into a single, plant-wide program. The consolidated program, called the Brunswick Improvement Program (BIP), was established. Major objectives of the BIP and measurable results are presented

Insights from the U.S. department of Energy plant safety evaluation program of VVER and RBMK reactors

International Nuclear Information System (INIS)

Petri, M.C.; Binder, J.L.; Pasedag, W.F.

2001-01-01

Throughout the years 1990 the U.S. Department of Energy has worked build capability in countries of the former Soviet Union to assess the safety of their VVER and RBMK reactors. Through this Plant Safety Evaluation Program, deterministic and probabilistic analyses have been used to provide a documented plant risk profile to support safe plant operation and to set priorities for safety upgrades. Work has been sponsored at thirteen nuclear power plant sites in eight countries. The Plant Safety Evaluation Program has resulted in immediate and long-term safety benefits for the Soviet-designed nuclear plants. (author)

DSNP, Program and Data Library System for Dynamic Simulation of Nuclear Power Plant

International Nuclear Information System (INIS)

Saphier, D.; Madell, J.; Dean, E.

1988-01-01

1 - Description of problem or function: DSNP (Dynamic Simulator for Nuclear Power-Plants) is a system of programs and data files by which a nuclear power plant, or part thereof, can be simulated. The acronym DSNP is used interchangeably for the DSNP language, the DSNP libraries, the DSNP pre-compiler, and the DSNP document generator. The DSNP language is a special-purpose, block-oriented digital- simulation language developed to facilitate the preparation of dynamic simulations of a large variety of nuclear power plants. It is a user-oriented language that permits the user to prepare simulation programs directly from power plant block diagrams and flow charts by recognizing the symbolic DSNP statements for the appropriate physical components and listing these statements in a logical sequence according to the flow of physical properties in the simulated power plant. Physical components of nuclear power plants are represented by functional blocks, or modules. Many of the more complex components are represented by several modules. The nuclear reactor, for example, has a kinetic module, a power distribution module, a feedback module, a thermodynamic module, a hydraulic module, and a radioactive heat decay module. These modules are stored in DSNP libraries in the form of a DSNP subroutine or function, a block of statements, a macro, or a combination of the above. Basic functional blocks such as integrators, pipes, function generators, connectors, and many auxiliary functions representing properties of materials used in nuclear power plants are also available. The DSNP pre-compiler analyzes the DSNP simulation program, performs the appropriate translations, inserts the requested modules from the library, links these modules together, searches necessary data files, and produces a simulation program in FORTRAN. FORTRAN is considered to be a subset of DSNP and can be inserted anywhere in the simulation program without restriction. I/O statements can be located anywhere in

Results from the Nuclear Plant Aging Research Program: Their use in inspection activities

Energy Technology Data Exchange (ETDEWEB)

Gunther, W.; Taylor, J. (Brookhaven National Lab., Upton, NY (USA))

1990-09-01

The US NCR's Nuclear Plant Aging Research (NPAR) Program has determined the susceptibility to aging of components and systems, and the potential for aging to impact plant safety and availability. The NPAR Program also identified methods for detecting and mitigating aging in components. This report describes the NPAR results which can enhance NRC inspection activities. Recommendations are provided for communicating pertinent information to NRC inspectors. These recommendations are based on a detailed assessment of the NRC's Inspection Program, and feedback from resident and regional inspectors as described within. Examples of NPAR report summaries and aging inspection guides for components and systems are included. 13 refs., 3 figs., 4 tabs.

Examination of the program to avoid round-off error

International Nuclear Information System (INIS)

Shiota, Y.; Kusunoki, T.; Tabushi, K.; Shimomura, K.; Kitou, S.

2005-01-01

The MACRO programs which express a simple shape such as PLANE, SPHERE, CYLINDER and CONE, are used to the formation of the geometry in EGS4. Each MACRO calculates the important value for the main code to recognize the configured geometry. This calculation process may generate the calculation error due to the effect of a round-off error. SPHERE, CYLINDER and CONE MACRO include the function to avoid the effect, but PLANE MACRO dose not include. The effect of the round-off error is small usually in case of PLANE MACRO, however a slant plane may cause the expansion of the effect. Therefore, we have configured the DELPLANE program with the function to avoid the effect of the round-off error. In this study, we examine the DELPLANE program using the simply geometry with slant plane. As a result, the normal PLANE MACRO generates the round-off error, however DELPLANE program dose not generates one. (author)

Regulatory approach of the monitoring the effectiveness of maintenance at nuclear power plants program

International Nuclear Information System (INIS)

Vajgel, Stefan

2009-03-01

The electrical power generation using nuclear power plants requires this installation being safety, reliable and available for the working periods. For this purpose, an adequate, effective and well conducted maintenance program makes an essential and useful tool to the owner of the plant. However, it is necessary to follow the regulatory requirements for this program implementation which monitories this maintenance effectiveness. There are Brazilian norms requirements which must be followed. The international regulatory guides establish these requirements in good details but it is necessary to verify if this methodology for implementing can be totally applied here in Brazil. Then, the american guide NUMARC 93-01 which details how can be implemented a program for this monitoring, shows some methods for using. In this thesis, the Delphi and Probabilistic Safety Analysis were briefly included because they were preferred for implementing this monitoring.in a Brazilian plant. The results which are being obtained show that, looking the regulatory aspects, the NUMARC 93-01 follows our regulations and gives good results for the plant management. (author)

Results of technical and economical examinations for substantiation of special plant design for reprocessing and radioactive wastes disposal

International Nuclear Information System (INIS)

Galkin, A.V.; Baldov, A.N.

2001-01-01

In the paper the results of technical and economical examinations for substantiation of special plant design for reprocessing and radioactive wastes disposal are presented. Ground for the examination conducting was Health of Nation Programme ratified by the President and a number of Governmental decisions. The special plant is planned in the Mangystau Region. In the framework of feasibility study the data base by the worldwide known technologies was implemented, on reprocessing and experience of radioactive waste disposal. The technical requirements for the special plant construction are determined. The alternative options by structure content and site location of the special plant and radioactive waste disposal are cited

Meteorological monitoring Program in the location to the Juragua Nuclear Power Plant

International Nuclear Information System (INIS)

Linares Gonzalez, M.E.; Ramos Biltres, E.O.; Prendes Alonso, M.

1998-01-01

The objective gives the work it is to present the meteorological Monitoring program in the Juragua nuclear power plant, which you makes according to the standards settled down by the OIEA, the standards give the World meteorological organization and the demands to the content and elaboration gives the Nuclear Power Plant security documents DTN-1.03.91

Japan`s international cooperation programs on seismic safety of nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Sanada, Akira [Agency of Natural Resources and Energy, Tokyo (Japan)

1997-03-01

MITI is promoting many international cooperation programs on nuclear safety area. The seismic safety of nuclear power plants (NPPs) is a one of most important cooperation areas. Experts from MITI and related organization join the multilateral cooperation programs carried out by international organization such as IAEA, OECD/NEA etc. MITI is also promoting bilateral cooperation programs such as information exchange meetings, training programs and seminars on nuclear safety with several countries. Concerning to the cooperation programs on seismic safety of NPPs such as information exchange and training, MITI shall continue and expand these programs. (J.P.N.)

ROS-mediated abiotic stress-induced programmed cell death in plants

Directory of Open Access Journals (Sweden)

Veselin ePetrov

2015-02-01

Full Text Available During the course of their ontogenesis, plants are continuously exposed to a large variety of abiotic stress factors which can damage tissues and jeopardize the survival of the organism unless properly countered. While animals can simply escape and thus evade stressors, plants as sessile organisms have developed complex strategies to withstand them. When the intensity of a detrimental factor is high, one of the defense programs employed by plants is the induction of programmed cell death (PCD. This is an active, genetically controlled process which is initiated to isolate and remove damaged tissues thereby ensuring the survival of the organism. The mechanism of PCD induction usually includes an increase in the levels of reactive oxygen species (ROS which are utilized as mediators of the stress signal. Abiotic stress-induced PCD is not only a process of fundamental biological importance, but also of considerable interest to agricultural practice as it has the potential to significantly influence crop yield. Therefore, numerous scientific enterprises have focused on elucidating the mechanisms leading to and controlling PCD in response to adverse conditions in plants. This knowledge may help to develop novel strategies to obtain more resilient crop varieties with improved tolerance and enhanced productivity. The aim of the present review is to summarize the recent advances in research on ROS-induced PCD related to abiotic stress and the role of the organelles in the process.

Survey of radionuclide emissions from coal-fired power plants and examination of impacts from a proposed circulating fluidized bed boiler power plant

International Nuclear Information System (INIS)

Steiner, C.P.; Militana, L.M.; Harvey, K.A.; Kinsey, G.D.

1995-01-01

This paper presents the results of a literature survey that examined radionuclide emissions from coal-fired power plants. Literature references from both the US and foreign countries are presented. Emphasis is placed on references from the US because the radionuclide emissions from coal-fired power plants are related to radionuclide concentrations in the coal, which vary widely throughout the world. The radionuclides were identified and quantified for various existing power plants reported in the literature. Applicable radionuclide emissions criteria discovered in the literature search were then applied to a proposed circulating fluidized bed boiler power plant. Based upon the derived radionuclide emission rates applied to the proposed power plant, an air quality modeling analysis was performed. The estimated ambient concentrations were compared to the most relevant existing regulatory ambient levels for radionuclides

Utilization of aging program results in plant inspections

International Nuclear Information System (INIS)

Gunther, W.; Fullwood, R.

1989-01-01

Research conducted under the auspices of the US Nuclear Regulatory Commission Nuclear Plant Aging Research (NPAR) Program has resulted in a large data base of component and system operating experience. This data base has been used to determine equipment aging susceptibility and the potential for equipment aging to impact plant safety and reliability. Methods of detecting and mitigating component and system aging have also been identified. This paper discusses how the NPAR results could be used to focus inspection activities on age-sensitive components and systems and on the specific modes and mechanisms of age degradation. These activities range from the regular inspections conducted by resident inspectors to extensive special inspections such as the Safety System Functional Inspection typically conducted by a team of inspectors. 5 refs., 3 figs., 1 tab

Utilization of aging program results in plant inspections

International Nuclear Information System (INIS)

Gunther, W.; Fullwood, R.

1988-01-01

Research conducted under the auspices of the US Nuclear Regulatory Commission Nuclear Plant Aging Research (NPAR) Program has resulted in a large data base of component and system operating experience. This data base has been used to determine equipment aging susceptibility and the potential for equipment aging to impact plant safety and reliability. Methods of detecting and mitigating component and system aging have also been identified. This paper discusses how the NPAR results could be used to focus inspection activities on age-sensitive components and systems and on the specific modes and mechanisms of age degradation. These activities range from the regular inspections conducted by resident inspectors to extensive special inspections such as the Safety System Functional Inspection typically conducted by a team of inspectors. 5 refs., 3 figs., 1 tab

Oak Ridge Y-12 Plant groundwater protection program management plan

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-06-01

The Oak Ridge Y- 1 2 Plant (Y-12 Plant) is owned by the United States Department of Energy (DOE) and managed by Lockheed Martin Energy Systems, Inc. (Energy Systems) under contract No. DE-AC05-84OR21400. The Y-12 Plant Groundwater Protection Program (GWPP), which was initiated in 1975, provides for the protection of groundwater resources consistent with Federal, State, and local regulations, and in accordance with DOE orders and Energy Systems policies and procedures. The Y-12 Plant is located in Anderson County, Tennessee, and is within the corporate limits of the City of Oak Ridge. The Y-12 Plant is one of three major DOE complexes that comprise the 37,000-acre Oak Ridge Reservation (ORR) located in Anderson and Roane counties. The Y-12 Plant is located in Bear Creek Valley at an elevation of about 950 feet (ft) above sea level. Bear Creek Valley is bounded on the northwest and southeast, and is isolated from populated areas of Oak Ridge, by parallel ridges that rise about 300 ft above the valley floor. The Y-12 Plant and its fenced buffer area are about 0.6 mile wide by 3.2 miles long and cover approximately 4,900 acres. The main industrialized section encompasses approximately 800 acres.

Oak Ridge Y-12 Plant groundwater protection program management plan

International Nuclear Information System (INIS)

1996-06-01

The Oak Ridge Y- 1 2 Plant (Y-12 Plant) is owned by the United States Department of Energy (DOE) and managed by Lockheed Martin Energy Systems, Inc. (Energy Systems) under contract No. DE-AC05-84OR21400. The Y-12 Plant Groundwater Protection Program (GWPP), which was initiated in 1975, provides for the protection of groundwater resources consistent with Federal, State, and local regulations, and in accordance with DOE orders and Energy Systems policies and procedures. The Y-12 Plant is located in Anderson County, Tennessee, and is within the corporate limits of the City of Oak Ridge. The Y-12 Plant is one of three major DOE complexes that comprise the 37,000-acre Oak Ridge Reservation (ORR) located in Anderson and Roane counties. The Y-12 Plant is located in Bear Creek Valley at an elevation of about 950 feet (ft) above sea level. Bear Creek Valley is bounded on the northwest and southeast, and is isolated from populated areas of Oak Ridge, by parallel ridges that rise about 300 ft above the valley floor. The Y-12 Plant and its fenced buffer area are about 0.6 mile wide by 3.2 miles long and cover approximately 4,900 acres. The main industrialized section encompasses approximately 800 acres

Evaluation of nuclear power plant environmental impact prediction, based on monitoring programs. Summary and recommendations

International Nuclear Information System (INIS)

Gore, K.L.; Thomas, J.M.; Kannberg, L.D.; Watson, D.G.

1977-02-01

An evaluation of the effectivenss of non-radiological environmental monitoring programs is presented. The monitoring programs for Monticello, Haddam Neck, and Millstone Nuclear Generating Plants are discussed. Recommendations for improvements in monitoring programs are presented

Investigation of practical use situation and performance for electric transient analysis programs in the U.S. nuclear power plants

International Nuclear Information System (INIS)

Shimada, Yoshio

2010-01-01

The purposes of the present study are firstly to investigate the status of practical use of electric transient analysis programs used in U.S. nuclear power plants, which has been extracted as good examples from the information analysis of overseas troubles, and secondly to select a program to be recommended for use in implementing electric transient analysis in domestic nuclear power plants. In addition, to promote its practical use, a selected electric transient analysis program was tested by simulating the transient response during a load sequence test of an emergency diesel generator (EDG) in a domestic representative nuclear plant to evaluate its simulation accuracy by comparing its result with the measured plant data. The results obtained are as follows: (1) In U.S. nuclear power plants, simulations using electric transient analysis programs, such as ETAP, EMPT, etc., are widely performed, which contributed to improve the plant safety. (2) A selected transient analysis program EMTP was verified in its accuracy in terms of transient response of active power, current, voltage and frequency of the EDG during the load sequence test in a domestic representative nuclear power plant. (author)

46 CFR 176.620 - Description of the Alternative Hull Examination (AHE) Program for certain passenger vessels.

Science.gov (United States)

2010-10-01

... 46 Shipping 7 2010-10-01 2010-10-01 false Description of the Alternative Hull Examination (AHE... Hull and Tailshaft Examinations § 176.620 Description of the Alternative Hull Examination (AHE) Program for certain passenger vessels. The Alternative Hull Examination (AHE) Program provides you with an...

A Qualitative Approach to Examining Knowledge Sharing in Iran Tax Administration Reform Program

Directory of Open Access Journals (Sweden)

Mehdi Shami Zanjanie

2012-02-01

Full Text Available The paper aims to examine knowledge sharing infrastructure of "Iran Tax Administration Reform Program". The qualitative approach by using case study method was applied in this research. In order to meet the research goal, four infrastructural dimensions of knowledge sharing were studied: leadership & strategy, culture, structure, and information technology. To the authors’ knowledge, this was maybe the first paper which examined knowledge sharing infrastructure in programs environment

Lessons Learned on University Education Programs of Chemical Engineering Principles for Nuclear Plant Operations - 13588

International Nuclear Information System (INIS)

Ryu, Jun-hyung

2013-01-01

University education aims to supply qualified human resources for industries. In complex large scale engineering systems such as nuclear power plants, the importance of qualified human resources cannot be underestimated. The corresponding education program should involve many topics systematically. Recently a nuclear engineering program has been initiated in Dongguk University, South Korea. The current education program focuses on undergraduate level nuclear engineering students. Our main objective is to provide industries fresh engineers with the understanding on the interconnection of local parts and the entire systems of nuclear power plants and the associated systems. From the experience there is a huge opportunity for chemical engineering disciple in the context of giving macroscopic overview on nuclear power plant and waste treatment management by strengthening the analyzing capability of fundamental situations. (authors)

Technical Proposal Salton Sea Geothermal Power Pilot Plant Program

Energy Technology Data Exchange (ETDEWEB)

None

1975-03-28

The proposed Salton Sea Geothermal Power Pilot Plant Program comprises two phases. The objective of Phase 1 is to develop the technology for power generation from high-temperature, high-salinity geothermal brines existing in the Salton Sea known geothermal resources area. Phase 1 work will result in the following: (a) Completion of a preliminary design and cost estimate for a pilot geothermal brine utilization facility. (b) Design and construction of an Area Resource Test Facility (ARTF) in which developmental geothermal utilization concepts can be tested and evaluated. Program efforts will be divided into four sub-programs; Power Generation, Mineral Extraction, Reservoir Production, and the Area Resources Test Facility. The Power Generation Subprogram will include testing of scale and corrosion control methods, and critical power cycle components; power cycle selection based on an optimization of technical, environmental and economic analyses of candidate cycles; preliminary design of a pilot geothermal-electric generating station to be constructed in Phase 2 of this program. The Mineral Extraction Subprogram will involve the following: selection of an optimum mineral recovery process; recommendation of a brine clean-up process for well injection enhancement; engineering, construction and operation of mineral recovery and brine clean-up facilities; analysis of facility operating results from environmental, economical and technical point-of-view; preliminary design of mineral recovery and brine clean-up facilities of sufficient size to match the planned pilot power plant. The Reservoir Production Subprogram will include monitoring the operation and maintenance of brine production, handling and injection systems which were built with private funding in phase 0, and monitoring of the brine characteristics and potential subsidence effects during well production and injection. Based on the above, recommendations and specifications will be prepared for production and

A Plant Health Care Program for Brambles in the Pacific Northwest

OpenAIRE

McElroy, F. D.

1992-01-01

Pratylenchus and Xiphinema species have been associated with decline and mortality of brambles (Rubus species) in the Pacific Northwest of the United States. These nematodes cause direct feeding damage and (or) transmit viruses that result in poor fruit quality and plant decline. A nematode management program has been developed by the author to minimize chemical use and nematode-induced damage while optimizing fruit production. Nematode management is an integral part of a total plant health c...

Educational systems - educational qualification of nuclear power plant personnel

International Nuclear Information System (INIS)

Boeger, H.

1986-01-01

In this lecture the following common features of education and training systems are described: - description of general school education, vocational training and engineering study programs, - allocation of categories of activities to normal school training backgrounds, - recommendations for educational and training programs required for various positions in nuclear power plants (formal and on-the-job training), - examinations and licences for the personnel at nuclear power plants. (orig./GL)

Development of Intelligent Database Program for PSI/ISI Data Management of Nuclear Power Plant (Part II)

International Nuclear Information System (INIS)

Park, Un Su; Park, Ik Keun; Um, Byong Guk; Lee, Jong Po; Han, Chi Hyun

2000-01-01

In a previous paper, we have discussed the intelligent Windows 95-based data management program(IDPIN) which was developed for effective and efficient management of large amounts of pre-/in-service inspection(PSI/ISI) data of Kori nuclear power plants. The IDPIN program enables the prompt extraction of previously conducted PSI/ISI conditions and results so that the time-consuming data management, painstaking data processing and analysis of the past are avoided. In this study, the intelligent Windows based data management program(WS-IDPIN) has been developed as an effective data management of PSI/ISI data for the Wolsong nuclear power plants. The WS-IDPIN program includes the modules of comprehensive management and analysis of PSI/ISI results, statistical reliability assessment program of PSI/ISI results(depth and length sizing performance etc), standardization of UT report form and computerization of UT results. In addition, the program can be further developed as a unique PSI/ISI data management expert system which can be part of the PSI/ISI total support system for Korean nuclear power plants

Fundamental attributes of a practical configuration management program for nuclear plant design control

International Nuclear Information System (INIS)

Klein, S.M.

1988-06-01

This summarizes the results of an evaluation of findings identifies during a number of Safety-System Functional Inspections and Safety System Outage Modification Inspections which are related to configuration management for nuclear plant design control. A computerized database of these findings was generated from a review of the design inspection reports. Based on the results of the evaluation, attributes of a configuration management program were developed which are responsive to minimizing these types of inspection findings. Incorporation of these key attributes is considered good practice in the development of a configuration management program for design control at operating nuclear plants

Review of operating history at the Palisades Nuclear Plant

International Nuclear Information System (INIS)

Mays, G.T.; Harrington, K.H.

1982-01-01

the Systematic Evaluation Program Branch (SEPB) of the Nuclear Regulatory Commission (NRC) is conducting the Systematic Evaluation Program whose purpose is to determine the safety margins of the design and operation of the eleven oldest operating commercial nuclear power plants in the United States. A portion of the SEP includes the compilation and interpretation of operational occurrences at these plants. This summary describes the methodology and results of the operational experience review of Palisades Nuclear Plant. The review includes a detailed examination of the operating experience in two segments - plant shutdowns and power reductions, and reportable events

A Study of Automation for Examination Analysis of Inservice Inspection for Nuclear Power Plant (I)

International Nuclear Information System (INIS)

Kim, W.

1985-01-01

The developing country, KOREA where does not possess the natural resources for traditional energy such as oil and gas, so. The nuclear energy is the most single reliable source available for closing the energy gap. For these reason, It is inavoidable to construct the nuclear power plant and to develop technology related nuclear energy. The rate of operation in large nuclear power facilities depends upon the performance of work system through design and construction, and also the applied technology. Especially, it is the most important element that safety and reliability in operation of nuclear power plant. In view of this aspects, Nuclear power plant is performed severe examinations during perceives and inservice inspection. This study provide an automation of analysis for volumetric examination which is required to nuclear power plant components. It is composed as follows: I. Introduction II. Inservice Inspection of Nuclear Power Plant * General Requirement. * Principle and Methods of Ultrasonic Test. * Study of Flaw Evaluation and Design of Classifying Formula for Flaws. III. Design of Automation for Flaw Evaluation. IV. An Example V. Conclusion In this theory, It is classifying the flaws, the formula of classifying flaws and the design of automation that is the main important point. As motioned the above, Owing to such as automatic design, more time could be allocated to practical test than that of evaluation of defects, Protecting against subjective bias tester by himself and miscalculation by dint of various process of computation. For the more, adopting this method would be used to more retaining for many test data and comparative evaluating during successive inspection intervals. Inspire of limitation for testing method and required application to test components, it provide useful application to flow evaluation for volumetric examination. Owing to the characteristics of nuclear power plant that is highly skill intensive industry and has huge system, the

CHAP: a composite nuclear plant simulation program applied to the 3000 MW(t) HTGR

International Nuclear Information System (INIS)

Secker, P.A.; Bailey, P.G.; Gilbert, J.S.; Willcutt, G.J.E. Jr.; Vigil, J.C.

