Science.gov

Sample records for plant safety 2007-2010

  1. Sources and Amounts of Animal, Dairy, and Plant Protein Intake of US Adults in 2007-2010.

    PubMed

    Pasiakos, Stefan M; Agarwal, Sanjiv; Lieberman, Harris R; Fulgoni, Victor L

    2015-08-01

    Dietary guidelines suggest consuming a mixed-protein diet, consisting of high-quality animal, dairy, and plant-based foods. However, current data on the distribution and the food sources of protein intake in a free-living, representative sample of US adults are not available. Data from the National Health and Nutrition Examination Survey (NHANES), 2007-2010, were used in these analyses (n = 10,977, age ≥ 19 years). Several US Department of Agriculture (USDA) databases were used to partition the composition of foods consumed into animal, dairy, or plant components. Mean ± SE animal, dairy, and plant protein intakes were determined and deciles of usual intakes were estimated. The percentages of total protein intake derived from animal, dairy, and plant protein were 46%, 16%, and 30%, respectively; 8% of intake could not be classified. Chicken and beef were the primary food sources of animal protein intake. Cheese, reduced-fat milk, and ice cream/dairy desserts were primary sources of dairy protein intake. Yeast breads, rolls/buns, and nuts/seeds were primary sources of plant protein intake. This study provides baseline data for assessing the effectiveness of public health interventions designed to alter the composition of protein foods consumed by the American public. PMID:26308049

  2. Increasing Plant Based Foods or Dairy Foods Differentially Affects Nutrient Intakes: Dietary Scenarios Using NHANES 2007-2010.

    PubMed

    Cifelli, Christopher J; Houchins, Jenny A; Demmer, Elieke; Fulgoni, Victor L

    2016-01-01

    Diets rich in plant foods and lower in animal-based products have garnered increased attention among researchers, dietitians and health professionals in recent years for their potential to, not only improve health, but also to lessen the environmental impact. However, the potential effects of increasing plant-based foods at the expense of animal-based foods on macro- and micronutrient nutrient adequacy in the U.S. diet is unknown. In addition, dairy foods are consistently under consumed, thus the impact of increased dairy on nutrient adequacy is important to measure. Accordingly, the objective of this study was to use national survey data to model three different dietary scenarios to assess the effects of increasing plant-based foods or dairy foods on macronutrient intake and nutrient adequacy. Data from the National Health and Nutrition Examination Survey (NHANES) 2007-2010 for persons two years and older (n = 17,387) were used in all the analyses. Comparisons were made of usual intake of macronutrients and shortfall nutrients of three dietary scenarios that increased intakes by 100%: (i) plant-based foods; (ii) protein-rich plant-based foods (i.e., legumes, nuts, seeds, soy); and (iii) milk, cheese and yogurt. Scenarios (i) and (ii) had commensurate reductions in animal product intake. In both children (2-18 years) and adults (≥19 years), the percent not meeting the Estimated Average Requirement (EAR) decreased for vitamin C, magnesium, vitamin E, folate and iron when plant-based foods were increased. However the percent not meeting the EAR increased for calcium, protein, vitamin A, and vitamin D in this scenario. Doubling protein-rich plant-based foods had no effect on nutrient intake because they were consumed in very low quantities in the baseline diet. The dairy model reduced the percent not meeting the EAR for calcium, vitamin A, vitamin D, magnesium, and protein, while sodium and saturated fat levels increased. Our modeling shows that increasing plant

  3. The Australian radiation protection and nuclear safety agency megavoltage photon thermoluminescence dosimetry postal audit service 2007-2010.

    PubMed

    Oliver, C P; Butler, D J; Webb, D V

    2012-03-01

    The Australian radiation protection and nuclear safety agency (ARPANSA) has continuously provided a level 1 mailed thermoluminescence dosimetry audit service for megavoltage photons since 2007. The purpose of the audit is to provide an independent verification of the reference dose output of a radiotherapy linear accelerator in a clinical environment. Photon beam quality measurements can also be made as part of the audit in addition to the output measurements. The results of all audits performed between 2007 and 2010 are presented. The average of all reference beam output measurements calculated as a clinically stated dose divided by an ARPANSA measured dose is 0.9993. The results of all beam quality measurements calculated as a clinically stated quality divided by an ARPANSA measured quality is 1.0087. Since 2011 the provision of all auditing services has been transferred from the Ionizing Radiation Standards section to the Australian Clinical Dosimetry Service (ACDS) which is currently housed within ARPANSA. PMID:22302465

  4. Evapotranspiration over spatially extensive plant communities in the Big Cypress National Preserve, southern Florida, 2007-2010

    USGS Publications Warehouse

    Shoemaker, W. Barclay; Lopez, Christian D.; Duever, Michael J.

    2011-01-01

    Net radiation and available energy explained most of the variability in ET observed at all five sites. Mean annual and monthly net radiation varied among the sites in response to cloud cover and the albedo of the land surface and plant community. Net radiation was greatest at the Cypress Swamp site, averaging about 130 W/m2 (watts per square meter) during the 3-year study. Net radiation was generally less at the Dwarf Cypress site, averaging about 115 W/m2 over 3 years. The Dwarf Cypress site apparently has the largest albedo, which likely is due to the sparse canopy and a highly reflective, calcareous, periphyton-covered land surface. Furthermore, mean annual net radiation was least in the first year of the study, which likely was due to greater cloud cover during a relatively wet year. In contrast, net radiation was greatest in the second year of the study, which likely was due to less cloud cover during a relatively dry year.

  5. B Plant interim safety basis

    SciTech Connect

    Chalk, S.E.

    1996-09-01

    This interim safety basis (ISB-008) replaces the B Plant Safety Analysis Report, WHC-SD-WM-SAR-013, Rev. 2 (WHC 1993a). ISB-008 uses existing accident analyses, modified existing accident analyses, and new accident analyses to prove that B Plant remains within the safety envelope for transition, deactivation, standby, and shutdown activities. The analyses in ISB-008 are in accordance with the most current requirements for analytical approach, risk determination, and configuration management. This document and supporting accident analyses replace previous design-basis documents.

  6. Changing Epidemiology of Common Cancers in Southern Iran, 2007-2010: A Cross Sectional Study.

    PubMed

    Masoompour, Seyed Masoom; Lankarani, Kamran B; Honarvar, Behnam; Tabatabaee, Seyed Hamidreza; Moghadami, Mohsen; Khosravizadegan, Zahra

    2016-01-01

    We have evaluated the ever changing epidemiology of cancers in Fars province, Iran since the re-establishment of Fars cancer registry. Based on the collected data from all related sources in Fars province from 2007-2010 we calculated the cancer age-standardized rates per 100,000 person-years (ASRs). The results are presented as incidence rates of cases by site according to the International Classification of Diseases for Oncology (ICD-O), sex, age, crude rate, and ASRs. In women the total ASR was 41.70 per 100,000 from 1985-1989 which had increased to 55.50 and 95.46 during 1998-2002 and 2007-2010. The incidence of breast cancer in women during 2007-2010 was about two and four times higher than 1998-2002 and 1985-1989. The incidence of colorectal cancer in women during 2007-2010 was about three and five times higher than 1998-2002 and 1985-1989. In men the total ASR was 62.9 per 100,000 in 1985-1989 that increased to 64.50 and 101.48 during 1998-2002 and 2007-2010. Although stomach cancer was the most common cancer among men during 1985-1989 and 1998-2002, but in recent study bladder cancer was the most common cancer among men in Fars province. The incidence of colorectal cancer in men during 2007-2010 was about three times higher than 1998-2002 and 1985-1989. This study shows growing incidence of cancer in southern Iran. The colorectal cancer in both genders had increased and its pattern is similar to western countries. In men, bladder and prostate cancers had a growing rate and the incidences of these cancers in the present study were greater than stomach cancer. PMID:27219458

  7. Kansas City Plant Celebrates Safety Milestone

    ScienceCinema

    None

    2010-09-01

    A gang of motorcycle riders arrived at the NNSA's Kansas City Plant on July 1 to help celebrate a significant safety achievement - working nearly five million hours, covering a one-year period without a lost-time injury. The bikers -- some of whom are plant employees -- represent Bikers Against Child Abuse, the local nonprofit selected to receive a $5,000 donation as part of the plant's safety achievement celebration. The organization was selected because it aligns with the plant's community outreach focus on Family Safety & Security and partnership with the plant's union members.

  8. Kansas City Plant Celebrates Safety Milestone

    SciTech Connect

    2010-07-06

    A gang of motorcycle riders arrived at the NNSA's Kansas City Plant on July 1 to help celebrate a significant safety achievement - working nearly five million hours, covering a one-year period without a lost-time injury. The bikers -- some of whom are plant employees -- represent Bikers Against Child Abuse, the local nonprofit selected to receive a $5,000 donation as part of the plant's safety achievement celebration. The organization was selected because it aligns with the plant's community outreach focus on Family Safety & Security and partnership with the plant's union members.

  9. Nuclear Plant/Hydrogen Plant Safety: Issues and Approaches

    SciTech Connect

    Steven R. Sherman

    2007-06-01

    The U.S. Department of Energy, through its agents the Next Generation Nuclear Plant Project and the Nuclear Hydrogen Initiative, is working on developing the technologies to enable the large scale production of hydrogen using nuclear power. A very important consideration in the design of a co-located and connected nuclear plant/hydrogen plant facility is safety. This study provides an overview of the safety issues associated with a combined plant and discusses approaches for categorizing, quantifying, and addressing the safety risks.

  10. Plant the Seeds of Safety

    ERIC Educational Resources Information Center

    Roy, Ken

    2004-01-01

    Both indoor and outdoor garden plants can cause problems. For example, the foliage of the bird-of-paradise and philodendron plants is toxic. A poinsettia leaf can kill a young child. Outdoor plants such as castor beans are highly dangerous. All parts of the potato and tomato plant are poisonous, except the potato and tomato themselves. Large…

  11. Occurrence and Distribution of Carbamate Pesticides and Metalaxyl in Southern Ontario Surface Waters 2007-2010.

    PubMed

    Struger, John; Grabuski, Josey; Cagampan, Steve; Sverko, Ed; Marvin, Chris

    2016-04-01

    Surface water sampling in 2007-2010 measured the occurrence of carbamates and metalaxyl during base flow conditions and wet weather events in southern Ontario surface waters. Carbaryl, metalaxyl and pirimicarb were the most frequently detected compounds. In 2008 these three compounds were detected in over 50 % of the samples. Overall mean concentrations of carbaryl and metalaxyl over the course of the study (2007-2010) were 15 and 18 ng/L, respectively. Elevated concentrations of carbaryl (~100 to ~950 ng/L) appeared associated with wet weather (high flow) events, while highest concentrations of metalaxyl (~20-1330 ng/L) were correlated with base flow conditions. We attributed these observations as the result of runoff of carbaryl from the watershed during rain events, while metalaxyl contamination may have resulted primarily from spray drift. PMID:26754544

  12. EDITORIAL: Safety aspects of fusion power plants

    NASA Astrophysics Data System (ADS)

    Kolbasov, B. N.

    2007-07-01

    This special issue of Nuclear Fusion contains 13 informative papers that were initially presented at the 8th IAEA Technical Meeting on Fusion Power Plant Safety held in Vienna, Austria, 10-13 July 2006. Following recommendation from the International Fusion Research Council, the IAEA organizes Technical Meetings on Fusion Safety with the aim to bring together experts to discuss the ongoing work, share new ideas and outline general guidance and recommendations on different issues related to safety and environmental (S&E) aspects of fusion research and power facilities. Previous meetings in this series were held in Vienna, Austria (1980), Ispra, Italy (1983), Culham, UK (1986), Jackson Hole, USA (1989), Toronto, Canada (1993), Naka, Japan (1996) and Cannes, France (2000). The recognized progress in fusion research and technology over the last quarter of a century has boosted the awareness of the potential of fusion to be a practically inexhaustible and clean source of energy. The decision to construct the International Thermonuclear Experimental Reactor (ITER) represents a landmark in the path to fusion power engineering. Ongoing activities to license ITER in France look for an adequate balance between technological and scientific deliverables and complying with safety requirements. Actually, this is the first instance of licensing a representative fusion machine, and it will very likely shape the way in which a more common basis for establishing safety standards and policies for licensing future fusion power plants will be developed. Now that ITER licensing activities are underway, it is becoming clear that the international fusion community should strengthen its efforts in the area of designing the next generations of fusion power plants—demonstrational and commercial. Therefore, the 8th IAEA Technical Meeting on Fusion Safety focused on the safety aspects of power facilities. Some ITER-related safety issues were reported and discussed owing to their potential

  13. Nuclear power-plant safety functions

    SciTech Connect

    Corcoran, W.R.; Finnicum, D.J.; Hubbard, F.R. III; Musick, C.R.; Walzer, P.F.

    1981-03-01

    The concept of safety functions is discussed. Ten critical safety functions and the multiple success paths available for accomplishing them are described. Use of the safety function concept in the development of emergency procedures, operator training, and control-room displays provides a systematic approach and a hierarchy of protection that an operator can use to mitigate the consequences of an event. The safety function concept can also be applied to the design and analysis of nuclear plant systems and to the evaluation of past expierience.

  14. Lidar surveys reveal eruptive volumes and rates at Etna, 2007-2010

    NASA Astrophysics Data System (ADS)

    Behncke, Boris; Fornaciai, Alessandro; Neri, Marco; Favalli, Massimiliano; Ganci, Gaetana; Mazzarini, Francesco

    2016-05-01

    The quantification of eruptive activity represents one major challenge in volcanology. Digital comparison of lidar-based elevation models of Etna (Italy) was made to quantify the volumes of volcanics emitted in 2007-2010. During this period, Etna produced several summit paroxysms followed by a flank eruption. We integrated the total volume difference resulting from the subtraction of the 2007 and 2010 digital elevation models with volumes of eruptive products based on field and aerial surveys to attribute volumes with hitherto unrealized precision to poorly constrained eruptions. The total erupted volume of 2007-2010 is >86 × 106 m3, most (~74 × 106 m3) of which is made up by the lava flows of the 2008-2009 flank eruption. The survey also reveals the high lava volume (5.73 × 106 m3) and average eruption rate (~400 m3 s-1) of the 10 May 2008 paroxysm, whose flow front stopped 6.2 km from the vent, not far from the town of Zafferana Etnea.

  15. Plutonium Finishing Plant safety evaluation report

    SciTech Connect

    Not Available

    1995-01-01

    The Plutonium Finishing Plant (PFP) previously known as the Plutonium Process and Storage Facility, or Z-Plant, was built and put into operation in 1949. Since 1949 PFP has been used for various processing missions, including plutonium purification, oxide production, metal production, parts fabrication, plutonium recovery, and the recovery of americium (Am-241). The PFP has also been used for receipt and large scale storage of plutonium scrap and product materials. The PFP Final Safety Analysis Report (FSAR) was prepared by WHC to document the hazards associated with the facility, present safety analyses of potential accident scenarios, and demonstrate the adequacy of safety class structures, systems, and components (SSCs) and operational safety requirements (OSRs) necessary to eliminate, control, or mitigate the identified hazards. Documented in this Safety Evaluation Report (SER) is DOE`s independent review and evaluation of the PFP FSAR and the basis for approval of the PFP FSAR. The evaluation is presented in a format that parallels the format of the PFP FSAR. As an aid to the reactor, a list of acronyms has been included at the beginning of this report. The DOE review concluded that the risks associated with conducting plutonium handling, processing, and storage operations within PFP facilities, as described in the PFP FSAR, are acceptable, since the accident safety analyses associated with these activities meet the WHC risk acceptance guidelines and DOE safety goals in SEN-35-91.

  16. Safety in nuclear power plants in India

    PubMed Central

    Deolalikar, R.

    2008-01-01

    Safety in nuclear power plants (NPPs) in India is a very important topic and it is necessary to dissipate correct information to all the readers and the public at large. In this article, I have briefly described how the safety in our NPPs is maintained. Safety is accorded overriding priority in all the activities. NPPs in India are not only safe but are also well regulated, have proper radiological protection of workers and the public, regular surveillance, dosimetry, approved standard operating and maintenance procedures, a well-defined waste management methodology, proper well documented and periodically rehearsed emergency preparedness and disaster management plans. The NPPs have occupational health policies covering periodic medical examinations, dosimetry and bioassay and are backed-up by fully equipped Personnel Decontamination Centers manned by doctors qualified in Occupational and Industrial Health. All the operating plants are ISO 14001 and IS 18001 certified plants. The Nuclear Power Corporation of India Limited today has 17 operating plants and five plants under construction, and our scientists and engineers are fully geared to take up many more in order to meet the national requirements. PMID:20040970

  17. Safety in nuclear power plants in India.

    PubMed

    Deolalikar, R

    2008-12-01

    Safety in nuclear power plants (NPPs) in India is a very important topic and it is necessary to dissipate correct information to all the readers and the public at large. In this article, I have briefly described how the safety in our NPPs is maintained. Safety is accorded overriding priority in all the activities. NPPs in India are not only safe but are also well regulated, have proper radiological protection of workers and the public, regular surveillance, dosimetry, approved standard operating and maintenance procedures, a well-defined waste management methodology, proper well documented and periodically rehearsed emergency preparedness and disaster management plans. The NPPs have occupational health policies covering periodic medical examinations, dosimetry and bioassay and are backed-up by fully equipped Personnel Decontamination Centers manned by doctors qualified in Occupational and Industrial Health. All the operating plants are ISO 14001 and IS 18001 certified plants. The Nuclear Power Corporation of India Limited today has 17 operating plants and five plants under construction, and our scientists and engineers are fully geared to take up many more in order to meet the national requirements. PMID:20040970

  18. EDITORIAL: Safety aspects of fusion power plants

    NASA Astrophysics Data System (ADS)

    Kolbasov, B. N.

    2007-07-01

    This special issue of Nuclear Fusion contains 13 informative papers that were initially presented at the 8th IAEA Technical Meeting on Fusion Power Plant Safety held in Vienna, Austria, 10-13 July 2006. Following recommendation from the International Fusion Research Council, the IAEA organizes Technical Meetings on Fusion Safety with the aim to bring together experts to discuss the ongoing work, share new ideas and outline general guidance and recommendations on different issues related to safety and environmental (S&E) aspects of fusion research and power facilities. Previous meetings in this series were held in Vienna, Austria (1980), Ispra, Italy (1983), Culham, UK (1986), Jackson Hole, USA (1989), Toronto, Canada (1993), Naka, Japan (1996) and Cannes, France (2000). The recognized progress in fusion research and technology over the last quarter of a century has boosted the awareness of the potential of fusion to be a practically inexhaustible and clean source of energy. The decision to construct the International Thermonuclear Experimental Reactor (ITER) represents a landmark in the path to fusion power engineering. Ongoing activities to license ITER in France look for an adequate balance between technological and scientific deliverables and complying with safety requirements. Actually, this is the first instance of licensing a representative fusion machine, and it will very likely shape the way in which a more common basis for establishing safety standards and policies for licensing future fusion power plants will be developed. Now that ITER licensing activities are underway, it is becoming clear that the international fusion community should strengthen its efforts in the area of designing the next generations of fusion power plants—demonstrational and commercial. Therefore, the 8th IAEA Technical Meeting on Fusion Safety focused on the safety aspects of power facilities. Some ITER-related safety issues were reported and discussed owing to their potential

  19. Waste Isolation Pilot Plant Safety Analysis Report

    SciTech Connect

    1995-11-01

    The following provides a summary of the specific issues addressed in this FY-95 Annual Update as they relate to the CH TRU safety bases: Executive Summary; Site Characteristics; Principal Design and Safety Criteria; Facility Design and Operation; Hazards and Accident Analysis; Derivation of Technical Safety Requirements; Radiological and Hazardous Material Protection; Institutional Programs; Quality Assurance; and Decontamination and Decommissioning. The System Design Descriptions`` (SDDS) for the WIPP were reviewed and incorporated into Chapter 3, Principal Design and Safety Criteria and Chapter 4, Facility Design and Operation. This provides the most currently available final engineering design information on waste emplacement operations throughout the disposal phase up to the point of permanent closure. Also, the criteria which define the TRU waste to be accepted for disposal at the WIPP facility were summarized in Chapter 3 based on the WAC for the Waste Isolation Pilot Plant.`` This Safety Analysis Report (SAR) documents the safety analyses that develop and evaluate the adequacy of the Waste Isolation Pilot Plant Contact-Handled Transuranic Wastes (WIPP CH TRU) safety bases necessary to ensure the safety of workers, the public and the environment from the hazards posed by WIPP waste handling and emplacement operations during the disposal phase and hazards associated with the decommissioning and decontamination phase. The analyses of the hazards associated with the long-term (10,000 year) disposal of TRU and TRU mixed waste, and demonstration of compliance with the requirements of 40 CFR 191, Subpart B and 40 CFR 268.6 will be addressed in detail in the WIPP Final Certification Application scheduled for submittal in October 1996 (40 CFR 191) and the No-Migration Variance Petition (40 CFR 268.6) scheduled for submittal in June 1996. Section 5.4, Long-Term Waste Isolation Assessment summarizes the current status of the assessment.