1977-01-01

The Composite HTGR Analysis Program (CHAP) is a general systems analysis program which has been developed at LASL. The program is being used for simulating large HTGR nuclear power plant operation and accident transients. The general features and analytical methods of the CHAP program are discussed. Features of the large HTGR model and results of model transients are also presented

Tecnomatix Plant Simulation modeling and programming by means of examples

CERN Document Server

Bangsow, Steffen

2015-01-01

This book systematically introduces the development of simulation models as well as the implementation and evaluation of simulation experiments with Tecnomatix Plant Simulation. It deals with all users of Plant Simulation, who have more complex tasks to handle. It also looks for an easy entry into the program. Particular attention has been paid to introduce the simulation flow language SimTalk and its use in various areas of the simulation. The author demonstrates with over 200 examples how to combine the blocks for simulation models and how to deal with SimTalk for complex control and analys

Research and examinations at the Tono Mines. Fiscal year's programs (Heisei 12 fiscal year). Technical report

International Nuclear Information System (INIS)

2000-04-01

This program showed details on the research and examination program of the Japan Nuclear Cycle Development Institute to be carried out at the Tono Mines in the Heisei 12 fiscal year, according to the 'Fundamental program on research and examinations at the Tono Mines' established on October, 1998. And, this program is carried out under an aim at understanding of transfer and delay performance of materials in deposit rocks with uranium and geological features such as fault, and at development of technology and apparatus for general investigation and evaluation of geological environment, as a stratum science research. Here were described on research and examination of mechanical stability on the rock board, research and examination of geological environment around a tunnel, research and examination of material transfer in the rock board, and research and examination of the Tsukiyoshi stratum abstractly before 1999 and in details at 2000 fiscal years. (G.K.)

Hanford Waste Vitrification Plant Project Waste Form Qualification Program Plan

International Nuclear Information System (INIS)

Randklev, E.H.

1993-06-01

The US Department of Energy has created a waste acceptance process to help guide the overall program for the disposal of high-level nuclear waste in a federal repository. This Waste Form Qualification Program Plan describes the hierarchy of strategies used by the Hanford Waste Vitrification Plant Project to satisfy the waste form qualification obligations of that waste acceptance process. A description of the functional relationship of the participants contributing to completing this objective is provided. The major activities, products, providers, and associated scheduling for implementing the strategies also are presented

European passive plant program A design for the 21st century

International Nuclear Information System (INIS)

Adomaitis, D.; Oyarzabal, M.

1998-01-01

In 1994, a group of European utilities initiated, together with Westinghouse and its industrial partner GENESI (an Italian consortium including ANSALDO and FIAT), a program designated EPP (European Passive Plant) to evaluate Westinghouse passive nuclear plant technology for application in Europe. The following major tasks were accomplished: (1) the impacts of the European utility requirements (EUR) on the Westinghouse nuclear island design were evaluated; and (2) a 1000 MWe passive plant reference design (EP1000) was established which conforms to the EUR and is expected to be licensable in Europe. With respect to safety systems and containment, the reference plant design closely follows that of the Westinghouse simplified pressurized water reactor (SPWR) design, while the AP600 plant design has been taken as the basis for the EP1000 reference design in the auxiliary system design areas. However, the EP1000 design also includes features required to meet the EUR, as well as key European licensing requirements. (orig.)

Handbook of nuclear power plant seismic fragilities, Seismic Safety Margins Research Program

International Nuclear Information System (INIS)

Cover, L.E.; Bohn, M.P.; Campbell, R.D.; Wesley, D.A.

1983-12-01

The Seismic Safety Margins Research Program (SSMRP) has a gola to develop a complete fully coupled analysis procedure (including methods and computer codes) for estimating the risk of an earthquake-induced radioactive release from a commercial nuclear power plant. As part of this program, calculations of the seismic risk from a typical commercial nuclear reactor were made. These calculations required a knowledge of the probability of failure (fragility) of safety-related components in the reactor system which actively participate in the hypothesized accident scenarios. This report describes the development of the required fragility relations and the data sources and data reduction techniques upon which they are based. Both building and component fragilities are covered. The building fragilities are for the Zion Unit 1 reactor which was the specific plant used for development of methodology in the program. Some of the component fragilities are site-specific also, but most would be usable for other sites as well

The IEAGHG Power Plant Assessment Program (PPAP). Development and testing June 2002-October 2005

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-12-15

The Power Plant Assessment Program (PPAP) is an Excel based program which allows alternative CO{sub 2} capture technologies for centralised power generation to be compared using multi-criteria analysis. This report outlines recent development work on the program and the results obtained from evaluating a range of novel capture processes with it.

Quality assurance program description: Hanford Waste Vitrification Plant, Part 1

International Nuclear Information System (INIS)

1992-01-01

This document describes the Department of Energy's Richland Field Office (DOE-RL) quality assurance (QA) program for the processing of high-level waste as well as the Vitrification Project Quality Assurance Program for the design and construction of the Hanford Waste Vitrification Plant (HWVP). It also identifies and describes the planned activities that constitute the required quality assurance program for the HWVP. This program applies to the broad scope of quality-affecting activities associated with the overall HWVP Facility. Quality-affecting activities include designing, purchasing, fabricating, handling, shipping, storing, cleaning, erecting, installing, inspecting, testing, maintaining, repairing, and modifying. Also included are the development, qualification, and production of waste forms which may be safely used to dispose of high-level radioactive waste resulting from national defense activities. The HWVP QA program is made up of many constituent programs that are being implemented by the participating organizations. This Quality Assurance program description is intended to outline and define the scope and application of the major programs that make up the HWVP QA program. It provides a means by which the overall program can be managed and directed to achieve its objectives. Subsequent parts of this description will identify the program's objectives, its scope, application, and structure

Intergrated plant safety assessment. Systematic evaluation program. Palisades plant, Consumers Power Company, Docket No. 50-255. Final report

International Nuclear Information System (INIS)

1982-10-01

The Nuclear Regulatory Commission (NRC) has published its Final Integrated Plant Safety Assessment Report (IPSAR) (NUREG-0820), under the scope of the Systematic Evaluation Program (SEP), for Consumers Power Company's Palisades Plant located in Covert, Van Buren County, Michigan. The SEP was initiated by the NRC to review the design of older operating nuclear reactor plants to reconfirm and document their safety. This report documents the review completed under the SEP for the Palisades Plant. The review has provided for (1) as assessment of the significance of differences between current technical positions on selected safety issues and those that existed when the Palisades Plant was licensed, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety when all supplements to the Final IPSAR and the Safety Evaluation Report for converting the license from a provisional to a full-term license have been issued. The report also addresses the comments and recommendations made by the Advisory Committee on Reactor Safeguards in connection with its review of the Draft Report, issued in April 1982

Availability Improvement Program for Louisiana Power and Light's Waterford 3 Nuclear Power Plant

International Nuclear Information System (INIS)

Simoneaux, G.E.

1985-01-01

The Middle South Utilities System (MSUS) began an Availability Improvement Program (AIP) in the late nineteen-seventies for the benefit of all the operating units making up the System. This paper describes the methodology that is being employed in implementing a formal Avalability Improvement Program for a new nuclear unit known as Waterford 3. The tasks needed to install and maintain the AIP at Waterford 3 are discussed in terms of Analytical Methodology, Avalability Data System, and Plant Imvolvement. In particular, the AIP will provide: Management reporting; External reporting; A self-sufficient core of trained avalability personnel; Procedures and methodologies to monitor plant availability and to analyze availability problems

Competitiveness of biomass-fueled electrical power plants.

Science.gov (United States)

Bruce A. McCarl; Darius M. Adams; Ralph J. Alig; John T. Chmelik

2000-01-01

One way countries like the United States can comply with suggested rollbacks in greenhouse gas emissions is by employing power plants fueled with biomass. We examine the competitiveness of biomass-based fuel for electrical power as opposed to coal using a mathematical programming structure. We consider fueling power plants from milling residues, whole trees, logging...

GESIT: a thermodynamic program for single cycle gas turbine plants with and without intercoolers

Energy Technology Data Exchange (ETDEWEB)

Heil, J

1973-08-01

A computer program for the thermodynamic modeling of singlecycle gas turbine plants is described. A high-temperature reactor is assumed as a heat source in the program, but the HTR can be replaced with another heat source without difficulty. Starting from a set of independent data, the program calculates efficiencies and mass flows. It indicates all values for a heat and power balance and prints out the temperatures and pressures for the different parts of the cycle. Besides this, the program is able to optimize the compression ratios for minimal power input. It also takes into account turbine rotor cooling (at the roots of the blades). Furthermore, the program is able to use either total pressure loss or specified losses in different parts of the cycle. The program GESlT can also handle systems with one or two intercoolers, or with no intercooler. GESIT gives all input and output values for the heat exchangers and turbo-machines. First the single-cycle gas turbine plant is described. After that the computational basis for the program and the program structure is explained. Instructions for data input are given so that the program can be immediately utilized. An example of input data together with the associated output is presented. (auth)

International efforts to reduce occupational radiation exposure at nuclear power plants

International Nuclear Information System (INIS)

Khan, T.A.; Baum, J.W.

1986-01-01

The efficacy of various national programs on dose reduction is examined with a view to evaluating the most significant factors that help in reducing occupational exposure. Among the most successful of the dose reduction programs at water reactors are those of France, Sweden, and Canada where average annual plant doses are significantly less than the dose at US plants. Important research is also going on in other countries such as the UK, West Germany, Switzerland, and Japan. Some programs are directed towards hardware solutions; others are oriented towards such approaches as better work planning and procedures. The general thrust and some of the specifics of these programs are examined and factors which may be applicable to US conditions are discussed

The Waste Isolation Pilot Plant Performance Assessment Program

International Nuclear Information System (INIS)

Myers, J.; Coons, W.E.; Eastmond, R.; Morse, J.; Chakrabarti, S.; Zurkoff, J.; Colton, I.D.; Banz, I.

1986-01-01

The Waste Isolation Pilot Plant (WIPP) Performance Assessment Program involves a comprehensive analysis of the WIPP project with respect to the recently finalized Environmental Protection Agency regulations regarding the long-term geologic isolation of radioactive wastes. The performance assessment brings together the results of site characterization, underground experimental, and environmental studies into a rigorous determination of the performance of WIPP as a disposal system for transuranic radioactive waste. The Program consists of scenario development, geochemical, hydrologic, and thermomechanical support analyses and will address the specific containment and individual protection requirements specified in 40 CFR 191 sub-part B. Calculated releases from these interrelated analyses will be reported as an overall probability distribution of cumulative release resulting from all processes and events occurring over the 10,000 year post-closure period. In addition, results will include any doses to the public resulting from natural processes occurring over the 1,000 year post-closure period. The overall plan for the WIPP Performance Assessment Program is presented along with approaches to issues specific to the WIPP project

Waste Isolation Pilot Plant Groundwater Protection Management Program Plan

Energy Technology Data Exchange (ETDEWEB)

Washington TRU Solutions

2002-09-24

U.S. Department of Energy (DOE) Order 5400.1, General Environmental Protection Program, requires each DOE site to prepare a Groundwater Protection Management Program Plan. This document fulfills the requirement for the Waste Isolation Pilot Plant (WIPP). This document was prepared by the Hydrology Section of the Westinghouse TRU Solutions LLC (WTS) Environmental Compliance Department, and it is the responsibility of this group to review the plan annually and update it every three years. This document is not, nor is it intended to be, an implementing document that sets forth specific details on carrying out field projects or operational policy. Rather, it is intended to give the reader insight to the groundwater protection philosophy at WIPP.

Integrated plant safety assessment: Systematic Evaluation Program. LaCrosse Boiling Water Reactor, Dairyland Power Cooperative, Docket No. 50-409

International Nuclear Information System (INIS)

1983-04-01

The Systematic Evaluation Program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to confirm and document their safety. The review provides: (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of the La Crosse Boiling Water Reactor, operated by Dairyland Power Cooperative. The La Crosse plant is one of 10 plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addresed. Equipment and procedural changes have been identified as a result of the review

Failure analysis and success analysis: roles in plant aging assessments

International Nuclear Information System (INIS)

Johnson, A.B. Jr.

1985-06-01

Component aging investigations are an important element in NRC's Nuclear Plant Aging Research (NPAR) strategy. Potential sources of components include plants in decommissioning and commercial plant, both for in situ tests and for examination of equipment removed from service. Nuclear utilities currently have voluntary programs addressing aspects of equipment reliability, such as root cause analysis for safety-related equipment that malfunctions, and trending analysis to follow the course of both successful and abnormal equipment performance. Properly coordinated, the NPAR and utility programs offer an important approach to establish the data base necessary for life extension of nuclear electrical generating plants

46 CFR 71.50-15 - Description of the Alternative Hull Examination (AHE) Program for certain passenger vessels.

Science.gov (United States)

2010-10-01

... 46 Shipping 3 2010-10-01 2010-10-01 false Description of the Alternative Hull Examination (AHE... Description of the Alternative Hull Examination (AHE) Program for certain passenger vessels. The Alternative Hull Examination (AHE) Program provides you with an alternative to a drydock examination by allowing...

EPRI's nuclear power plant instrumentation and control program and its applicability to advanced reactors

International Nuclear Information System (INIS)

Naser, J.; Torok, R.; Wilkinson, D.

1997-01-01

I ampersand C systems in nuclear power plants need to be upgraded over the lifetime of the plant in a reliable and cost-effective manner to replace obsolete equipment, to reduce O ampersand M costs, to improve plant performance, and to maintain safety. This applies to operating plants now and will apply to advanced reactors in the future. The major drivers for the replacement of the safety, control, and information systems in nuclear power plants are the obsolescence of the existing hardware and the need for more cost-effective power production. Competition between power producers is dictating more cost-effective power production. The increasing O ampersand M costs to maintain systems experiencing obsolescence problems is counter to the needs for more cost-effective power production and improved competitiveness. This need for increased productivity applies to government facilities as well as commercial plants. Increasing competition will continue to be a major factor in the operation of both operating plants and advanced reactors. It will continue to dictate the need for improved productivity and cost-effectiveness. EPRI and its member nuclear utilities are working together on an industry wide I ampersand C Program to address I ampersand C issues and to develop cost-effective solutions. A majority of the I ampersand C products and demonstrations being developed under this program will benefit advanced reactors in both the design and operational phases of their life cycle as well as it will benefit existing plants. 20 refs

Nondestructive examination requirements for PWR vessel internals

International Nuclear Information System (INIS)

Spanner, J.

2015-01-01

This paper describes the requirements for the nondestructive examination of pressurized water reactor (PWR) vessel internals in accordance with the requirements of the EPRI Material Reliability Program (MRP) inspection standard for PWR internals (MRP-228) and the American Society of Mechanical Engineers Section XI In-service Inspection. The MRP vessel internals examinations have been performed at nuclear plants in the USA since 2009. The objective of the inspection standard is to provide the requirements for the nondestructive examination (NDE) methods implemented to support the inspection and evaluation of the internals. The inspection standard contains requirements specific to the inspection methodologies involved as well as requirements for qualification of the NDE procedures, equipment and personnel used to perform the vessel internals inspections. The qualification requirements for the NDE systems will be summarized. Six PWR plants in the USA have completed inspections of their internals using the Inspection and Evaluation Guideline (MRP-227) and the Inspection Standard (MRP-228). Examination results show few instances of service-induced degradation flaws, as expected. The few instances of degradation have mostly occurred in bolting

Development of a SPV management program for nuclear power plants

International Nuclear Information System (INIS)

Lee, Eun-Chan; Na, Jang-Hwan; Lee, Doo-Young; Oh, Seong-Jong; Jerng, Dong-Wook

2009-01-01

The Single Point Vulnerability (SPV) is a characteristic of a component whose failure results in plant transients. KHNP (Korea Hydro and Nuclear Power Co.) has evaluated major systems with critical components and developed a SPV management program to reduce the trip frequency and to raise plant's availability. This study includes a comprehensive methodology for SPV evaluation and its results. This methodology consists of the qualitative evaluation focused on the SPV component list preparation and the quantitative evaluation through FMEA (Failure Mode Effect Analyses) and FTA (Fault Tree Analyses) of critical systems. The qualitative evaluation reduced differences of the SPV lists between the identically designed plants and established strategies for the improvement of the SPV component reliability. The quantitative evaluation identified additional SPV components and developed the fault tree model for a Trip Monitor which showed logic relationships of channel components in the trip-related systems. (author)

Teaming up for Literacy: Examining Participants' Contributions to a Collaborative Family-Based Program

Science.gov (United States)

Kumar, Tracey

2016-01-01

This study of participants' contributions to a university-based family literacy program was informed by both "funds of knowledge" (Moll, 1992) and "multiple literacies" (Auerbach, 1995). The study examined participants' contributions to the design, implementation, and evaluation of a university-based family literacy program. In…

Vacuolar processing enzyme in plant programmed cell death

Directory of Open Access Journals (Sweden)

Noriyuki eHatsugai

2015-04-01

Full Text Available Vacuolar processing enzyme (VPE is a cysteine proteinase originally identified as the proteinase responsible for the maturation and activation of vacuolar proteins in plants, and it is known to be an orthologue of animal asparaginyl endopeptidase (AEP/VPE/legumain. VPE has been shown to exhibit enzymatic properties similar to that of caspase 1, which is a cysteine protease that mediates the programmed cell death (PCD pathway in animals. Although there is limited sequence identity between VPE and caspase 1, their predicted three-dimensional structures revealed that the essential amino-acid residues for these enzymes form similar pockets for the substrate peptide YVAD. In contrast to the cytosolic localization of caspases, VPE is localized in vacuoles. VPE provokes vacuolar rupture, initiating the proteolytic cascade leading to PCD in the plant immune response. It has become apparent that the VPE-dependent PCD pathway is involved not only in the immune response, but also in the responses to a variety of stress inducers and in the development of various tissues. This review summarizes the current knowledge on the contribution of VPE to plant PCD and its role in vacuole-mediated cell death, and it also compares VPE with the animal cell death executor caspase 1.

NRC research program on plant aging: Listing and abstracts of reports issued through February 1, 1989

International Nuclear Information System (INIS)

Kondic, N.N.

1989-08-01

The US Nuclear Regulatory Commission is conducting the Nuclear Plant Aging Research (NPAR) Program. This is a comprehensive hardware-oriented program focused on understanding the aging mechanisms of components and systems in nuclear plants. The NPAR Program also focuses on methods for simulating and monitoring the aging-related degradation of these components and systems. This document contains a listing and index of reports generated in the NPAR Program that were issued through February 1, 1989, and abstracts of those reports. Each abstract describes the elements of the research covered in the report and outlines the significant results. For the convenience of the user, the reports are indexed by personal author, corporate author, and subject

Hanford Waste Vitrification Plant Quality Assurance Program description for high-level waste form development and qualification. Revision 3, Part 2

Energy Technology Data Exchange (ETDEWEB)

1993-08-01

The Hanford Waste Vitrification Plant Project has been established to convert the high-level radioactive waste associated with nuclear defense production at the Hanford Site into a waste form suitable for disposal in a deep geologic repository. The Hanford Waste Vitrification Plant will mix processed radioactive waste with borosilicate material, then heat the mixture to its melting point (vitrification) to forin a glass-like substance that traps the radionuclides in the glass matrix upon cooling. The Hanford Waste Vitrification Plant Quality Assurance Program has been established to support the mission of the Hanford Waste Vitrification Plant. This Quality Assurance Program Description has been written to document the Hanford Waste Vitrification Plant Quality Assurance Program.

Evaluation of Millstone Nuclear Power Plant, Environmental Impact prediction, based on monitoring programs

International Nuclear Information System (INIS)

Gore, K.L.; Thomas, J.M.; Kannberg, L.D.; Watson, D.G.

1977-02-01

This report evaluates the nonradiological monitoring program at Millstone Nuclear Power Plant. Both operational as well as preoperational monitoring programs were analyzed to produce long-term (5 yr or longer) data sets, where possible. In order to determine the effectiveness of these monitoring programs, the appropriate data sets have to be analyzed by the appropriate statistical analysis. Thus, both open literature and current statistical analysis being developed at Pacific Northwest Laboratories (PNL) were employed in data analysis

Evaluation of Millstone Nuclear Power Plant, Environmental Impact prediction, based on monitoring programs

Energy Technology Data Exchange (ETDEWEB)

Gore, K.L.; Thomas, J.M.; Kannberg, L.D.; Watson, D.G.

1977-02-01

This report evaluates the nonradiological monitoring program at Millstone Nuclear Power Plant. Both operational as well as preoperational monitoring programs were analyzed to produce long-term (5 yr or longer) data sets, where possible. In order to determine the effectiveness of these monitoring programs, the appropriate data sets have to be analyzed by the appropriate statistical analysis. Thus, both open literature and current statistical analysis being developed at Pacific Northwest Laboratories (PNL) were employed in data analysis.

Relevant aspects of a quality assurance program applied to a nuclear power plant operation

International Nuclear Information System (INIS)

Fernandez, J.C.

1987-01-01

The purpose of this work was to enumerate the most relevant subjects to be taken into account for the elaboration of a Quality Assurance Program aimed to regulate a nuclear power plant operation. At first, it was necessary to point out the relevance that implies the presence of a group of personnel, experienced in quality assurance with enough knowledge on the technical and organizing aspects of the plant. Other aspect to be taken into account was the contemplation of the international requirements, through the International Atomic Energy Agency and of the national requirements that each country had set up by the corresponding regulating agencies. These organizations pointed out the minimum rules that must be followed for the adequate and efficient execution of a program. The Quality Assurance Manual and the program and work procedures constituted the Quality Assurance Program which must be checked as regards its fulfillment by auditors and quality assurance supervisions. (Author)

Final Report on the Operation and Maintenance Improvement Program for Concentrating Solar Power Plants

International Nuclear Information System (INIS)

Cohen, Gilbert E.; Kearney, David W.; Kolb, Gregory J.

1999-01-01

This report describes the results of a six-year, $6.3 million project to reduce operation and maintenance (O ampersand M) costs at power plants employing concentrating solar power (CSP) technology. Sandia National Laboratories teamed with KJC Operating Company to implement the O ampersand M Improvement Program. O ampersand M technologies developed during the course of the program were demonstrated at the 150-MW Kramer Junction solar power park located in Boron, California. Improvements were made in the following areas: (a) efficiency of solar energy collection, (b) O ampersand M information management, (c) reliability of solar field flow loop hardware, (d) plant operating strategy, and (e) cost reduction associated with environmental issues. A 37% reduction in annual O ampersand M costs was achieved. Based on the lessons learned, an optimum solar- field O ampersand M plan for future CSP plants is presented. Parabolic trough solar technology is employed at Kramer Junction. However, many of the O ampersand M improvements described in the report are also applicable to CSP plants based on solar power tower or dish/engine concepts

Final Report on the Operation and Maintenance Improvement Program for Concentrating Solar Power Plants

Energy Technology Data Exchange (ETDEWEB)

Cohen Gilbert E.; Kearney, David W.; Kolb, Gregory J.

1999-06-01

This report describes the results of a six-year, $6.3 million project to reduce operation and maintenance (O&M) costs at power plants employing concentrating solar power (CSP) technology. Sandia National Laboratories teamed with KJC Operating Company to implement the O&M Improvement Program. O&M technologies developed during the course of the program were demonstrated at the 150-MW Kramer Junction solar power park located in Boron, California. Improvements were made in the following areas: (a) efficiency of solar energy collection, (b) O&M information management, (c) reliability of solar field flow loop hardware, (d) plant operating strategy, and (e) cost reduction associated with environmental issues. A 37% reduction in annual O&M costs was achieved. Based on the lessons learned, an optimum solar- field O&M plan for future CSP plants is presented. Parabolic trough solar technology is employed at Kramer Junction. However, many of the O&M improvements described in the report are also applicable to CSP plants based on solar power tower or dish/engine concepts.

Next Generation Nuclear Plant Methods Technical Program Plan -- PLN-2498

Energy Technology Data Exchange (ETDEWEB)

Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

2010-09-01

One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the “highly ranked” phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

Development of reliability program for emergency diesel generators in domestic nuclear power plants

International Nuclear Information System (INIS)

Kim, Young Ho; Jung, Hyun Jong; Choi, Kwang Hee; Hong, Seoung Yeul

2001-01-01

Surveillance tests of Emergency Diesel Generators (EDGs) in Nuclear Power Plants (NPPs) have been conducted periodically to verify the reliability and integrity of the EDGs, however, it was found that these surveillance methods were so conservative and severe as to accelerate the degradation of the EDGs. Hence, new regulatory guideline, Reg. Guide 1.9 Rev. 3, was established by the U.S. NRC to resolve these problems. But it requires the additional implementation of reliability program of the EDGs to improve the actual reliability of them. In Korea, the EDGs of Yonggwang nuclear units 3 and 4 were the first plant applying new Reg. guide 1.9 rev.3 and implementing EDG reliability program. Furthermore it is expected that new guideline for the EDGs will be applied to other EDGs of Korean NPPs. In this paper, this reliability program is described, and it can be used as a reference for other EDGs in Korean NPPs

NRC Research Program on Plant Aging: Listing and summaries of reports issued through June 1991

International Nuclear Information System (INIS)

Kondic, N.N.; Hill, E.L.

1991-07-01

The US Nuclear Regulatory Commission is conducting the Nuclear Plant Aging Research (NPAR) Program. This is a comprehensive hardware-oriented engineering research program focused on understanding the aging mechanisms of components and systems in nuclear power plants. The NPAR program also focuses on methods for simulating and monitoring the aging-related degradation of these components and systems. In addition, it provides recommendations for effective maintenance to manage aging and for the implementation of the research results in the regulatory process. This document contains a listing and index of reports generated in the NPAR Program that were issued through June 1991 and summaries of those reports. Each summary describes the elements of the research covered in the report and outlines the significant results. For the convenience of the user, the reports are indexed by personal author, corporate author, and subject. 102 refs

NRC research program on plant aging: Listing and summaries of reports issued through July 1992

International Nuclear Information System (INIS)

Kondic, N.N.

1992-09-01

The US Nuclear Regulatory Commission is conducting the Nuclear Plant Aging Research (NPAR) Program. This is a comprehensive hardware-oriented engineering research program focused on understanding the aging mechanisms of components and systems in nuclear power plants. The NPAR program also focuses on methods for simulating and monitoring the aging-related degradation of these components and systems. In addition, it provides recommendations for effective maintenance to manage aging and for implementation of the research results in the regulatory process. This document contains a listing and index of reports generated in the NPAR Program that were issued through July 1992 and summaries of those reports. Each summary describes the elements of the research covered in the report and outlines the significant results. For the convenience of the user, the reports are indexed by personal author, corporate author, and subject

NRC research program on plant aging: Listing and summaries of reports issued through May 1990

International Nuclear Information System (INIS)

Kondic, N.N.; Hill, E.L.

1990-07-01

The US Nuclear Regulatory Commission is conducting the Nuclear Plant Aging Research (NPAR) Program. This is a comprehensive hardware-oriented engineering research program focused on understanding the aging mechanisms of components and systems in nuclear plants. The NPAR program also focuses on methods for simulating and monitoring the aging-related degradation of these components and systems. In addition, it provides recommendations for effective maintenance to manage aging and for the implementation of the research results in the regulatory process. This document contains a listing and index of reports generated in the NPAR Program that were issued through May 1990 and summaries of those reports. Each summary describes the elements of the research covered in the report and outlines the significant results. For the convenience of the user, the reports are indexed by personal author, corporate author, and subject

Basis for snubber aging research: Nuclear Plant Aging Research Program

International Nuclear Information System (INIS)

Brown, D.P.; Palmer, G.R.; Werry, E.V.; Blahnik, D.E.

1990-01-01

This report describes a research plan to address the safety concerns of aging in snubbers used on piping and equipment in commercial nuclear power plants. The work is to be performed under Phase 2 of the Snubber Aging Study of the Nuclear Plant Aging Research Program of the US Nuclear Regulatory Commission with the Pacific Northwest Laboratory (PNL) as the prime contractor. Research conducted by PNL under Phase 1 provided an initial assessment of snubber operating experience and was primarily based on a review of licensee event reports. The work proposed is an extension of Phase 1 and includes research at nuclear power plants and in test laboratories. Included is technical background on the design and use of snubbers in commercial nuclear power applications; the primary failure modes of both hydraulic and mechanical snubbers are discussed. The anticipated safety, technical, and regulatory benefits of the work, along with concerns of the NRC and the utilities, are also described. 21 refs., 7 figs., 1 tab

46 CFR 115.660 - Continued participation in the Alternative Hull Examination (AHE) Program.

Science.gov (United States)

2010-10-01

... 46 Shipping 4 2010-10-01 2010-10-01 false Continued participation in the Alternative Hull... MORE THAN 49 PASSENGERS INSPECTION AND CERTIFICATION Hull and Tailshaft Examinations § 115.660 Continued participation in the Alternative Hull Examination (AHE) Program. (a) To continue to participate in...

46 CFR 176.660 - Continued participation in the Alternative Hull Examination (AHE) Program.

Science.gov (United States)

2010-10-01

... 46 Shipping 7 2010-10-01 2010-10-01 false Continued participation in the Alternative Hull... (CONTINUED) SMALL PASSENGER VESSELS (UNDER 100 GROSS TONS) INSPECTION AND CERTIFICATION Hull and Tailshaft Examinations § 176.660 Continued participation in the Alternative Hull Examination (AHE) Program. (a) To...

Industrial Fuel Gas Demonstration Plant Program. Monthly, quarterly and annual progress report, December 1978 and Calender Year 1978

Energy Technology Data Exchange (ETDEWEB)

None

1978-01-01

A new pilot plant program developed by DOE and the team members, was started on September 20, 1978. Pilot plant success was achieved in obtaining an ash balanced condition for several days with ash agglomeration with a pure coal feed. This was the objective of the first three months of the approved program.

V-Model based Configuration Management Program for New-Build Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

An, Kyungik [PartDB Co. Ltd., Daejeon (Korea, Republic of); Cho, Yoon Sang [KHNP Co. Ltd., Daejeon (Korea, Republic of); Freeland, Kent R. [Industrial Analysts Incorporated, New Hampshire (United States)

2014-05-15

As NPP operators undertook design basis reconstitution efforts, they began to realize that the design basis is a foundation for Configuration Management (CM). This realization was made evident in the magnitude of the problems that were being observed. This experience also raised serious questions about how the information being developed to produce the design basis documents would be kept up to date in the future. A process to reconstitute the design basis is likely to be ineffective if CM controls are not in place. The right IT solution for CM depends upon a number of factors, including the nuclear power plant culture, budget, target technology, and the nuclear power plant owner/operator's standards, requirements and limitations for its generating fleet. Comprehensive CM Program for NPP is the single greatest strategy to meet the commitment to nuclear excellence. The safety and viability of nuclear power, particularly at the fleet level, depends upon the development of positive design control and design basis to better understanding plant operating dynamics and margin management, along with technology to control the realization of such design in the physical plant. However the most of plant facilities are modified many times, often without suitable support needed to confirm with their design base and to update their engineering data, maintenance rules and operating procedures. This lack of equilibrium between the requirements, design information and physical plant still remains a important issue. This study focuses on how to manage the configuration information of NPP using systems engineering V-model approach, and proposes data model to manage the configuration information in relation to manage their life cycle. Comprehensive CM Program and IMS for NPP life cycle support is the greatest strategy to meet the commitment to nuclear safety.

Update on the EPRI power generation risk-based inservice inspection pilot plant studies

International Nuclear Information System (INIS)

Gosselin, S.R.

1997-01-01

The scope for ASME Section XI ISI programs is largely based on deterministic results contained in design stress reports. These reports are normally very conservative and may not be an accurate representation of failure potential. Service experience has shown that failures are due to either corrosion or fatigue and typically occur in areas not included in the plant's ISI program. Consequently, nuclear plants are devoting significant resources to inspection programs that provide minimum benefit. As an alternative, significant industry attention has been devoted to the application of risked-based selection criteria in order to determine the scope of inservice inspection (ISI) programs at nuclear power plants. Preliminary EPRI studies indicate that the application of these techniques will allow operating nuclear plants to reduce the examination scope of current ISI programs by as much as 60 to 80%, significantly reduce costs, and continue to maintain high nuclear plant safety standards

At What Cost? Examining the Cost Effectiveness of a Universal Social-Emotional Learning Program

Science.gov (United States)

Hunter, Leah J.; DiPerna, James C.; Hart, Susan Crandall; Crowley, Max

2018-01-01

Although implementation of universal social-emotional learning programs is becoming more common in schools, few studies have examined the cost-effectiveness of such programs. As such, the purpose of this article is two fold. First, we provide an overview of cost-effectiveness methods for school-based programs, and second, we share results of a…

Fiscal year 1995 well plugging and abandonment program Y-12 Plant, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1995-09-01

This report is a synopsis of the progress of the well plugging and abandonment program at the Y-12 Plant, Oak Ridge, Tennessee, from September 1994 through August 1995. A total of 67 wells, piezometers, and borings were plugged and abandoned during the period of time covered in this report. All wells and borings were plugged and abandoned if (1) its construction did not meet current standards (substandard construction); (2) it was irreparably damaged or had deteriorated beyond practical repair; (3) its location interfered with or otherwise impeded site operations, construction, or closure activities; or (4) special circumstances existed as defined on a case-by-case basis and approved by the Y-12 Plant Groundwater Protection Program (GWPP) Manager. This summary report contains: general geologic setting of the Y-12 Plant and vicinity; discussion of well plugging and abandonment methods, grouting procedures, and waste management practices (a Waste Management Plan for Drilling Activities is included in Appendix C); summaries of plugging and abandonment activities at each site; and quality assurance/quality control (QA/QC) and health and safety protocols used during the FY 1995 Plugging and Abandonment Program

Fiscal year 1995 well plugging and abandonment program Y-12 Plant, Oak Ridge, Tennessee

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-09-01

This report is a synopsis of the progress of the well plugging and abandonment program at the Y-12 Plant, Oak Ridge, Tennessee, from September 1994 through August 1995. A total of 67 wells, piezometers, and borings were plugged and abandoned during the period of time covered in this report. All wells and borings were plugged and abandoned if (1) its construction did not meet current standards (substandard construction); (2) it was irreparably damaged or had deteriorated beyond practical repair; (3) its location interfered with or otherwise impeded site operations, construction, or closure activities; or (4) special circumstances existed as defined on a case-by-case basis and approved by the Y-12 Plant Groundwater Protection Program (GWPP) Manager. This summary report contains: general geologic setting of the Y-12 Plant and vicinity; discussion of well plugging and abandonment methods, grouting procedures, and waste management practices (a Waste Management Plan for Drilling Activities is included in Appendix C); summaries of plugging and abandonment activities at each site; and quality assurance/quality control (QA/QC) and health and safety protocols used during the FY 1995 Plugging and Abandonment Program.

Bohunice Nuclear Power Plant Safety Upgrading Program

International Nuclear Information System (INIS)

Toth, A.; Fagula, L.

1996-01-01

Bohunice nuclear Power Plant generation represents almost 50% of the Slovak republic electric power production. Due to such high level of commitment to nuclear power in the power generation system, a special attention is given to safe and reliable operation of NPPs. Safety upgrading and operational reliability improvement of Bohunice V-1 NPP was carried out by the Bohunice staff continuously since the plant commissioning. In the 1990 - 1993 period extensive projects were realised. As a result of 'Small Reconstruction of the Bohunice V-1 NPP', the standards of both the nuclear safety and operational reliability have been significantly improved. The implementation of another modifications that will take place gradually during extended refuelling outages and overhauls in the course of 1996 through 1999, is referred to as the Gradual Reconstruction of the Bohunice V-1 Plant. The general goal of the V-1 NPP safety upgrading is the achievement of internationally acceptable level of nuclear safety. Extensive and financially demanding modification process of Bohunice V-2 NPP is likely to be implemented after a completion of the Gradual Reconstruction of the Bohunice V-1 NPP, since the year 1999. With this in mind, a first draft of the strategy of the Bohunice V-2 NPP upgrading program based on Probabilistic Safety assessment consideration was developed. A number of actions with a general effect on Bohunice site safety is evident. All these activities are aimed at reaching the essential objective of Bohunice NPP Management - to ensure a safe, reliable and effective electric energy and heat generation at the Bohunice site. (author)

Introduction to an open source internet-based testing program for medical student examinations.

Science.gov (United States)

Lee, Yoon-Hwan

2009-12-20

The author developed a freely available open source internet-based testing program for medical examination. PHP and Java script were used as the programming language and postgreSQL as the database management system on an Apache web server and Linux operating system. The system approach was that a super user inputs the items, each school administrator inputs the examinees' information, and examinees access the system. The examinee's score is displayed immediately after examination with item analysis. The set-up of the system beginning with installation is described. This may help medical professors to easily adopt an internet-based testing system for medical education.

Environmental justice and factors that influence participation in tree planting programs in Portland, Oregon, U.S

Science.gov (United States)

Geoffrey H. Donovan; John Mills

2014-01-01

Many cities have policies encouraging homeowners to plant trees. For these policies to be effective, it is important to understand what motivates a homeowner’s tree-planting decision. Researchers address this question by identifying variables that influence participation in a tree-planting program in Portland, Oregon, U.S. According to the study, homeowners with street...

46 CFR 71.50-27 - Alternative Hull Examination (AHE) program options: Divers or underwater remotely operated...

Science.gov (United States)

2010-10-01

... 46 Shipping 3 2010-10-01 2010-10-01 false Alternative Hull Examination (AHE) program options...-27 Alternative Hull Examination (AHE) program options: Divers or underwater remotely operated vehicle... operations; (2) Provide permanent hull markings, a temporary grid system of wires or cables spaced not more...

Examinations of fuel debris samples from Three Mile Island Unit 2

International Nuclear Information System (INIS)

Nagase, Fumihisa

2012-01-01

In the accident at the Fukushima-Daiichi nuclear power plants, fuels were molten due to loss of coolant and heat-up of the reactor core. Information on properties of molten fuels (debris) is important to analyze progress of the accident, estimate the status inside the damaged reactors and work on a plan for debris removal. Extensive examinations for properties of debris have been conducted after the accident at the Three Mile Island Unit 2 in 1979. The Japan Atomic Energy Agency conducted a part of the examinations in the frame of the OECD/NEA Three Mile Island Vessel Investigation Program. This issue report outline and main results of the TMI-2 debris examination programs. (author)

Design of a PLC control program for a batch plant : VHS case study 1

NARCIS (Netherlands)

Mader, A.H.; Brinksma, E.; Wupper, H.; Bauer, N.

2001-01-01

This article reports on the systematic design and validation of a PLC control program for the batch plant that has been selected as a case study for the EC project on Verification of Hybrid Systems (VHS). We show how a correct design of the control program can be obtained in an incremental manner

Design of a PLC Control Program for a Batch Plant - VHS Case Study 1

NARCIS (Netherlands)

Mader, Angelika H.; Brinksma, Hendrik; Wupper, H.; Bauer, N.

2001-01-01

This article reports on the systematic design and validation of a PLC control program for the batch plant that has been selected as a case study for the EC project on Verification of Hybrid Systems (VHS). We show how a correct design of the control program can be obtained in an incremental manner

Encapsulation pilot plant of radioactive wastes in thermosetting resins

International Nuclear Information System (INIS)

1982-01-01

The thermosetting resins (polyesters, epoxides) are used to encapsulate the low and intermediate - level radioactive wastes. The testing program concerning the drums produced by the pilot plant of the Chooz nuclear power plant is described. The installation operating is examined while thinking of the industrial application. The production costs are then evaluated

Quality assurance program manual for nuclear power plants. Volume I. Policies

International Nuclear Information System (INIS)

1975-01-01

Policies and procedures are presented which comply with current NRC regulatory requirements and industry codes and standards in effect during the design, procurement, construction, testing, operation, refueling, maintenance, repair and modification activities associated with nuclear power plants. Specific NRC and industry documents that contain the requirements, including the issue dates in effect, are identified in each nuclear power plant's Safety Analysis Report. The requirements established by these documents form the basis for the Consumers Power Quality Assurance Program, which is implemented to control those structures, systems, components and operational safety actions listed in each nuclear power plant's Quality List (Q-List). As additional and revised requirements are issued by the NRC and professional organizations involved in nuclear activities, they will be reviewed for their impact on this manual, and changes will be made where considered necessary

The waste isolation pilot plant regulatory compliance program

International Nuclear Information System (INIS)

Mewhinney, J.A.; Kehrman, R.F.

1996-01-01

The passage of the WIPP Land Withdrawal Act of 1992 (LWA) marked a turning point for the Waste Isolation Pilot Plant (WIPP) program. It established a Congressional mandate to open the WIPP in as short a time as possible, thereby initiating the process of addressing this nation's transuranic (TRU) waste problem. The DOE responded to the LWA by shifting the priority at the WIPP from scientific investigations to regulatory compliance and the completion of prerequisites for the initiation of operations. Regulatory compliance activities have taken four main focuses: (1) preparing regulatory submittals; (2) aggressive schedules; (3) regulator interface; and (4) public interactions

Only in dying, life: programmed cell death during plant development.

Science.gov (United States)

Van Hautegem, Tom; Waters, Andrew J; Goodrich, Justin; Nowack, Moritz K

2015-02-01

Programmed cell death (PCD) is a fundamental process of life. During the evolution of multicellular organisms, the actively controlled demise of cells has been recruited to fulfil a multitude of functions in development, differentiation, tissue homeostasis, and immune systems. In this review we discuss some of the multiple cases of PCD that occur as integral parts of plant development in a remarkable variety of cell types, tissues, and organs. Although research in the last decade has discovered a number of PCD regulators, mediators, and executers, we are still only beginning to understand the mechanistic complexity that tightly controls preparation, initiation, and execution of PCD as a process that is indispensable for successful vegetative and reproductive development of plants. Copyright © 2014 Elsevier Ltd. All rights reserved.

Requirements for auditing of quality assurance programs for nuclear power plants

International Nuclear Information System (INIS)

Anon.

1979-01-01

Requirements and guidance are provided for establishing and implementing a system of internal and external audits of quality assurance programs for nuclear power plants, including the preparation, performance, reporting and follow-up of audits by both the auditing and the audited organizations. This standard is to be used in conjunction with ANSI N45.2

Quality assurance program application during the decommissioning phase of the Shoreham Nuclear Plant

International Nuclear Information System (INIS)

Patch, R.L.

1993-01-01

The application of Quality Assurance (QA) requirements for operating nuclear power plants has evolved over the last 30 years. QA programs started as good management practices and evolved to a process that is implemented integral to very detailed Probabilistic Risk Assessments (PRAs). QA programs for controlling activities during decommissioning of nuclear power plants are still in their infancy. Regulatory guidance is currently being developed, and much of what exists is in the form of draft guidance documents. In determining where to apply QA controls during decommissioning, a series of questions must be asked: Is there an existing regulatory commitment? (Safety related or safety significant activity); Are there any postulated accidents which need to be prevented or mitigated; What are the unacceptable risks; Are there other key factors, such as human performance issues and Industrial Safety Programs, to be considered? Which QA controls are needed and to what extent they should be applied must be evaluated on a case by case basis. How much QA to apply is usually a risk evaluation in itself. Can you afford not to apply a specific control? Can you afford to apply costly and rigorous quality control programs? These questions had to be answered at the Shoreham Nuclear Power Station (SNPS) in order to develop and implement an acceptable and effective Quality Assurance program. Exploring the SNPS open-quotes lessons learnedclose quotes on how to apply a quality assurance program during decommissioning is what the following discussion is about

Introduction to an Open Source Internet-Based Testing Program for Medical Student Examinations

Directory of Open Access Journals (Sweden)

Yoon-Hwan Lee

2009-12-01

Full Text Available The author developed a freely available open source internet-based testing program for medical examination. PHP and Java script were used as the programming language and postgreSQL as the database management system on an Apache web server and Linux operating system. The system approach was that a super user inputs the items, each school administrator inputs the examinees’ information, and examinees access the system. The examinee’s score is displayed immediately after examination with item analysis. The set-up of the system beginning with installation is described. This may help medical professors to easily adopt an internet-based testing system for medical education.

Nuclear power plant life time improvement and management program in Korea

International Nuclear Information System (INIS)

Sung Yull Hong; Ill Seok Jeong; Taek Ho Song

1995-01-01

Korea Electric Power Research Institute (KEPRI) of Korea Electric Power Corporation (KEPCO) has performed a lifetime management of nuclear power plant program (LMNPP), ''Nuclear Power Plant Lifetime Management (PLIM) (I)'', since November 1993, which is a feasibility study of the Kori Unit 1 lifetime management including aging evaluation of the thirteen major components. The results of the PLIM(I) will provide information which is necessary for decision making of the Kori Unit 1 lifetime improvement. A plan of the work scope and schedule for the next phase, PLIM(II), will also be provided by this project. This paper introduced KEPRI's basic strategy of LMNPP, PLIM organization, current status, some interim results of the PLIM(I), and other related programs in Korea. So far, we have done field data survey, systems/structures screening, components prioritization, lifetime evaluation methodology study, and fracture mechanics tests of the Kori Unit 1 reactor pressure vessel surveillance coupons. Currently life assessment of the major components and PLIM economic evaluation of Kori Unit 1 are under way. (author)

A novel approach for studying programmed cell death in living plant tissues

DEFF Research Database (Denmark)

Mark, Christina

to traditional approaches. Future applications of this type of setup could be used for other types of plant tissues such as leaves or germinating embryos for studying the effects of e.g. biotic and abiotic stresses or for screening of compounds for biological effects. Due to the ease of use and many......Programmed cell death (PCD) is a highly regulated process in which cells are killed as part of developmental programmes or as defence mechanisms against pathogens, but the process is less well understood in plant cells compared to animal cells. Reactive oxygen species (ROS) are involved in PCD...... in plants, but the relationship between and mechanisms behind ROS and PCDhas not yet been fully elucidated due to the involvement of complex signalling networks. Elucidation of these mechanisms and signalling pathways will allow manipulation of cell death in plants, which could help to improve yield...

Computer Program Application Study for Newly Constructed Fossil Power Plant Performance Analysis

Energy Technology Data Exchange (ETDEWEB)

Lee, Hyun; Park, Jong Jeng [Korea Electric Power Research Institute, Taejon (Korea, Republic of)

1996-12-31

The power plant is affected in its availability and economy significantly by the equipment degraded gradually as operation continues, which makes it quite important to evaluate the plant performance more accurately and analyze its effects to the plant economy quantitatively. The methodology thereof includes many calculation steps and requires huge man hours and efforts but would produce relatively less precise results than desired. The object of the project first aims to figure out a methodology which can analyze numerically the inherent effects of each equipment on the cycle performance as well as its performance evaluation and which further helps to determine more reasonable investment for the effective plant economy. Another aspect of the project results in the implementation of the methodology which is embodied in the sophisticated computer programs based on the conventional personal computer with the interactive graphic user interface facilities. (author). 44 refs., figs.

Computer Program Application Study for Newly Constructed Fossil Power Plant Performance Analysis

Energy Technology Data Exchange (ETDEWEB)

Lee, Hyun; Park, Jong Jeng [Korea Electric Power Research Institute, Taejon (Korea, Republic of)

1997-12-31

The power plant is affected in its availability and economy significantly by the equipment degraded gradually as operation continues, which makes it quite important to evaluate the plant performance more accurately and analyze its effects to the plant economy quantitatively. The methodology thereof includes many calculation steps and requires huge man hours and efforts but would produce relatively less precise results than desired. The object of the project first aims to figure out a methodology which can analyze numerically the inherent effects of each equipment on the cycle performance as well as its performance evaluation and which further helps to determine more reasonable investment for the effective plant economy. Another aspect of the project results in the implementation of the methodology which is embodied in the sophisticated computer programs based on the conventional personal computer with the interactive graphic user interface facilities. (author). 44 refs., figs.