  20. Lipid Screening in Children and Adolescents in Community Practice 2007-2010

    PubMed Central

    Margolis, Karen L.; Greenspan, Louise C.; Trower, Nicole K.; Daley, Matthew F.; Daniels, Stephen R.; Lo, Joan C.; Kharbanda, Elyse O.; Sinaiko, Alan R.; Magid, David J.; Parker, Emily D.; Chandra, Malini; Tavel, Heather M.; O'Connor, Patrick J.

    2014-01-01

    Background Integrated guidelines on cardiovascular health and risk reduction in children issued in 2011 newly recommended universal screening for dyslipidemia in children at 9-11 years and 17-21 years. Methods and Results We determined the frequency and results of lipid testing in 301,080 children and adolescents aged 3-19 enrolled in three large U.S. health systems in 2007-2010 before the 2011 guidelines were issued. Overall, 9.8% of the study population was tested for lipids. The proportion tested varied by BMI percentile (5.9% of normal weight, 10.8% of overweight and 26.9% of obese children) and age (8.9% of 9-11 year olds and 24.3% of 17-19 year olds). In normal weight individuals, 2.8% of 9-11 year olds and 22.0% of 17-19 year olds were tested. In multivariable models, age and BMI category remained strongly associated with lipid testing. Sex, race, ethnicity, and blood pressure were weakly associated with testing. Abnormal lipid levels were found in 8.6% for total cholesterol, 22.5% for HDL-C, 12.0% for non-HDL-C, 8.0% for LDL-C and 21% for triglycerides (age 10-19). There was a strong and graded association of abnormal lipid levels with BMI, particularly for HDL-C and triglycerides (2- to 6-fold higher odds ratio in obese compared with normal weight children). Conclusions Lipid screening was uncommon in 9-11 year olds and was performed in a minority of 17-19 year olds during 2007-2010. These data serve as a benchmark for assessing change in practice patterns after the new recommendations for pediatric lipid screening and management. PMID:25160839

  1. The health of male veterans and nonveterans aged 25-64: United States, 2007-2010.

    PubMed

    Kramarow, Ellen A; Pastor, Patricia N

    2012-08-01

    The well-being of military personnel and their families is a topic of growing concern in public health. The effects of military service on physical and psychological health, especially after extended overseas deployments, are complex. There may also be long-term consequences of military service for the health and health care utilization of veterans as they age (1). Today, over 12 million men aged 25-64 in the United States are veterans, representing 15% of the total U.S. male population at those ages (2). More attention is now being paid to gathering accurate data to help veterans readjust to civilian life (3). Many studies of veterans only use information from military or veteran databases, which limits the ability to make comparisons with the overall population. This report uses data from the 2007-2010 National Health Interview Survey (NHIS) to describe the health status of community-dwelling male veterans aged 25-64. It directly compares the health status of veterans with nonveterans on a variety of measures. PMID:23101789

  2. Association between arsenic exposure and thyroid function: data from NHANES 2007-2010.

    PubMed

    Jain, Ram B

    2016-01-01

    The association of arsenic variables in urine, total arsenic (UAS), arsenobetaine (UAB), dimethylarsinic acid (UDMA), and arsenic adjusted for arsenobetaine (UAAS) with thyroid-stimulating hormone (TSH), free and total serum thyroxine (FT4, TT4), free and total triiodothyronine (FT3, TT3), and thyroglobulin (TGN) was evaluated by analyzing data from 2007-2010 National Health and Nutrition Examination Survey. For iodine deficient males, there was a positive association between TSH and UDMA (p < 0.01) and a negative association between the levels of TT4 and UDMA (p < 0.01). Levels of UAAS were inversely associated with the levels of TT4 for both iodine-deficient (p = 0.054) and iodine-replete females (p < 0.01). For iodine-replete females, levels of both TSH and TGN increased with decrease in the levels of both UAB (p < 0.01) and UAS (p < 0.01). There was also a negative association between TSH and UAB as well as UAS (p < 0.01). For iodine-replete males, increased levels of UDMA were associated with decreasing levels of FT4 (p = 0.03). PMID:26153429

  3. Anthropometric reference data for children and adults: United States, 2007-2010.

    PubMed

    Fryar, Cheryl D; Gu, Qiuping; Ogden, Cynthia L

    2012-10-01

    Objective-This report presents national anthropometric reference data for all ages of the U.S. population in 2007-2010, adding to results published previously from the years 1960-2006. Methods-Data are from the National Health and Nutrition Examination Survey (NHANES), a complex, stratified, and multistage probability sample of the civilian noninstitutionalized U.S. population. Anthropometry measurements were obtained from 20,015 survey participants. The anthropometric measures included weight, height, recumbent length, circumferences, limb lengths, and skinfold thickness measurements. Results-The tables in this report include weighted population means, standard errors of the means, and selected percentiles of body measurement values. Because measurements varied by sex and age (as well as race and ethnicity in adults), results are reported by these subgroups. Conclusions-These latest NHANES data add to the knowledge about trends in child growth and development and trends in the distribution of body measurements, such as weight and height, in the U.S. population. PMID:25204692

  4. Plutonium finishing plant safety systems and equipment list

    SciTech Connect

    Bergquist, G.G.

    1995-01-06

    The Safety Equipment List (SEL) supports Analysis Report (FSAR), WHC-SD-CP-SAR-021 and the Plutonium Finishing Plant Operational Safety Requirements (OSRs), WHC-SD-CP-OSR-010. The SEL is a breakdown and classification of all Safety Class 1, 2, and 3 equipment, components, or system at the Plutonium Finishing Plant complex.

  5. Technical Safety Appraisal of the Pinellas Plant

    SciTech Connect

    Not Available

    1991-01-01

    This report presents the Technical Safety Appraisal (TSA) of the Pinellas Plant in Pinellas County, Florida. The plant is owned and controlled by the US Department of Energy and operated by General Electric Neutron Devices (GEND). The TSA was performed during the period January 15--31, 1989, in support of a Tiger Team Assessment which occurred during the period January 15 to February 2, 1989. The TSA provided the Safety and Health Subteam input to the Tiger Team Assessment. The completion of the assessment process includes: (1) submission of the Team's preliminary findings and concerns, in a Draft Report, to the Manager, Albuquerque Operations Office and to the site contractors at the conclusion of the onsite assessment; (2) review of the Draft Report for technical and factual accuracy; incorporation of the appropriate review comments, suggested changes, and modifications, as well as input from all interested Program Secretarial Offices; preparation of a draft Action Plan by the Albuquerque Operations Office to address the Concerns, and submittal of that Action Plan through the Program Office to ES H for their review and comment. The Secretary approved the final Action Plan on December 16, 1990, and directed its implementation. The comments and suggestions of the Program Secretarial Offices, the Operations Office, and the site contractor have been incorporated, as appropriate, in this report prior to its publication.

  6. Interplanetary shocks and foreshocks observed by STEREO during 2007-2010

    NASA Astrophysics Data System (ADS)

    Blanco-Cano, X.; Kajdič, P.; Aguilar-Rodríguez, E.; Russell, C. T.; Jian, L. K.; Luhmann, J. G.

    2016-02-01

    Interplanetary shocks in the heliosphere modify the solar wind through which they pass. In particular, shocks play an important role in particle acceleration. During the extended solar minimum (2007-2010) STEREO observed 65 forward shocks driven by stream interactions (SI), with magnetosonic Mach numbers Mms ≈ 1.1-4.0 and shock normal angles θBN ~ 20-87°. We analyze the waves associated with these shocks and find that the region upstream can be permeated by whistler waves (f ~ 1 Hz) and/or ultra low frequency (ULF) waves (f ~ 10-2-10-1 Hz). While whistlers appear to be generated at the shock, the origin of ULF waves is most probably associated with local kinetic ion instabilities. We find that when the Mach number (Mms) is low and the shock is quasi-perpendicular (θBN > 45°) whistler waves remain close to the shock. As Mms increases, the shock profile changes and can develop a foot and overshoot associated with ion reflection and gyration. Whistler precursors can be superposed on the foot region, so that some quasi-perpendicular shocks have characteristics of both subcritical and supercritical shocks. When the shock is quasi-parallel (θBN < 45°) a large foreshock with suprathermal ions and waves can form. Upstream, there are whistler trains at higher frequencies whose characteristics can be slightly modified probably by reflected and/or leaked ions and by almost circularly polarized waves at lower frequencies that may be locally generated by ion instabilities. In contrast with planetary bow shocks, most of the upstream waves studied here are mainly transverse and no steepening occurs. Some quasi-perpendicular shocks (45° < θBN < 60°) are preceded by ULF waves and ion foreshocks. Fluctuations downstream of quasi-parallel shocks tend to have larger amplitudes than waves in the sheath of quasi-perpendicular shocks. We compare SI-driven shock properties with those of shocks generated by interplanetary coronal mass ejections (ICMEs). During the same years

  7. 78 FR 47010 - Proposed Safety Evaluation for Plant-Specific

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-08-02

    ... COMMISSION Proposed Safety Evaluation for Plant-Specific Technical Specifications Task Force Traveler... requesting public comment on the proposed model safety evaluation (SE) for plant- specific adoption of... ``Begin Web- based ADAMS Search.'' For problems with ADAMS, please contact the NRC's Public Document...

  8. Integrated deterministic and probabilistic safety analysis for safety assessment of nuclear power plants

    DOE PAGESBeta

    Di Maio, Francesco; Zio, Enrico; Smith, Curtis; Rychkov, Valentin

    2015-07-06

    The present special issue contains an overview of the research in the field of Integrated Deterministic and Probabilistic Safety Assessment (IDPSA) of Nuclear Power Plants (NPPs). Traditionally, safety regulation for NPPs design and operation has been based on Deterministic Safety Assessment (DSA) methods to verify criteria that assure plant safety in a number of postulated Design Basis Accident (DBA) scenarios. Referring to such criteria, it is also possible to identify those plant Structures, Systems, and Components (SSCs) and activities that are most important for safety within those postulated scenarios. Then, the design, operation, and maintenance of these “safety-related” SSCs andmore » activities are controlled through regulatory requirements and supported by Probabilistic Safety Assessment (PSA).« less

  9. Integrated deterministic and probabilistic safety analysis for safety assessment of nuclear power plants

    SciTech Connect

    Di Maio, Francesco; Zio, Enrico; Smith, Curtis; Rychkov, Valentin

    2015-07-06

    The present special issue contains an overview of the research in the field of Integrated Deterministic and Probabilistic Safety Assessment (IDPSA) of Nuclear Power Plants (NPPs). Traditionally, safety regulation for NPPs design and operation has been based on Deterministic Safety Assessment (DSA) methods to verify criteria that assure plant safety in a number of postulated Design Basis Accident (DBA) scenarios. Referring to such criteria, it is also possible to identify those plant Structures, Systems, and Components (SSCs) and activities that are most important for safety within those postulated scenarios. Then, the design, operation, and maintenance of these “safety-related” SSCs and activities are controlled through regulatory requirements and supported by Probabilistic Safety Assessment (PSA).

  10. Victimization among female and male sexual minority status groups: evidence from the British Crime Survey 2007-2010.

    PubMed

    Mahoney, Bere; Davies, Michelle; Scurlock-Evans, Laura

    2014-01-01

    International surveys of victims show crime rates in England and Wales, including hate crimes, are among the highest in Europe. Nevertheless, sexual minority status is a less considered risk factor in general victimization research. This study used sexual minority status and sex to predict victimization across British Crime Surveys from 2007-2010. Logistic regression analyses showed sexual minority status groups were more likely than heterosexuals to be victimized from any and some specific crimes. However, bisexuals rather than lesbians or gay men were more consistently victimized, notably by sexual attacks and within the household. Implications for understanding victimization among these groups are discussed. PMID:24972149

  11. Safety/security interface assessments at commercial nuclear power plants

    SciTech Connect

    Byers, K.R.; Brown, P.J.; Norderhaug, L.R.

    1985-07-01

    The findings of the Haynes Task Force Committee (NUREG-0992) are used as the basis for defining safety/security assessment team activities at commercial nuclear power plants in NRC Region V. A safety/security interface assessment outline and the approach used for making the assessments are presented along with the composition of team members. As a result of observing simulated plant emergency conditions during scheduled emergency preparedness exercises, examining security and operational response procedures, and interviewing plant personnel, the team has identified instances where safety/security conflicts can occur. 2 refs.

  12. Improving the safety of LWR power plants. Final report

    SciTech Connect

    Not Available

    1980-04-01

    This report documents the results of the Study to identify current, potential research issues and efforts for improving the safety of Light Water Reactor (LWR) power plants. This final report describes the work accomplished, the results obtained, the problem areas, and the recommended solutions. Specifically, for each of the issues identified in this report for improving the safety of LWR power plants, a description is provided in detail of the safety significance, the current status (including information sources, status of technical knowledge, problem solution and current activities), and the suggestions for further research and development. Further, the issues are ranked for action into high, medium, and low priority with respect to primarily (a) improved safety (e.g. potential reduction in public risk and occupational exposure), and secondly (b) reduction in safety-related costs (improving or maintaining level of safety with simpler systems or in a more cost-effective manner).

  13. Passive Safety Features in Advanced Nuclear Power Plant Design

    NASA Astrophysics Data System (ADS)

    Tahir, M.; Chughtai, I. R.; Aslam, M.

    2013-03-01

    For implementation of advance passive safety features in future nuclear power plant design, a passive safety system has been proposed and its response has been observed for Loss of Coolant Accident (LOCA) in the cold leg of a reactor coolant system. In a transient simulation the performance of proposed system is validated against existing safety injection system for a reference power plant of 325 MWe. The existing safety injection system is a huge system and consists of many active components including pumps, valves, piping and Instrumentation and Control (I&C). A good running of the active components of this system is necessary for its functionality as high head safety injection system under design basis accidents. Using reactor simulation technique, the proposed passive safety injection system and existing safety injection system are simulated and tested for their performance under large break LOCA for the same boundary conditions. Critical thermal hydraulic parameters of both the systems are presented graphically and discussed. The results obtained are approximately the same in both the cases. However, the proposed passive safety injection system is a better choice for such type of reactors due to reduction in components with improved safety.

  14. Work practices, fatigue, and nuclear power plant safety performance.

    PubMed

    Baker, K; Olson, J; Morisseau, D

    1994-06-01

    This paper focuses on work practices that may contribute to fatigue-induced performance decrements in the commercial nuclear power industry. Specifically, the amount of overtime worked by operations, technical, and maintenance personnel and the 12-h operator shift schedule are studied. Although overtime for all three job categories was fairly high at a number of plants, the analyses detected a clear statistical relationship only between operations overtime and plant safety performance. The results for the 12-h operator shift schedule were ambiguous. Although the 12-h operator shift schedule was correlated with operator error, it was not significantly related to the other five safety indicators. This research suggests that at least one of the existing work practices--the amount of operator overtime worked at some plants--represents a safety concern in this industry; however, further research is required before any definitive conclusions can be drawn. PMID:8070790

  15. Safety Evaluation Report of the Waste Isolation Pilot Plant Contact Handled (CH) Waste Documented Safety Analysis

    SciTech Connect

    Washington TRU Solutions LLC

    2005-09-01

    This Safety Evaluation Report (SER) documents the Department of Energy’s (DOE's) review of Revision 9 of the Waste Isolation Pilot Plant Contact Handled (CH) Waste Documented Safety Analysis, DOE/WIPP-95-2065 (WIPP CH DSA), and provides the DOE Approval Authority with the basis for approving the document. It concludes that the safety basis documented in the WIPP CH DSA is comprehensive, correct, and commensurate with hazards associated with CH waste disposal operations. The WIPP CH DSA and associated technical safety requirements (TSRs) were developed in accordance with 10 CFR 830, Nuclear Safety Management, and DOE-STD-3009-94, Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Safety Analysis Reports.

  16. Aging of nuclear power plant safety cables

    SciTech Connect

    Gillen, K.T.; Salazar, E.A.

    1986-01-01

    Results from an extensive aging program on polymeric materials stripped from unused nuclear reactor safety cables are described. Mechanical damage was monitored after room temperature aging in a Co-60 gamma radiation source at various humidities and radiation dose rates ranging from 1.2 Mrad/h to 2 krad/h. For chloroprene, chlorosulfonated polyethylene, and silicone materials, the mechanical degradation was found to depend only on the total integrated radiation dose, implying that radiation dose rate effects are small. On the other hand, strong evidence for radiation dose rate effects were found for an ethylene propylene rubber material and a cross-linked polyolefin material. Humidity effects were determined to be insignificant for all the materials studied.

  17. Nuclear power plant safety related pump issues

    SciTech Connect

    Colaccino, J.

    1996-12-01

    This paper summarizes of a number of pump issues raised since the Third NRC/ASME Symposium on Valve and Pump Testing in 1994. General issues discussed include revision of NRC Inspection Procedure 73756, issuance of NRC Information Notice 95-08 on ultrasonic flow meter uncertainties, relief requests for tests that are determined by the licensee to be impractical, and items in the ASME OM-1995 Code, Subsection ISTB, for pumps. The paper also discusses current pump vibration issues encountered in relief requests and plant inspections - which include smooth running pumps, absolute vibration limits, and vertical centrifugal pump vibration measurement requirements. Two pump scope issues involving boiling water reactor waterlog and reactor core isolation cooling pumps are also discussed. Where appropriate, NRC guidance is discussed.

  18. SAFETY EVALUATION OF RENOVATED WASTEWATER FROM A POULTRY PROCESSING PLANT

    EPA Science Inventory

    A three-phase evaluation of reclaimed process wastewater for reuse was undertaken at the Sterling Processing Corporation plant in Oakland, Maryland. The main objective was to evaluate the safety for human consumption of poultry exposed during processing to an average 50 percent m...

  19. Focus on food safety: Human pathogens on plants

    Technology Transfer Automated Retrieval System (TEKTRAN)

    This article introduces the first Focus Issue of Phytopathology, a dedicated issue of the journal that highlights a topic of significant interest to our readership. This first Focus Issue addresses the topic of food safety and the biology of human pathogens on plants, a relatively new problem in pla...