A lifecycle management program for NPP turbine balance of plant

International Nuclear Information System (INIS)

Manabe, Jun; Yamakami, Katsuhiko; Hiraoka, Satoshi; Kawai, Toshinari

2009-01-01

A lifecycle management program, for turbine balance of plant of light water reactor units which had been operated for more than 20 years but still having a long intended residual life time, was proposed and implemented from the view point of system and equipment supplier. Here would be introduced the program executed for several utilities. The program consists of unit surveillance analyzing both operation and inspection data, degradation assessment for the equipment and prospecting for the future by planning the proper measures for the issues based on both technology and economy. The program is introduced exampling the generating power affected by main steam pressure reduction derived from the scale adhesion and degradation of equipment. Multidisciplinary optimum design for the replacement of the feedwater heaters, one of the items of the planning, is introduced. Additionally would be introduced the new concept maintenance support program, mainly applied to the units already replaced their principal machines and auxiliaries, configured with both the condition based maintenance system monitoring the trend of parameters of a component and the diagnosis of malfunctions ascertaining the equipment by analyzing and synthesizing operation parameters. (author)

Technical evaluation report on the Third 10-year Interval Inservice Inspection Program Plan: Florida Power and Light Company, Turkey Point Nuclear Power Plant, Units 3 and 4 (Docket Numbers 50-250 and 50-251)

International Nuclear Information System (INIS)

Brown, B.W.; Feige, E.J.; Galbraith, S.G.; Porter, A.M.

1995-02-01

This report presents the results of the evaluation of the Turkey Point Nuclear Power Plant, Units 3 and 4, Third 10-Year Interval Inservice Inspection Program Plan, Revision 0, submitted September 9, 1993, including the requests for relief from the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, requirements that the licensee has determined to be impractical. The Turkey Point Nuclear Power Plant, Units 3 and 4, Third 10-Year Interval Inservice Inspection Program Plan is evaluated in Section 2 of this report. The inservice inspection (ISI) program plan is evaluated for (a) compliance with the appropriate edition/addenda of Section XI, (b) acceptability of the examination sample, (c) correctness of the application of system or component examination exclusion criteria, and (d) compliance with ISI-related commitments identified during previous Nuclear Regulatory Commission (NRC) reviews. The requests for relief are evaluated in Section 3 of this report

National Peer Reviews. Self-assessment programs of German nuclear power plants

International Nuclear Information System (INIS)

Grauf, E.

2000-01-01

Preliminary experience seems to indicate that the concept of national peer reviews is a useful tool capable of improving and harmonizing the standards of operation in German plants. However, a final evaluation is possible only after completion of the program, i.e. probably by the end 2000. The internal national peer reviews do not replace existing reviews, such as the WANO peer reviews or the IAEA OSART missions, but rather supplement them. As a major element of self-assessment, they mainly serve to exchange effectively among German plants know-how and experience, to harmonize standards of plant operation, eliminate any weak spots identified, and generally counteract blindness to one's own faults. Whether the envisaged objective of standardized plant operations will be achieved in the end depends very much on the way in which the results of the reviews will be handled. In particular, it will be interesting to see to what extent there is willingness to take on board any recommendations and proposals made and/or introduce what is called good operating practice. (orig.) [de

Material protection control and accounting program activities at the Urals electrochemical integrated plant

International Nuclear Information System (INIS)

McAllister, S.

1997-01-01

The Urals Electrochemical Integrated Plant (UEIP) is the Russian Federation's largest uranium enrichment plant and one of three sites in Russia blending high enriched uranium (HEU) into commercial grade low enriched uranium. UEIP is located approximately 70 km north of Yekaterinburg in the closed city of Novouralsk (formerly Sverdlovsk- 44). DOE's MPC ampersand A program first met with UEIP in June of 1996, however because of some contractual issues the work did not start until September of 1997. The six national laboratories participating in DOE's Material Protection Control and Accounting program are cooperating with UEIP to enhance the capabilities of the physical protection, access control, and nuclear material control and accounting systems. The MPC ampersand A work at UEIP is expected to be completed during fiscal year 2001

Experimental program plan for the Waste Isolation Pilot Plant

Energy Technology Data Exchange (ETDEWEB)

1994-01-01

The US Department of Energy has prepared this Experimental Program Plan for the Waste Isolation Pilot Plant (EPP) to provide a summary of the DOE experimental efforts needed for the performance assessment process for the WIPP, and of the linkages of this process to the appropriate regulations. The Plan encompasses a program of analyses of the performance of the planned repository based on scientific studies, including tests with transuranic waste at laboratory sites, directed at evaluating compliance with the principal regulations governing the WIPP. The Plan begins with background information on the WIPP project, the requirements of the LWA (Land Withdrawal Act), and its objective and scope. It then presents an overview of the regulatory requirements and the compliance approach. Next are comprehensive discussions of plans for compliance with disposal regulations, followed by the SWDA (Solid Waste Disposal Act) and descriptions of activity programs designed to provide information needed for determining compliance. Descriptions and justifications of all currently planned studies designed to support regulatory compliance activities are also included.

Experimental program plan for the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

1994-01-01

The US Department of Energy has prepared this Experimental Program Plan for the Waste Isolation Pilot Plant (EPP) to provide a summary of the DOE experimental efforts needed for the performance assessment process for the WIPP, and of the linkages of this process to the appropriate regulations. The Plan encompasses a program of analyses of the performance of the planned repository based on scientific studies, including tests with transuranic waste at laboratory sites, directed at evaluating compliance with the principal regulations governing the WIPP. The Plan begins with background information on the WIPP project, the requirements of the LWA (Land Withdrawal Act), and its objective and scope. It then presents an overview of the regulatory requirements and the compliance approach. Next are comprehensive discussions of plans for compliance with disposal regulations, followed by the SWDA (Solid Waste Disposal Act) and descriptions of activity programs designed to provide information needed for determining compliance. Descriptions and justifications of all currently planned studies designed to support regulatory compliance activities are also included

TMI-2 Technical Information and Examination Program. 1984 annual report

International Nuclear Information System (INIS)

Hess, C.J.

1985-04-01

In 1984, the US Department of Energy's Technical Information and Examination Program entered its fifth year of research and development work at Three Mile Island Unit 2 (TMI-2) and at the Idaho National Engineering Laboratory and other supporting laboratories. The work concentrated on six major areas: waste immobilization, reactor evaluation, data acquisition, information and industry coordination, core activities, and EPICOR II and waste research and disposition

An overview of the United States Department of Energy Plant Lifetime Improvement Program

International Nuclear Information System (INIS)

Rosinski, S.T.; Clauss, J.M.; Harrison, D.L.

2004-01-01

Since 1985, the U.S. Department of Energy (DOE) has been working with the nuclear industry and the U.S. Nuclear Regulatory Commission (NRC) to establish and demonstrate the option to extend the life of nuclear power plants through the renewal of operating licenses. This paper focuses primarily on DOE'S Plant Lifetime Improvement (PLIM) Program efforts to develop the technical criteria and bases for effective aging management and lifetime improvement for continued operation of nuclear power plants. This paper describes current projects to resolve generic technical issues, including degradation of long-lived components, reactor pressure vessel (RPV) embrittlement management approaches, and analytical methodologies to characterize RPV integrity. (author)

Native plant development and restoration program for the Great Basin, USA

Science.gov (United States)

N. L. Shaw; M. Pellant; P. Olweli; S. L. Jensen; E. D. McArthur

2008-01-01

The Great Basin Native Plant Selection and Increase Project, organized by the USDA Bureau of Land Management, Great Basin Restoration Initiative and the USDA Forest Service, Rocky Mountain Research Station in 2000 as a multi-agency collaborative program (http://www.fs.fed.us/rm/boise/research/shrub/greatbasin.shtml), has the objective of improving the availability of...

Integrated plant safety assessment. Systematic Evaluation Program. La Crosse Boiling Water Reactor. Dairyland Power Cooperative, Docket No. 50-409. Final report

International Nuclear Information System (INIS)

1983-06-01

The Systematic Evaluation Program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to confirm and document their safety. The review provides (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of the La Crosse Boiling Water Reactor, operated by Dairyland Power Cooperative. The La Crosse plant is one of 10 plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review

Integrated Plant Safety Assessment: Systematic Evaluation Program. Yankee Nuclear Power Station, Yankee Atomic Electric Company, Docket No. 50-29. Final report

International Nuclear Information System (INIS)

1983-06-01

The Systematic Evaluation program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to confirm and document their safety. The review provides: (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of Yankee Nuclear Power Station, operated by Yankee Atomic Electric Company. The Yankee plant is one of 10 plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review

Integrated Plant Safety Assessment, Systematic Evaluation Program. Yankee Nuclear Power Station, Yankee Atomic Electric Company, Docket No. 50-29. Draft report

International Nuclear Information System (INIS)

1983-02-01

The Systematic Evaluation Program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to confirm and document their safety. The review provides (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of Yankee Nuclear Power Station, operated by Yankee Atomic Electric Company. The Yankee plant is one of 10 plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review

Environmental program audit: Oak Ridge Gaseous Diffusion Plant, Roane County, Tennessee. Final report

International Nuclear Information System (INIS)

Smith, W.M.; Waller, R.

1985-01-01

An environmental audit of the Oak Ridge Gaseous Diffusion Plant (ORGDP) was conducted by a team of NUS scientists and engineers during the week of June 3 through June 7, 1985. ORGDP is owned by the Department of Energy and operated by Martin-Marietta Energy Systems, Inc. To enrich uranium feedstocks for nuclear fuels. The team evaluated ORGDP in terms of compliance with environmental regulations and DOE Orders, the adequacy of pollution control equipment, the effectiveness of environmental monitoring, and the application of quality control procedures to environmental programs. The audit was conducted by observing operations, inspecting facilities, evaluating analysis and monitoring techniques, reviewing reports and data, and interviewing personnel. Overall, the ORGDP environmental program appears to be well structured and has attempted to address all areas of air, water, and land media likely to be affected by the operations of the facility. The plant management is knowledgeable about environmental concerns and has established clear, well-defined goals to address these areas. An adequate professional staff is available to manage the environmental program

Examining strategies to facilitate vitamin B1 biofortification of plants by genetic engineering

Directory of Open Access Journals (Sweden)

Lucille ePourcel

2013-05-01

Full Text Available Thiamin (vitamin B1 is made by plants and microorganisms but is an essential micronutrient in the human diet. All organisms require it as a cofactor in its form as thiamin pyrophosphate (TPP for the activity of key enzymes of central metabolism. In humans, deficiency is widespread particularly in populations where polished rice is a major component of the diet. Considerable progress has been made on the elucidation of the biosynthesis pathway within the last few years enabling concrete strategies for biofortification purposes to be devised, with a particular focus here on genetic engineering. Furthermore, the vitamin has been shown to play a role in both abiotic and biotic stress responses. The precursors for de novo biosynthesis of thiamin differ between microorganisms and plants. Bacteria use intermediates derived from purine and isoprenoid biosynthesis, whereas the pathway in yeast involves the use of compounds from the vitamin B3 and B6 groups. Plants on the other hand use a combination of the bacterial and yeast pathways and there is subcellular partitioning of the biosynthesis steps. Specifically, thiamin biosynthesis occurs in the chloroplast of plants through the separate formation of the pyrimidine and thiazole moieties, which are then coupled to form thiamin monophosphate (TMP. Phosphorylation of thiamin to form TPP occurs in the cytosol. Therefore, thiamin (or TMP must be exported from the chloroplast to the cytosol for the latter step to be executed. The regulation of biosynthesis is mediated through riboswitches, where binding of the product TPP to the pre-mRNA of a biosynthetic gene modulates expression. Here we examine and hypothesize on genetic engineering approaches attempting to increase the thiamin content employing knowledge gained with the model plant Arabidopsis thaliana. We will discuss the regulatory steps that need to be taken into consideration and can be used a prerequisite for devising such strategies in crop plants.

Optimization of planting pattern plan in Logung irrigation area using linear program

Science.gov (United States)

Wardoyo, Wasis; Setyono

2018-03-01

Logung irrigation area is located in Kudus Regency, Central Java Province, Indonesia. Irrigation area with 2810 Ha of extent is getting water supply from Logung dam. Yet, the utilization of water at Logung dam is not optimal and the distribution of water is still not evenly distributed. Therefore, this study will discuss about the optimization of irrigation water utilization based on the beginning of plant season. This optimization begins with the analysis of hydrology, climatology and river discharge in order to determine the irrigation water needs. After determining irrigation water needs, six alternatives of planting patterns with the different early planting periods, i.e. 1st November, 2nd November, 3rd November, 1st December, 2nd December, and 3rd December with the planting pattern of rice-secondary crop-sugarcane is introduced. It is continued by the analysis of water distribution conducted using linear program assisted by POM-Quantity method for Windows 3 with the reliable discharge limit and the available land area. Output of this calculation are to determine the land area that can be planted based on the type of plant and growing season, and to obtaine the profits of harvest yields. Based on the optimum area of each plant species with 6 alternatives, the most optimum area was obtained at the early planting periods on 3rd December with the production profit of Rp 113.397.338.854,- with the planting pattern of rice / beans / sugarcane-rice / beans / sugarcane-beans / sugarcane.

46 CFR 71.50-31 - Continued participation in the Alternative Hull Examination (AHE) program.

Science.gov (United States)

2010-10-01

... 46 Shipping 3 2010-10-01 2010-10-01 false Continued participation in the Alternative Hull... the Alternative Hull Examination (AHE) program. (a) To continue to participate in the AHE Program, vessel operators must conduct an annual hull condition assessment. At a minimum, vessel operators must...

Comparison of L-system applications towards plant modelling, music rendering and score generation using visual language programming

Science.gov (United States)

Lim, Chen Kim; Tan, Kian Lam; Yusran, Hazwanni; Suppramaniam, Vicknesh

2017-10-01

Visual language or visual representation has been used in the past few years in order to express the knowledge in graphic. One of the important graphical elements is fractal and L-Systems is a mathematic-based grammatical model for modelling cell development and plant topology. From the plant model, L-Systems can be interpreted as music sound and score. In this paper, LSound which is a Visual Language Programming (VLP) framework has been developed to model plant to music sound and generate music score and vice versa. The objectives of this research has three folds: (i) To expand the grammar dictionary of L-Systems music based on visual programming, (ii) To design and produce a user-friendly and icon based visual language framework typically for L-Systems musical score generation which helps the basic learners in musical field and (iii) To generate music score from plant models and vice versa using L-Systems method. This research undergoes a four phases methodology where the plant is first modelled, then the music is interpreted, followed by the output of music sound through MIDI and finally score is generated. LSound is technically compared to other existing applications in the aspects of the capability of modelling the plant, rendering the music and generating the sound. It has been found that LSound is a flexible framework in which the plant can be easily altered through arrow-based programming and the music score can be altered through the music symbols and notes. This work encourages non-experts to understand L-Systems and music hand-in-hand.

Examining the Factors of Licensure Examination for Teachers Performance for Program Strategy Enhancement

Directory of Open Access Journals (Sweden)

Januard D. Dagdag

2017-11-01

Full Text Available Passing the Licensure Examination for Teachers (LET has been the ultimate focus of tertiary education institutions in the Philippines to meet the present demand of local and global parties and communities. Hence, various strategies are conducted to increase the likelihood that the prospect will happen. With this, the current study determines the predictors of LET performance of the 146 Bachelor of Secondary Education graduates that could serve as basis for enhancing program strategies for a better LET rating. A descriptive correlational method through the analysis of registration data on LET, grade weighted average, college admission test (CAT scores, and course audit scores was conducted. Descriptive statistics and correlational tests were employed in the analysis of these data. Results showed that low LET performance is influenced by low performances in academics and admission test, and limited course audit units taken. Admission test performance, however, does not predict LET performance in Major. On the other hand, course audit performance can only forecast licensure exam scores in Major. Hence, to increase LET performance, the program should consider benchmarking from LET performing institutions, choose the right faculty to teach a course, secure the validity and/or reliability of instructional materials and assessment tools with LET competencies, strictly implement the admission and retention policy, and assess regularly the efficacy of the course audit in all areas

Department of Energy's safety and health program for enrichment plant workers is not adequately implemented

International Nuclear Information System (INIS)

Staats, E.B.

1980-01-01

The Department of Energy's (DOE's) program to protect the safety and health of employees at its contractor-operated uranium enrichment plants has not been fully implemented by DOE's Oak Ridge Operations Office. Appraisals and inspections of plant conditions are not as frequent and/or as thorough as required. Instead of independently investigating employee complaints, DOE has delegated this responsibility to the contractor. It is recommended that the Secretary of Energy make sure that Oak Ridge properly conducts inspections and appraisals and investigates and follows up on all employee complaints. He should also take steps to provide increased independence and objectivity in the Oak Ridge Operations Office's safety and health program. Furthermore, the Congress should authorize the Secretary of Energy to institute a program of non-reimbursable penalties and fines for violations of safety and health standards and procedures

Station blackout transient at the Browns Ferry Unit 1 Plant: a severe accident sequence analysis (SASA) program study

International Nuclear Information System (INIS)

Schultz, R.R.

1982-01-01

Operating plant transients are of great interest for many reasons, not the least of which is the potential for a mild transient to degenerate to a severe transient yielding core damage. Using the Browns Ferry (BF) Unit-1 plant as a basis of study, the station blackout sequence was investigated by the Severe Accident Sequence Analysis (SASA) Program in support of the Nuclear Regulatory Commission's Unresolved Safety Issue A-44: Station Blackout. A station blackout transient occurs when the plant's AC power from a comemrcial power grid is lost and cannot be restored by the diesel generators. Under normal operating conditions, f a loss of offsite power (LOSP) occurs [i.e., a complete severance of the BF plants from the Tennessee Valley Authority (TVA) power grid], the eight diesel generators at the three BF units would quickly start and power the emergency AC buses. Of the eight diesel generators, only six are needed to safely shut down all three units. Examination of BF-specific data show that LOSP frequency is low at Unit 1. The station blackout frequency is even lower (5.7 x 10 - 4 events per year) and hinges on whether the diesel generators start. The frequency of diesel generator failure is dictated in large measure by the emergency equipment cooling water (EECW) system that cools the diesel generators

The Savannah River Plant low-level waste segregation program

International Nuclear Information System (INIS)

Wheeler, V.B.

1987-01-01

To extend the life of the Savannah River Plant (SRP) Radioactive Waste Burial Ground, a sitewide program has been implemented to segregate waste that is essentially free of contamination from routine radioactive waste. Much of the low-level waste disposed of as radioactive has no detectable contamination and can be buried in a sanitary landfill. A Landfill Monitoring Facility (LMF) will be constructed at SRP to house the state-of-the-art technology required to provide a final survey on the candidate waste streams that had previously been classified as radioactive. 3 figs

Severe accident management program at Cofrentes Nuclear Power Plant

International Nuclear Information System (INIS)

Borondo, L.; Serrano, C.; Fiol, M.J.; Sanchez, A.

2000-01-01

Cofrentes Nuclear Power Plant (GE BWR/6) has implemented its specific Severe Accident Management Program within this year 2000. New organization and guides have been developed to successfully undertake the management of a severe accident. In particular, the Technical Support Center will count on a new ''Severe Accident Management Team'' (SAMT) which will be in charge of the Severe Accident Guides (SAG) when Control Room Crew reaches the Emergency Operation Procedures (EOP) step that requires containment flooding. Specific tools and training have also been developed to help the SAMT to mitigate the accident. (author)

Training and qualification of nuclear power plant operators

International Nuclear Information System (INIS)

Ohsuga, Y.

2008-01-01

Based on training experiences of the nuclear power plant operators of pressurized water reactors (PWR) at the Nuclear Power Training Center Ltd. (NTC) in Japan, training programs were reviewed referring to US training programs. A systematic approach is deployed to them, which mainly consist of on-the-job training and the NTC training courses to meet the needs of all operators from beginners to experienced veterans according to their experiences and objectives. The NTC training is conducted using the simulators that simulate the nuclear power plant dynamics through the use of computers. The operators trained at the NTC work in the central control room of every PWR power plant. The NTC also carries out the qualification examinations for the shift managers. (T. Tanaka)

Fiscal year 1994 well installation program summary report, Y-12 Plant, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1994-09-01

This report summarizes the well installation activities conducted during the federal fiscal year (FY) 1994 drilling program at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Synopses of monitoring well construction/well development data, well location rationale, geological/hydrological observations, quality assurance/quality control methods, and health and safety monitoring are included. Two monitoring wells were installed and one piezometer installation was attempted, but not completed, during the FY 1994 drilling program. In addition, SAIC provided health and safety and geotechnical oversight for two soil borings in support of the Y-12 Underground Storage Tank (UST) Program. All new monitoring wells were developed by either a 2.0-in. diameter swab rig or by hand bailing until nonspecific indicator parameters (pH and specific conductance) attained steady-state levels. Turbidity levels were lowered, if required, to the extent practicable by continued development beyond a steady-state level of pH and conductance. All well installation was conducted following industry-standard methods and approved procedures in the Environment Surveillance Procedures Quality Control Program (Energy Systems 1988), the Resource Conservation and Recovery Act (RCRA) Groundwater Monitoring Technical Enforcement Guidance Document (EPA 1986), and Guidelines for Installation of Monitor Wells at the Y-12 Plant (Geraghty and Miller 1985). Health and safety monitoring and field screening of drilling returns and development waters were conducted in accordance with approved Martin Marietta Energy Systems, Inc. (Energy Systems) guidelines. All of the monitoring wells installed during FY 1994 at the Y-12 Plant were of screened construction

The microcomputer scientific software series 7: data recorder program for storing plant lists and calculating synecological coordinates.

Science.gov (United States)

Kevin Nimerfro; Gary Brand

1993-01-01

Describes a computer program designed for data recorders that stores plant lists and computes synecological coordinates from the stored list. The method of synecological coordinates uses plant species present on a site to quantify the site`s environmental factors.

An Examination of New Counselor Mentor Programs

Science.gov (United States)

Bass, Erin; Gardner, Lauren; Onwukaeme, Chika; Revere, Dawn; Shepherd, Denise; Parrish, Mark S.

2013-01-01

An analysis of current new counselor mentor programs reveals the need for such programs, but information regarding established programs is limited. A review of the literature addresses program characteristics and data obtained from existing mentor program participants. An overview of four programs explaining the framework outlined for mentoring…

Examining Sense of Community among Medical Professionals in an Online Graduate Program

Directory of Open Access Journals (Sweden)

Kadriye O. Lewis

2015-01-01

Full Text Available As the number of online degree programs continues to grow, one of the greatest challenges is developing a sense of community among learners who do not convene at the same time and place. This study examined the sense of community among medical professionals in an online graduate program for healthcare professionals. We took the sample from a fully online program delivered jointly by a state university and a local children's hospital in the Midwest. We administered Rovai's Classroom Community Survey with 11 additional demographic questions. We also utilized online interviews to further explore students’ understanding of sense of community. A bi-factor model was fitted to the online sense of community survey data. Using multivariate analysis of variance (MANOVA and univariate analysis of variance (ANOVA we identified potential group differences. The qualitative data were analyzed thematically in a recursive and iterative process. Study results suggested that a dominant factor existed: sense of community with two sub-domain factors including sense of learning and sense of connectedness. No significant differences in sense of community with regard to gender, native language, or area of medical practice were detected. However, results showed a difference in sense of community between the three courses examined. This study is the first to examine the sense of community among online medical professionals. Since our findings are in contrast to those of previous studies, this opens the door to additional studies around the possible differences between the community characteristics and needs of medical professionals as online students.

Aquatic Plant Control Research Program

National Research Council Canada - National Science Library

Cofrancesco, Alfred

1998-01-01

.... This search for natural plant enemies (insects and fungal pathogens) has led researchers to the native ranges of noxious aquatic plants, located throughout the continents of Africa, Asia, Europe, and Australia...

Interaction of electromagnetic pulse with commercial nuclear-power-plant systems

Energy Technology Data Exchange (ETDEWEB)

Ericson, D.M. Jr.; Strawe, D.F.; Sandberg, S.J.; Jones, V.K.; Rensner, G.D.; Shoup, R.W.; Hanson, R.J.; Williams, C.B.

1983-02-01

This study examines the interaction of the electromagnetic pulse from a high altitude nuclear burst with commercial nuclear power plant systems. The potential vulnerability of systems required for safe shutdown of a specific nuclear power plant are explored. EMP signal coupling, induced plant response and component damage thresholds are established using techniques developed over several decades under Defense Nuclear Agency sponsorship. A limited test program was conducted to verify the coupling analysis technique as applied to a nuclear power plant. The results are extended, insofar as possible, to other nuclear plants.

Interaction of electromagnetic pulse with commercial nuclear-power-plant systems

International Nuclear Information System (INIS)

Ericson, D.M. Jr.; Strawe, D.F.; Sandberg, S.J.; Jones, V.K.; Rensner, G.D.; Shoup, R.W.; Hanson, R.J.; Williams, C.B.

1983-02-01

This study examines the interaction of the electromagnetic pulse from a high altitude nuclear burst with commercial nuclear power plant systems. The potential vulnerability of systems required for safe shutdown of a specific nuclear power plant are explored. EMP signal coupling, induced plant response and component damage thresholds are established using techniques developed over several decades under Defense Nuclear Agency sponsorship. A limited test program was conducted to verify the coupling analysis technique as applied to a nuclear power plant. The results are extended, insofar as possible, to other nuclear plants

Oregon state university's advanced plant experiment (APEX) AP1000 integral facility test program

International Nuclear Information System (INIS)

Reyes, J.N.; Groome, J.T.; Woods, B.G.; Young, E.; Abel, K.; Wu, Q.

2005-01-01

Oregon State University (OSU) has recently completed a three year study of the thermal hydraulic behavior of the Westinghouse AP1000 passive safety systems. Eleven Design Basis Accident (DBA) scenarios, sponsored by the U.S. Department of Energy (DOE) with technical support from Westinghouse Electric, were simulated in OSU's Advanced Plant Experiment (APEX)-1000. The OSU test program was conducted within the purview of the requirements of 10CFR50 Appendix B, NQA-1 and 10 CFR 21 and the test data was used to provide benchmarks for computer codes used in the final design approval of the AP1000. In addition to the DOE certification testing, OSU conducted eleven confirmatory tests for the U.S. Nuclear Regulatory Commission. This paper presents the test program objectives, a description of the APEX-1000 test facility and an overview of the test matrix that was conducted in support of plant certification. (authors)

Fuel Gas Demonstration Plant Program. Volume I. Demonstration plant

Energy Technology Data Exchange (ETDEWEB)

1979-01-01

The objective of this project is for Babcock Contractors Inc. (BCI) to provide process designs, and gasifier retort design for a fuel gas demonstration plant for Erie Mining Company at Hoyt Lake, Minnesota. The fuel gas produced will be used to supplement natural gas and fuel oil for iron ore pellet induration. The fuel gas demonstration plant will consist of five stirred, two-stage fixed-bed gasifier retorts capable of handling caking and non-caking coals, and provisions for the installation of a sixth retort. The process and unit design has been based on operation with caking coals; however, the retorts have been designed for easy conversion to handle non-caking coals. The demonstration unit has been designed to provide for expansion to a commercial plant (described in Commercial Plant Package) in an economical manner.

Plant and Industry Experience. MAS-122. Waste Isolation Division (WID). Management and Supervisor Training (MAST) Program.

Science.gov (United States)

Westinghouse Electric Corp., Carlsbad, NM.

This learning module, which is part of a management and supervisor training program for managers and supervisors employed at the Department of Energy's Waste Isolation Division, is designed to prepare trainees to use plant and industry experience to improve plant safety and reliability. The following topics are covered in the module's individual…

Development of intelligent database program for PSI/ISI data management of nuclear power plant

International Nuclear Information System (INIS)

Um, Byong Guk; Park, Un Su; Park, Ik Keun; Park, Yun Won; Kang, Suk Chul

1998-01-01

An intelligent database program has been developed under fully compatible with windows 95 for the construction of total support system and the effective management of Pre-/In-Service Inspection data. Using the database program, it can be executed the analysis and multi-dimensional evaluation of the defects detected during PSI/ISI in the pipe and the pressure vessel of the nuclear power plants. And also it can be used to investigate the NDE data inspected repetitively and the contents of treatment, and to offer the fundamental data for application of evaluation data related to Fracture Mechanics Analysis(FMA). Furthermore, the PSI/ISI database loads and material properties can be utilized to secure the higher degree of safety, integrity, reliability, and life-prediction of components and systems in nuclear power plant.

Examining Variations in Fourth-Grade Children's Participation in School Breakfast and Lunch Programs by Student and Program Demographics

Science.gov (United States)

Guinn, Caroline H.; Baxter, Suzanne Domel; Finney, Christopher J.; Hitchcock, David B.

2013-01-01

Purpose/Objectives: Analyses were conducted to examine variations in fourth-grade children's participation in school-breakfast and school-lunch programs by weekday, month, socioeconomic status, absenteeism, gender, and school-breakfast location. Methods: Fourth-grade children were participants in a dietary-reporting validation study during either…

Operation of Wastewater Treatment Plants: A Field Study Training Program. Volume I. Second Edition.

Science.gov (United States)

California State Univ., Sacramento. Dept. of Civil Engineering.

This manual was prepared by experienced wastewater collection system workers to provide a home study course to develop new qualified workers and expand the abilities of existing workers. This volume is directed primarily towards entry-level operators and the operators of ponds, package plants, or small treatment plants. Ten chapters examine the…

N Reactor Production Assurance Program blance of plant evaluation: report of findings and conclusions

International Nuclear Information System (INIS)

Hurd, E.N.; Bitten, E.J.

1985-03-01

Fourteen tasks were identified by UNC Nuclear Industries for evaluating the life expectancy of N Reactor structures, systems and components in the Balance of Plant portion of the Production Assurance Program. A Westinghouse Hanford Company (WHC) evaluation team was assigned to each of these fourteen tasks. A uniform set of criteria was used by all teams in evaluating the problems that may be encountered during the extended plant operating lifetime. The overall conclusion is that extended life to those Balance of Plant components and systems studied can be achieved. Problems with the potential for compromising that conclusion are identified, and feasible solutions are provided

The fusarium mycotoxin deoxynivalenol can inhibit plant apoptosis-like programmed cell death.

Directory of Open Access Journals (Sweden)

Mark Diamond

Full Text Available The Fusarium genus of fungi is responsible for commercially devastating crop diseases and the contamination of cereals with harmful mycotoxins. Fusarium mycotoxins aid infection, establishment, and spread of the fungus within the host plant. We investigated the effects of the Fusarium mycotoxin deoxynivalenol (DON on the viability of Arabidopsis cells. Although it is known to trigger apoptosis in animal cells, DON treatment at low concentrations surprisingly did not kill these cells. On the contrary, we found that DON inhibited apoptosis-like programmed cell death (PCD in Arabidopsis cells subjected to abiotic stress treatment in a manner independent of mitochondrial cytochrome c release. This suggested that Fusarium may utilise mycotoxins to suppress plant apoptosis-like PCD. To test this, we infected Arabidopsis cells with a wild type and a DON-minus mutant strain of F. graminearum and found that only the DON producing strain could inhibit death induced by heat treatment. These results indicate that mycotoxins may be capable of disarming plant apoptosis-like PCD and thereby suggest a novel way that some fungi can influence plant cell fate.

An Examination of Peer-Delivered Parenting Skills Programs Across New York State.

Science.gov (United States)

Acri, Mary C; Craig, Nancy; Adler, Josh

2018-03-24

Peers are an important adjunct to the public mental health service system, and are being increasingly utilized across the country as a cost-effective solution to workforce shortages. Despite the tremendous growth of peer-delivered support over the past two decades, it has only been within the past few years that peer programs have been the subject of empirical inquiry. The purpose of this study was to examine the prevalence and characteristics of peer-delivered parenting programs across the New York State public mental health service system. We surveyed 46 family peer organizations across New York State regarding their delivery of structured peer-delivered parenting programs. Thirty-four (76%) completed the questionnaire, and of them, 18 (53%) delivered a parenting program. Subsequent interviews with seven of the 18 organizations revealed peer organizations had been delivering eight unique parenting programs for upwards of two decades. Additionally, organizations offered multiple supports to families to participate. Training, supervision, and issues around fidelity are discussed, as well as the implications of this study for states utilizing a peer workforce.

A nuclear power plant operator's view on the effects of ICRP recommendation 26 upon his radiation protection program

International Nuclear Information System (INIS)

Selleslagh, E.

1981-01-01

The effects of ICRP recommendation 26 on rules to be implemented by nuclear power plant operators in their radiation protection program, are examined from various points of view: legal and para-legal aspects such as implementation by local authorities and interference with the regulatory process, external and internal irradiation control and limitation, ALARA and cost-benefit aspects, and the record keeping and monitoring requirements. It appears that certain parts of ICRP 26 were not retained by Euratom and thus have little chance of appearing in modified European law. Nonetheless, they are applied through licensing practices. ICRP 26 itself either confirms existing practice, which was often more conservative than law, or relaxes limits, and provides a more logical context for non-whole body exposures. ALARA-rules and practices cause an additional administrative burden, but this already existed and provides useful data for the plant management. The problem of ''zero dose'' and of converting in vivo measurements to dose in case the intakes are unknown, are addressed briefly. It is concluded that ICRP 26 brings no real changes for radiation protection in nuclear power plants, except maybe some increased flexibility, and that the operators are pretty happy with it, but less so with the way it is being imposed on them. (author)

United States Department of Agriculture-Agricultural Research Service research programs on microbes for management of plant-parasitic nematodes.

Science.gov (United States)

Meyer, Susan L F

2003-01-01

Restrictions on the use of conventional nematicides have increased the need for new methods of managing plant-parasitic nematodes. Consequently, nematode-antagonistic microbes, and active compounds produced by such organisms, are being explored as potential additions to management practices. Programs in this area at the USDA Agricultural Research Service investigate applied biocontrol agents, naturally occurring beneficial soil microbes and natural compounds. Specific research topics include use of plant growth-promoting rhizobacteria and cultural practices for management of root-knot and ring nematodes, determination of management strategies that enhance activity of naturally occurring Pasteuria species (bacterial obligate parasites of nematodes), studies on interactions between biocontrol bacteria and bacterial-feeding nematodes, and screening of microbes for compounds active against plant-parasitic nematodes. Some studies involve biocontrol agents that are active against nematodes and soil-borne plant-pathogenic fungi, or combinations of beneficial bacteria and fungi, to manage a spectrum of plant diseases or to increase efficacy over a broader range of environmental conditions. Effective methods or agents identified in the research programs are investigated as additions to existing management systems for plant-parasitic nematodes.

Integrated plant safety assessment: Systematic Evaluation Program, San Onofre Nuclear Generating Station, Unit 1 (Docket No. 50-206): Final report

International Nuclear Information System (INIS)

1986-12-01

The Systematic Evaluation Program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to reconfirm and document their safety. The review provides: (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues; (2) a basis for deciding on how these differences should be resolved in an integrated plant review; and (3) a documented evaluation of plant safety. This report documents the review of San Onofre Nuclear Generating Station, Unit 1, operated by Southern California Edison Company. The San Onofre plant is one of ten plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review. This report will be one of the bases in considering the issuance of a full-term operating license in place of the existing provisional operating license. This report also addresses the comments and recommendations made by the Advisory Committee on Reactor Safeguards in connection with its review of the draft report issued in April 1985

San Diego Multiple Species Conservation Program (MSCP) Rare Plant Monitoring Review and Revision

Science.gov (United States)

McEachern, Kathryn; Pavlik, Bruce M.; Rebman, Jon; Sutter, Rob

2007-01-01

Introduction The San Diego Multiple Species Conservation Program (MSCP) was developed for the conservation of plants and animals in the south part of San Diego County, under the California Natural Community Conservation Planning Act of 1991 (California Department of Fish and Game) and the Federal Endangered Species Act of 1973, as amended (16 U.S. Code 1531-1544.) The Program is on the leading edge of conservation, as it seeks to both guide development and conserve at-risk species with the oversight of both State and Federal agencies. Lands were identified for inclusion in the MSCP based on their value as habitat for at-risk plants or plant communities (Natural Community Conservation Planning, 2005). Since its inception in the mid-1990s the Program has protected over 100,000 acres, involving 15 jurisdictions and the U.S. Fish and Wildlife Service (USFWS) and California Department of Fish and Game (CDFG) in the conservation of 87 taxa. Surveys for covered species have been conducted, and management and monitoring have been implemented at some high priority sites. Each jurisdiction or agency manages and monitors their conservation areas independently, while collaborating regionally for long-term protection. The San Diego MSCP is on the forefront of conservation, in one of the most rapidly growing urban areas of the country. The planning effort that developed the MSCP was state-of-the-art, using expert knowledge, spatial habitat modeling, and principles of preserve design to identify and prioritize areas for protection. Land acquisition and protection are ahead of schedule for most jurisdictions. Surveys have verified the locations of many rare plant populations known from earlier collections, and they provide general information on population size and health useful for further conservation planning. Management plans have been written or are in development for most MSCP parcels under jurisdictional control. Several agencies are developing databases for implementation

Examining the Feasibility and Effectiveness of a Community-Based Obesity Prevention Program

Science.gov (United States)

Cotter, Elizabeth W.; Bera, Victoria; Elsemore, Johanna; Snelling, Anastasia

2018-01-01

Background: Latinos in the United States are at heightened risk for obesity and health disparities, yet community-based interventions to promote health are limited. Purpose: This research examined the feasibility and efficacy of a culturally relevant obesity prevention program (Vivir Sano), which included stress reduction and behavioral lifestyle…

Assessment of Primary Representational Systems with Neurolinguistic Programming: Examination of Preliminary Literature.

Science.gov (United States)

Dorn, Fred J.; And Others

1983-01-01

Reviews the inconsistent findings of studies on neurolinguistic programing and recommends some areas that should be examined to verify various claims. Discusses methods of assessing client's primary representational systems, including predicate usage and eye movements, and suggests that more reliable methods of assessing PRS must be found. (JAC)

Martin Marietta Paducah Gaseous Diffusion Plant comprehensive earthquake emergency management program

International Nuclear Information System (INIS)

1990-01-01

Recognizing the value of a proactive, integrated approach to earthquake preparedness planning, Martin Marietta Energy Systems, Inc. initiated a contract in June 1989 with Murray State University, Murray, Kentucky, to develop a comprehensive earthquake management program for their Gaseous Diffusion Plant in Paducah, Kentucky. The overall purpose of the program is to mitigate the loss of life and property in the event of a major destructive earthquake. The program includes four distinct (yet integrated) components: an emergency management plan, with emphasis on the catastrophic earthquake; an Emergency Operations Center Duty Roster Manual; an Integrated Automated Emergency Management Information System (IAEMIS); and a series of five training program modules. The PLAN itself is comprised of four separate volumes: Volume I -- Chapters 1--3; Volume II -- Chapters 4--6, Volume III -- Chapter 7, and Volume IV -- 23 Appendices. The EOC Manual (which includes 15 mutual aid agreements) is designated as Chapter 7 in the PLAN and is a ''stand alone'' document numbered as Volume III. This document, Volume I, provides an introduction, summary and recommendations, and the emergency operations center direction and control

Martin Marietta Paducah Gaseous Diffusion Plant comprehensive earthquake emergency management program

International Nuclear Information System (INIS)

1990-01-01

Recognizing the value of a proactive, integrated approach to earthquake preparedness planning, Martin Marietta Energy Systems, Inc. initiated a contract in June 1989 with Murray State University, Murray, Kentucky, to develop a comprehensive earthquake management program for their Gaseous Diffusion Plant in Paducah, Kentucky (PGDP -- Subcontract No. 19P-JV649V). The overall purpose of the program is to mitigate the loss of life and property in the event of a major destructive earthquake. The program includes four distinct (yet integrated) components: (1) an emergency management plan with emphasis on the catas trophic earthquake; (2) an Emergency Operations Center Duty Roster Manual; (3) an Integrated Automated Emergency Management Information System (IAEMIS); and (4) a series of five training program modules. The PLAN itself is comprised of four separate volumes: Volume I -- Chapters 1--3; Volume II -- Chapters 4--6; Volume III -- Chapter 7; and Volume IV -- 23 Appendices. The EOC Manual (which includes 15 mutual aid agreements) is designated as Chapter 7 in the PLAN and is this document numbered as Volume III

Attributes of Candidates Passing the ABS Certifying Examination on the First Attempt-Program Directors׳ Perspective.

Science.gov (United States)

Sheikh, Mohd Raashid; Hulme, Michael

2016-01-01

The American Board of Surgery Certifying Examination (CE) is a pivotal event in a surgeon's career development, as it is the last challenge before achieving Board certification. First-time pass rate on the CE is one of the key metrics of surgery residency programs. The overall pass rate on the CE has declined significantly in recent years. The goal of this study was the identification of attributes of general surgery residents that are associated with passing the CE at the first attempt. The modified Delphi process was used to survey general surgery program directors. The study was conducted in 2 rounds in the interest of time available for surgical education research fellowship project. All 259 program directors were contacted in each round of surveys. In all, 49 (19%) responded to the first round and 54 (21%) responded to the second round of survey. The characteristics of a successful resident on CE include confidence, self-motivation, sound knowledge base, strong performance on the Board's training examination (American Board of Surgery In-Training Examination), and mock orals, and good communication skills. Postgraduate years 4 and 5 are the most likely resident levels at which failure could be predicted. Copyright © 2015 Association of Program Directors in Surgery. Published by Elsevier Inc. All rights reserved.

Operating experience and systems analysis at Trillo NPP: A program intended for systematic review of plant safety systems to assess design basis requirements compliance

International Nuclear Information System (INIS)

Vega, R. de la

1996-01-01

The program was defined to apply to all plant safety systems and/or systems included in plant Technical Specifications. The goal of the program was to ensure, by systematic design, construction, and commissioning review, the adequacy of safety systems, structures and components to fulfill their safety functions. Also, as a result of the program, it was established that a complete, unambiguous, systematic, design basis definition shall take place. And finally, a complete documental review of the plant design shall result from the program execution

What about improving the productivity of electric power plants

International Nuclear Information System (INIS)

Lawroski, H.; Knecht, P.D.; Prideaux, D.L.; Zahner, R.R.

1976-01-01

The FEA in April of 1974 established an Interagency Task Group on Power Plant Reliability, which was charged with the broad objective of improving the productivity of existing and planned large fossil-fueled and nuclear power plants. It took approximately 11 months for the task force to publish a report, ''Report on Improving the Productivity of Electrical Power Plants'' (FEA-263-G), a detailed analysis and comparison of successful and below-average-performance power plants. The Nuclear Service Corp. portion of this study examined four large central-station power plants: two fossil (coal) and two nuclear plants. Only plants with electrical generation capacities greater than 400 MWe were considered. The study included the following: staff technical skill, engineering support, QA program, plant/corporate coordination, operation philosophy, maintenance programs, federal/state regulations, network control, and equipment problems. Personnel were interviewed, and checklists providing input from some 21 or more plant and corporate personnel of each utility were utilized. Reports and other documentation were also reviewed. It was recognized early that productivity is closely allied to technical skills and positive motivation. For this reason, considerable attention was given to people in this study

Lace plant ethylene receptors, AmERS1a and AmERS1c, regulate ethylene-induced programmed cell death during leaf morphogenesis.

Science.gov (United States)

Rantong, Gaolathe; Evans, Rodger; Gunawardena, Arunika H L A N

2015-10-01

The lace plant, Aponogeton madagascariensis, is an aquatic monocot that forms perforations in its leaves as part of normal leaf development. Perforation formation occurs through developmentally regulated programmed cell death (PCD). The molecular basis of PCD regulation in the lace plant is unknown, however ethylene has been shown to play a significant role. In this study, we examined the role of ethylene receptors during perforation formation. We isolated three lace plant ethylene receptors AmERS1a, AmERS1b and AmERS1c. Using quantitative PCR, we examined their transcript levels at seven stages of leaf development. Through laser-capture microscopy, transcript levels were also determined in cells undergoing PCD and cells not undergoing PCD (NPCD cells). AmERS1a transcript levels were significantly lower in window stage leaves (in which perforation formation and PCD are occurring) as compared to all other leaf developmental stages. AmERS1a and AmERS1c (the most abundant among the three receptors) had the highest transcript levels in mature stage leaves, where PCD is not occurring. Their transcript levels decreased significantly during senescence-associated PCD. AmERS1c had significantly higher transcript levels in NPCD compared to PCD cells. Despite being significantly low in window stage leaves, AmERS1a transcripts were not differentially expressed between PCD and NPCD cells. The results suggested that ethylene receptors negatively regulate ethylene-controlled PCD in the lace plant. A combination of ethylene and receptor levels determines cell fate during perforation formation and leaf senescence. A new model for ethylene emission and receptor expression during lace plant perforation formation and senescence is proposed.

Los Alamos Nuclear Plant Analyzer: an interactive power-plant simulation program

International Nuclear Information System (INIS)

Steinke, R.; Booker, C.; Giguere, P.; Liles, D.R.; Mahaffy, J.H.; Turner, M.R.

1984-01-01

The Nuclear Plant Analyzer (NPA) is a computer-software interface for executing the TRAC or RELAP5 power-plant systems codes. The NPA is designed to use advanced supercomputers, long-distance data communications, and a remote workstation terminal with interactive computer graphics to analyze power-plant thermal-hydraulic behavior. The NPA interface simplifies the running of these codes through automated procedures and dialog interaction. User understanding of simulated-plant behavior is enhanced through graphics displays of calculational results. These results are displayed concurrently with the calculation. The user has the capability to override the plant's modeled control system with hardware-adjustment commands. This gives the NPA the utility of a simulator, and at the same time, the accuracy of an advanced, best-estimate, power-plant systems code for plant operation and safety analysis

Nuclear Plant Analyzer: an interactive TRAC/RELAP Power-Plant Simulation Program

International Nuclear Information System (INIS)

Steinke, R.; Booker, C.; Giguere, P.; Liles, D.; Mahaffy, J.; Turner, M.; Wiley, R.