  20. Health Effects of Unemployment in Denmark, Norway and Sweden 2007-2010: Differing Economic Conditions, Differing Results?

    PubMed

    Heggebø, Kristian

    2016-07-01

    This article investigates short-term health effects of unemployment for individuals in Denmark, Norway, and Sweden during an economic downturn (2007-2010) that hit the Scandinavian countries with diverging strength. The longitudinal part of the European Union Statistics on Income and Living Conditions (EU-SILC) data material is analyzed, and results from generalized least squares estimation indicate that Denmark is the only Scandinavian country in which health status deteriorated among the unemployed. The individual-level (and calendar year) fixed-effect results confirm the negative relationship between unemployment and health status in Denmark. This result is robust across different subsamples, model specifications, and changes in both the dependent and independent variable. Health status deteriorated especially among women and people in prime working age (30-59 years). There is, however, only scant evidence of short-term health effects among the recently unemployed in Norway and Sweden. The empirical findings are discussed in light of: (1) the adequacy of the unemployment insurance system, (2) the likelihood of re-employment for the displaced worker, and (3) selection patterns into and out of employment in the years preceding and during the economic downturn. PMID:26970456

  1. Defining pathogenic verocytotoxin-producing Escherichia coli (VTEC) from cases of human infection in the European Union, 2007-2010.

    PubMed

    Messens, W; Bolton, D; Frankel, G; Liebana, E; McLAUCHLIN, J; Morabito, S; Oswald, E; Threlfall, E J

    2015-06-01

    During 2007-2010, 13 545 confirmed human verocytotoxin (VT)-producing Escherichia coli (VTEC) infections were reported in the European Union, including 777 haemolytic uraemic syndrome (HUS) cases. Clinical manifestations were reported for 53% of cases, 64% of which presented with diarrhoea alone and 10% with HUS. Isolates from 85% of cases were not fully serotyped and could not be classified on the basis of the Karmali seropathotype concept. There is no single or combination of phenotypic or genetic marker(s) that fully define 'pathogenic' VTEC. Isolates which contain the vtx2 (verocytotoxin 2) gene in combination with the eae (intimin-encoding) gene or aaiC (secreted protein of enteroaggregative E. coli) and aggR (plasmid-encoded regulator) genes have been associated with a higher risk of more severe illness. A molecular approach targeting genes encoding VT and other virulence determinants is thus proposed to allow an assessment of the potential severity of disease that may be associated with a given VTEC isolate. PMID:25921781

  2. Effects of Health Education of Diabetic Patient’s Knowledge at Diabetic Health Centers, Khartoum State, Sudan: 2007-2010

    PubMed Central

    MakkiAwouda, Fathia Osman; Elmukashfi, Taha Ahmed; Hag Al-Tom, Seed Ahmed

    2014-01-01

    Background: Educating and training diabetic patients is necessary for controlling and improving their health. Methods: It was Quasi-experimental study design study. The study aimed to determine the effects of health education on the achievements of diabetic patients regarding control and improvement of their health status; at Diabetic Health Centers in Khartoum State, Sudan; 2007-2010. The target populations were diabetic patients, who attended the diabetic health centers to receive their treatment. Using simple random sampling 152 patients were selected (58 males and 94 females). Before and after comparison was done. Data was processed using SPSS and pair t-test was used to determine the effect of health education. P-value equal or less than 0.05 was considered statistically significant. Findings: Test for before and after comparison was found to be statistically significant (p<0.05) for diabetic patients. They gained more knowledge after the implementation of the program; particularly in the areas of the nature and signs and symptoms of the disease, signs and symptoms of hypo & hyperglycemia, causes and warning signs of foot problems, foot care, and importance of exercises. Conclusion and Recommendations: Health education of diabetic patients is crucial for control of diabetes. Capacity building of diabetic health centers, strengthening diabetic patients association, and more research to study the effect of health education on diabetic patients were needed. PMID:24576384

  3. Relation between diet cost and Healthy Eating Index 2010 scores among adults in the United States 2007-2010

    PubMed Central

    Rehm, Colin D.; Monsivais, Pablo; Drewnowski, Adam

    2016-01-01

    Background Food prices may be one reason for the growing socioeconomic disparities in diet quality. Objective To evaluate the association between diet costs and the Healthy Eating Index-2010 (HEI-2010). Methods Cross-sectional study based on 11,181 adults from the 2007-2010 National Health and Nutrition Examination Survey, analyzed in spring 2014. Diet cost was estimated by linking dietary data with a national food price database. The HEI-2010, a measure of adherence to the Dietary Guidelines, was the outcome. The population ratio method was used to estimate the average HEI-2010 scores by quintile of energy-adjusted diet cost. Additional analyses evaluated the association between cost and HEI-2010 components. Results There was a strong positive association between lower energy-adjusted diet costs and lower HEI-2010 scores. The association was stronger among women (p-interaction=0.003). Lower diet costs were associated with lower consumption of vegetables, fruit, whole grains, and seafood, and higher consumption of refined grains and solid fat, alcohol and added sugars. Conclusions Lower energy-adjusted diet costs were associated with lower-quality diets. Future efforts to improve the nutritional status of the US public should take food prices and diet costs into account. PMID:25625693

  4. HFE safety reviews of advanced nuclear power plant control rooms

    NASA Technical Reports Server (NTRS)

    Ohara, John

    1994-01-01

    Advanced control rooms (ACR's) will utilize human-system interface (HSI) technologies that may have significant implications for plant safety in that they will affect the operator's overall role and means of interacting with the system. The Nuclear Regulatory Commission (NRC) reviews the human factors engineering (HFE) aspects of HSI's to ensure that they are designed to good HFE principles and support performance and reliability in order to protect public health and safety. However, the only available NRC guidance was developed more than ten years ago, and does not adequately address the human performance issues and technology changes associated with ACR's. Accordingly, a new approach to ACR safety reviews was developed based upon the concept of 'convergent validity'. This approach to ACR safety reviews is described.

  5. The Safety of Cruciferous Plants in Humans: A Systematic Review

    PubMed Central

    Scott, Ori; Galicia-Connolly, Elaine; Adams, Denise; Surette, Soleil; Vohra, Sunita; Yager, Jerome Y.

    2012-01-01

    Some cruciferous plants may serve as preventive treatments for several medical conditions; our objective was to systematically investigate their safety in humans. Four electronic databases were searched, and, of 10,831 references identified, 50 were included. Data were extracted by two independent reviewers, whereafter the association between interventions and adverse events was assessed. Adverse events in 53 subjects were identified through clinical trials; of these, altered drug metabolism was rated as certainly/likely caused by cruciferous plants. Adverse events in 1247 subjects were identified through observational studies, of which none received high causality ratings. Adverse events in 35 subjects were identified through case reports, of which allergies and warfarin resistance were rated as certainly/likely caused by cruciferous plants. We conclude that cruciferous plants are safe in humans, with the exception of allergies. Individuals treated with warfarin should consult their physician. Further investigation of uses of cruciferous plants in preventative medicine is warranted. PMID:22500092

  6. Safety Second: the NRC and America's nuclear power plants

    SciTech Connect

    Adato, M.; MacKenzie, J.; Pollard, R.; Weiss, E.

    1987-01-01

    In 1975, Congress created the Nuclear Regulatory Commission (NRC). Its primary responsibility was to be the regulation of the nuclear power industry in order to maintain public health and safety. On March 28, 1979, in the worst commercial nuclear accident in US history, the plant at Three Mile Island began to leak radioactive material. How was Three Mile Island possible. Where was the NRC. This analysis by the Union of Concerned Scientists (UCS) of the NRC's first decade, points specifically to the factors that contributed to the accident at Three Mile Island. The NRC, created as a watchdog of the nuclear power industry, suffers from problems of mindset, says the UCS. The commission's problems are political, not technical; it repeatedly ranks special interests above the interest of public safety. This book critiques the NRC's performance in four specific areas. It charges that the agency has avoided tackling the most pervasive safety issues; has limited public participation in decision making and power plant licensing; has failed to enforce safety standards or conduct adequate regulation investigations; and, finally, has maintained a fraternal relationship with the industry it was created to regulate, serving as its advocate rather than it adversary. The final chapter offers recommendations for agency improvement that must be met if the NRC is to fulfill its responsibility for safety first.

  7. Aging of safety class 1E transformers in safety systems of nuclear power plants

    SciTech Connect

    Roberts, E.W.; Edson, J.L.; Udy, A.C.

    1996-02-01

    This report discusses aging effects on safety-related power transformers in nuclear power plants. It also evaluates maintenance, testing, and monitoring practices with respect to their effectiveness in detecting and mitigating the effects of aging. The study follows the US Nuclear Regulatory Commission`s (NRC`s) Nuclear Plant-Aging Research approach. It investigates the materials used in transformer construction, identifies stressors and aging mechanisms, presents operating and testing experience with aging effects, analyzes transformer failure events reported in various databases, and evaluates maintenance practices. Databases maintained by the nuclear industry were analyzed to evaluate the effects of aging on the operation of nuclear power plants.

  8. Qualification of Safety-Related Software in Nuclear Power Plants

    SciTech Connect

    Johnson, G L

    2000-06-13

    Digital instrumentation and control systems have the potential of offering significant benefits over traditional analog systems in Nuclear Power Plant safety systems, but there are also significant difficulties in qualifying digital systems to the satisfaction of regulators. Digital systems differ in fundamental ways from analog systems. New methods for safety qualification, which take these differences into account, would ease the regulatory cost and promote use of digital systems. This paper offers a possible method for assisting in the analysis of digital system software, as one step in an improved qualification process.

  9. Safety system augmentation at Russian nuclear power plants

    SciTech Connect

    Scerbo, J.A.; Satpute, S.N.; Donkin, J.Y.; Reister, R.A. |

    1996-12-31

    This paper describes the design and procurement of a Class IE DC power supply system to upgrade plant safety at the Kola Nuclear Power Plant (NPP). Kola NPP is located above the Arctic circle at Polyarnie Zorie, Murmansk, Russia. Kola NPP consists of four units. Units 1 and 2 have VVER-440/230 type reactors: Units 3 and 4 have VVER-440/213 type reactors. The VVER-440 reactor design is similar to the pressurized water reactor design used in the US. This project provided redundant, Class 1E DC station batteries and DC switchboards for Kola NPP, Units 1 and 2. The new DC power supply system was designed and procured in compliance with current nuclear design practices and requirements. Technical issues that needed to be addressed included reconciling the requirements in both US and Russian codes and satisfying the requirements of the Russian nuclear regulatory authority. Close interface with ATOMENERGOPROEKT (AEP), the Russian design organization, KOLA NPP plant personnel, and GOSATOMNADZOR (GAN), the Russian version of US Nuclear Regulatory Commission, was necessary to develop a design that would assure compliance with current Russian design requirements. Hence, this project was expected to serve as an example for plant upgrades at other similar VVER-440 nuclear plants. In addition to technical issues, the project needed to address language barriers and the logistics of shipping equipment to a remote section of the Former Soviet Union (FSU). This project was executed by Burns and Roe under the sponsorship of the US DOE as part of the International Safety Program (INSP). The INSP is a comprehensive effort, in cooperation with partners in other countries, to improve nuclear safety worldwide. A major element within the INSP is the improvement of the safety of Soviet-designed nuclear reactors.

  10. Total, Free, and Added Sugar Consumption and Adherence to Guidelines: The Dutch National Food Consumption Survey 2007-2010.

    PubMed

    Sluik, Diewertje; van Lee, Linde; Engelen, Anouk I; Feskens, Edith J M

    2016-02-01

    A high sugar intake is a subject of scientific debate due to the suggested health implications and recent free sugar recommendations by the WHO. The objective was to complete a food composition table for added and free sugars, to estimate the intake of total sugars, free sugars, and added sugars, adherence to sugar guidelines and overall diet quality in Dutch children and adults. In all, 3817 men and women (7-69 years) from the Dutch National Food Consumption Survey 2007-2010 were studied. Added and free sugar content of products was assigned by food composition tables and using labelling and product information. Diet was assessed with two 24-h recalls. Diet quality was studied in adults with the Dutch Healthy Diet-index. Total sugar intake was 22% Total Energy (%TE), free sugars intake 14 %TE, and added sugar intake 12 %TE. Sugar consumption was higher in children than adults. Main food sources of sugars were sweets and candy, non-alcoholic beverages, dairy, and cake and cookies. Prevalence free sugar intake <10 %TE was 5% in boys and girls (7-18 years), 29% in women, and 33% in men. Overall diet quality was similar comparing adults adherent and non-adherent to the sugar guidelines, although adherent adults had a higher intake of dietary fiber and vegetables. Adherence to the WHO free sugar guidelines of <5 %TE and <10 %TE was generally low in the Netherlands, particularly in children. Adherence to the added and free sugar guidelines was not strongly associated with higher diet quality in adults. PMID:26828518

  11. Factors associated with low water intake among South Korean adolescents - Korea National Health and Nutrition Examination Survey, 2007-2010.

    PubMed

    Lee, Haeng-Shin; Park, Sohyun; Kim, Mi-Hyun

    2014-02-01

    Water is essential for life and plain water instead of sugar-sweetened beverages is one approach for decreasing energy intake. Due to limited data on characteristics associated with water intake among Korean adolescents, this study examined associations of demographic and behavioral characteristics with plain water intake by using nationally representative sample of South Korean adolescents. The data (2007-2010 Korea National Health and Nutrition Examination Survey) for 1,288 high school-aged adolescents (15-18 years) were used. Multivariable logistic regression was used to calculate adjusted odds ratios (OR) for factors associated with low water intake (< 4 cups/day) and very low water intake (< 2.5 cups/day). Nationwide, 38.4% and 19.0% of adolescents reported drinking water < 4.0 cups/day and < 2.5 cups/day, respectively. The mean plain water intake was 5.7 cups/day for males and 4.1 cups/day for females. Females had significantly higher odds for drinking water < 2.5 cups/day (OR = 2.2) than males, whereas adolescents with low milk consumption had significantly lower odds for drinking water < 2.5 cups/day (OR = 0.7). Factors significantly associated with a greater odds for drinking water < 4 cups/daywere being female (OR = 2.8) and not meeting physical activity recommendations (≥ 20 min/day on < 3 days/week) (OR = 1.6). Being underweight, overweight, and obese were significantly associated with reduced odds for drinking water < 4 cups/day (OR = 0.7, 0.4 and 0.5, respectively). However, intake of soda, coffee drinks, fruits, vegetables, and sodium and eating out were not significantly associated with low or very low water intake. These findings may be used to target intervention efforts to increase plain water intake as part of a healty lifestyle. PMID:24611109

  12. Personnel Safety for Future Magnetic Fusion Power Plants

    SciTech Connect

    Lee Cadwallader

    2009-07-01

    The safety of personnel at existing fusion experiments is an important concern that requires diligence. Looking to the future, fusion experiments will continue to increase in power and operating time until steady state power plants are achieved; this causes increased concern for personnel safety. This paper addresses four important aspects of personnel safety in the present and extrapolates these aspects to future power plants. The four aspects are personnel exposure to ionizing radiation, chemicals, magnetic fields, and radiofrequency (RF) energy. Ionizing radiation safety is treated well for present and near-term experiments by the use of proven techniques from other nuclear endeavors. There is documentation that suggests decreasing the annual ionizing radiation exposure limits that have remained constant for several decades. Many chemicals are used in fusion research, for parts cleaning, as use as coolants, cooling water cleanliness control, lubrication, and other needs. In present fusion experiments, a typical chemical laboratory safety program, such as those instituted in most industrialized countries, is effective in protecting personnel from chemical exposures. As fusion facilities grow in complexity, the chemical safety program must transition from a laboratory scale to an industrial scale program that addresses chemical use in larger quantity. It is also noted that allowable chemical exposure concentrations for workers have decreased over time and, in some cases, now pose more stringent exposure limits than those for ionizing radiation. Allowable chemical exposure concentrations have been the fastest changing occupational exposure values in the last thirty years. The trend of more restrictive chemical exposure regulations is expected to continue into the future. Other issues of safety importance are magnetic field exposure and RF energy exposure. Magnetic field exposure limits are consensus values adopted as best practices for worker safety; a typical

  13. Technical Safety Appraisal of the Rocky Flats Plant

    SciTech Connect

    Brown, Blake P.

    1989-01-01

    This report provides the results of a Technical Safety Appraisal (TSA) of the Rocky Flats Plant (RFP) conducted November 14 to 18 and November 28 to December 9, 1988. This appraisal covered the effectiveness and improvements in the RFP safety program across the site, evaluating progress to date against standards of accepted practice. The appraisal included coverage of the timeliness and effectiveness of actions taken in response to the recommendations/concerns in three previous Technical Safety Appraisals (TSAs) of RFP Bldg. 707 conducted in July 1986, Bldgs. 771/774 conducted in October/November 1986, and Bldgs. 776/777 conducted in January/February 1988. Results of this appraisal are given in Section IV for each of 14 technical safety areas at RFP. These results include a discussion, conclusions and any new safety concerns for each technical safety area. Appendix A contains a description of the system for categorizing concerns, and the concerns are tabulated in Appendix B. Appendix C reports on the evaluation of the contractor's actions and the current status of each of the 230 recommendations and concerns contained in the three previous TSA reports.

  14. Safety Evaluation for Packaging (onsite) T Plant Canyon Items

    SciTech Connect

    OBRIEN, J.H.

    2000-07-14

    This safety evaluation for packaging (SEP) evaluates and documents the ability to safely ship mostly unique inventories of miscellaneous T Plant canyon waste items (T-P Items) encountered during the canyon deck clean off campaign. In addition, this SEP addresses contaminated items and material that may be shipped in a strong tight package (STP). The shipments meet the criteria for onsite shipments as specified by Fluor Hanford in HNF-PRO-154, Responsibilities and Procedures for all Hazardous Material Shipments.

  15. Floating LNG plant will stress reliability and safety

    SciTech Connect

    Kinney, C.D.; Schulz, H.R.; Spring, W.

    1997-07-01

    Mobil has developed a unique floating LNG plant design after extensive studies that set safety as the highest priority. The result is a production, storage and offloading platform designed to produce 6 million tons per year of LNG and up to 55,000 bpd of condensate from 1 Bcfd of feed gas. All production and off-loading equipment is supported by a square donut-shaped concrete hull, which is spread-moored. The hull contains storage tanks for 250,000 m{sup 3} of LNG, 6540,000 bbl of condensate and ballast water. Both LNG and condensate can be directly offloaded to shuttle tankers. Since the plant may be moved to produce from several different gas fields during its life, the plant and barge were designed to be generic. It can be used at any location in the Pacific Rim, with up to 15% CO{sub 2}, 100 ppm H{sub 2}S, 55 bbl/MMcf condensate and 650 ft water depth. It can be modified to handle other water depths, depending upon the environment. In addition, it is much more economical than an onshore grassroots LNG plant, with potential capital savings of 25% or more. The paper describes the machinery, meteorology and oceanography, and safety engineering.

  16. Plutonium Finishing Plant (PFP) Safety Class and Safety Significant Commercial Grade Items (CGI) Critical Characteristic

    SciTech Connect

    THOMAS, R.J.

    2000-04-24

    This document specifies the critical characteristics for Commercial Grade Items (CGI) procured for use in the Plutonium Finishing Plant as required by HNF-PRO-268 and HNF-PRO-1819. These are the minimum specifications that the equipment must meet in order to properly perform its safety function. There may be several manufacturers or models that meet the critical characteristics of any one item.

  17. Fuzzy-logic-based safety verification framework for nuclear power plants.

    PubMed

    Rastogi, Achint; Gabbar, Hossam A

    2013-06-01

    This article presents a practical implementation of a safety verification framework for nuclear power plants (NPPs) based on fuzzy logic where hazard scenarios are identified in view of safety and control limits in different plant process values. Risk is estimated quantitatively and compared with safety limits in real time so that safety verification can be achieved. Fuzzy logic is used to define safety rules that map hazard condition with required safety protection in view of risk estimate. Case studies are analyzed from NPP to realize the proposed real-time safety verification framework. An automated system is developed to demonstrate the safety limit for different hazard scenarios. PMID:23020592

  18. 78 FR 4477 - Review of Safety Analysis Reports for Nuclear Power Plants, Introduction

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-01-22

    ... COMMISSION Review of Safety Analysis Reports for Nuclear Power Plants, Introduction AGENCY: Nuclear... subsection to NUREG-0800, ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power..., Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants:...

  19. An integrated and pragmatic approach: Global plant safety management

    NASA Astrophysics Data System (ADS)

    McNutt, Jack; Gross, Andrew

    1989-05-01

    The Bhopal disaster in India in 1984 has compelled manufacturing companies to review their operations in order to minimize their risk exposure. Much study has been done on the subject of risk assessment and in refining safety reviews of plant operations. However, little work has been done to address the broader needs of decision makers in the multinational environment. The corporate headquarters of multinational organizations are concerned with identifying vulnerable areas to assure that appropriate risk-minimization measures are in force or will be taken. But the task of screening global business units for safety prowess is complicated and time consuming. This article takes a step towards simplifying this process by presenting the decisional model developed by the authors. Beginning with an overview of key issues affecting global safety management, the focus shifts to the multinational vulnerability model developed by the authors, which reflects an integration of approaches. The article concludes with a discussion of areas for further research. While the global chemical industry and major incidents therein are used for illustration, the procedures and solutions suggested here are applicable to all manufacturing operations.

  20. Safety assessment in plant layout design using indexing approach: implementing inherent safety perspective. Part 1 - guideword applicability and method description.

    PubMed

    Tugnoli, Alessandro; Khan, Faisal; Amyotte, Paul; Cozzani, Valerio

    2008-12-15

    Layout planning plays a key role in the inherent safety performance of process plants since this design feature controls the possibility of accidental chain-events and the magnitude of possible consequences. A lack of suitable methods to promote the effective implementation of inherent safety in layout design calls for the development of new techniques and methods. In the present paper, a safety assessment approach suitable for layout design in the critical early phase is proposed. The concept of inherent safety is implemented within this safety assessment; the approach is based on an integrated assessment of inherent safety guideword applicability within the constraints typically present in layout design. Application of these guidewords is evaluated along with unit hazards and control devices to quantitatively map the safety performance of different layout options. Moreover, the economic aspects related to safety and inherent safety are evaluated by the method. Specific sub-indices are developed within the integrated safety assessment system to analyze and quantify the hazard related to domino effects. The proposed approach is quick in application, auditable and shares a common framework applicable in other phases of the design lifecycle (e.g. process design). The present work is divided in two parts: Part 1 (current paper) presents the application of inherent safety guidelines in layout design and the index method for safety assessment; Part 2 (accompanying paper) describes the domino hazard sub-index and demonstrates the proposed approach with a case study, thus evidencing the introduction of inherent safety features in layout design. PMID:18406519

  1. Improved nuclear power plant operations and safety through performance-based safety regulation.

    PubMed

    Golay, M W

    2000-01-01

    This paper illustrates some of the promise and needed future work for risk-informed, performance-based regulation (RIPBR). RIPBR is an evolving alternative to the current prescriptive method of nuclear safety regulation. Prescriptive regulation effectively constitutes a long, fragmented checklist of requirements that safety-related systems in a plant must satisfy. RIPBR, instead, concentrates upon satisfying negotiated performance goals and incentives for judging and rewarding licensee behavior to improve safety and reduce costs. In a project reported here, a case study was conducted concerning a pressurized water reactor (PWR) emergency diesel generator (EDG). Overall, this work has shown that the methods of RIPBR are feasible to use, and capable of justifying simultaneous safety and economic nuclear power improvements. However, it also reveals several areas where the framework of RIPBR should be strengthened. First, researchers need better data and understanding regarding individual component-failure modes that may cause components to fail. Not only are more data needed on failure rates, but more data and understanding are needed to enable analysts to evaluate whether these failures become more likely as the interval between tests is increased. This is because the current state of failure data is not sufficiently finely detailed to define the failure rates of individual component failure modes; such knowledge is needed when changing component-specific regulatory requirements. Second, the role of component testing, given that a component has failed, needs to be strengthened within the context of RIPBR. This includes formulating requirements for updating the prior probability distribution of a component failure rate and conducting additional or more frequent testing. Finally, as a means of compensating for unavoidable uncertainty as an obstacle to regulatory decision-making, limits to knowledge must be treated explicitly and formally. This treatment includes the

  2. Environment, safety and health progress assessment of the Pantex Plant

    SciTech Connect

    Not Available

    1993-03-01

    This report documents the result of the US Department of Energy (DOE) Environment, Safety and Health (ES H) Progress Assessment of the Pantex Plant, in Amarillo, Texas, conducted from March 15 through March 26, 1993. The ES H Progress Assessments are part of DOE's continuing effort to institutionalize line management accountability and the self-assessment process throughout DOE and its contractor organizations. The purpose of the Pantex Plant ES H Progress Assessment is to provide the Secretary of Energy and senior DOE management with concise independent information on the following: (1) change in culture and attitude related to ES H activities; (2) progress and effectiveness of the ES H corrective actions resulting from previous Tiger Team Assessments; (3) adequacy and effectiveness of the ES H self-assessment programs of the DOE line organizations and the site management and operating contractor; and (4) effectiveness of DOE and contractor management structures, resources, and systems to effectively address ES H problems and new ES H initiatives.

  3. Steam generator tube degradation at the Doel 4 plant influence on plant operation and safety

    SciTech Connect

    Scheveneels, G.

    1997-02-01

    The steam generator tubes of Doel 4 are affected by a multitude of corrosion phenomena. Some of them have been very difficult to manage because of their extremely fast evolution, non linear evolution behavior or difficult detectability and/or measurability. The exceptional corrosion behavior of the steam generator tubes has had its drawbacks on plant operation and safety. Extensive inspection and repair campaigns have been necessary and have largely increased outage times and radiation exposure to personnel. Although considerable effort was invested by the utility to control corrosion problems, non anticipated phenomena and/or evolution have jeopardized plant safety. The extensive plugging and repairs performed on the steam generators have necessitated continual review of the design basis safety studies and the adaptation of the protection system setpoints. The large asymmetric plugging has further complicated these reviews. During the years many preventive and recently also defence measures have been implemented by the utility to manage corrosion and to decrease the probability and consequences of single or multiple tube rupture. The present state of the Doel 4 steam generators remains troublesome and further examinations are performed to evaluate if continued operation until June `96, when the steam generators will be replaced, is justified.

  4. 33 CFR 165.115 - Safety and Security Zones; Pilgrim Nuclear Power Plant, Plymouth, Massachusetts.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Safety and Security Zones; Pilgrim Nuclear Power Plant, Plymouth, Massachusetts. 165.115 Section 165.115 Navigation and Navigable... Coast Guard District § 165.115 Safety and Security Zones; Pilgrim Nuclear Power Plant,...

  5. 33 CFR 165.115 - Safety and Security Zones; Pilgrim Nuclear Power Plant, Plymouth, Massachusetts.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 33 Navigation and Navigable Waters 2 2011-07-01 2011-07-01 false Safety and Security Zones; Pilgrim Nuclear Power Plant, Plymouth, Massachusetts. 165.115 Section 165.115 Navigation and Navigable... Coast Guard District § 165.115 Safety and Security Zones; Pilgrim Nuclear Power Plant,...

  6. 33 CFR 165.115 - Safety and Security Zones; Pilgrim Nuclear Power Plant, Plymouth, Massachusetts.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 33 Navigation and Navigable Waters 2 2013-07-01 2013-07-01 false Safety and Security Zones; Pilgrim Nuclear Power Plant, Plymouth, Massachusetts. 165.115 Section 165.115 Navigation and Navigable... Coast Guard District § 165.115 Safety and Security Zones; Pilgrim Nuclear Power Plant,...

  7. 33 CFR 165.115 - Safety and Security Zones; Pilgrim Nuclear Power Plant, Plymouth, Massachusetts.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 33 Navigation and Navigable Waters 2 2012-07-01 2012-07-01 false Safety and Security Zones; Pilgrim Nuclear Power Plant, Plymouth, Massachusetts. 165.115 Section 165.115 Navigation and Navigable... Coast Guard District § 165.115 Safety and Security Zones; Pilgrim Nuclear Power Plant,...

  8. 33 CFR 165.115 - Safety and Security Zones; Pilgrim Nuclear Power Plant, Plymouth, Massachusetts.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 33 Navigation and Navigable Waters 2 2014-07-01 2014-07-01 false Safety and Security Zones; Pilgrim Nuclear Power Plant, Plymouth, Massachusetts. 165.115 Section 165.115 Navigation and Navigable... Coast Guard District § 165.115 Safety and Security Zones; Pilgrim Nuclear Power Plant,...

  9. Potential safety-related incidents with possible applicability to a nuclear fuel reprocessing plant

    SciTech Connect

    Durant, W.S.; Perkins, W.C.; Lee, R.; Stoddard, D.H.

    1982-05-20

    The Safety Technology Group is developing methodology that can be used to assess the risk of operating a plant to reprocess spent nuclear fuel. As an early step in the methodology, a preliminary hazards analysis identifies safety-related incidents. In the absence of appropriate safety features, these incidents could lead to significant consequences and risk to onsite personnel or to the public. This report is a compilation of potential safety-related incidents that have been identified in studies at SRL and in safety analyses of various commercially designed reprocessing plants. It is an expanded revision of the version originally published as DP-1558, Published December 1980.

  10. Nuclear criticality safety evaluation of Spray Booth Operations in X-705, Portsmouth Gaseous Diffusion Plant

    SciTech Connect

    Sheaffer, M.K.; Keeton, S.C.

    1993-09-20

    This report evaluates nuclear criticality safety for Spray Booth Operations in the Decontamination and Recovery Facility, X-705, at the Portsmouth Gaseous Diffusion Plant. A general description of current procedures and related hardware/equipment is presented. Control parameters relevant to nuclear criticality safety are explained, and a consolidated listing of administrative controls and safety systems is developed. Based on compliance with DOE Orders and MMES practices, the overall operation is evaluated, and recommendations for enhanced safety are suggested.

  11. Analysis of transmitted drug resistance in Spain in the years 2007-2010 documents a decline in mutations to the non-nucleoside drug class.

    PubMed

    Monge, S; Guillot, V; Alvarez, M; Peña, A; Viciana, P; García-Bujalance, S; Pérez Elias, M J; Iribarren, J A; Gutiérrez, F; Itziar Casado, M; Garcia, F

    2012-11-01

    We have studied transmitted drug resistance (TDR) in 1.864 antiretroviral-naïve patients entering CoRIS (Spain) during 2007-2010. An overall 8.58% TDR was observed (3.92%, nucleoside reverse transcriptase inhibitors (NRTIs); 3.86%, non-nucleoside reverse transcriptase inhibitors (NNRTIs); 2.31%, protease inhibitors), with a significant decreasing trend over time for NNRTIs (5.53%, 2007; 2.45%, 2010; p for trend = 0.044). Non-B subtype prevalence was 15.93%, with a significant increase (11.95%, 2007; 18.14%, 2010; p for trend = 0.018), mainly related to immigration. Having no formal education increased the risk of TDR to NNRTIs (OR, 7.26), and carrying a non-B subtype reduced the risk of TDR to NRTIs (OR, 0.27). These findings may have important implications for treatment guidelines and laboratory testing recommendations. PMID:23016666

  12. Using game technologies to improve the safety of construction plant operations.

    PubMed

    Guo, Hongling; Li, Heng; Chan, Greg; Skitmore, Martin

    2012-09-01

    Many accidents occur world-wide in the use of construction plant and equipment, and safety training is considered by many to be one of the best approaches to their prevention. However, current safety training methods/tools are unable to provide trainees with the hands-on practice needed. Game technology-based safety training platforms have the potential to overcome this problem in a virtual environment. One such platform is described in this paper - its characteristics are analysed and its possible contribution to safety training identified. This is developed and tested by means of a case study involving three major pieces of construction plant, which successfully demonstrates that the platform can improve the process and performance of the safety training involved in their operation. This research not only presents a new and useful solution to the safety training of construction operations, but illustrates the potential use of advanced technologies in solving construction industry problems in general. PMID:22664683

  13. Nuclear power plants in China's coastal zone: risk and safety

    NASA Astrophysics Data System (ADS)

    Lu, Qingshui; Gao, Zhiqiang; Ning, Jicai; Bi, Xiaoli; Gao, Wei

    2014-10-01

    Nuclear power plants are used as an option to meet the demands for electricity due to the low emission of CO2 and other contaminants. The accident at the Fukushima nuclear power plant in 2011 has forced the Chinese government to adjust its original plans for nuclear power. The construction of inland nuclear power plants was stopped, and construction is currently only permitted in coastal zones. However, one obstacle of those plants is that the elevation of those plants is notably low, ranging from 2 to 9 meters and a number of the nuclear power plants are located in or near geological fault zones. In addition, the population density is very high in the coastal zones of China. To reduce those risks of nuclear power plants, central government should close the nuclear power plants within the fault zones, evaluate the combined effects of storm surges, inland floods and tidal waves on nuclear power plants and build closed dams around nuclear power plants to prevent damage from storm surges and tidal waves. The areas without fault zones and with low elevation should be considered to be possible sites for future nuclear power plants if the elevation can be increased using soil or civil materials.

  14. 78 FR 25488 - Qualification Tests for Safety-Related Actuators in Nuclear Power Plants

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-05-01

    ...The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG), DG-1235, ``Qualification Tests for Safety-Related Actuators in Nuclear Power Plants.'' DG-1235 is proposed Revision 1 of RG 1.73, dated January 1974. This revision endorses, with clarifications, the enhanced consensus practices for qualifying safety-related actuators, and actuator......

  15. Evaluating software for safety systems in nuclear power plants

    SciTech Connect

    Lawrence, J.D.; Persons, W.L.; Preckshot, G.G.; Gallagher, J.

    1994-01-11

    In 1991, LLNL was asked by the NRC to provide technical assistance in various aspects of computer technology that apply to computer-based reactor protection systems. This has involved the review of safety aspects of new reactor designs and the provision of technical advice on the use of computer technology in systems important to reactor safety. The latter includes determining and documenting state-of-the-art subjects that require regulatory involvement by the NRC because of their importance in the development and implementation of digital computer safety systems. These subjects include data communications, formal methods, testing, software hazards analysis, verification and validation, computer security, performance, software complexity and others. One topic software reliability and safety is the subject of this paper.

  16. Safety and Nonsafety Communications and Interactions in International Nuclear Power Plants

    SciTech Connect

    Kisner, Roger A; Mullens, James Allen; Wilson, Thomas L; Wood, Richard Thomas; Korsah, Kofi; Qualls, A L; Muhlheim, Michael David; Holcomb, David Eugene; Loebl, Andy

    2007-08-01

    Current industry and NRC guidance documents such as IEEE 7-4.3.2, Reg. Guide 1.152, and IEEE 603 do not sufficiently define a level of detail for evaluating interdivisional communications independence. The NRC seeks to establish criteria for safety systems communications that can be uniformly applied in evaluation of a variety of safety system designs. This report focuses strictly on communication issues related to data sent between safety systems and between safety and nonsafety systems. Further, the report does not provide design guidance for communication systems nor present detailed failure modes and effects analysis (FMEA) results for existing designs. This letter report describes communications between safety and nonsafety systems in nuclear power plants outside the United States. A limited study of international nuclear power plants was conducted to ascertain important communication implementations that might have bearing on systems proposed for licensing in the United States. This report provides that following information: 1.communications types and structures used in a representative set of international nuclear power reactors, and 2.communications issues derived from standards and other source documents relevant to safety and nonsafety communications. Topics that are discussed include the following: communication among redundant safety divisions, communications between safety divisions and nonsafety systems, control of safety equipment from a nonsafety workstation, and connection of nonsafety programming, maintenance, and test equipment to redundant safety divisions during operation. Information for this report was obtained through publicly available sources such as published papers and presentations. No proprietary information is represented.

  17. Racial and ethnic disparities in future testing intentions for HIV: United States, 2007-2010: results from the National Health Interview Survey.

    PubMed

    Murray, Kenya; Oraka, Emeka

    2014-07-01

    This study examined racial/ethnic differences in rationale for intending to test for HIV. Data were analyzed from 98,971 adults from the 2007-2010 National Health Interview Survey. An estimated 38.5 % of respondents previously tested for HIV. Testing as part of a medical checkup or procedure was the most common reason for being tested among studied racial/ethnic groups. Non-Hispanic whites (80.7 %) and non-Hispanic Asians (71.2 %) had higher proportions (p < 0.001) of respondents that have not been tested for HIV due to believing they were unlikely exposed. Non-Hispanic blacks (ARR: 2.55; 95 % CI 2.39-2.72) and Hispanics (ARR: 1.81; 95 % CI 1.68-1.95) who ever tested for HIV were significantly more likely to report positive future testing intentions compared to non-Hispanic whites. Additional efforts to increase the availability of HIV tests by making HIV testing a routine part of medical care and increasing knowledge of HIV transmission, risk-perception, and treatment may reduce racial/ethnic disparities in HIV testing. PMID:24136452

  18. Knowledge is key to safety; Plants that poison horses

    Technology Transfer Automated Retrieval System (TEKTRAN)

    Horses are relatively selective grazers and generally they are poisoned less frequently than other livestock. However, there are exceptions. Some poisonous plants are palatable to horses and exposed horses readily eat them. Other plants may be eaten by some horses even though they are unpalatable...

  19. 78 FR 67206 - Qualification Tests for Safety-Related Actuators in Nuclear Power Plants

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-11-08

    ... Plants'' on May 1, 2013, (78 FR 25488) for a 60 day public comment period. The public comment period... COMMISSION Qualification Tests for Safety-Related Actuators in Nuclear Power Plants AGENCY: Nuclear... Commission (NRC) is issuing revision 1 to regulatory guide (RG) 1.73, ``Qualification Tests for...

  20. Industrial Fuel Gas Demonstration Plant Program. Task III, Demonstration plant safety, industrial hygiene, and major disaster plan (Deliverable No. 35)

    SciTech Connect

    1980-03-01

    This Health and Safety Plan has been adopted by the IFG Demonstration Plant managed by Memphis Light, Gas and Water at Memphis, Tennessee. The plan encompasses the following areas of concern: Safety Plan Administration, Industrial Health, Industrial Safety, First Aid, Fire Protection (including fire prevention and control), and Control of Safety Related Losses. The primary objective of this plan is to achieve adequate control of all potentially hazardous activities to assure the health and safety of all employees and eliminate lost work time to both the employees and the company. The second objective is to achieve compliance with all Federal, state and local laws, regulations and codes. Some thirty specific safe practice instruction items are included.