1984-01-01

The Nuclear Plant Analyzer (NPA) is a computer-software interface for executing the TRAC or RELAP5 power-plant systems codes. The NPA is designed to use advanced supercomputers, long-distance data communications, and a remote workstation terminal with interactive computer graphics to analyze power-plant thermal-hydraulic behavior. The NPA interface simplifies the running of these codes through automated procedures and dialog interaction. User understanding of simulated-plant behavior is enhanced through graphics displays of calculational results. These results are displayed concurrently with the calculation. The user has the capability to override the plant's modeled control system with hardware adjustment commands. This gives the NPA the utility of a simulator, and at the same time, the accuracy of an advanced, best-estimate, power-plant systems code for plant operation and safety analysis

Y-12 Plant Groundwater Protection Program Groundwater and Surface Water sampling and Analysis Plan for Calendar Year 2000

International Nuclear Information System (INIS)

1999-01-01

This plan provides a description of the groundwater and surface water quality monitoring activities planned for calendar year (CY) 2000 at the U.S. Department of Energy (DOE) Y-12 Plant that will be managed by tie Y-12 Plant Groundwater Protection Program (GWPP). Groundwater and surface water monitoring during CY 2000 will be performed in three hydrogeologic regimes at the Y-12 Plant: the Bear Creek Hydrogeologic Regime (Bear Creek Regime), the Upper East Fork Poplar Creek Hydrogeologic Regime (East Fork Regime), and the Chestnut Ridge Hydrogeologic Regime (Chestnut Ridge Regime). The Bear Creek and East Fork regimes are located in Bear Creek Valley, and the Chestnut Ridge Regime is located south of the Y-12 Plant (Figure 1). Groundwater and surface water monitoring performed under the auspices of the Y-12 Plant GWPP during CY 2000 will comply with: Tennessee Department of Environment and Conservation regulations governing detection monitoring at nonhazardous Solid Waste Disposal Facilities (SWDF); and DOE Order 5400.1 surveillance monitoring and exit pathway/perimeter monitoring. Some of the data collected for these monitoring drivers also will be used to meet monitoring requirements of the Integrated Water Quality Program, which is managed by Bechtel Jacobs Company LLC. Data from five wells that are monitored for SWDF purposes in the Chestnut Ridge Regime will be used to comply with requirements specified in the Resource Conservation and Recovery Act post closure permit regarding corrective action monitoring. Modifications to the CY 2000 monitoring program may be necessary during implementation. Changes in regulatory or programmatic requirements may alter the analytes specified for selected monitoring wells, or wells could be added or removed from the planned monitoring network. All modifications to the monitoring program will be approved by the Y-12 Plant GWPP manager and documented as addenda to this sampling and analysis plan

Integrated-plant-safety assessment Systematic Evaluation Program. Dresden Nuclear Power Station, Unit 2, Commonwealth Edison Company, Docket No. 50-237

International Nuclear Information System (INIS)

1982-10-01

The Systematic Evaluation Program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to reconfirm and document their safety. The review provides: (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues; (2) a basis for deciding on how these differences should be resolved in an integrated plant review; and (3) a documented evaluation of plant safety. This report documents the review of Dresden Nuclear Generating Station, Unit 2 owned and operated by the Commonwealth Edison Company and located in Grundy County, Illinois. Dresden Unit 2 is one of ten plants reviewed under Phase II of this program, which indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review. It is expected that this report will be one of the bases in considering the issuance of a full-term operating license in place of the existing provisional operating license

Nuclear Plant Aging Research (NPAR) program plan: Components, systems, and structures

International Nuclear Information System (INIS)

1987-09-01

The nuclear plant aging research described in this plan is intended to resolve issues related to the aging and service wear of equipment and systems and major components at commercial reactor facilities and their possible impact on plant safety. Emphasis has been placed on identification and characterization of the mechanisms of material and component degradation during service and evaluation of methods of inspection, surveillance, condition monitoring, and maintenance as means of mitigating such effects. Specifically, the goals of the program are as follows: (1) to identify and characterize aging and service wear effects which, if unchecked, could cause degradation of equipment, a systems, and major components and thereby impair plant safety; (2) to identify methods of inspection, surveillance, and monitoring, or of evaluating residual life of equipment, systems, and major components, which will ensure timely detection of significant aging effects prior to loss of safety function; and (3) to evaluate the effectiveness of storage, maintenance, repair, and replacement practices in mitigating the rate and extent of degradation caused by aging and service wear

Fiscal year 1993 well plugging and abandonment program, Y-12 Plant, Oak Ridge, Tennessee

Energy Technology Data Exchange (ETDEWEB)

1993-09-01

This report is a synopsis of the progress of the well plugging and abandonment program at the Y-12 Plant, Oak Ridge, Tennessee, from December 1992 through August 20, 1993. A total of 70 wells and borings were plugged and abandoned during the period of time covered in this report. All wells and borings were plugged and abandoned in accordance with the Monitoring Well Plugging and Abandonment Plan for the US Department of Energy, Y-12 Plant, Oak Ridge, Tennessee (HSW, Inc. 1991).

Next Generation Nuclear Plant Materials Research and Development Program Plan, Revision 4

Energy Technology Data Exchange (ETDEWEB)

G.O. Hayner; R.L. Bratton; R.E. Mizia; W.E. Windes; W.R. Corwin; T.D. Burchell; C.E. Duty; Y. Katoh; J.W. Klett; T.E. McGreevy; R.K. Nanstad; W. Ren; P.L. Rittenhouse; L.L. Snead; R.W. Swindeman; D.F. Wlson

2007-09-01

DOE has selected the High Temperature Gas-cooled Reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production. It will have an outlet gas temperature in the range of 950°C and a plant design service life of 60 years. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed reactor and use low-enriched uranium, TRISO-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. Some of the general and administrative aspects of the R&D Plan include: • Expand American Society of Mechanical Engineers (ASME) Codes and American Society for Testing and Materials (ASTM) Standards in support of the NGNP Materials R&D Program. • Define and develop inspection needs and the procedures for those inspections. • Support selected university materials related R&D activities that would be of direct benefit to the NGNP Project. • Support international materials related collaboration activities through the DOE sponsored Generation IV International Forum (GIF) Materials and Components (M&C) Project Management Board (PMB). • Support document review activities through the Materials Review Committee (MRC) or other suitable forum.

Design and analysis of aquatic monitoring programs at nuclear power plants

International Nuclear Information System (INIS)

McKenzie, D.H.; Kannberg, L.D.; Gore, K.L.; Arnold, E.M.; Watson, D.G.

1977-11-01

This report addresses some of the problems of designing, conducting, and analyzing aquatic environmental monitoring programs for impact assessment of nuclear power plants. The concepts discussed are applicable to monitoring the effects of chemical, radioactive, or thermal effluents. The concept of control and treatment station pairs is the fundamental basis for the experimental method proposed. This concept is based on the hypothesis that the relationship between the two stations forming the pair can be estimated from the preoperational period and that this relationship holds during the operational period. Any changes observed in this relationship during the operational period are assumed to be the result of the power plant impacts. Thus, it is important that station pairs are selected so it can be assumed that they respond to natural environmental changes in a manner that maintains that relationship. The major problem in establishing the station pairs will be the location of the control station. The universal heterogeneity in the environment will prevent the establishment of identical station pairs. The requirement that the control station remain unaffected by the operation of the power plant dictates a spacial separation with its associated differences in habitat. Thus, selection of the control station will be based upon balancing the following two criteria: (1) far enough away from the plant site to be beyond the plant influence, and (2) close enough to the treatment station that the biological communities will respond to natural environmental changes consistently in the same manner

Design and Assessment of an Associate Degree-Level Plant Operations Technical Education Program

Science.gov (United States)

Selwitz, Jason Lawrence

2017-01-01

Research was undertaken to develop and evaluate an associate degree-level technical education program in Plant Operations oriented towards training students in applied science, technology, engineering, and mathematics (STEM) skills and knowledge relevant to a spectrum of processing industries. This work focuses on four aspects of the curriculum…

Quality assurance of analytical, scientific, and design computer programs for nuclear power plants

International Nuclear Information System (INIS)

1994-06-01

This Standard applies to the design and development, modification, documentation, execution, and configuration management of computer programs used to perform analytical, scientific, and design computations during the design and analysis of safety-related nuclear power plant equipment, systems, structures, and components as identified by the owner. 2 figs

Quality assurance of analytical, scientific, and design computer programs for nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-06-01

This Standard applies to the design and development, modification, documentation, execution, and configuration management of computer programs used to perform analytical, scientific, and design computations during the design and analysis of safety-related nuclear power plant equipment, systems, structures, and components as identified by the owner. 2 figs.

Examining Volunteer Motivations and Recruitment Strategies For Engagement in Urban Forestry

Directory of Open Access Journals (Sweden)

Christine Moskell

2010-01-01

Full Text Available Few studies in urban forestry have examined the motivations of urban forestry volunteers. In this research, two social psychological theories (Volunteer Functions Inventory and Volunteer Process Model are utilized to examine motivations for participating in tree planting activities. The Volunteer Functions Inventory can be used to examine the needs, goals and motivations that individuals seek to fulfill through volunteerism. The Volunteer Process Model sheds light on the antecedents, experiences and consequences of volunteerism at multiple levels (individual, interpersonal, organizational, societal. An understanding of volunteer motivations can aid practitioners in the development and implementation of participatory urban forestry programs that are attractive to stakeholders. We conducted a survey of volunteers who participated in a MillionTreesNYC volunteer planting event and a focus group of urban forestry practitioners. Survey results reveal that volunteers have varied motivations and a limited knowledge of the community level impacts of trees. Results from the focus group reveal that providing education about the benefits of trees and maintaining long-term communication with volunteers are frequently used strategies for engagement. However, the public’s lack of knowledge about urban forestry and an inability to connect to audiences are practitioner-identified challenges for recruiting stakeholders to participate in their programs.

Monitoring programmed cell death of living plant tissues in microfluidics using electrochemical and optical techniques

DEFF Research Database (Denmark)

Mark, Christina; Heiskanen, Arto; Svensson, Birte

Programmed cell death (PCD) in plants can influence the outcome of yield and quality of crops through its important role in seed germination and the defence process against pathogens. The main scope of the project is to apply microfluidic cell culture for the measurement of electrochemically......, since it is known that reactive oxygen species, which are affected by changes in the redox activity of the cells3, are involved in PCD in plants, but the relationship between and mechanisms behind ROS and PCD is only poorly understood in plant cells4. Recently, it has been shown, using optical detection...

46 CFR 115.620 - Description of the Alternative Hull Examination (AHE) Program for certain passenger vessels.

Science.gov (United States)

2010-10-01

... 46 Shipping 4 2010-10-01 2010-10-01 false Description of the Alternative Hull Examination (AHE... ACCOMMODATIONS FOR MORE THAN 49 PASSENGERS INSPECTION AND CERTIFICATION Hull and Tailshaft Examinations § 115.620 Description of the Alternative Hull Examination (AHE) Program for certain passenger vessels. The Alternative...

Detection and plant monitoring programs: lessons from an intensive survey of Asclepias meadii with five observers.

Directory of Open Access Journals (Sweden)

Helen M Alexander

Full Text Available Monitoring programs, where numbers of individuals are followed through time, are central to conservation. Although incomplete detection is expected with wildlife surveys, this topic is rarely considered with plants. However, if plants are missed in surveys, raw count data can lead to biased estimates of population abundance and vital rates. To illustrate, we had five independent observers survey patches of the rare plant Asclepias meadii at two prairie sites. We analyzed data with two mark-recapture approaches. Using the program CAPTURE, the estimated number of patches equaled the detected number for a burned site, but exceeded detected numbers by 28% for an unburned site. Analyses of detected patches using Huggins models revealed important effects of observer, patch state (flowering/nonflowering, and patch size (number of stems on probabilities of detection. Although some results were expected (i.e. greater detection of flowering than nonflowering patches, the importance of our approach is the ability to quantify the magnitude of detection problems. We also evaluated the degree to which increased observer numbers improved detection: smaller groups (3-4 observers generally found 90 - 99% of the patches found by all five people, but pairs of observers or single observers had high error and detection depended on which individuals were involved. We conclude that an intensive study at the start of a long-term monitoring study provides essential information about probabilities of detection and what factors cause plants to be missed. This information can guide development of monitoring programs.

Detection and plant monitoring programs: lessons from an intensive survey of Asclepias meadii with five observers.

Science.gov (United States)

Alexander, Helen M; Reed, Aaron W; Kettle, W Dean; Slade, Norman A; Bodbyl Roels, Sarah A; Collins, Cathy D; Salisbury, Vaughn

2012-01-01

Monitoring programs, where numbers of individuals are followed through time, are central to conservation. Although incomplete detection is expected with wildlife surveys, this topic is rarely considered with plants. However, if plants are missed in surveys, raw count data can lead to biased estimates of population abundance and vital rates. To illustrate, we had five independent observers survey patches of the rare plant Asclepias meadii at two prairie sites. We analyzed data with two mark-recapture approaches. Using the program CAPTURE, the estimated number of patches equaled the detected number for a burned site, but exceeded detected numbers by 28% for an unburned site. Analyses of detected patches using Huggins models revealed important effects of observer, patch state (flowering/nonflowering), and patch size (number of stems) on probabilities of detection. Although some results were expected (i.e. greater detection of flowering than nonflowering patches), the importance of our approach is the ability to quantify the magnitude of detection problems. We also evaluated the degree to which increased observer numbers improved detection: smaller groups (3-4 observers) generally found 90 - 99% of the patches found by all five people, but pairs of observers or single observers had high error and detection depended on which individuals were involved. We conclude that an intensive study at the start of a long-term monitoring study provides essential information about probabilities of detection and what factors cause plants to be missed. This information can guide development of monitoring programs.

Plant life extension program for Indian PHWR power plants - Actual experience and future plans

International Nuclear Information System (INIS)

Sharma, M.B.; Ghoshal, B.; Shirolkar, K.M.; Ahmad, S.N.

2002-01-01

Full text: The Nuclear Power Corporation of India Limited (NPCIL) is responsible for design, construction and operation for all nuclear power plants in India. Currently, it has fourteen (14) reactor units under operation and another eight units are under various stages of planning and construction. India has adopted Pressurised Heavy Water Reactors (PHWRs) for the initial phase of its nuclear power program. In the earlier PHWRs zircaloy-2 has been used as coolant tube material. Subsequent studies and experience have shown their life to be considerably lower (about 10 full power years) than originally estimated. This meant that reactors at Rajasthan - 1 and 2 Madras - 1 and 2 Narora - 1 and 2 and Kakrapara-1 would require en-masse coolant channel replacement at least once in their lifetime. Subsequent reactors from Kakrapara-2 onwards would not need this en-masse coolant channel replacement as the coolant tube material has been upgraded to Zr 2.5% Nb. En-masse coolant channel replacement and other life extension work have been carried out successfully in Rajasthan Unit-2 (RAPS-2). Madras unit-2 (MAPS-2) has been shutdown since January 2002 and preparatory work for en-masse coolant channel replacement and plant life extension is in progress. This paper discusses in brief the experience of RAPS-2 in carrying out the above jobs as well as the strategies being adopted for MAPS-2. Since the coolant channel replacement work requires a plant outage of about 18 months, this opportunity is used to extend life of existing systems as well as upgradation work. This life extension and upgradation program is based on the results of detailed in service inspection, evaluation of performance of critical equipment, obsolescence and other strategic reasons. This paper discusses in detail some of the major areas of work done, for example introduction of supplementary control room, process control, computer based plant information and event analysis systems, provision of enhanced

Nuclear power plant thermal-hydraulic performance research program plan

International Nuclear Information System (INIS)

1988-07-01

The purpose of this program plan is to present a more detailed description of the thermal-hydraulic research program than that provided in the NRC Five-Year Plan so that the research plan and objectives can be better understood and evaluated by the offices concerned. The plan is prepared by the Office of Nuclear Regulatory Research (RES) with input from the Office of Nuclear Reactor Regulation (NRR) and updated periodically. The plan covers the research sponsored by the Reactor and Plant Systems Branch and defines the major issues (related to thermal-hydraulic behavior in nuclear power plants) the NRC is seeking to resolve and provides plans for their resolution; relates the proposed research to these issues; defines the products needed to resolve these issues; provides a context that shows both the historical perspective and the relationship of individual projects to the overall objectives; and defines major interfaces with other disciplines (e.g., structural, risk, human factors, accident management, severe accident) needed for total resolution of some issues. This plan addresses the types of thermal-hydraulic transients that are normally considered in the regulatory process of licensing the current generation of light water reactors. This process is influenced by the regulatory requirements imposed by NRC and the consequent need for technical information that is supplied by RES through its contractors. Thus, most contractor programmatic work is administered by RES. Regulatory requirements involve the normal review of industry analyses of design basis accidents, as well as the understanding of abnormal occurrences in operating reactors. Since such transients often involve complex thermal-hydraulic interactions, a well-planned thermal-hydraulic research plan is needed

33 CFR Appendix C to Part 273 - Information Requirements for Aquatic Plant Control Program Environmental Impact Statements

Science.gov (United States)

2010-07-01

... Aquatic Plant Control Program Environmental Impact Statements C Appendix C to Part 273 Navigation and... Environmental Impact Statements 1. Description of the problem. a. Pests. Identify the pest to be controlled by.... Relationship to environmental situation. Non-target organisms and integrated pest management programs. 2...

Fiscal year 1996 well plugging and abandonment program Y-12 Plant, Oak Ridge, Tennessee

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-04-01

This report is a synopsis of the progress of the well plugging and abandonment program at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee, from August 1995 through August 1996. A total of 27 wells, piezometers, and borings were plugged and abandoned during the period of time covered in this report. All wells and borings were plugged and abandoned in accordance with the Monitoring Well Plugging and Abandonment Plan for the U.S. Department of Energy, Y-12 Plant, Oak Ridge, Tennessee (HSW, Inc. 1991).

CAL--ERDA program manual. [Building Design Language; LOADS, SYSTEMS, PLANT, ECONOMICS, REPORT, EXECUTIVE, CAL-ERDA

Energy Technology Data Exchange (ETDEWEB)

Hunn, B. D.; Diamond, S. C.; Bennett, G. A.; Tucker, E. F.; Roschke, M. A.

1977-10-01

A set of computer programs, called Cal-ERDA, is described that is capable of rapid and detailed analysis of energy consumption in buildings. A new user-oriented input language, named the Building Design Language (BDL), has been written to allow simplified manipulation of the many variables used to describe a building and its operation. This manual provides the user with information necessary to understand in detail the Cal-ERDA set of computer programs. The new computer programs described include: an EXECUTIVE Processor to create computer system control commands; a BDL Processor to analyze input instructions, execute computer system control commands, perform assignments and data retrieval, and control the operation of the LOADS, SYSTEMS, PLANT, ECONOMICS, and REPORT programs; a LOADS analysis program that calculates peak (design) zone and hourly loads and the effect of the ambient weather conditions, the internal occupancy, lighting, and equipment within the building, as well as variations in the size, location, orientation, construction, walls, roofs, floors, fenestrations, attachments (awnings, balconies), and shape of a building; a Heating, Ventilating, and Air-Conditioning (HVAC) SYSTEMS analysis program capable of modeling the operation of HVAC components including fans, coils, economizers, humidifiers, etc.; 16 standard configurations and operated according to various temperature and humidity control schedules. A plant equipment program models the operation of boilers, chillers, electrical generation equipment (diesel or turbines), heat storage apparatus (chilled or heated water), and solar heating and/or cooling systems. An ECONOMIC analysis program calculates life-cycle costs. A REPORT program produces tables of user-selected variables and arranges them according to user-specified formats. A set of WEATHER ANALYSIS programs manipulates, summarizes and plots weather data. Libraries of weather data, schedule data, and building data were prepared.

The program of reactors and nuclear power plants; Programa de reactores y centrales nucleares

Energy Technology Data Exchange (ETDEWEB)

Calabrese, Carlos R [Comision Nacional de Energia Atomica, General San Martin (Argentina). Centro Atomico Constituyentes

2001-07-01

Into de framework of the program of research reactors and nuclear power plants, the operating Argentine reactors are described. The uses of the research reactors in Argentina are summarized. The reactors installed by Argentina in other countries (Peru, Algeria, Egypt) are briefly described. The CAREM project for the design and construction of an innovator small power reactor (27 MWe) is also described in some detail. The next biennial research and development program for reactor is briefly outlined.

Integrated safety assessment report, Haddam Neck Plant (Docket No. 50-213): Integrated Safety Assessment Program: Draft report

International Nuclear Information System (INIS)

1987-07-01

The integrated assessment is conducted on a plant-specific basis to evaluate all licensing actions, licensee initiated plant improvements and selected unresolved generic/safety issues to establish implementation schedules for each item. Procedures allow for a periodic updating of the schedules to account for licensing issues that arise in the future. The Haddam Neck Plant is one of two plants being reviewed under the pilot program. This report indicates how 82 topics selected for review were addressed, and presents the staff's recommendations regarding the corrective actions to resolve the 82 topics and other actions to enhance plant safety. 135 refs., 4 figs., 5 tabs

Technical basis for the internal dosimetry program at the Y-12 Plant

International Nuclear Information System (INIS)

Ashley, J.C.; Barber, J.M.; Snapp, L.M.; Turner, J.E.

1992-01-01

Since the beginning of plant operations. almost all work with radioactive materials has involved isotopes associated with uranium, enriched or depleted in U 235 . While limited quantities of isotopes of elements other than uranium are present, workplace monitoring and precess knowledge have established that internal exposure from these other isotopes is insignificant in comparison with uranium. While the changing plant mission may necessitate the consideration of internal exposure from other isotopes at some point in time, only enriched and depleted uranium will be considered in this basis document. The portions of the internal dosimetry technical basis which may be unique to the Y-12 Plant is considered in this manual. This manual presents the technical basis of the routine in vivo and in vitro bioassay programs including choice of frequency, participant selection criteria, and action level guidelines. Protocols for special bioassay will be presented in the chapters which described the basis for intake, uptake, and dam assessment. A discussion of the factors which led to the need to develop a special biokinetic model for uranium at the Y-12 Plant, as well as a description of the model's basic parameters, are included in this document

[Evaluation of prerequisites programs for a HACCP plan for frozen sardine plant].

Science.gov (United States)

Rosas, Patricia; Reyes, Genara

2008-06-01

Good manufacturing practices (GMP) and sanitation standard operating procedures (SSOP) are prerequisites programs for the application of the Hazard Analysis and Critical Control Point (HACCP) system as a food safety approach during processing. The aim of this study was to evaluate GMP/SSOP prerequisites in processing line of frozen whole sardine (Sardinella aurita). The GMP compliance was verified according to a standard procedure of the Ministry for the Health of Venezuela, and the SSOP were assessed according to a checklist proposed by the FDA. GMP and SSOP were evaluated following a demerit-based approach. A percentage value was calculated and referred to as sanitary effectiveness. Results indicated that the plant had a good level of compliance with GMP from assessment of buildings and facilities, equipment and tools, hygienic requisites of the production, assurance of the hygiene quality, storage and transportation, and the percentage of sanitary effectiveness was 84%. The level of compliance for SSOP was 53,12% with demerits found in all assessed aspects consisting of inexistent guidelines, lack of control in the sanitary plan and lack of leadership in applying corrective actions. Thus, an improvement in the plant sanitation program was designed targeting SSOP.

Evaluation of the integrity and duration of the Laguna Verde nuclear power plant life- Plant Life Management program (PLIM). TC MEX 04/53 Technical Cooperation Project

International Nuclear Information System (INIS)

Arganis J, C.R.; Diaz S, A.; Aguilar T, J.A.

2006-01-01

As part of the IAEA TC MEX 04/53 Project 'Evaluation of the integrity and extension of life of the Laguna Verde nuclear power plant Handling Program of plant' whose objective is the one of beginning the actions to apply the methodology of Handling of plant life in the Unit 1 of the Laguna Verde Nucleo electric Central for to obtain the Renovation of License in 2020 the ININ, through the Department of Synthesis and Characterization of materials has carried out more of 20 analysis of susceptibility to the intergranular cracking for corrosion under effort in interns so much of the reactor of the unit 1 like of the unit 2 documenting the current state of components based on the type or types of materials that conform them, to it thermomechanical history, operational and of production, as well as of the particularities associated to its use and operation. For the application of the methodology of life handling of plant 5 structure systems or pilot components were selected, to carry out the programs of handling of the aging and handling of plant life: The encircling of the reactor core (Core Shroud), the reactor pressure vessel (Reactor Pressure Vessel), the primary container (Primary Containment), the recirculation system of feeding water (Reactor Feed Water) and cables. (Author)

The evolution of the Waste Isolation Pilot Plant (WIPP) project's public affairs program

International Nuclear Information System (INIS)

Walter, L.H.

1988-01-01

As a first-of-a-kind facility, the Waste Isolation Pilot Plant (WIPP) presents a unique perspective on the value of designing a public affairs program that grown with and complements a project's evolution from construction to operations. Like the project itself, the public affairs programs progressed through several stages to its present scope. During the construction phase, foundations were laid in the community. Then, in this past year as the project entered a preoperational status, emphasis shifted to broaden the positive image that had been created locally. In this stage, public affairs presented the project's positive elements to the various state agencies, government officials, and federal organizations involved in our country's radioactive waste management program. Most recently, and continuing until receipt of the first shipment of waste in October 1988, an even broader, more aggressive public affairs program is planned

The development of the Waste Isolation Pilot Plant (WIPP) project's public affairs program

International Nuclear Information System (INIS)

Walter, L.H.