  1. Safety assessment of genetically modified plants with deliberately altered composition

    PubMed Central

    Halford, Nigel G; Hudson, Elizabeth; Gimson, Amy; Weightman, Richard; Shewry, Peter R; Tompkins, Steven

    2014-01-01

    The development and marketing of ‘novel’ genetically modified (GM) crops in which composition has been deliberately altered poses a challenge to the European Union (EU)'s risk assessment processes, which are based on the concept of substantial equivalence with a non-GM comparator. This article gives some examples of these novel GM crops and summarizes the conclusions of a report that was commissioned by the European Food Safety Authority on how the EU's risk assessment processes could be adapted to enable their safety to be assessed. PMID:24735114

  2. Safety assessment of genetically modified plants with deliberately altered composition.

    PubMed

    Halford, Nigel G; Hudson, Elizabeth; Gimson, Amy; Weightman, Richard; Shewry, Peter R; Tompkins, Steven

    2014-08-01

    The development and marketing of 'novel' genetically modified (GM) crops in which composition has been deliberately altered poses a challenge to the European Union (EU)'s risk assessment processes, which are based on the concept of substantial equivalence with a non-GM comparator. This article gives some examples of these novel GM crops and summarizes the conclusions of a report that was commissioned by the European Food Safety Authority on how the EU's risk assessment processes could be adapted to enable their safety to be assessed. PMID:24735114

  3. The role of PRA in the safety assessment of VVER Nuclear Power Plants in Ukraine.

    SciTech Connect

    Kot, C.

    1999-05-10

    Ukraine operates thirteen (13) Soviet-designed pressurized water reactors, VVERS. All Ukrainian plants are currently operating with annually renewable permits until they update their safety analysis reports (SARs), in accordance with new SAR content requirements issued in September 1995, by the Nuclear Regulatory Authority and the Government Nuclear Power Coordinating Committee of Ukraine. The requirements are in three major areas: design basis accident (DBA) analysis, probabilistic risk assessment (PRA), and beyond design-basis accident (BDBA) analysis. The last two requirements, on PRA and BDBA, are new, and the DBA requirements are an expanded version of the older SAR requirements. The US Department of Energy (USDOE), as part of its Soviet-Designed Reactor Safety activities, is providing assistance and technology transfer to Ukraine to support their nuclear power plants (NPPs) in developing a Western-type technical basis for the new SARs. USDOE sponsored In-Depth Safety Assessments (ISAs) are in progress at three pilot nuclear reactor units in Ukraine, South Ukraine Unit 1, Zaporizhzhya Unit 5, and Rivne Unit 1, and a follow-on study has been initiated at Khmenytskyy Unit 1. The ISA projects encompass most areas of plant safety evaluation, but the initial emphasis is on performing a detailed, plant-specific Level 1 Internal Events PRA. This allows the early definition of the plant risk profile, the identification of risk significant accident sequences and plant vulnerabilities and provides guidance for the remainder of the safety assessments.

  4. Security during safety-related emergencies at nuclear power plants

    SciTech Connect

    Moul, D.A.

    1984-07-01

    Under a commission from the Office of Nuclear Regulatory Research, NRC, a study was performed by a team of analysts relative to licensing practices and the role of security as they relate to safeguards during safety-related emergencies (SREs). Methodology included a literature search, site visits to representative nuclear reactors and analysis of the regulatory and licensee planning bases. Problems relating to security actions during SREs were examined primarily in the following areas: organization for response, planning, training and qualification, equipment, procedures employed, facilities, and preparation for safeguards against sabotage during an SRE. Recommendations were made as to how improvements could be made in the regulatory approach, and in licensee planning and procedural mechanisms as they relate to the subject matter under examination. The results of the study also had implications for the safety/safeguards interface problem currently under review by the NRC.

  5. Safety analysis, 200 Area, Savannah River Plant: Separations area operations

    SciTech Connect

    Perkins, W.C.; Lee, R.; Allen, P.M.; Gouge, A.P.

    1991-07-01

    The nev HB-Line, located on the fifth and sixth levels of Building 221-H, is designed to replace the aging existing HB-Line production facility. The nev HB-Line consists of three separate facilities: the Scrap Recovery Facility, the Neptunium Oxide Facility, and the Plutonium Oxide Facility. There are three separate safety analyses for the nev HB-Line, one for each of the three facilities. These are issued as supplements to the 200-Area Safety Analysis (DPSTSA-200-10). These supplements are numbered as Sup 2A, Scrap Recovery Facility, Sup 2B, Neptunium Oxide Facility, Sup 2C, Plutonium Oxide Facility. The subject of this safety analysis, the, Plutonium Oxide Facility, will convert nitrate solutions of {sup 238}Pu to plutonium oxide (PuO{sub 2}) powder. All these new facilities incorporate improvements in: (1) engineered barriers to contain contamination, (2) barriers to minimize personnel exposure to airborne contamination, (3) shielding and remote operations to decrease radiation exposure, and (4) equipment and ventilation design to provide flexibility and improved process performance.

  6. Association with meteo-climatological factors and daily emergency visits for renal colic and urinary calculi in Cuneo, Italy. A retrospective observational study, 2007-2010

    NASA Astrophysics Data System (ADS)

    Condemi, Vincenzo; Gestro, Massimo; Dozio, Elena; Tartaglino, Bruno; Corsi Romanelli, Massimiliano Marco; Solimene, Umberto; Meco, Roberto

    2015-03-01

    The incidence of nephrolithiasis is rising worldwide, especially in women and with increasing age. Incidence and prevalence of kidney stones are affected by genetic, nutritional, and environmental factors. The aim of this study is to investigate the link between various meteorological factors (independent variables) and the daily number of visits to the Emergency Department (ED of the S. Croce and Carle Hospital of Cuneo for renal colic (RC) and urinary stones (UC) as the dependent variable over the years 2007-2010. The Poisson generalized regression models (PGAMs) have been used in different progressive ways. The results of PGAMs (stage 1) adjusted for seasonal and calendar factors confirmed a significant correlation ( p < 0.03) with the thermal parameter. Evaluation of the dose-response effect [PGAMs combined with distributed lags nonlinear models (DLNMs)—stage 2], expressed in terms of relative risk (RR) and cumulative relative risk (RRC), indicated a relative significant effect up to 15 lag days of lag (RR > 1), with a first peak after 5 days (lag ranges 0-1, 0-3, and 0-5) and a second weak peak observed along the 5-15 lag range days. The estimated RR for females was significant, mainly in the second and fourth age group considered (19-44 and >65 years): RR for total ED visits 1.27, confidence interval (CI) 1.11-1.46 (lag 0-5 days); RR 1.42, CI 1.01-2.01 (lag 0-10 days); and RR 1.35, CI 1.09-1.68 (lag 0-15 days). The research also indicated a moderate involvement of the thermal factor in the onset of RC caused by UC, exclusively in the female sex. Further studies will be necessary to confirm these results.

  7. Association with meteo-climatological factors and daily emergency visits for renal colic and urinary calculi in Cuneo, Italy. A retrospective observational study, 2007-2010.

    PubMed

    Condemi, Vincenzo; Gestro, Massimo; Dozio, Elena; Tartaglino, Bruno; Corsi Romanelli, Massimiliano Marco; Solimene, Umberto; Meco, Roberto

    2015-03-01

    The incidence of nephrolithiasis is rising worldwide, especially in women and with increasing age. Incidence and prevalence of kidney stones are affected by genetic, nutritional, and environmental factors. The aim of this study is to investigate the link between various meteorological factors (independent variables) and the daily number of visits to the Emergency Department (ED of the S. Croce and Carle Hospital of Cuneo for renal colic (RC) and urinary stones (UC) as the dependent variable over the years 2007-2010.The Poisson generalized regression models (PGAMs) have been used in different progressive ways. The results of PGAMs (stage 1) adjusted for seasonal and calendar factors confirmed a significant correlation (p < 0.03) with the thermal parameter. Evaluation of the dose-response effect [PGAMs combined with distributed lags nonlinear models (DLNMs)-stage 2], expressed in terms of relative risk (RR) and cumulative relative risk (RRC), indicated a relative significant effect up to 15 lag days of lag (RR > 1), with a first peak after 5 days (lag ranges 0-1, 0-3, and 0-5) and a second weak peak observed along the 5-15 lag range days. The estimated RR for females was significant, mainly in the second and fourth age group considered (19-44 and >65 years): RR for total ED visits 1.27, confidence interval (CI) 1.11-1.46 (lag 0-5 days); RR 1.42, CI 1.01-2.01 (lag 0-10 days); and RR 1.35, CI 1.09-1.68 (lag 0-15 days). The research also indicated a moderate involvement of the thermal factor in the onset of RC caused by UC, exclusively in the female sex. Further studies will be necessary to confirm these results. PMID:24970114

  8. [Studies and safety evaluation of aflatoxins in herbal plants].

    PubMed

    Ledzion, Ewa; Rybińska, Krystyna; Postupolski, Jacek; Kurpińska-Jaworska, Jolanta; Szczesna, Małgorzata

    2011-01-01

    Herbs and herbal products are commonly used in food and pharmaceutical industries. The aim of this study was to test herbal plants for contamination with aflatoxins (AF), genotoxic, cancerogenic and hepatotoxic compounds which can cause immunotoxic and allergic effects as well as growth disorders. Aflatoxins were determined by high performance liquid chromatography (HPLC) with post column derivatization involving bromination with pyridinium hydrobromide perbromide (PBPB). Extracts was cleaned-up by immunoaffinity columns (IAC). The contents of aflatoxins B, B, G, and G, in more than 500 herbal plants samples mainly from Eastern Poland were investigated. Samples were supplied by manufacturers (herbal facilities) in 2006-2010 years. In all the evaluated samples the levels of aflatoxins above the detection limits of methods applied were not observed: for AF B1--0.2 microg/kg; AF B2--0.03 microg/kg; AF G1--0.3 microg/kg; AF G2--0.03 microg/kg (PN-EN 14123) and for AF B1--0.15 microg/kg (Ph. Eur.6, 2008:2.8.18). All the herbal plants tested for contamination with aflatoxins should be considered safe, which indicates that manufacturers used good manufacturing practices during drying and storage of raw materials. PMID:22435291

  9. The 10 MWe solar thermal central receiver pilot plant: Beam safety tests and analyses

    NASA Astrophysics Data System (ADS)

    Brumleve, T. D.

    1984-07-01

    Potential eye hazards of reflected heliostat beams were evaluated and the adequacy of the beam safety central strategy at the 10 MWe solar thermal central receiver pilot plant was verified. Special video techniques were used during helicopter flyovers and a ground level to determine retinal irradiance and image size relative to a reference Sun. Receiver brightness was also measured. Measured values were consistent with analyses, and safety provisions at the plant were found to be adequate. Other beam control strategies for heliostats designed to stow face-up in high winds are studied, and one strategy is checked experimentally during the helicopter flyover tests.

  10. Safety assessment of animal- and plant-derived amino acids as used in cosmetics.

    PubMed

    Burnett, Christina; Heldreth, Bart; Bergfeld, Wilma F; Belsito, Donald V; Hill, Ronald A; Klaassen, Curtis D; Liebler, Daniel C; Marks, James G; Shank, Ronald C; Slaga, Thomas J; Snyder, Paul W; Andersen, F Alan

    2014-01-01

    The Cosmetic Ingredient Review Expert Panel (Panel) reviewed the safety of animal- and plant-derived amino acid mixtures, which function as skin and hair conditioning agents. The safety of α-amino acids as direct food additives has been well established, based on extensive research through acute and chronic dietary exposures and the Panel previously has reviewed the safety of individual α-amino acids in cosmetics. The Panel focused its review on dermal irritation and sensitization data relevant to the use of these ingredients in topical cosmetics. The Panel concluded that these 21 ingredients are safe in the present practices of use and concentration as used in cosmetics. PMID:25323218

  11. [Health & safety in a steel plant: technical and managerial action].

    PubMed

    Fusato, M

    2012-01-01

    The report presents the experience in a steel company to improve the management of issues relating to health and safety of workers. The first part of the work focuses on the description of the interventions made by the company in recent years, which can be divided into technical interventions on production facilities, training and information, organizational activities and specific projects in collaboration with the health service. The second part presents the certification project according to OHSAS 18001, with particular focus on the efforts for a lean management of the documentation required by the management systems and for the automation of internal processes. The last part finally describes in detail the manner in which it was decided to address some issues that significantly affect the factory doctor: the recording and analysis of accidents and medications, management of hazardous substances and personal protective equipment. PMID:23405577

  12. Safety aspects of fuel handling in IGCC and PFBC plants

    SciTech Connect

    Wilen, C.; Rautalin, A.

    1999-07-01

    Safety-technical characteristics of fuels, primarily biomass and, as reference, coal have been studied at VTT Energy since the year 1993. The work has related mainly to the development work of feeding and handling systems for pressurized gasification and combustion technology. This paper compares various pressurized system alternatives based primarily on lock-hopper feeding technology. A significant issue is how to arrange pressurization and sufficiently safe conditions. New alternatives to produce inert gas and the latest dust explosion suppression technology are assessed. New data on the safety-technical characteristics of renewable fuels, wastes, low-rank coals and mixtures of these, created in a research project funded by EC under the Joule 3 Programme are presented. Dust explosion testing was performed at initial pressures of up to 15 bar and temperatures of 150 C to simulate pressurized drying and handling of the biomass fuels. Inerting tests with nitrogen and flue gases were carried out to determine the requirements of non-explosive conditions. Very high explosion pressures and rates of pressure rise are measured at elevated initial pressures. The required level of inertization on dust explosions is dependent of the initial pressure and temperature. Safe operation would require an oxygen concentration of max 10 vol% in the surrounding atmosphere. The allowable oxygen concentration decreases with increasing initial temperature. For all powders tested this decrease was more or less the same, around 1--3 vol% per 100 C temperature rise. Suppression tests were performed in co-operation with Coal Technology Development Division of British Coal Corp. to assess the usability of this explosion protection method for biomass fuels in elevated conditions.

  13. Biosafety Test for Plant Growth-Promoting Bacteria: Proposed Environmental and Human Safety Index (EHSI) Protocol

    PubMed Central

    Vílchez, Juan I.; Navas, Alfonso; González-López, Jesús; Arcos, Susana C.; Manzanera, Maximino

    2016-01-01

    Plant growth-promoting bacteria (PGPB) colonize plants and enhance their growth by different mechanisms. Some of these microorganisms may represent a potential threat to human, animal or plant health; however, their use might be approved in parts of Europe if they have been recommended as plant growth enhancers. The current regulatory framework has resulted in a fragmented, contradictory system, and there is an urgent need to establish harmonized protocols for the predictability, efficiency, consistency and especially the safety of PGPB for human and animal health and for the environment. In response to current efforts to update biosafety policies and provide alternative methods to replace the use of vertebrate animals, we propose a panel of tests and an evaluation system to reliably determine the biosafety of bacterial strains used as PGPB. Based on the results of different tests, we propose a scoring system to evaluate the safety of candidates for PGPB within the limitations of the assays used. PMID:26779168

  14. Status of safety issues at licensed power plants: TMI Action Plan requirements; unresolved safety issues; generic safety issues; other multiplant action issues. Supplement 3

    SciTech Connect

    Not Available

    1993-12-01

    As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, the NRC established a program for publishing an annual report on the status of licensee implementation and NRC verification of safety issues in major NRC requirements areas. This information was initially compiled and reported in three NUREG-series volumes. Volume 1, published in March 1991, addressed the status of Three Mile Island (TMI) Action Plan Requirements. Volume 2, published in May 1991, addressed the status of unresolved safety issues (USIs). Volume 3, published in June 1991, addressed the implementation and verification status of generic safety issues (GSIs). The first annual supplement, which combined these volumes into a single report and presented updated information as of September 30, 1991, was published in December 1991. The second annual supplement, which provided updated information as of September 30, 1992, was published in December 1992. Supplement 2 also provided the status of licensee implementation and NRC verification of other multiplant action (MPA) issues not related to TMI Action Plan requirements, USIs, or GSIs. This third annual NUREG report, Supplement 3, presents updated information as of September 30, 1993. This report gives a comprehensive description of the implementation and verification status of TMI Action Plan requirements, safety issues designated as USIs, GSIs, and other MPAs that have been resolved and involve implementation of an action or actions by licensees. This report makes the information available to other interested parties, including the public. Additionally, this report serves as a follow-on to NUREG-0933, ``A Prioritization of Generic Safety Issues,`` which tracks safety issues until requirements are approved for imposition at licensed plants or until the NRC issues a request for action by licensees.

  15. Luminant's Big Brown Plant wins for continuous improvement and safety programs

    SciTech Connect

    Peltier, R.

    2008-07-15

    Staff from Luminant's Big Brown Plant accepted the PRB Coal Users' Group's top honour for innovative improvements to coal-handling systems and a sterling safety record. The numbers reveal their accomplishments: an average EFOR less than 4%, an availability factor averaging 90% for a plant that burns a lignite/PRB mix, and staff who worked more than 2.6 million man-hours since March 2000 without a lost-time injury. 13 photos., 1 tab.

  16. Potential safety-related incidents with possible applicability to a nuclear fuel reprocessing plant

    SciTech Connect

    Perkins, W.C.; Durant, W.S.; Dexter, A.H.

    1980-12-01

    The occurrence of certain potential events in nuclear fuel reprocessing plants could lead to significant consequences involving risk to operating personnel or to the general public. This document is a compilation of such potential initiating events in nuclear fuel reprocessing plants. Possible general incidents and incidents specific to key operations in fuel reprocessing are considered, including possible causes, consequences, and safety features designed to prevent, detect, or mitigate such incidents.

  17. Pinellas Plant: Child Care/Partnership School safety assessment

    SciTech Connect

    1989-11-01

    The Albuquerque Operations Office through the Pinellas Plant Area Office is involved in a joint venture to establish a Partnership School and a Day Care Facility at the Plant. The venture is unique in that it is based on a partnership with the local county school system. The county school system will provide the teachers, supplies and classroom furnishings for the operation of the school for pre-kindergarten, kindergarten, first and second grade during regular school hours. The Government will provide the facility and its normal operating and maintenance costs. A Day Care Facility will also be available for children from infancy through the second grade for outside school hours. The day care will be operated as a non-profit corporation. Fees paid by parents with children in the day care center will cove the cost of staff, food, supplies and liability insurance. Again, the government will provide the facility and its normal operating and maintenance costs. Between 75 and 90 children are expected in the first year of operation. The Partnership School will consist of one class each for pre-kindergarten, kindergarten and first grade. Second grade will be added in 1990. The total estimated number of children for both the Child Care and Partnership School should not exceed 200 children. Expected benefits include reduced absenteeism, tardiness and turnover and thus increased productivity. The program will be an asset in recruiting and retaining the best workforce. Other benefits include improved education for the children.

  18. Do ethnobotanical and laboratory data predict clinical safety and efficacy of anti-malarial plants?

    PubMed Central

    2011-01-01

    Background Over 1200 plant species are reported in ethnobotanical studies for the treatment of malaria and fevers, so it is important to prioritize plants for further development of anti-malarials. Methods The “RITAM score” was designed to combine information from systematic literature searches of published ethnobotanical studies and laboratory pharmacological studies of efficacy and safety, in order to prioritize plants for further research. It was evaluated by correlating it with the results of clinical trials. Results and discussion The laboratory efficacy score correlated with clinical parasite clearance (rs=0.7). The ethnobotanical component correlated weakly with clinical symptom clearance but not with parasite clearance. The safety component was difficult to validate as all plants entering clinical trials were generally considered safe, so there was no clinical data on toxic plants. Conclusion The RITAM score (especially the efficacy and safety components) can be used as part of the selection process for prioritising plants for further research as anti-malarial drug candidates. The validation in this study was limited by the very small number of available clinical studies, and the heterogeneity of patients included. PMID:21411018

  19. Plant Modernization with Digital Reactor Protection System Safety System Upgrades at US Nuclear Power Stations

    SciTech Connect

    Heckle, Wm. Lloyd; Bolian, Tricia W.

    2006-07-01

    As the current fleet of nuclear power plants in the US reaches 25+ years of operation, obsolescence is driving many utilities to implement upgrades to both their safety and non-safety-related Instrumentation and Control (I and C) Systems. Digital technology is the predominant replacement technology for these upgrades. Within the last 15 years, digital control systems have been deployed in non-safety- related control applications at many utilities. In addition, a few utilities have replaced small safety-related systems utilizing digital technology. These systems have shown digital technology to be robust, reliable and simpler to maintain. Based upon this success, acceptance of digital technology has gained momentum with both utilities and regulatory agencies. Today, in an effort to extend the operating lives of their nuclear stations and resolve obsolescence of critical components, utilities are now pursuing digital technology for replacement of their primary safety systems. AREVA is leading this effort in the United States with the first significant digital upgrade of a major safety system. AREVA has previously completed upgrades to safety-related control systems emergency diesel engine controls and governor control systems for a hydro station which serves as the emergency power source for a nuclear station. Currently, AREVA is implementing the replacement of both the Reactor Protection System (RPS) and the Engineered Safety Features Actuation System (ESFAS) on all three units at a US PWR site. (authors)

  20. Technical safety appraisal: Buildings 776/777 Rocky Flats Plant

    SciTech Connect

    Field, H C

    1988-03-01

    Buildings 776/777 at the Rocky Flats Plant are major components of the production complex at the plant site. They have been in operation since 1957. The operations taking place in the buildings are nuclear weapons production support, processing of weapons assemblies returned from Pantex, waste processing, research and development in support of production, special projects, and those generated by support groups, such as maintenance. The appraisal team identified nine deficiencies that it believed required prompt attention. DOE management for EH, the program office (Defense Programs), and the field office analyzed the information provided by the appraisal team and instituted compensatory measures for closer monitoring of contractor activities by knowledgeable DOE staff and staff from other sites. Concurrently, the contractor was requested to address both short-term and long-term remedial measures to correct the identified issues as well as the underlying problems. The contractor has provided his action plan, which is included. This plan was under evaluation by EH and the DOE program office at the time this report was prepared. In addressing the major areas of concern identified above, a well as the specific deficiencies identified by the appraisal team, the contractor and the field office are cautioned to search for the root causes for the problems and to direct corrective actions to those root causes rather than solely to the symptoms to assure the sustainability of the improvements being made. The results of prior TSAs led DOE to conclude that previous corrective actions were not sufficient in that a large number of the individual findings are recurrent. Pending completion of remedial actions over the next few months, enhanced DOE oversight of the contractor is warranted.

  1. Safety Culture Assessment in Petrochemical Industry: A Comparative Study of Two Algerian Plants

    PubMed Central

    Boughaba, Assia; Hassane, Chabane; Roukia, Ouddai

    2014-01-01

    Background To elucidate the relationship between safety culture maturity and safety performance of a particular company. Methods To identify the factors that contribute to a safety culture, a survey questionnaire was created based mainly on the studies of Fernández-Muñiz et al. The survey was randomly distributed to 1000 employees of two oil companies and realized a rate of valid answer of 51%. Minitab 16 software was used and diverse tests, including the descriptive statistical analysis, factor analysis, reliability analysis, mean analysis, and correlation, were used for the analysis of data. Ten factors were extracted using the analysis of factor to represent safety culture and safety performance. Results The results of this study showed that the managers' commitment, training, incentives, communication, and employee involvement are the priority domains on which it is necessary to stress the effort of improvement, where they had all the descriptive average values lower than 3.0 at the level of Company B. Furthermore, the results also showed that the safety culture influences the safety performance of the company. Therefore, Company A with a good safety culture (the descriptive average values more than 4.0), is more successful than Company B in terms of accident rates. Conclusion The comparison between the two petrochemical plants of the group Sonatrach confirms these results in which Company A, the managers of which are English and Norwegian, distinguishes itself by the maturity of their safety culture has significantly higher evaluations than the company B, who is constituted of Algerian staff, in terms of safety management practices and safety performance. PMID:25180135

  2. Next Generation Nuclear Plant Structures, Systems, and Components Safety Classification White Paper

    SciTech Connect

    Pete Jordan

    2010-09-01

    This white paper outlines the relevant regulatory policy and guidance for a risk-informed approach for establishing the safety classification of Structures, Systems, and Components (SSCs) for the Next Generation Nuclear Plant and sets forth certain facts for review and discussion in order facilitate an effective submittal leading to an NGNP Combined Operating License application under 10 CFR 52.

  3. 77 FR 15399 - Model Safety Evaluation for Plant-Specific Adoption of Technical Specifications Task Force...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-03-15

    ... (76 FR 73737), is available under ADAMS Accession No. ML120200484. NRC's PDR: You may examine and... COMMISSION Model Safety Evaluation for Plant-Specific Adoption of Technical Specifications Task Force...-specific adoption of Technical Specifications (TS) Task Force (TSTF) Traveler TSTF-505, Revision...

  4. 77 FR 69507 - Proposed Model Safety Evaluation for Plant-Specific Adoption of Technical Specifications Task...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-11-19

    ...The U.S. Nuclear Regulatory Commission (NRC) is requesting public comment on the proposed model safety evaluation (SE) for plant- specific adoption of Technical Specifications (TS) Task Force (TSTF) Traveler TSTF-535, Revision 0, ``Revise Shutdown Margin Definition to Address Advanced Fuel...

  5. 78 FR 47012 - Developing Software Life Cycle Processes Used in Safety Systems of Nuclear Power Plants

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-08-02

    ...The U.S. Nuclear Regulatory Commission (NRC) is issuing a revised regulatory guide (RG), revision 1 of RG 1.173, ``Developing Software Life Cycle Processes for Digital Computer Software used in Safety Systems of Nuclear Power Plants.'' This RG endorses the Institute of Electrical and Electronic Engineers (IEEE) Standard (Std.) 1074-2006, ``IEEE Standard for Developing a Software Project Life......

  6. Factors influencing workers to follow food safety management systems in meat plants in Ontario, Canada.

    PubMed

    Ball, Brita; Wilcock, Anne; Aung, May

    2009-06-01

    Small and medium sized food businesses have been slow to adopt food safety management systems (FSMSs) such as good manufacturing practices and Hazard Analysis Critical Control Point (HACCP). This study identifies factors influencing workers in their implementation of food safety practices in small and medium meat processing establishments in Ontario, Canada. A qualitative approach was used to explore in-plant factors that influence the implementation of FSMSs. Thirteen in-depth interviews in five meat plants and two focus group interviews were conducted. These generated 219 pages of verbatim transcripts which were analysed using NVivo 7 software. Main themes identified in the data related to production systems, organisational characteristics and employee characteristics. A socio-psychological model based on the theory of planned behaviour is proposed to describe how these themes and underlying sub-themes relate to FSMS implementation. Addressing the various factors that influence production workers is expected to enhance FSMS implementation and increase food safety. PMID:20183193

  7. AP1000{sup R} nuclear power plant safety overview for spent fuel cooling

    SciTech Connect

    Gorgemans, J.; Mulhollem, L.; Glavin, J.; Pfister, A.; Conway, L.; Schulz, T.; Oriani, L.; Cummins, E.; Winters, J.

    2012-07-01

    The AP1000{sup R} plant is an 1100-MWe class pressurized water reactor with passive safety features and extensive plant simplifications that enhance construction, operation, maintenance, safety and costs. The AP1000 design uses passive features to mitigate design basis accidents. The passive safety systems are designed to function without safety-grade support systems such as AC power, component cooling water, service water or HVAC. Furthermore, these passive features 'fail safe' during a non-LOCA event such that DC power and instrumentation are not required. The AP1000 also has simple, active, defense-in-depth systems to support normal plant operations. These active systems provide the first level of defense against more probable events and they provide investment protection, reduce the demands on the passive features and support the probabilistic risk assessment. The AP1000 passive safety approach allows the plant to achieve and maintain safe shutdown in case of an accident for 72 hours without operator action, meeting the expectations provided in the U.S. Utility Requirement Document and the European Utility Requirements for passive plants. Limited operator actions are required to maintain safe conditions in the spent fuel pool via passive means. In line with the AP1000 approach to safety described above, the AP1000 plant design features multiple, diverse lines of defense to ensure spent fuel cooling can be maintained for design-basis events and beyond design-basis accidents. During normal and abnormal conditions, defense-in-depth and other systems provide highly reliable spent fuel pool cooling. They rely on off-site AC power or the on-site standby diesel generators. For unlikely design basis events with an extended loss of AC power (i.e., station blackout) or loss of heat sink or both, spent fuel cooling can still be provided indefinitely: - Passive systems, requiring minimal or no operator actions, are sufficient for at least 72 hours under all possible pool

  8. Vulnerability, safety and response of nuclear power plants to the hydroclimatic hazards

    NASA Astrophysics Data System (ADS)

    János Katona, Tamás; Vilimi, András

    2016-04-01

    The Great Tohoku Earthquake and Tsunami, and the severe accident at Fukushima Dai-ichi nuclear power plant 2011 alerted the nuclear industry to danger of extreme rare natural hazards. The subsequent "stress tests" performed by the nuclear industry in Europe and all over the world identifies the nuclear power plant (NPP) vulnerabilities and define the measures for increasing the plant safety. According to the international practice of nuclear safety regulations, the cumulative core damage frequency for NPPs has to be 10-5/a, and the cumulative frequency of early large release has to be 10-6/a. In case of operating plants these annual probabilities can be little higher, but the licensees are obliged to implement all reasonable practicable measures for increasing the plant safety. For achieving the required level of safety, design basis of NPPs for natural hazards has to be defined at the 10-4/a ⎯10-5/a levels of annual exceedance probability. Tornado hazard is some kind of exception, e.g., the design basis annual probability for tornado in the US is equal to 10-7/a. Design of the NPPs shall provide for an adequate margin to protect items ultimately necessary to prevent large or early radioactive releases in the event of levels of natural hazards exceeding those to be considered for design. The plant safety has to be reviewed for accounting the changes of the environmental conditions and natural hazards in case of necessity, but as minimum every ten years in the frame of periodic safety reviews. Long-term forecast of environmental conditions and hazards has to be accounted for in the design basis of the new plants. Changes in hydroclimatic variables, e.g., storms, tornadoes, river floods, flash floods, extreme temperatures, droughts affect the operability and efficiency as well as the safety the NPPs. Low flow rates and high water temperature in the rivers may force to operate at reduced power level or shutdown the plant (Cernavoda NPP, Romania, August 2009). The

  9. 78 FR 47011 - Software Unit Testing for Digital Computer Software Used in Safety Systems of Nuclear Power Plants

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-08-02

    ... identification as Draft Regulatory Guide, DG-1208 on August 22, 2012 (77 FR 50722) for a 60-day public comment... COMMISSION Software Unit Testing for Digital Computer Software Used in Safety Systems of Nuclear Power Plants..., ``Software Unit Testing for Digital Computer Software Used in Safety Systems of Nuclear Power Plants.''...

  10. 78 FR 47805 - Test Documentation for Digital Computer Software Used in Safety Systems of Nuclear Power Plants

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-08-06

    ... issued with a temporary identification as Draft Regulatory Guide, DG-1207 on August 22, 2012 (77 FR 50720... COMMISSION Test Documentation for Digital Computer Software Used in Safety Systems of Nuclear Power Plants..., ``Test Documentation for Digital Computer Software Used in Safety Systems of Nuclear Power Plants.''...

  11. Safety evaluation of some wild plants in the New Nordic Diet.

    PubMed

    Mithril, Charlotte; Dragsted, Lars Ove

    2012-12-01

    One of the dietary components in the New Nordic Diet, is plants from the wild countryside. However, these may have a high content of bioactive components, some of which could be toxic in larger quantities. The objective of this paper is to outline a strategy for safety evaluation of wild plants not covered in current food compositional databases and to apply the method for selected plants used in the New Nordic Diet recipes. Four examples of typical wild edible plants were evaluated (stinging nettle, sorrel, chickweed and common lambsquarters), and based on substantial equivalence with known food plants the majority of the bioactive components reported were within the range experienced when eating or drinking typical food stuffs. For most compounds the hazards could be evaluated as minor. The only precaution found was for common lambsquarters because of its presumed high level of oxalic acid. It is concluded that a substance-by-substance evaluation of intake by equivalence to common foods is a useful and efficient strategy to evaluate the safety of newly introduced wild edible plants. Further evaluation and better compositional analyses are warranted before a daily consumption of significant amounts of wild edible plants can be generally regarded as safe. PMID:23009884

  12. Organizational analysis and safety for utilities with nuclear power plants: an organizational overview. Volume 1. [PWR; BWR

    SciTech Connect

    Osborn, R.N.; Olson, J.; Sommers, P.E.; McLaughlin, S.D.; Jackson, M.S.; Scott, W.G.; Connor, P.E.

    1983-08-01

    This two-volume report presents the results of initial research on the feasibility of applying organizational factors in nuclear power plant (NPP) safety assessment. A model is introduced for the purposes of organizing the literature review and showing key relationships among identified organizational factors and nuclear power plant safety. Volume I of this report contains an overview of the literature, a discussion of available safety indicators, and a series of recommendations for more systematically incorporating organizational analysis into investigations of nuclear power plant safety.

  13. Applying the results of probablistic safety analysis of nuclear power plants: a survey of experience

    SciTech Connect

    Andrews, W.B.; Herttrich, M.; Koeberlein, K.; Schwager

    1985-01-01

    To date, discussions of the many different types of potential applications of PRA/PSA results and insights to safety-decision-making have been mainly theoretical. Various safety goals have been proposed as decision criteria. However, the discussion on the role of PRA/PSA and Safety Goals in safety-decision-making, especially in licensing, is controversial. A Working Group of the OECD Nuclear Energy Agency is completing a compilation and evaluation of real examples of past and present practical experience with the application of probabilistic methods in reactor safety decision-making, with the idea of developing a common understanding in this area. More than fifty different cases where PRA has influenced decision-making have been surveyed. These include, for example, regulatory changes, fixing of licensing requirements, plant specific modifications of design of operation, prioritization of safety issues and emergency planning. This feedback of experience - both positive and negative - with PRA/PSA applications is considered to provide guidance on how probabilistic approaches can be introduced into current safety practices, and on desirable future developments in probabilistic methods and specific PSA/PRA studies. Generic insights from the survey are given.

  14. An assessment of criticality safety at the Department of Energy Rocky Flats Plant, Golden, Colorado, July--September 1989

    SciTech Connect

    Mattson, Roger J.

    1989-09-01

    This is a report on the 1989 independent Criticality Safety Assessment of the Rocky Flats Plant, primarily in response to public concerns that nuclear criticality accidents involving plutonium may have occurred at this nuclear weapon component fabrication and processing plant. The report evaluates environmental issues, fissile material storage practices, ventilation system problem areas, and criticality safety practices. While no evidence of a criticality accident was found, several recommendations are made for criticality safety improvements. 9 tabs.

  15. Nuclear Safety Risk Management in Refueling Outage of Qinshan Nuclear Power Plant

    SciTech Connect

    Meijing Wu; Guozhang Shen

    2006-07-01

    The NPP is used to planning maintenance, in-service inspection, surveillance test, fuel handling and design modification in the refueling outage; the operator response capability will be reduced plus some of the plant systems out of service or loss of power at this time. Based on 8 times refueling outage experiences of the Qinshan NPP, this article provide some good practice and lesson learned for the nuclear safety risk management focus at four safety function areas of Residual Heat Removal Capability, Inventory Control, Power availability and Reactivity control. (authors)

  16. CONFERENCE REPORT: Summary of the 8th IAEA Technical Meeting on Fusion Power Plant Safety

    NASA Astrophysics Data System (ADS)

    Girard, J. Ph.; Gulden, W.; Kolbasov, B.; Louzeiro-Malaquias, A.-J.; Petti, D.; Rodriguez-Rodrigo, L.

    2008-01-01

    Reports were presented covering a selection of topics on the safety of fusion power plants. These included a review on licensing studies developed for ITER site preparation surveying common and non-common issues (i.e. site dependent) as lessons to a broader approach for fusion power plant safety. Several fusion power plant models, spanning from accessible technology to more advanced-materials based concepts, were discussed. On the topic related to fusion-specific technology, safety studies were reported on different concepts of breeding blanket modules, tritium handling and auxiliary systems under normal and accident scenarios' operation. The testing of power plant relevant technology in ITER was also assessed in terms of normal operation and accident scenarios, and occupational doses and radioactive releases under these testings have been determined. Other specific safety issues for fusion have also been discussed such as availability and reliability of fusion power plants, dust and tritium inventories and component failure databases. This study reveals that the environmental impact of fusion power plants can be minimized through a proper selection of low activation materials and using recycling technology helping to reduce waste volume and potentially open the route for its reutilization for the nuclear sector or even its clearance into the commercial circuit. Computational codes for fusion safety have been presented in support of the many studies reported. The on-going work on establishing validation approaches aiming at improving the prediction capability of fusion codes has been supported by experimental results and new directions for development have been identified. Fusion standards are not available and fission experience is mostly used as the framework basis for licensing and target design for safe operation and occupational and environmental constraints. It has been argued that fusion can benefit if a specific fusion approach is implemented, in particular

  17. Use of artificial intelligence to enhance the safety of nuclear power plants

    SciTech Connect

    Uhrig, R.E.

    1988-01-01

    In the operation of a nuclear power plant, the sheer magnitude of the number of process parameters and systems interactions poses difficulties for the operators, particularly during abnormal or emergency situations. Recovery from an upset situation depends upon the facility with which the available raw data can be converted into and assimilated as meaningful knowledge. Plant personnel are sometimes affected by stress and emotion, which may have varying degrees of influence on their performance. Expert systems can take some of the uncertainty and guesswork out of their decisions by providing expert advice and rapid access to a large information base. Application of artificial intelligence technologies, particularly expert systems, to control room activities in a nuclear power plant has the potential to reduce operator error and improve power plant safety and reliability. 12 refs.

  18. Protection of Operators and Environment - the Safety Concept of the Karlsruhe Vitrification Plant VEK

    SciTech Connect

    Fleisch, J.; Kuttruf, H.; Lumpp, W.; Pfeifer, W.; Roth, G.; Weisenburger, S.

    2002-02-26

    The Karlsruhe Vitrification Plant (VEK) plant is a milestone in decommissioning and complete dismantling of the former Karlsruhe Reprocessing Plant WAK, which is in an advanced stage of disassembly. The VEK is scheduled to vitrify approx. 70 m3 of the highly radioactive liquid waste (HLW) resulting from reprocessing. Site preparation, civil work and component manufacturing began in 1999. The building will be finalized by mid of 2002, hot vitrification operation is currently scheduled for 2004/2005. Provisions against damages arising from construction and operation of the VEK had to be made in accordance with the state of the art as laid down in the German Atomic Law and the Radiation Protection Regulations. For this purpose, the appropriate analysis of accidents and their external and internal impacts were investigated. During the detailed design phase, a failure effects analysis was carried out, in which single events were studied with respect to the objectives of protection and ensuring activity containment, limiting radioactive discharges to the environment and protecting of the staff. Parallel to the planning phase of the VEK plant a cold prototype test facility (PVA) covering the main process steps was constructed and operated at the Institut fuer Nukleare Entsorgung (INE) of FZK. This pilot operation served to demonstrate the process technique and its operation with a simulated waste solution, and to test the main items of equipment, but was conducted also to use the experimental data and experience to back the safety concept of the radioactive VEK plant. This paper describes the basis of the safety concept of the VEK plant and results of the failure effect analysis. The experimental simulation of the failure scenarios, their effect on the process behavior, and the controllability of these events as well as the effect of the results on the safety concept of VEK are discussed. Additionally, an overview of the actual status of civil work and manufacturing of

  19. A probabilistic safety analysis of UF{sub 6} handling at the Portsmouth Gaseous Diffusion Plant

    SciTech Connect

    Boyd, G.J.; Lewis, S.R.; Summitt, R.L.