1988-01-01

The Waste Isolation Pilot Plant (WIPP) offers a perspective on the value of designing flexibility into a public affairs program to enable it to grow with and complement a project's evolution from construction through to operations. This paper discusses how the WIPP public affairs program progressed through several stages to its present scope. During the WIPP construction phase, the public affairs program laid a foundation for Project acceptance in the community. A speaker's bureau, a visitors program, and various community outreach and support programs emphasized the educational and socioeconomic benefits of having this controversial project in Carlsbad. Then, in this past year as the project entered a preoperational status, the public affairs program emphasis shifted to broaden the positive image that had been created locally. In this stage, the program promoted the project's positive elements with the various state agencies, government officials, and federal organizations involved in our country's radioactive waste management and transportation program. Currently, an even broader, more aggressive public affairs program is planned. During this stage public affairs will be engaged in a comprehensive institutional and outreach program, explaining and supporting WIPP's mission in each of the communities and agencies affected by the operation of the country's first geologic repository

Anhydrobiosis and programmed cell death in plants: Commonalities and Differences

Directory of Open Access Journals (Sweden)

Samer Singh

2015-05-01

Full Text Available Anhydrobiosis is an adaptive strategy of certain organisms or specialised propagules to survive in the absence of water while programmed cell death (PCD is a finely tuned cellular process of the selective elimination of targeted cell during developmental programme and perturbed biotic and abiotic conditions. Particularly during water stress both the strategies serve single purpose i.e., survival indicating PCD may also function as an adaptive process under certain conditions. During stress conditions PCD cause targeted cells death in order to keep the homeostatic balance required for the organism survival, whereas anhydrobiosis suspends cellular metabolic functions mimicking a state similar to death until reestablishment of the favourable conditions. Anhydrobiosis is commonly observed among organisms that have ability to revive their metabolism on rehydration after removal of all or almost all cellular water without damage. This feature is widely represented in terrestrial cyanobacteria and bryophytes where it is very common in both vegetative and reproductive stages of life-cycle. In the course of evolution, with the development of advanced vascular system in higher plants, anhydrobiosis was gradually lost from the vegetative phase of life-cycle. Though it is retained in resurrection plants that primarily belong to thallophytes and a small group of vascular angiosperm, it can be mostly found restricted in orthodox seeds of higher plants. On the contrary, PCD is a common process in all eukaryotes from unicellular to multicellular organisms including higher plants and mammals. In this review we discuss physiological and biochemical commonalities and differences between anhydrobiosis and PCD.

A measurement control program for plutonium isotopic gamma-ray systems at the Rocky Flats Plant

International Nuclear Information System (INIS)

Fleissner, J.G.

1986-01-01

A sound measurement control (MC) program should be an integral part of every nondestructive assay measurement system used for the assay of special nuclear materials. This paper describes a measurement control program for plutonium isotopic composition measurements, using high-resolution gamma-ray spectroscopy, that has been implemented in the Analytical Laboratories and the Chemistry Standards Laboratory at the Rocky Flats Plant. This MC program emphasizes the standardization of data collection procedures along with the implementation of internal and external measurement control checks to provide the requisite measurement quality assurance

Summary of the Semiscale Program, 1965-1986

International Nuclear Information System (INIS)

Loomis, G.G.

1987-07-01

This document summarizes significant results from the Semiscale Program, which examined pressurized water reactor (PWR) safety issues from 1965 to 1986. Most of these issues were related to plant response during loss-of-coolant accidents and operational transients. The Semiscale program utilized a series of non-nuclear, scaled, PWR plant simulators to provide thermal-hydraulic data at prototypical pressures and temperatures for a wide range of nuclear safety issues. Presented are: a historical perspective of the Semiscale Program relative to reactor safety with a catalog of the Semiscale experimental facilities and data bases, the relationship of Semiscale results to 10 CFR Part 50 (Appendix K), the impact of Semiscale results on scaling experimental results to full sized operating plants, a summary of safety issues that were addressed by Semiscale testing as they arose throughout the operational lifetime of Semiscale, the contributions of the Semiscale Program to safety technology, a description of phenomena observed during Semiscale testing, the impact of Semiscale data on code development and assessment, the applicability of the Semiscale data base for code development and assessment, and finally, major conclusions and accomplishments of the Semiscale program

Integrated-plant-safety assessment Systematic Evaluation program. Millstone Nuclear Power Station, Unit 1, Northeast Nuclear Energy Company, Docket No. 50-245

International Nuclear Information System (INIS)

1982-11-01

The Systematic Evaluation Program was initiated in February 1977 to review the designs of older operating nuclear reactor plants to reconfirm and document their safety. The review provides: (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of the Millstone Nuclear Power Station, Unit 1, operated by Northeast Nuclear Energy Company (located in Waterford, Connecticut). Millstone Nuclear Power Station, Unit 1, is one of ten plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review. It is expected that this report will be one of the bases in considering the issuance of a full-term operating license in place of the existing provisional operating license

Martin Marietta Paducah Gaseous Diffusion Plant comprehensive earthquake emergency management program

International Nuclear Information System (INIS)

1990-01-01

Recognizing the value of a proactive, integrated approach to earthquake preparedness planning, Martin Marietta Energy Systems, Inc. initiated a contract in June 1989 with Murray State University, Murray, Kentucky, to develop a comprehensive earthquake management program for their Gaseous Diffusion Plant in Paducah, Kentucky (PGDP -- Subcontract No. 19P-JV649V). The overall purpose of the program is to mitigate the loss of life and property in the event of a major destructive earthquake. The program includes four distinct (yet integrated) components: an emergency management plan, with emphasis on the catastrophic earthquake; an Emergency Operations Center Duty Roster Manual; an Integrated Automated Emergency Management Information System (IAEMIS); and a series of five training program modules. The PLAN itself is comprised of four separate volumes: Volume I -- Chapters 1--3; Volume II -- Chapters 4--6, Volume III -- Chapter 7, and Volume IV -- 23 Appendices. The EOC Manual (which includes 15 mutual aid agreements) is designated as Chapter 7 in the PLAN and is a ''stand alone'' document numbered as Volume III. This document, Volume II, discusses methodology, engineering and environmental analyses, and operational procedures

Martin Marietta Paducah Gaseous Diffusion Plant comprehensive earthquake emergency management program

International Nuclear Information System (INIS)

1990-01-01

Recognizing the value of a proactive, integrated approach to earthquake preparedness planning, Martin Marietta Energy Systems, Inc, initiated a contract in June 1989 with Murray State University, Murray, Kentucky, to develop a comprehensive earthquake management program for their Gaseous Diffusion Plant in Paducah, Kentucky (PGDP--Subcontract No. 19P-JV649V). The overall purpose of the program is to mitigate the loss of life and property in the event of a major destructive earthquake. The program includes four distinct (yet integrated) components: (1) an emergency management plan, with emphasis on the catas trophic earthquake, (2) an Emergency Operations Center Duty Roster Manual, (3) an Integrated Automated Emergency Management Information System (IAEMIS), and (4) a series of five training program modules. The PLAN itself is comprised of four separate volumes: Volume I--Chapters 1--3; Volume II--Chapters 4--6, Volume III--Chapter 7, and Volume IV--23 Appendices. The EOC Manual (which includes 15 mutual aid agreements) is designated as Chapter 7 in the PLAN and is a ''stand alone'' document numbered as Volume III. This document, Volume IV contains the appendices to this report

Hanford Waste Vitrification Plant quality assurance program description for defense high-level waste form development and qualification

International Nuclear Information System (INIS)

Hand, R.L.

1990-12-01

The US Department of Energy-Office of Civilian Radioactive Waste Management has been designated the national high-level waste repository licensee and the recipient for the canistered waste forms. The Office of Waste Operations executes overall responsibility for producing the canistered waste form. The Hanford Waste Vitrification Plant Project, as part of the waste form producer organization, consists of a vertical relationship. Overall control is provided by the US Department of Energy-Environmental Restoration and Waste Management Headquarters; with the US Department of Energy-Office of Waste Operations; the US Department of Energy- Headquarters/Vitrification Project Branch; the US Department of Energy-Richland Operations Office/Vitrification Project Office; and the Westinghouse Hanford Company, operations and engineering contractor. This document has been prepared in response to direction from the US Department of Energy-Office of Civilian Radioactive Waste Management through the US Department of Energy-Richland Operations Office for a quality assurance program that meets the requirements of the US Department of Energy. This document provides guidance and direction for implementing a quality assurance program that applies to the Hanford Waste Vitrification Plant Project. The Hanford Waste Vitrification Plant Project management commits to implementing the quality assurance program activities; reviewing the program periodically, and revising it as necessary to keep it current and effective. 12 refs., 6 figs., 1 tab

Y-12 Plant waste minimization strategy

International Nuclear Information System (INIS)

Kane, M.A.

1987-01-01

The 1984 Amendments to the Resource Conservation and Recovery Act (RCRA) mandate that waste minimization be a major element of hazardous waste management. In response to this mandate and the increasing costs for waste treatment, storage, and disposal, the Oak Ridge Y-12 Plant developed a waste minimization program to encompass all types of wastes. Thus, waste minimization has become an integral part of the overall waste management program. Unlike traditional approaches, waste minimization focuses on controlling waste at the beginning of production instead of the end. This approach includes: (1) substituting nonhazardous process materials for hazardous ones, (2) recycling or reusing waste effluents, (3) segregating nonhazardous waste from hazardous and radioactive waste, and (4) modifying processes to generate less waste or less toxic waste. An effective waste minimization program must provide the appropriate incentives for generators to reduce their waste and provide the necessary support mechanisms to identify opportunities for waste minimization. This presentation focuses on the Y-12 Plant's strategy to implement a comprehensive waste minimization program. This approach consists of four major program elements: (1) promotional campaign, (2) process evaluation for waste minimization opportunities, (3) waste generation tracking system, and (4) information exchange network. The presentation also examines some of the accomplishments of the program and issues which need to be resolved

The Devil Is in the Details: Examining the Evidence for "Proven" School-Based Drug Abuse Prevention Programs

Science.gov (United States)

Gandhi, Allison Gruner; Murphy-Graham, Erin; Petrosino, Anthony; Chrismer, Sara Schwartz; Weiss, Carol H.

2007-01-01

In an effort to promote evidence-based practice, government officials, researchers, and program developers have developed lists of model programs in the prevention field. This article reviews the evidence used by seven best-practice lists to select five model prevention programs. The authors' examination of this research raises questions about the…

An overview of the United States Department of Energy plant lifetime improvement program

International Nuclear Information System (INIS)

Rosinski, S.T.; Clauss, J.M.; Harrison, D.L.

1993-01-01

Today, 109 nuclear power plants provide over 20 percent of the electrical energy generated in the US. The operating license of the first of these plants will expire in the year 2000; one third of the operating licenses will expire by 2010 and the remaining plant licenses are scheduled to expire by 2033. The National Energy Strategy assumes that 70 percent of these plants will continue to operate beyond their current license expiration to assist in ensuring an adequate, diverse, and environmentally acceptable energy supply for economic growth. In order to preserve this energy resource in the US three major tasks must be successfully completed: (1) establishment of the regulations, technical standards, and procedures for the preparation and review of a license renewal application; (2) development, verification, and validation of the various technical criteria and bases for needed monitoring, refurbishment, or replacement of plant equipment; and (3) demonstration of the regulatory process. Since 1985, the US Department of Energy (DOE) has been working with the nuclear industry and the US Nuclear Regulatory Commission (NRC) to establish and demonstrate the option to extend the life of nuclear power plants through the renewal of operating licenses. This paper focuses primarily on DOE's Plant Lifetime Improvement (PLIM) Program efforts to develop the technical criteria and bases for effective aging management and lifetime improvement for continued operation of nuclear power plants. This paper describes current projects to resolve generic technical issues, including degradation of long-lived components, reactor pressure vessel (RPV) embrittlement management approaches, and analytical methodologies to characterize RPV integrity

Mitigation of inbreeding while preserving genetic gain in genomic breeding programs for outbred plants.

Science.gov (United States)

Lin, Zibei; Shi, Fan; Hayes, Ben J; Daetwyler, Hans D

2017-05-01

Heuristic genomic inbreeding controls reduce inbreeding in genomic breeding schemes without reducing genetic gain. Genomic selection is increasingly being implemented in plant breeding programs to accelerate genetic gain of economically important traits. However, it may cause significant loss of genetic diversity when compared with traditional schemes using phenotypic selection. We propose heuristic strategies to control the rate of inbreeding in outbred plants, which can be categorised into three types: controls during mate allocation, during selection, and simultaneous selection and mate allocation. The proposed mate allocation measure GminF allocates two or more parents for mating in mating groups that minimise coancestry using a genomic relationship matrix. Two types of relationship-adjusted genomic breeding values for parent selection candidates ([Formula: see text]) and potential offspring ([Formula: see text]) are devised to control inbreeding during selection and even enabling simultaneous selection and mate allocation. These strategies were tested in a case study using a simulated perennial ryegrass breeding scheme. As compared to the genomic selection scheme without controls, all proposed strategies could significantly decrease inbreeding while achieving comparable genetic gain. In particular, the scenario using [Formula: see text] in simultaneous selection and mate allocation reduced inbreeding to one-third of the original genomic selection scheme. The proposed strategies are readily applicable in any outbred plant breeding program.

A successful environmental remediation program closure and post-closure activities (CAPCA) Y-12 Plant, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

Bowers, M.H.

1991-01-01

The Resource Conservation and Recovery Act (RCRA) closure of eleven waste management units at the Department of Energy's (DOE's) Oak Ridge Y-12 Plant is nearing completion. The Oak Ridge Y-12 Plant is managed by Martin Marietta Energy Systems, Inc. for the US Department of Energy under Contract DE-AC05-84OR21400. The Closure and Post Closure Program (CAPCA) has been accomplished on an accelerated schedule through the efforts of a dedicated team from several organizations. This paper relates experience gained from the program that can be of benefit on other DOE environmental remediation projects. Technical design and construction aspects, as well as project management considerations, are discussed

Examining the effectiveness of a restorative justice program for various types of juvenile offenders.

Science.gov (United States)

Bergseth, Kathleen J; Bouffard, Jeffrey A

2013-09-01

Restorative justice (RJ) programs have become widespread in the United States and in other countries. These programs are often seen as a viable alternative to traditional retributive processing, especially for minor, and sometimes more serious, forms of delinquency and adult criminality. The programs hold promise for achieving several goals, including increased community and victim involvement, greater satisfaction with the case outcomes, improved offender compliance, increased perceptions of fairness, and even recidivism reduction. Meta-analyses have demonstrated varying degrees of program success in recidivism reduction, which may in part reflect differential effectiveness of the RJ approach for various kinds of offenders. This study examined whether an RJ program for juvenile offenders had differential impacts on recidivism across various offender characteristics (including age, gender, racial group, offending history, and current offense). Results generally support the effectiveness of the program for many types of offenders. Implications for future research and potential improvements to the RJ model are discussed.

Examination of program exposure across intervention delivery modes: face-to-face versus internet

Directory of Open Access Journals (Sweden)

Mummery W Kerry

2007-03-01

Full Text Available Abstract Background There has been increasing interest in the ability of the internet to produce behaviour change. The focus of this study was to describe program exposure across three intervention groups from a randomised trial (RT comparing traditional face-to-face, internet-mediated (combined internet plus face-to-face, and internet-only program delivery. Methods Baseline and immediately post-intervention survey data, and exposure rates from participants that commenced the RT were included (n = 192. Exposure was defined as either face-to-face attendance, website usage, or a combination of both for the internet-mediated group. Characteristics of participants who were exposed to at least 75% of the program material were explored. Descriptive analysis and logistical regression were used to examine differences between groups for program exposure. Results All groups showed decrease in program exposure over time. Differences were also observed (χ2 = 10.37, p Conclusion These results suggest that the internet groups were as effective as the face-to-face delivery mode in engaging participants in the program material. However, different delivery methods may be more useful to different sub-populations. It is important to explore which target groups that internet-based programs are best suited, in order to increase their impact.

Fiscal year 1996 well installation program summary, Y-12 Plant Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1997-04-01

This report summarizes the well installation activities conducted during the federal fiscal year (FY) 1996 drilling program at the Oak Ridge Y-12 Plant, Oak Ridge Tennessee. Synopses of monitoring well construction/well development data, well location rationale, geological/hydrological observations, quality assurance/quality control methods, and health and safety monitoring are included. Two groundwater monitoring wells were installed during the FY 1996 drilling program. One of the groundwater monitoring wells was installed in the Lake Reality area and was of polyvinyl chloride screened construction. The other well, installed near the Ash Disposal Basin, was of stainless steel construction

Fiscal year 1995 well installation program summary Y-12 Plant, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1995-09-01

This report summarizes the well installation activities conducted during the federal fiscal year (FY) 1995 drilling program at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee (including activities that were performed in late FY 1994, but not included in the FY 1994 Well Installation Program Summary Report). Synopses of monitoring well construction/well development data, well location rationale, geological/hydrological observations, quality assurance/quality control methods, and health and safety monitoring are included. Three groundwater monitoring wells and two gas monitoring probes were installed during the FY 1995 drilling program. One of the groundwater monitoring wells was installed at Landfill VI, the other two in the Boneyard/Burnyard area. All of the groundwater monitoring wells were constructed with stainless steel screens and casings. The two gas monitoring probes were installed at the Centralized Sanitary Landfill II and were of polyvinyl chloride (PVC) screened construction. Eleven well rehabilitation/redevelopment efforts were undertaken during FY 1995 at the Y-12 Plant. All new monitoring wells and wells targeted for redevelopment were developed by either a 2.0-in. diameter swab rig or by hand bailing until nonspecific parameters (pH and specific conductance) attained steady-state levels. Turbidity levels were lowered, if required, to the extent practicable by continued development beyond a steady-state level of pH and conductance

The refinement of a cultural standardized patient examination for a general surgery residency program.

Science.gov (United States)

Chun, Maria B J; Deptula, Peter; Morihara, Sarah; Jackson, David S

2014-01-01

Recent articles have documented the importance of cultural competency in surgery. Surgical residency programs have used the Objective Structured Clinical Examinations or cultural standardized patient examinations as a training tool. Past studies evaluating cultural competency have noted the importance of including an observational (control) arm, which would allow for a more objective assessment of a resident's competency in this area. The purpose of our article is to present the results of a follow-up study to a pilot cultural standardized patient examination for surgery residents. All first-year surgery residents were required to participate in the videotaped cultural SP examination as part of the general surgery residency curriculum. Two measures were used to assess resident performance. On the day of the examination, the Cross-Cultural Care Survey was administered. The examination was assessed by the residents themselves, faculty observers, and standardized patients, using a written checklist that was developed to evaluate residents on all 6 Accreditation Council for Graduate Medical Education competencies. The current study includes 20 first-year surgery residents from academic years 2011 to 2012 and 2012 to 2013. The examination of pretest differences in groups found that students born outside of the United States had significantly higher scores on attitude (t = -2.68, df = 18, p = 0.02), but no statistically significant differences were found in skillfulness or knowledge or in the overall rating scale. For the overall rating scale, change from pretest to posttest was statistically significant (t = -2.25, df = 18, p = 0.04). Further analysis revealed that students who were born in the United States demonstrated a significant increase in ratings (t = -3.08, df = 10, p = 0.01) whereas students who were not born in the United States showed little change (t = -0.35, df = 7, p = 0.74). These results show that the means in attitude scales changed little for all

Risk maps for targeting exotic plant pest detection programs in the United States

Science.gov (United States)

R.D. Magarey; D.M. Borchert; J.S. Engle; M Garcia-Colunga; Frank H. Koch; et al

2011-01-01

In the United States, pest risk maps are used by the Cooperative Agricultural Pest Survey for spatial and temporal targeting of exotic plant pest detection programs. Methods are described to create standardized host distribution, climate and pathway risk maps for the top nationally ranked exotic pest targets. Two examples are provided to illustrate the risk mapping...

Annual summary report on the Decontamination and Decommissioning Program at the Oak Ridge Y-12 Plant for the period ending September 30, 1992

International Nuclear Information System (INIS)

1993-02-01

The Y-12 Decontamination and Decommissioning (D ampersand D) Program provides for the ultimate disposition of plant process buildings and their supporting facilities. The overall objective is to enable the Y-12 Plant to meet applicable environmental regulations and Department of Energy (DOE) orders to protect human health and the environment from contaminated facilities through decommissioning activities. This objective is met by providing for the surveillance and maintenance (S ampersand M) of accepted standby or shutdown facilities awaiting decommissioning; planning for decommissioning of these facilities; and implementing a program to accomplish the safe, cost-effective, and orderly disposition of contaminated facilities. The Y-12 D ampersand D Program was organized during FY 1992 to encompass the needs of surplus facilities at the Y-12 Plant. The need existed for a program which would include Weapons Program facilities as well as other facilities used by several programs within the Y-12 Plant. Building 9201-4 (Alpha 4) is the only facility that is formally in the D ampersand D Program. Funding for the work completed in FY 1992 was shared by the Environmental Restoration and Waste Management Program (EW-20) and Weapons Operations (GB-92). This report summarizes the FY 1992 D ampersand D activities associated with Building 9201-4. A section is provided for each task; the tasks include surveillance, routine and special maintenance, safety, and D ampersand D planning

Summary and conclusions of a program addressing aging of nuclear power plant concrete structures

International Nuclear Information System (INIS)

Naus, D.J.; Oland, C.B.; Hookham, C.J.; Graves, H.L. III

1999-01-01

Research has been conducted by the Oak Ridge National Laboratory to address aging management of nuclear power plant concrete structures. The purpose was to identify potential structural safety issues and acceptance criteria for use in continued service assessments. The focus of this program was on structural integrity rather than on leaktightness or pressure retention of concrete structures. Primary program accomplishments include formulation of a Structural Materials Information Center that contains data and information on the time variation of material properties under the influence of pertinent environmental stressors and aging factors for 144 materials, an aging assessment methodology to identify critical structures and degradation factors that can potentially impact their performance, guidelines and evaluation criteria for use in condition assessments of reinforced concrete structures, and a reliability-based methodology for current condition assessments and estimations of future performance of reinforced concrete nuclear power plant structures. In addition, in-depth evaluations were conducted of several nondestructive evaluation and repair-related technologies to develop guidance on their applicability. (orig.)

Safe shutdown of Defense Program facilities at the Mound Plant, Miamisburg, Ohio

International Nuclear Information System (INIS)

Anderson, H.F.; Bantz, P.D.; Luthy, D.F.

1996-01-01

The Mound Plant was one of several production sites in the US Department of Energy's Defense Programs (DP) Weapons Complex. As a result of the downsizing of the weapons program, certain operations at Mound are being transferred to other DOE sites and the DP buildings at Mound are being shutdown. The objectives of the program are to reduce the hazardous and financial liabilities to DOE and to foster the reuse of facilities for economic development. The overall program is described. The process began with the categorization of excess DP buildings into three groups depending on their anticipated future use. The draft DOE/EM-60 Acceptance Criteria were used to develop a detailed shutdown checklist as the foundation of the process. The overall program budget, schedule, ad options for disposition of materials and components is presented. Accomplishments in FY94 and FY95 are described. By the end of FY95, all excess energetic materials and components, all excess chemicals (from non-radiation areas) and significant amounts of radioactive materials have been removed from the site. By the end of FY95, 47 of the 72 buildings in the program have been taken through all ten of the draft EM-60 acceptance criteria. Lessons learned, based on experience at Mound to date, are summarized

Waste Isolation Pilot Plant Groundwater Protection Management Program Plan

International Nuclear Information System (INIS)

1993-01-01

The DOE has mandated in DOE Order 5400.1 that its operations will be conducted in an environmentally safe manner. The Waste Isolation Pilot Plant (WIPP) will comply with DOE Order 5400.1 and will conduct its operations in a manner that ensures the safety of the environment and the public. This document outlines how the WIPP will protect and preserve groundwater within and surrounding the WIPP facility. Groundwater protection is just one aspect of the WIPP environmental protection effort. The WIPP groundwater surveillance program is designed to determine statistically if any changes are occurring in groundwater characteristics within and surrounding the WIPP facility. If a change is noted, the cause will be determined and appropriate corrective action initiated

Scientific challenges in the field of invasive alien plant management

CSIR Research Space (South Africa)

Van Wilgen, BW

2004-01-01

Full Text Available This article examines scientific challenges in the field of invasion alien plant management in South Africa. Overview of the Working for Water program, Issues of research funding, and Biological control research. It also includes some of the papers...