    1991-12-31

    A probabilistic safety study of UF{sub 6} handling activities at the Portsmouth Gaseous Diffusion Plant has recently been completed. The analysis provides a unique perspective on the safety of UF{sub 6} handling activities. The estimated release frequencies provide an understanding of current risks, and the examination of individual contributors yields a ranking of important plant features and operations. Aside from the probabilistic results, however, there is an even more important benefit derived from a systematic modeling of all operations. The integrated approach employed in the analysis allows the interrelationships among the equipment and the required operations to be explored in depth. This paper summarizes the methods used in the study and provides an overview of some of the technical insights that were obtained. Specific areas of possible improvement in operations are described.

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

    SciTech Connect

    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.

  1. Probabilistic Safety Study Applications Program for inspection of the Indian Point Unit 3 Nuclear Power Plant

    SciTech Connect

    Taylor, J.H.; Fullwood, R.; Fresco, A.

    1986-03-01

    By prioritizing the various areas of interest for inspection and by better defining inspection needs, the NRC expects to make more effective use of finite inspection resources by concentrating on those potential areas most significant to safety. Through review and application of the Indian Point Unit 3 Probabilistic Safety Study's numerical data and event tree modeling, and by utilizing related documents, a technical basis for prioritizing areas for NRC inspection has been developed. This was then tested at the plant site for the NRC Operating Reactor Inspection Program, I and E Manual Chapter 2515. Inspection activities addressed include normal operations, system and component testing, maintenance and surveillance. A computer program entitled NSPKTR, which was developed specifically for this program, modeled the internal plant states to the system level and performed the risk and importance calculations. 17 refs., 21 tabs.

  2. Implementation of external hazards in Probabilistic Safety Assessment for nuclear power plants

    NASA Astrophysics Data System (ADS)

    Kumar, Manorma; Klug, Joakim; Raimond, Emmanuel

    2015-04-01

    The paper will focus on the discussion on implementation of external hazards in the probabilistic safety assessment (PSA) methods for the extreme external hazards mainly focused on Seismic, Flooding, Meteorological Hazards (e.g. Storm, Extreme temperature, snow pack), Biological infestation, Lightening hazards, Accidental Aircraft crash and man- made hazards including natural external fire and external explosion. This will include discussion on identification of some good practices on the implementation of external hazards in Level 1 PSA, with a perspective of development of extended PSA and introduction of relevant modelling for external hazards in an existing Level 1 PSA. This paper is associated to the European project ASAMPSAE (www.asampsa.eu) which gathers more than 30 organizations (industry, research, safety control) from Europe, US and Japan and which aims at identifying some meaningful practices to extend the scope and the quality of the existing probabilistic safety analysis developed for nuclear power plants.

  3. Organizational analysis and safety for utilities with nuclear power plants: perspectives for organizational assessment. Volume 2. [PWR; BWR

    SciTech Connect

    Osborn, R.N.; Olson, J.; Sommers, P.E.; McLaughlin, S.D.; Jackson, M.S.; Nadel, M.V.; Scott, W.G.; Connor, P.E.; Kerwin, N.; Kennedy, J.K. Jr.

    1983-08-01

    This two-volume report presents the results of initial research on the feasibility of applying organizational factors in nuclear power plant (NPP) safety assessment. Volume 1 of this report contains an overview of the literature, a discussion of available safety indicators, and a series of recommendations for more systematically incorporating organizational analysis into investigations of nuclear power plant safety. The six chapters of this volume discuss the major elements in our general approach to safety in the nuclear industry. The chapters include information on organizational design and safety; organizational governance; utility environment and safety related outcomes; assessments by selected federal agencies; review of data sources in the nuclear power industry; and existing safety indicators.

  4. Criticality safety evaluation of Rocky Flats Plant one-gallon shipping containers

    SciTech Connect

    Shaw, M.E.

    1991-12-01

    Criticality safety calculations have been performed to provide an analytical basis for handling, storage and transport of Rocky Flats Plant (RFP) one-gallon shipping containers. A mass limit was establish for metal (solid uranium or plutonium) and slurries (undissolved U or Pu solids in a ``mud,`` ``sludge,`` or ``slurry``). A separate volume limit was developed for plutonium solutions (liquids, either aqueous or organic, containing no visible undissolved solids).

  5. Criticality safety evaluation of Rocky Flats Plant one-gallon shipping containers

    SciTech Connect

    Shaw, M.E.

    1991-12-01

    Criticality safety calculations have been performed to provide an analytical basis for handling, storage and transport of Rocky Flats Plant (RFP) one-gallon shipping containers. A mass limit was establish for metal (solid uranium or plutonium) and slurries (undissolved U or Pu solids in a mud,'' sludge,'' or slurry''). A separate volume limit was developed for plutonium solutions (liquids, either aqueous or organic, containing no visible undissolved solids).

  6. Safety evaluation for packaging for onsite transfer of B Plant organic waste

    SciTech Connect

    Mercado, M.S.

    1996-10-07

    This safety evaluation for packaging authorizes the use of a 17,500-L (4,623-gal) tank manufactured by Brenner Tank, Incorporated, to transport up to 16,221 L (4,285 gal) of radioactive organic liquid waste. The waste will be transported from the organic loading pad to a storage pad. Both pads are within the B Plant complex, but approximately 4 mi apart.

  7. Impact of mechanical- and maintenance-induced failures of main reactor coolant pump seals on plant safety

    SciTech Connect

    Azarm, M A; Boccio, J L; Mitra, S

    1985-12-01

    This document presents an investigation of the safety impact resulting from mechanical- and maintenance-induced reactor coolant pump (RCP) seal failures in nuclear power plants. A data survey of the pump seal failures for existing nuclear power plants in the US from several available sources was performed. The annual frequency of pump seal failures in a nuclear power plant was estimated based on the concept of hazard rate and dependency evaluation. The conditional probability of various sizes of leak rates given seal failures was then evaluated. The safety impact of RCP seal failures, in terms of contribution to plant core-melt frequency, was also evaluated for three nuclear power plants. For leak rates below the normal makeup capacity and the impact of plant safety were discussed qualitatively, whereas for leak rates beyond the normal make up capacity, formal PRA methodologies were applied. 22 refs., 17 figs., 19 tabs.

  8. Aging of turbine drives for safety-related pumps in nuclear power plants

    SciTech Connect

    Cox, D.F.

    1995-06-01

    This study was performed to examine the relationship between time-dependent degradation and current industry practices in the areas of maintenance, surveillance, and operation of steam turbine drives for safety-related pumps. These pumps are located in the Auxiliary Feedwater (AFW) system for pressurized-water reactor plants and in the Reactor Core Isolation Cooling and High-Pressure Coolant Injection systems for boiling-water reactor plants. This research has been conducted by examination of failure data in the Nuclear Plant Reliability Data System, review of Licensee Event Reports, discussion of problems with operating plant personnel, and personal observation. The reported failure data were reviewed to determine the cause of the event and the method of discovery. Based on the research results, attempts have been made to determine the predictability of failures and possible preventive measures that may be implemented. Findings in a recent study of AFW systems indicate that the turbine drive is the single largest contributor to AFW system degradation. However, examination of the data shows that the turbine itself is a reliable piece of equipment with a good service record. Most of the problems documented are the result of problems with the turbine controls and the mechanical overspeed trip mechanism; these apparently stem from three major causes which are discussed in the text. Recent improvements in maintenance practices and procedures, combined with a stabilization of the design, have led to improved performance resulting in a reliable safety-related component. However, these improvements have not been universally implemented.

  9. Safety assessment of GM plants: An updated review of the scientific literature.

    PubMed

    Domingo, José L

    2016-09-01

    In a wide revision of the literature conducted in 2000, I noted that the information in scientific journals on the safety of genetically modified (GM) foods in general, and GM plants in particular, was scarce. Of course, it was not sufficient to guarantee that the consumption of these products should not mean risks for the health of the consumers. Because of the scientific interest in GM organisms (GMOs), as well as the great concern that the consumption of GM foods/plants has raised in a number of countries, I conducted two subsequent revisions (2007 and 2011) on the adverse/toxic effects of GM plants. In the present review, I have updated the information on the potential adverse health effects of GM plants consumed as food and/or feed. With only a few exceptions, the reported studies in the last six years show rather similar conclusions; that is to say, the assessed GM soybeans, rice, corn/maize and wheat would be as safe as the parental species of these plants. However, in spite of the notable increase in the available information, studies on the long-term health effects of GM plants, including tests of mutagenicity, teratogenicity and carcinogenicity seem to be still clearly necessary. PMID:27317828

  10. A literature review on the safety assessment of genetically modified plants.

    PubMed

    Domingo, José L; Giné Bordonaba, Jordi

    2011-05-01

    In recent years, there has been a notable concern on the safety of genetically modified (GM) foods/plants, an important and complex area of research, which demands rigorous standards. Diverse groups including consumers and environmental Non Governmental Organizations (NGO) have suggested that all GM foods/plants should be subjected to long-term animal feeding studies before approval for human consumption. In 2000 and 2006, we reviewed the information published in international scientific journals, noting that the number of references concerning human and animal toxicological/health risks studies on GM foods/plants was very limited. The main goal of the present review was to assess the current state-of-the-art regarding the potential adverse effects/safety assessment of GM plants for human consumption. The number of citations found in databases (PubMed and Scopus) has dramatically increased since 2006. However, new information on products such as potatoes, cucumber, peas or tomatoes, among others was not available. Corn/maize, rice, and soybeans were included in the present review. An equilibrium in the number research groups suggesting, on the basis of their studies, that a number of varieties of GM products (mainly maize and soybeans) are as safe and nutritious as the respective conventional non-GM plant, and those raising still serious concerns, was currently observed. Nevertheless, it should be noted that most of these studies have been conducted by biotechnology companies responsible of commercializing these GM plants. These findings suggest a notable advance in comparison with the lack of studies published in recent years in scientific journals by those companies. All this recent information is herein critically reviewed. PMID:21296423

  11. Characterisation of Liquefaction Effects for Beyond-Design Basis Safety Assessment of Nuclear Power Plants

    NASA Astrophysics Data System (ADS)

    Bán, Zoltán; Győri, Erzsébet; János Katona, Tamás; Tóth, László

    2015-04-01

    -tree procedure. Earlier studies have shown that the potentially liquefiable layer at Paks Nuclear Power Plant is situated in relatively large depth. Therefore the applicability and adequacy of the methods at high overburden pressure is important. In case of existing facilities, the geotechnical data gained before construction aren't sufficient for the comprehensive liquefaction analysis. Performance of new geotechnical survey is limited. Consequently, the availability of the data has to be accounted while selection the analysis methods. Considerations have to be made for dealing with aleatory uncertainty related to the knowledge of the soil conditions. It is shown in the paper, a careful comparison and analysis of the results obtained by different methodologies provides the basis of the selection of practicable methods for the safety analysis of nuclear power plant for beyond design basis liquefaction hazard.

  12. Individual plant examination program: Perspectives on reactor safety and plant performance. Parts 2--5: Final report; Volume 2

    SciTech Connect

    1997-12-01

    This report provides perspectives gained by reviewing 75 Individual Plant Examination (IPE) submittals pertaining to 108 nuclear power plant units. IPEs are probabilistic analyses that estimate the core damage frequency (CDF) and containment performance for accidents initiated by internal events. The US Nuclear Regulatory Commission (NRC) reviewed the IPE submittals with the objective of gaining perspectives in three major areas: (1) improvements made to individual plants as a result of their IPEs and the collective results of the IPE program, (2) plant-specific design and operational features and modeling assumptions that significantly affect the estimates of CDF and containment performance, and (3) strengths and weaknesses of the models and methods used in the IPEs. These perspectives are gained by assessing the core damage and containment performance results, including overall CDF, accident sequences, dominant contributions to component failure and human error, and containment failure modes. Methods, data, boundary conditions, and assumptions used in the IPEs are considered in understanding the differences and similarities observed among the various types of plants. This report is divided into three volumes containing six parts. Part 1 is a summary report of the key perspectives gained in each of the areas identified above, with a discussion of the NRC`s overall conclusions and observations. Part 2 discusses key perspectives regarding the impact of the IPE Program on reactor safety. Part 3 discusses perspectives gained from the IPE results regarding CDF, containment performance, and human actions. Part 4 discusses perspectives regarding the IPE models and methods. Part 5 discusses additional IPE perspectives. Part 6 contains Appendices A, B and C which provide the references of the information from the IPEs, updated PRA results, and public comments on draft NUREG-1560 respectively.

  13. Individual plant examination program: Perspectives on reactor safety and plant performance. Part 1: Final summary report; Volume 1

    SciTech Connect

    1997-12-01

    This report provides perspectives gained by reviewing 75 Individual Plant Examination (IPE) submittals pertaining to 108 nuclear power plant units. IPEs are probabilistic analyses that estimate the core damage frequency (CDF) and containment performance for accidents initiated by internal events. The US Nuclear Regulatory Commission (NRC) reviewed the IPE submittals with the objective of gaining perspectives in three major areas: (1) improvements made to individual plants as a result of their IPEs and the collective results of the IPE program, (2) plant-specific design and operational features and modeling assumptions that significantly affect the estimates of CDF and containment performance, and (3) strengths and weaknesses of the models and methods used in the IPEs. These perspectives are gained by assessing the core damage and containment performance results, including overall CDF, accident sequences, dominant contributions to component failure and human error, and containment failure modes. Methods, data, boundary conditions, and assumptions used in the IPEs are considered in understanding the differences and similarities observed among the various types of plants. This report is divided into three volumes containing six parts. Part 1 is a summary report of the key perspectives gained in each of the areas identified above, with a discussion of the NRC`s overall conclusions and observations. Part 2 discusses key perspectives regarding the impact of the IPE Program on reactor safety. Part 3 discusses perspectives gained from the IPE results regarding CDF, containment performance, and human actions. Part 4 discusses perspectives regarding the IPE models and methods. Part 5 discusses additional IPE perspectives. Part 6 contains Appendices A, B and C which provide the references of the information from the IPEs, updated PRA results, and public comments on draft NUREG-1560 respectively.

  14. Plant sterols: factors affecting their efficacy and safety as functional food ingredients

    PubMed Central

    Berger, Alvin; Jones, Peter JH; Abumweis, Suhad S

    2004-01-01

    Plant sterols are naturally occurring molecules that humanity has evolved with. Herein, we have critically evaluated recent literature pertaining to the myriad of factors affecting efficacy and safety of plant sterols in free and esterified forms. We conclude that properly solubilized 4-desmetyl plant sterols, in ester or free form, in reasonable doses (0.8–1.0 g of equivalents per day) and in various vehicles including natural sources, and as part of a healthy diet and lifestyle, are important dietary components for lowering low density lipoprotein (LDL) cholesterol and maintaining good heart health. In addition to their cholesterol lowering properties, plant sterols possess anti-cancer, anti-inflammatory, anti-atherogenicity, and anti-oxidation activities, and should thus be of clinical importance, even for those individuals without elevated LDL cholesterol. The carotenoid lowering effect of plant sterols should be corrected by increasing intake of food that is rich in carotenoids. In pregnant and lactating women and children, further study is needed to verify the dose required to decrease blood cholesterol without affecting fat-soluble vitamins and carotenoid status. PMID:15070410

  15. Safety-related coating work for light-water nuclear power plants

    SciTech Connect

    Levy, A.M.

    1983-11-01

    Preparation of standards for safety-related coating work for light-water nuclear power plants has been the first priority, until recently, of Committee D-33 on Protective Coating and Lining Work for Power Generation Facilities. Coating is a term well understood in the industry as referring to a material. Coating work is more recent and an all inclusive term to define all operations required to accomplish a complete coating job. The term is constructed to include all materials, equipment, labor, testing, management and supervision, preparation of surfaces, consideration of ambient conditions, application of coating systems, and inspection. The primary purposes of safety-related work include: reducing the degree of contamination; providing readily decontaminable surfaces; and providing a protective covering that can readily be removed (if it cannot be decontaminated to a safe level) without damage to the metal or concrete surfaces.

  16. The safety assessment of food ingredients derived from plant cell, tissue and organ cultures: a review.

    PubMed

    Murthy, Hosakatte Niranjana; Georgiev, Milen I; Park, So-Young; Dandin, Vijayalaxmi S; Paek, Kee-Yoeup

    2015-06-01

    Plant cell, tissue and organ cultures (PCTOC) have become an increasingly attractive alternative for the production of various high molecular weight molecules which are used as flavourings, fragrances, colouring agents and food additives. Although PCTOC products are cultivated in vitro in a contamination free environment, the raw material produced from PCTOC may contain many components apart from the target compound. In some cases, PCTOC raw materials may also carry toxins, which may be naturally occurring or accumulated during the culture process. Assessment of the safety of PCTOC products is, therefore, a priority of the biotech industries involved in their production. The safety assessment involves the evaluation of starting material, production process and the end product. Before commercialisation, PCTOC products should be evaluated for their chemical and biological properties, as well as for their toxicity. In this review, measures and general criteria for biosafety evaluation of PCTOC products are addressed and thoroughly discussed. PMID:25624252

  17. Institutional implications of establishing safety goals for nuclear power plants. [PWR; BWR

    SciTech Connect

    Morris, F.A.; Hooper, R.L.

    1983-07-01

    The purpose of this project is to anticipate and address institutional problems that may arise from the adoption of NRC's proposed Policy Statement on Safety Goals for Nuclear Power Plants. The report emphasizes one particular category of institutional problems: the possible use of safety goals as a basis for legal challenges to NRC actions, and the resolution of such challenges by the courts. Three types of legal issues are identified and analyzed. These are, first, general legal issues such as access to the legal system, burden of proof, and standard of proof. Second is the particular formulation of goals. Involved here are such questions as sustainable rationale, definitions, avoided issues, vagueness of time and space details, and degree of conservatism. Implementation brings up the third set of issues which include interpretation and application, linkage to probabilistic risk assessment, consequences as compared to events, and the use of results.

  18. Audit of construction of an environmental, safety, and health analytical laboratory at the Pantex Plant

    SciTech Connect

    1995-10-01

    This document is a report from the Office of the Inspector General, US DOE. The report evaluates the need for the construction of an Environmental, Safety, and Health Laboratory at the Pantex Plant and if this project is the most cost effective manner in which to meet mission needs. It was found that: (1) mission needs were being met with existing facilities, (2) required evaluations of alternatives were not performed, (3) decisions were made based on out-dated justifications, and (4) the expenditure of $8.4M was unnecessary. As a result, it was recommended that funded be suspended until the need is clearly established.