Integrated Plant Safety Assessment, Systematic Evaluation Program: Yankee Nuclear Power Station (Docket No. 50-29)

International Nuclear Information System (INIS)

1987-10-01

The US Nuclear Regulatory Commission (NRC) has prepared Supplement 1 to the final Integrated Plant Safety Assessment Report (IPSAR) (NUREG-0825), under the scope of the Systematic Evaluation Program (SEP), for Yankee Atomic Electric Company's Yankee Nuclear Power Station located in Rowe, Massachusetts. The SEP was initiated by the NRC to review the design of older operating nuclear power plants to reconfirm and document their safety. This report documents the review completed under the SEP for those issues that required refined engineering evaluations or the continuation of ongoing evaluations after the Final IPSAR for the Yankee plant was issued. The review has provided for (1) an assessment of the significance of differences between current technical positions on selected safety issues and those that existed when Yankee was licensed, (2) a basis for deciding how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. 2 tabs

Senescence and programmed cell death in plants: polyamine action mediated by transglutaminase

Directory of Open Access Journals (Sweden)

Stefano eDel Duca

2014-04-01

Full Text Available Research on polyamines in plants laps a long way of about 50 years and many roles have been discovered for these aliphatic cations. Polyamines regulate cell division, differentiation, organogenesis, reproduction, dormancy-break and senescence, homeostatic adjustments in response to external stimuli and stresses. Nevertheless, the molecular mechanisms of their multiple activities are still matter of research. Polyamines are present in free and bound forms and interact with several important cell molecules; some of these interactions may occur by covalent linkages catalyzed by transglutaminase, giving rise to ‘cationisation’ or cross-links among specific proteins. Senescence and PCD can be delayed by polyamines; in order to re-interpret some of these effects and to obtain new insights into their molecular mechanisms, their conjugation has been revised here. The transglutaminase-mediated interactions between proteins and polyamines are the main target of this review. After an introduction on the characteristics of this enzyme, on its catalysis and role in PCD in animals, the plant senescence and PCD models in which TGase has been studied, are presented: the corolla of naturally senescing or excised flowers, the leaves senescing, either excised or not, the pollen during self-incompatible pollination, the hypersensitive response and the tuber storage parenchyma during dormancy release. In all the models examined, transglutaminase appears to be involved by a similar molecular mechanism as described during apoptosis in animal cells, even though several substrates are different. Its effect is probably related to the type of PCD, but mostly to the substrate to be modified in order to achieve the specific PCD program. As a cross-linker of polyamines and proteins, transglutaminase is an important factor involved in multiple, sometimes controversial, roles of polyamines during senescence and PCD.

Examining the effectiveness of micro-enterprise development programs in Malaysia

Directory of Open Access Journals (Sweden)

Noor Raihani Zainol

2017-06-01

Full Text Available Previous studies on socioeconomic development have examined the effect of development initiatives (i.e., access to finance and training on several socioeconomic indicators (i.e., income, empowerment, asset, quality of life, employment. These studies have focused mostly on the outcomes of specific types of programs offered by specific development organizations. This study however focuses on informal women micro-entrepreneurs’ participation in various development programs available to them and their influence on entrepreneurial competencies, human capital development, competitive advantages, economic vulnerability, supportive environment, and performance of micro-enterprises. This cross-sectional study adopted the purposive random sampling method and collected data from 384 informal women entrepreneurs from the local markets in different districts of Kelantan, Malaysia. The findings show that the development program participants have relatively higher levels of entrepreneurial competencies, human capital development, and higher levels of enterprise performance compared to non-participants. It is also noted that the level of economic vulnerability is relatively low among participants compared to non-participants. However, these findings contradict most of the earlier studies that show a significant positive impact of micro-credit on socio-economic wellbeing, as the difference in entrepreneurial competencies, human capital development, economic vulnerability, and performance of micro-enterprises among participants and non-participants in this study is not statistically significant. However, findings reported significantly higher levels of competitive advantages, and better supportive environment among the participants compared to the non-participants. Development organizations should therefore focus on expanding their outreach to spread the positive effects of their development programs towards uplifting the economic condition of low and middle

Implementing the objective structured clinical examination in a geriatrics fellowship program-a 3-year experience.

Science.gov (United States)

Avelino-Silva, Thiago J; Gil, Luiz A; Suemoto, Claudia K; Kikuchi, Elina L; Lin, Sumika M; Farias, Luciana L; Jacob-Filho, Wilson

2012-07-01

The Objective Structured Clinical Examination (OSCE) appears to be an effective alternative for assessing not only medical knowledge, but also clinical skills, including effective communication and physical examination skills. The purpose of the current study was to implement an OSCE model in a geriatrics fellowship program and to compare the instrument with traditional essay examination. Seventy first- and second-year geriatric fellows were initially submitted to a traditional essay examination and scored from 0 to 10 by a faculty member. The same fellows subsequently underwent an OSCE with eight 10-minute stations covering a wide range of essential aspects of geriatric knowledge. Each OSCE station had an examiner responsible for its evaluation according to a predefined checklist. Checklist items were classified for analysis purposes as clinical knowledge items (CKI) and communication skills items (CSI); fellow responses were scored from 0 to 10.Although essay examinations took from 30 to 45 minutes to complete, 180-200 minutes were required to evaluate fellows using the proposed OSCE method. Fellows scored an average of 6.2 ± 1.2 on the traditional essay examination and 6.6 ± 1.0 on the OSCE (P examination was similar to their performance on CKI (P = .13). Second-year fellows performed better than first-year fellows on the essay examination (P geriatrics fellowship program. Combining different testing modalities may provide the best assessment of competence for various domains of knowledge, skills, and behavior. © 2012, Copyright the Authors Journal compilation © 2012, The American Geriatrics Society.

46 CFR 115.625 - Eligibility requirements for the Alternative Hull Examination (AHE) Program for certain passenger...

Science.gov (United States)

2010-10-01

... 46 Shipping 4 2010-10-01 2010-10-01 false Eligibility requirements for the Alternative Hull... OVERNIGHT ACCOMMODATIONS FOR MORE THAN 49 PASSENGERS INSPECTION AND CERTIFICATION Hull and Tailshaft Examinations § 115.625 Eligibility requirements for the Alternative Hull Examination (AHE) Program for certain...

Development of the Chinshan plant analyzer and its assessment with plant data

International Nuclear Information System (INIS)

Shihjen Wang; Chunsheng Chien; Jungyuh Jang; Shawcuang Lee

1993-01-01

To apply fast and accurate simulation techniques to Taiwanese nuclear power plants, plant analyzer technology was transferred to Taiwan from the Brookhaven National Laboratory (BNL) through a cooperative program. The Chinshan plant analyzer is developed on the AD100 peripheral processor systems, based on the BNL boiling water reactor plant analyzer. The BNL plant analyzer was first converted from MPS10 programming for AD10 to ADSIM programming for AD100. It was then modified for the Taiwan Power Company's Chinshan power station. The simulation speed of the Chinshan plant analyzer is eight times faster than real time. A load rejection transient performed at 100% of full power during startup tests was simulated with the Chinshan plant analyzer, and the results were benchmarked against test data. The comparison shows good agreement between calculated results and test data

Pilot program to identify valve failures which impact the safety and operation of light water nuclear power plants

International Nuclear Information System (INIS)

Tsacoyeanes, J.C.; Raju, P.P.

1980-04-01

The pilot program described has been initiated under the Department of Energy Light Water Reactor Safety Research and Development Program and has the following specific objectives: to identify the principal types and causes of failures in valves, valve operators and their controls and associated hardware, which lead to, or could lead to plant trip; and to suggest possible remedies for the prevention of these failures and recommend future research and development programs which could lead to minimizing these valve failures or mitigating their effect on plant operation. The data surveyed cover incidents reported over the six-year period, beginning 1973 through the end of 1978. Three sources of information on valve failures have been consulted: failure data centers, participating organizations in the nuclear power industry, and technical documents

Nondestructive examinations performance demonstration standpoint of the BCCN (Nuclear Construction Inspection Office)

International Nuclear Information System (INIS)

Deschamps, J.; Novat, J.

1994-01-01

The part played by in service non-destructive examinations (NDE) in the safety assessment of French nuclear power plants has developed considerably since startup of the first PWR unit 15 years ago. In 15 years of operation and continued plant construction, defects came to light, revealed either by a non-destructive examination or a leak occurring in operation or during hydrostatic test. It is consequently necessary to operate reactors affected by defects already detected or liable to develop according to a known mechanism. This practice is only acceptable if it can be proved that the defects will remain harmless in all situations. This implies that they can be detected without fail beyond a certain threshold, that they can be characterized and that their propensity to develop can be measured. In some cases, only NDE data can justify the continued operation of a reactor. Maximum guarantees as to the performances and reliability of these examinations are consequently indispensable, since plant safety conclusions will be based on their results. This paper discusses: the advantages of an NDE performance demonstration program; practical assessments role; and NDE performance demonstration stages

Methodology of aging management in structures, systems and components of a nuclear power plant and its application to a pilot program in Laguna Verde

International Nuclear Information System (INIS)

Jarvio C, G.; Fernandez S, G.

2009-10-01

From its origin the nuclear power plants confront the effects of time and of environment, giving as result the aging of its structures, systems and components. In this document the general process is described for the establishment of Aging Management Program developed by IAEA. Following the program methodology is guaranteed that a nuclear power plant manages the aging effects appropriately and to make decisions for its solution, assuring the characteristic functions of structures, systems and components of same nuclear power plant. On the other hand, the implantation of an aging management program constitutes the base for development of a licence renovation program, like it can be the specific case of the Central Laguna Verde Units 1 and 2. (Author)

Aquatic Plant Control Research Program. Allelopathic Aquatic Plants for Aquatic Plant Management: A Feasibility Study

Science.gov (United States)

1989-10-01

1978. " Ecotoxicology of aquatic plant communi- ties," Principles of Ecotoxicology , SCOPE Report 12, Chapter 11, pp 239-255. [Heavy metals, Pollutants...Phragmites communis and Equisetum limosum were cultivated . They found plant-plant influences depend on soil type. Typha latifolia, S. A2 lacustris, and

An evaluation of the Browns Ferry Nuclear Plant preventive maintenance program based on reliability centered maintenance analysis

International Nuclear Information System (INIS)

McCullough, C.L.; McCullough, C.A.

1989-01-01

Reliability centered maintenance (RCM) techniques were used to support a preventative maintenance (PM) upgrade program (PMUP) performed at TVA Browns Ferry Nuclear Plant (BFNP). The purpose of the RCM analysis was to identify critical equipment based on risk and economic importance and to evaluate the PM activities applicable to that equipment. The analysis may be conveniently divided into three steps, which will be outlined in the Approach section of this paper. The net benefit of the RCM approach was a prioritization of the focus of the PM upgrade program so that plant components receive attention proportional to their importance, and assurance that PM activities properly address the most likely component failure causes

Study of the environmental costs to nuclear power plants using the SIMPACTS program

Energy Technology Data Exchange (ETDEWEB)

Menzel, Francine; Sabundjian, Gaiane; Mutarelli, Rita de Cassia, E-mail: fmenzel@ipen.b, E-mail: gdjian@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2011-07-01

The nuclear energy presents advantages in comparison with other kinds of energy sources, when their externalities are evaluated. Externality is a term that represents the side effects of production of goods or services on other people not directly involved in the activity. The externalities can be identified and related to the term environmental cost. The environmental cost is a externality that somehow affects the environment, converted into economic terms, to then be compared with other costs of an action or enterprise. The environmental cost can be calculated through programs for that purpose, however for the nuclear area is the most used SIMPACTS, developed by the International Atomic Energy Agency (IAEA). The motivation for this work arose from the need to have a complete assessment of environmental costs from nuclear power reactors, although it is known that this kind of form of energy generation show an advantage over others with regard to externalities. This work is the first step in implementing the program SIMPACTS in plant Angra 2 in order to calculate the environmental cost of their operation. The objective is to develop a methodology for calculating environmental cost for nuclear power reactors. SIMPACTS program will be used to identify the advantages and disadvantages of a cost analysis of environmental and perform the calculation of environmental costs for Angra 2, with the aim of minimizing the environmental impacts of its operation. From an extensive literature search, is presented in this paper the methodology for calculating the environmental cost of the program SIMPACTS and some results of calculations with the environmental cost in international power reactors other power generation plants. (author)

Study of the environmental costs to nuclear power plants using the SIMPACTS program

International Nuclear Information System (INIS)

Menzel, Francine; Sabundjian, Gaiane; Mutarelli, Rita de Cassia

2011-01-01

The nuclear energy presents advantages in comparison with other kinds of energy sources, when their externalities are evaluated. Externality is a term that represents the side effects of production of goods or services on other people not directly involved in the activity. The externalities can be identified and related to the term environmental cost. The environmental cost is a externality that somehow affects the environment, converted into economic terms, to then be compared with other costs of an action or enterprise. The environmental cost can be calculated through programs for that purpose, however for the nuclear area is the most used SIMPACTS, developed by the International Atomic Energy Agency (IAEA). The motivation for this work arose from the need to have a complete assessment of environmental costs from nuclear power reactors, although it is known that this kind of form of energy generation show an advantage over others with regard to externalities. This work is the first step in implementing the program SIMPACTS in plant Angra 2 in order to calculate the environmental cost of their operation. The objective is to develop a methodology for calculating environmental cost for nuclear power reactors. SIMPACTS program will be used to identify the advantages and disadvantages of a cost analysis of environmental and perform the calculation of environmental costs for Angra 2, with the aim of minimizing the environmental impacts of its operation. From an extensive literature search, is presented in this paper the methodology for calculating the environmental cost of the program SIMPACTS and some results of calculations with the environmental cost in international power reactors other power generation plants. (author)

Next Generation Nuclear Plant Methods Research and Development Technical Program Plan -- PLN-2498

Energy Technology Data Exchange (ETDEWEB)

Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

2008-09-01

One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the “highly ranked” phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

Transuranic waste examination quality assurance at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Bower, J.M.

1987-01-01

Since 1954, defense-generated transuranic (TRU) waste has been received at the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory (INEL). A major objective of the Department of Energy (DOE) Nuclear Waste Management Programs is the proper management of the defense-generated TRU waste. The Stored Waste Examination Pilot Plant (SWEPP) is providing nondestructive examination and assay of retrievably stored contact handled TRU waste in order to certify it to the Waste Isolation Pilot Plant Waste Acceptance Crtieria (WIPP-WAC). SWEPP's capabilities for certifying contact handled waste containers include weighing, real-time radiographic examination, fissile material assay examination, container integrity examination, radiological surveys and labeling of waste containers. These processes involve not only instrument accuracy but also a wide range of technician interpretation from moderate on the assay to 100% on the radiograph. This, therefore, requires a variety of quality assurance techniques to ensure that the examinations and certifications are being performed correctly. The purpose of this paper is to discuss the methods utilized by SWEPP for checking on the examination process and to ensure that waste certifications are being properly performed. Included is the application of the quality assurance techniques to each examination system, the management of the data generated by the examination, and the verifications to ensure accurate certification. 1 ref

Y-12 Plant Groundwater Protection Program: Groundwater and surface water sampling and analysis plan for Calendar Year 1998

International Nuclear Information System (INIS)

1997-09-01

This plan provides a description of the groundwater and surface water quality monitoring activities planned for calendar year (CY) 1998 at the Department of Energy (DOE) Y-12 Plant. These monitoring activities are managed by the Y-12 Plant Environmental Compliance Organization through the Y-12 Plant Groundwater Protection Program (GWPP). Groundwater and surface water monitoring during CY 1998 will be performed in three hydrogeologic regimes at the Y-12 Plant: the Bear Creek Hydrogeologic Regime (Bear Creek Regime), the Upper East Fork Poplar Creek Hydrogeologic Regime (East Fork Regime), and the Chestnut Ridge Hydrogeologic Regime (Chestnut Ridge Regime). The Bear Creek and East Fork regimes are located within Bear Creek Valley, and the Chestnut Ridge Regime is located south of the Y-12 Plant. Groundwater and surface water monitoring will be performed during CY 1998 to comply with: (1) requirements specified in Resource Conservation and Recover Act (RCRA) post-closure permits regarding RCRA corrective action monitoring and RCRA detection monitoring; (2) Tennessee Department of Environment and Conservation regulations governing detection monitoring at nonhazardous solid waste management facilities; and (3) DOE Order 5400.1 surveillance monitoring and exit pathway monitoring. Data from some of the sampling locations in each regime will be used to meet the requirements of more than one of the monitoring drivers listed above. Modifications to the CY 1998 monitoring program may be necessary during implementation. For example, changes in regulatory requirements may alter the parameters specified for selected monitoring wells, or wells could be removed from the planned monitoring network. All modifications to the monitoring program will be approved by the Y-12 Plant GWPP manager and documented as addenda to this sampling and analysis plan

Enhancing plant performance in newer CANDU plants utilizing PLiM methodologies

International Nuclear Information System (INIS)

Azeez, S.; Krishnan, V.S.; Nickerson, J.H.; Kakaria, B.

2002-01-01

Over the past 5 years, Atomic Energy of Canada Ltd. (AECL) has been working with CANDU utilities on comprehensive and integrated CANDU PLiM programs for successful and reliable operation through design life and beyond. Considerable progress has been made in the development of CANDU PLiM methodologies and implementation of the outcomes at the plants. The basis of CANDU PLiM programs is to understand the ageing degradation mechanisms, prevent/minimize the effects of these phenomena in the Critical Structures, Systems and Components (CSSCs), and maintain the CSSC condition as close as possible in the best operating condition. Effective plant practices in surveillance, maintenance, and operations are the primary means of managing ageing. From the experience to date, the CANDU PLiM program will modify and enhance, but not likely replace, existing plant programs that address ageing. However, a successful PLiM program will provide assurance that these existing plant programs are both effective and can be shown to be effective, in managing ageing. This requires a structured and managed approach to both the assessment and implementation processes

Evaluation of training programs: A pragmatic perspective

International Nuclear Information System (INIS)

Wilkinson, J.D.

1996-01-01

The Canadian nuclear regulatory agency endorses the Systematic Approach to Training (SAT) as the most reliable method of providing effective, efficient training to Nuclear Power Plant (NPP) personnel. However the benefits of SAT cannot be realized unless all five phases of SAT are implemented. This is particularly true with respect to evaluation. Although each phase of SAT builds on the preceding one, the evaluation phase continuously feeds back into each of the others and also provides the means to verify the entire training programme building process. It is useful, therefore, to examine the issues relating to the what, why, who, when and how of training programme evaluation. ''What'' identifies the various aspects of the training programme to be evaluated, including the need for training, the training standard, the task list, trainer competence, test results, training results, program acceptance and numerous indicators that identify a need for evaluation. ''Why'' addresses legal and regulatory aspects, resource management, worker and public safety, worker and trainer competence and morale, and the cost/benefit of the training program. ''Who'' examines the need to involve trainers, trainees, plant subject matter experts (SMEs), and both plant and training centre supervisory and management staff. ''When'' addresses time-related concerns such as the importance of ensuring at the outset that the training program is actually needed, the necessity of responding promptly to local, national and world events, changes in legal and regulatory responsibilities, and the overriding importance of timely, routine training program evaluations. ''How'' describes the process of conducting a training program evaluation, and addresses the relationships of these five aspects of evaluation to each other. (author). 10 refs

Configuration management of modifications to nuclear power plants

International Nuclear Information System (INIS)

Capano, G.A.

1983-01-01

This paper examines Configuration Management (CM), which is a method of monitoring and controlling a power plant's data base to ensure that the data base remains consistent and reflects the physical characteristics of the plant. Myriad changes are imposed on power plant systems by regulatory requirements, operations, and administrative needs. This paper outlines the elements a CM program requires to track and assess the impacts of those changes on the data base, and to make necessary revisions. The paper notes several instances where CM has been used successfully, describes several practical applications of CM, and discusses potential cost savings that can be realized from these applications

A mathematical programming framework for early stage design of wastewater treatment plants

DEFF Research Database (Denmark)

Bozkurt, Hande; Quaglia, Alberto; Gernaey, Krist

2015-01-01

The increasing number of alternative wastewater treatment technologies and stricter effluent requirements make the optimal treatment process selection for wastewater treatment plant design a complicated problem. This task, defined as wastewater treatment process synthesis, is currently based on e...... the design problem is formulated as a Mixed Integer (Non)linear Programming problem e MI(N)LP e and solved. A case study is formulated and solved to highlight the application of the framework. © 2014 Elsevier Ltd. All rights reserved....... on expert decisions and previous experiences. This paper proposes a new approach based on mathematical programming to manage the complexity of the problem. The approach generates/identifies novel and optimal wastewater treatment process selection, and the interconnection between unit operations to create...

Final examination of trainees for nuclear power plant operators at an education and training centre

International Nuclear Information System (INIS)

Gieci, A.

1986-01-01

General and specialized theoretical training, on-the-job training in the training power plant and simulator training is followed by a final examination. The examination which is obligatory for all trainees is conceived according to Hick's law which requires linear dependence between the time which the operator needs for taking a decision on how to cope with a certain situation and the measure of entropy of the situation. Research in the field of man-machine relations has helped clarify the thinking of the operator who on the basis of received signals forms what is termed the conceptual model of the situation. The final examination should assess the trainee's ability to form conceptual models - the examination must therefore be something more than just a test of knowledge. The given questions and required answers must create a stress situation for the examinee such that the measure to which he is able to cope is conditioned by his ability to form conceptual models. The statutes of the final examinations were drawn up with the aim of achieving standardization and reproducibility. Questions are put through a special form (a model form is also given). (A.K.)

Seismic design of equipment and piping systems for nuclear power plants in Japan

International Nuclear Information System (INIS)

Minematsu, Akiyoshi

1997-01-01

The philosophy of seismic design for nuclear power plant facilities in Japan is based on 'Examination Guide for Seismic Design of Nuclear Power Reactor Facilities: Nuclear Power Safety Committee, July 20, 1981' (referred to as 'Examination Guide' hereinafter) and the present design criteria have been established based on the survey of governmental improvement and standardization program. The detailed design implementation procedure is further described in 'Technical Guidelines for Aseismic Design of Nuclear Power Plants, JEAG4601-1987: Japan Electric Association'. This report describes the principles and design procedure of the seismic design of equipment/piping systems for nuclear power plant in Japan. (J.P.N.)

Seismic design of equipment and piping systems for nuclear power plants in Japan

Energy Technology Data Exchange (ETDEWEB)

Minematsu, Akiyoshi [Tokyo Electric Power Co., Inc. (Japan)

1997-03-01

The philosophy of seismic design for nuclear power plant facilities in Japan is based on `Examination Guide for Seismic Design of Nuclear Power Reactor Facilities: Nuclear Power Safety Committee, July 20, 1981` (referred to as `Examination Guide` hereinafter) and the present design criteria have been established based on the survey of governmental improvement and standardization program. The detailed design implementation procedure is further described in `Technical Guidelines for Aseismic Design of Nuclear Power Plants, JEAG4601-1987: Japan Electric Association`. This report describes the principles and design procedure of the seismic design of equipment/piping systems for nuclear power plant in Japan. (J.P.N.)

Structural Aging Program to evaluate continued performance of safety-related concrete structures in nuclear power plants

International Nuclear Information System (INIS)

Naus, D.J.; Oland, C.B.; Ellingwood, B.R.

1994-01-01

This report discusses the Structural Aging (SAG) Program which is being conducted at the Oak Ridge National Laboratory (ORNL) for the United States Nuclear Regulatory commission (USNRC). The SAG Program is addressing the aging management of safety-related concrete structures in nuclear power plants for the purpose of providing improved technical bases for their continued service. The program is organized into three technical tasks: Materials Property Data Base, Structural Component Assessment/Repair Technologies, and Quantitative Methodology for continued Service Determinations. Objectives and a summary of recent accomplishments under each of these tasks are presented

Xylella fastidiosa: an examination of a re-emerging plant pathogen.