  19. Safety.

    ERIC Educational Resources Information Center

    Education in Science, 1996

    1996-01-01

    Discusses safety issues in science, including: allergic reactions to peanuts used in experiments; explosions in lead/acid batteries; and inspection of pressure vessels, such as pressure cookers or model steam engines. (MKR)

  20. Optical fiber sensors to improve the safety of nuclear power plants

    NASA Astrophysics Data System (ADS)

    Ferdinand, P.; Magne, S.; Laffont, G.

    2013-09-01

    Safety must always prevail in Nuclear Power Plants (NPPs), as shown at Fukushima-Daiichi. So, innovations are clearly needed to strengthen instrumentations, which went inoperative during this nuclear accident as a consequence of power supply losses. Possible improvements concern materials and structures, which may be remotely monitored thanks to Optical Fiber Sensors (OFS). We detail topics involving OFS helpful for monitoring, in nominal conditions as well as during a severe accident. They include distributed sensing (Rayleigh, Raman, Brillouin) for both temperature sensing and structure monitoring as well as H2 concentration and ionizing radiation monitoring. For future plants, Fiber Bragg Grating (FBG) sensors are considered up to high temperature for sodium-cooled fast reactor monitoring. These applications can benefit from fiber advantages: sensor multiplexing, multi-km range, no risk-to-people, no common failure mode with other technologies, remote sensing, and the ability to operate in case of power supply lost in the NPP.

  1. Medicinal plants in the treatment of women's disorders: Analytical strategies to assure quality, safety and efficacy.

    PubMed

    Masullo, Milena; Montoro, Paola; Mari, Angela; Pizza, Cosimo; Piacente, Sonia

    2015-09-10

    During last decades an increasing number of herbal products specifically targeting women's disorders has appeared in the worldwide marketplace. This growth highlights the need for a critical evaluation of quality, safety and efficacy of these products. Analytical techniques applied to the quality control of the main medicinal plants used for women health (relief of menopause and menstrual related symptoms) have been reviewed. Thanks to the innovation in analytical technology, identification and detection of secondary metabolites dramatically improved. In particular, hyphenated techniques have proved to be the most suitable for the rapid identification of compounds in plant matrix. Moreover, taking into account that differences in sample quality are not only found in the main compounds or in the chemical markers but also in the low-concentration compounds, fingerprint analysis might be a simple way for identification and quality control of herbal products containing a large number of low amounts of unknown compounds. Furthermore in several papers the informations obtained from the analysis of a plant have been processed by statistical elaborations. Medicinal plants here discussed are classified on the basis of the chemical markers used for their quality control. PMID:25863356

  2. Safety implications of cultural and cognitive issues in nuclear power plant operation.

    PubMed

    Carvalho, Paulo V R; Dos Santos, Isaac L; Vidal, Mario C R

    2006-03-01

    This research project was designed to investigate cultural and cognitive issues related to the work of nuclear power plant operators during their time on the job in the control room and during simulator training (emergency situations), in order to show how these issues impact on plant safety. The modeling of the operators work deals with the use of operational procedures, the constant changes in the focus of attention and the dynamics of the conflicting activities. The paper focuses on the relationships between the courses of action of the different operators and the constraints imposed by their working environment. It shows that the safety implications of the control room operators' cognitive and cultural issues go far beyond the formal organizational constructs usually implied. Our findings indicate that the competence required for the operators are concerned with developing the possibility of constructing situation awareness, managing conflicts, gaps and time problems created by ongoing task procedures, and dealing with distractions, developing skills for collaborative work. PMID:15993375

  3. [Genetically modified plants and food safety. State of the art and discussion in the European Union].

    PubMed

    Schauzu, M

    2004-09-01

    Placing genetically modified (GM) plants and derived products on the European Union's (EU) market has been regulated by a Community Directive since 1990. This directive was complemented by a regulation specific for genetically modified and other novel foods in 1997. Specific labelling requirements have been applicable for GM foods since 1998. The law requires a pre-market safety assessment for which criteria have been elaborated and continuously adapted in accordance with the state of the art by national and international bodies and organisations. Consequently, only genetically modified products that have been demonstrated to be as safe as their conventional counterparts can be commercialized. However, the poor acceptance of genetically modified foods has led to a de facto moratorium since 1998. It is based on the lack of a qualified majority of EU member states necessary for authorization to place genetically modified plants and derived foods on the market. New Community Regulations are intended to end this moratorium by providing a harmonized and transparent safety assessment, a centralised authorization procedure, extended labelling provisions and a traceability system for genetically modified organisms (GMO) and derived food and feed. PMID:15378169

  4. Updating Human Factors Engineering Guidelines for Conducting Safety Reviews of Nuclear Power Plants

    SciTech Connect

    O, J.M.; Higgins, J.; Stephen Fleger - NRC

    2011-09-19

    The U.S. Nuclear Regulatory Commission (NRC) reviews the human factors engineering (HFE) programs of applicants for nuclear power plant construction permits, operating licenses, standard design certifications, and combined operating licenses. The purpose of these safety reviews is to help ensure that personnel performance and reliability are appropriately supported. Detailed design review procedures and guidance for the evaluations is provided in three key documents: the Standard Review Plan (NUREG-0800), the HFE Program Review Model (NUREG-0711), and the Human-System Interface Design Review Guidelines (NUREG-0700). These documents were last revised in 2007, 2004 and 2002, respectively. The NRC is committed to the periodic update and improvement of the guidance to ensure that it remains a state-of-the-art design evaluation tool. To this end, the NRC is updating its guidance to stay current with recent research on human performance, advances in HFE methods and tools, and new technology being employed in plant and control room design. This paper describes the role of HFE guidelines in the safety review process and the content of the key HFE guidelines used. Then we will present the methodology used to develop HFE guidance and update these documents, and describe the current status of the update program.

  5. Effect of the Wavelet Scale Thresholding on the Geonet P-Phase Picker Performance for the borehole and surface stations URZ and EDRZ using the Matata Swarms of 2007-2010

    NASA Astrophysics Data System (ADS)

    Rastin, S. J.; Unsworth, C. P.; Gledhill, K. R.

    2014-12-01

    Geonet is responsible for providing information on the geological hazard events including about 15,000 earthquakes recorded by the New Zealand seismograph network per year. Such large numbers of earthquakes confirm the importance of having an accurate P-phase picker in order to find automatic solutions for hypocenters and reduce analyst's time needed to produce the reviewed catalogs. Geonet uses an Autoregressive-Akaike Information Criterion P-phase picker to estimate the P-phase onsets from the Butterworth filtered waveforms. We studied efficiency of the P-phase picker using waveforms of 3312 shallow earthquakes of the Matata swarms in 2007-2010. For stations EDRZ and URZ with large contributions to the Geonet locator, 48.80% and 32.88% of waveforms were reviewed by analysts. Such high rates of reviewed onsets indicated the need to improve the automatic phase picking's performance. To do so, we replaced the Butterworth filtering with the Wavelet Scale Thresholding (WST) and divided the re-estimated onsets into the "unchanged", "revised", "retrieved" and "adversely affected" classes. We studied effect of the Mexican hat and Haar WST on the P-phase picker's performance using quality control parameters including total and net improvements, onset corrections, picking errors and picking quality enhancement. Applying the Mexican hat WST mainly on scales 1 and 2 to the EDRZ recordings of chosen events resulted in large percentages for average total improvement (64.79%) and onset retrieval (31.95%) in 2007-2010. Efficiency of the Mexican hat WST at the URZ station was represented by small average retrieval of 2.76%, total and net improvement rates of 35.17% and 17.58% respectively. The small retrieval rate should be due the deep-borehole installation that filters the ambient noise and hence improves the quality of recordings. In spite of the reduced noise, path and site effects at the URZ station, the contribution of the Mexican hat WST to the quality enhancement of the

  6. Technical basis for environmental qualification of computer-based safety systems in nuclear power plants

    SciTech Connect

    Korsah, K.; Wood, R.T.; Tanaka, T.J.; Antonescu, C.E.

    1997-10-01

    This paper summarizes the results of research sponsored by the US Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. This research was conducted by the Oak Ridge National Laboratory (ORNL) and Sandia National Laboratories (SNL). ORNL investigated potential failure modes and vulnerabilities of microprocessor-based technologies to environmental stressors, including electromagnetic/radio-frequency interference, temperature, humidity, and smoke exposure. An experimental digital safety channel (EDSC) was constructed for the tests. SNL performed smoke exposure tests on digital components and circuit boards to determine failure mechanisms and the effect of different packaging techniques on smoke susceptibility. These studies are expected to provide recommendations for environmental qualification of digital safety systems by addressing the following: (1) adequacy of the present preferred test methods for qualification of digital I and C systems; (2) preferred standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging in qualification testing for equipment that is to be located in mild environments; and (5) determination of an appropriate approach to address smoke in a qualification program.

  7. Planting the seed: the 2009 Midwest Rural Agricultural Safety and Health Forum (MRASH).

    PubMed

    Donham, Kelley J

    2010-04-01

    The annual Midwest Rural Agricultural Safety and Health Forum (MRASH) is produced by the combined efforts and resources of Iowa's Center for Agricultural Safety and Health (I-CASH), the Great Plains Center for Agricultural Health, and The Heartland Center for Occupational Health. There is a regional focus for the conference on agricultural health issues for the 11 states of the upper Midwest, thus the new name for conference (MRASH). The purpose of this conference is to "plant the seeds" for stimulating and strengthening collaborative efforts among researchers, practitioner, agricultural producers, and medical professionals. This is accomplished by sharing cutting edge research, reviewing intervention theory and methodologies, reviewing activities of regional academic, public health, and nonprofit farm health and safety organization. The 2009 conference included plenary and topical breakout sessions. The plenary sessions included topics that have a relevance to the theory and practice of health interventions in populations. The breakout sessions were quite varied, with topics of community prevention programs (including Certified Safe Farm for large farms), AgrAbility programs, exposures from noise, pesticides, needle sticks, and all-terrain vehicle operation. The largest breakout session was on methicillin-resistant Staphylococcus aureus (MRSA). Should there be further questions of authors or the organizing committee, contact information is available at the following Web site address: http://www.public-health.uiowa.edu/ICASH/programs/MRASH/2009/index.htm. PMID:20407986

  8. Probabilistic Safety Assessment of External Flooding Protection for Nuclear Power Plants in Germany

    NASA Astrophysics Data System (ADS)

    Berg, Heinz Peter; Goertz, Rudolf; Froehmel, Thomas; Winter, Christian

    Methods to systematically analyse existing nuclear power plants (NPP) regarding the adequacy of their existing protection equipment against external hazards, e.g. flooding, can be of deterministic as well as probabilistic nature. In the past the adequacy of the protection measures has been assessed only on a deterministic basis. The German regulatory body has issued probabilistic safety assessment (PSA) guidelines, which had been elaborated for a comprehensive integrated safety review of all NPP in operation. Amongst others the guidelines imply, that probabilistic considerations regarding external flooding are required. This paper presents a newly developed graded approach for the probabilistic assessment of external flooding. Main aspects are explained such as the underlying probabilistic considerations and the mathematical procedures for the calculation of exceedance frequencies, which have recently been developed and issued as part of the German Nuclear Safety Standard. Exemplarily it has been investigated if extreme events such as tsunami waves could be a hazard for NPP at coastal sites in Germany. Here it could be shown that due to limited source mechanisms and the specific morphological conditions in the North Sea no dedicated measures for protection against tsunamis in the German Bight are necessary.

  9. Concentration of Actinides in Plant Mounds at Safety Test Nuclear Sites in Nevada

    SciTech Connect

    David S. Shafer; Jenna Gommes

    2008-09-15

    Plant mounds or blow-sand mounds are accumulations of soil particles and plant debris around large shrubs and are common features in deserts in the southwestern United States. Believed to be an important factor in their formation, the shrubs create surface roughness that causes wind-suspended particles to be deposited and resist further suspension. Shrub mounds occur in some plant communities on the Nevada Test Site, the Nevada Test and Training Range (NTTR), and Tonopah Test Range (TTR), including areas of surface soil contamination from past nuclear testing. In the 1970s as part of early studies to understand properties of actinides in the environment, the Nevada Applied Ecology Group (NAEG) examined the accumulation of isotopes of Pu, {sup 241}Am, and U in plant mounds at safety test sites. The NAEG studies found concentrations of these contaminants to be greater in shrub mounds than in the surrounding areas of desert pavement. For example, at Project 57 on the NTTR, it was estimated that 15 percent of the radionuclide inventory of the site was associated with shrub mounds, which accounted for 17 percent of the surface area of the site, a ratio of inventory to area of 0.85. At Clean Slate III at the TTR, 29 percent of the inventory was associated with approximately 32 percent of the site covered by shrub mounds, a ratio of 0.91. While the total inventory of radionuclides in intershrub areas was greater, the ratio of radionuclide inventory to area was 0.40 and 0.38, respectively, at the two sites. The comparison between the shrub mounds and adjacent desert pavement areas was made for only the top 5 cm since radionuclides at safety test sites are concentrated in the top 5 cm of intershrub areas. Not accounting for radionuclides associated with the shrub mounds would cause the inventory of contaminants and potential exposure to be underestimated. As part of its Environmental Restoration Soils Subproject, the U.S. Department of Energy (DOE), National Nuclear

  10. Safety and advantages of Bacillus thuringiensis-protected plants to control insect pests.

    PubMed

    Betz, F S; Hammond, B G; Fuchs, R L

    2000-10-01

    Plants modified to express insecticidal proteins from Bacillus thuringiensis (referred to as Bt-protected plants) provide a safe and highly effective method of insect control. Bt-protected corn, cotton, and potato were introduced into the United States in 1995/1996 and grown on a total of approximately 10 million acres in 1997, 20 million acres in 1998, and 29 million acres globally in 1999. The extremely rapid adoption of these Bt-protected crops demonstrates the outstanding grower satisfaction of the performance and value of these products. These crops provide highly effective control of major insect pests such as the European corn borer, southwestern corn borer, tobacco budworm, cotton bollworm, pink bollworm, and Colorado potato beetle and reduce reliance on conventional chemical pesticides. They have provided notably higher yields in cotton and corn. The estimated total net savings to the grower using Bt-protected cotton in the United States was approximately $92 million in 1998. Other benefits of these crops include reduced levels of the fungal toxin fumonisin in corn and the opportunity for supplemental pest control by beneficial insects due to the reduced use of broad-spectrum insecticides. Insect resistance management plans are being implemented to ensure the prolonged effectiveness of these products. Extensive testing of Bt-protected crops has been conducted which establishes the safety of these products to humans, animals, and the environment. Acute, subchronic, and chronic toxicology studies conducted over the past 40 years establish the safety of the microbial Bt products, including their expressed insecticidal (Cry) proteins, which are fully approved for marketing. Mammalian toxicology and digestive fate studies, which have been conducted with the proteins produced in the currently approved Bt-protected plant products, have confirmed that these Cry proteins are nontoxic to humans and pose no significant concern for allergenicity. Food and feed derived

  11. Continuous Improvement and the Safety Case for the Waste Isolation Pilot Plant Geologic Repository - 13467

    SciTech Connect

    Van Luik, Abraham; Patterson, Russell; Nelson, Roger; Leigh, Christi

    2013-07-01

    The Waste Isolation Pilot Plant (WIPP) is a geologic repository 2150 feet (650 m) below the surface of the Chihuahuan desert near Carlsbad, New Mexico. WIPP permanently disposes of transuranic waste from national defense programs. Every five years, the U.S. Department of Energy (DOE) submits an application to the U.S. Environmental Protection Agency (EPA) to request regulatory-compliance re-certification of the facility for another five years. Every ten years, DOE submits an application to the New Mexico Environment Department (NMED) for the renewal of its hazardous waste disposal permit. The content of the applications made by DOE to the EPA for re-certification, and to the NMED for permit-renewal, reflect any optimization changes made to the facility, with regulatory concurrence if warranted by the nature of the change. DOE points to such changes as evidence for its having taken seriously its 'continuous improvement' operations and management philosophy. Another opportunity for continuous improvement is to look at any delta that may exist between the re-certification and re-permitting cases for system safety and the consensus advice on the nature and content of a safety case as being developed and published by the Nuclear Energy Agency's Integration Group for the Safety Case (IGSC) expert group. DOE at WIPP, with the aid of its Science Advisor and teammate, Sandia National Laboratories, is in the process of discerning what can be done, in a reasonably paced and cost-conscious manner, to continually improve the case for repository safety that is being made to the two primary regulators on a recurring basis. This paper will discuss some aspects of that delta and potential paths forward to addressing them. (authors)

  12. Technology, Safety and Costs of Decommissioning a Reference Uranium Hexafluoride Conversion Plant

    SciTech Connect

    Elder, H. K.

    1981-10-01

    Safety and cost information is developed for the conceptual decommissioning of a commercial uranium hexafluoride conversion (UF{sub 6}) plant. Two basic decommissioning alternatives are studied to obtain comparisons between cost and safety impacts: DECON, and passive SAFSTOR. A third alternative, DECON of the plant and equipment with stabilization and long-term care of lagoon wastes. is also examined. DECON includes the immediate removal (following plant shutdown) of all radioactivity in excess of unrestricted release levels, with subsequent release of the site for public use. Passive SAFSTOR requires decontamination, preparation, maintenance, and surveillance for a period of time after shutdown, followed by deferred decontamination and unrestricted release. DECON with stabilization and long-term care of lagoon wastes (process wastes generated at the reference plant and stored onsite during plant operation} is also considered as a decommissioning method, although its acceptability has not yet been determined by the NRC. The decommissioning methods assumed for use in each decommissioning alternative are based on state-of-the-art technology. The elapsed time following plant shutdown required to perform the decommissioning work in each alternative is estimated to be: for DECON, 8 months; for passive SAFSTOR, 3 months to prepare the plant for safe storage and 8 months to accomplish deferred decontamination. Planning and preparation for decommissioning prior to plant shutdown is estimated to require about 6 months for either DECON or passive SAFSTOR. Planning and preparation prior to starting deferred decontamination is estimated to require an additional 6 months. OECON with lagoon waste stabilization is estimated to take 6 months for planning and about 8 months to perform the decommissioning work. Decommissioning cost, in 1981 dollars, is estimated to be $5.91 million for OECON. For passive SAFSTOR, preparing the facility for safe storage is estimated to cost $0

  13. Efficacy and safety of Stephania glabra: an alkaloid-rich traditional medicinal plant.

    PubMed

    Semwal, Deepak Kumar; Semwal, Ruchi Badoni

    2015-01-01

    Stephania glabra (Roxb.) Miers (Menispermaceae) has long been used for the treatment of asthma, tuberculosis, dysentery, hyperglycaemia, cancer, fever, intestinal complaints, sleep disturbances and inflammation in many Asian countries. It mainly contains alkaloids and, until now, over 30 alkaloids such as bisbenzylisoquinolines, hasubanalactams, berberines and aporphines have been isolated from its tuber. Most of its traditional medicinal activities are scientifically approved by various in vitro and in vivo studies. It shows remarkable anti-psychotic, anti-diabetic, antipyretic, analgesic, antimicrobial and anti-hypertensive activities. This work includes comprehensive information on the ethnobotany, chemistry and pharmacology of S. glabra. This review also focuses on the future perspectives with main emphasis on the establishment of therapeutic index and safety index of the plant. This review concludes that S. glabra has a great potential to treat various diseases, and could be used as a source for novel healthcare products in the near future, which needs further studies. PMID:25186139

  14. Efficacy and Safety of Medicinal Plants or Related Natural Products for Fibromyalgia: A Systematic Review

    PubMed Central

    de Souza Nascimento, Simone; DeSantana, Josimari Melo; Ribeiro, Êurica Adélia Nogueira; da Silva, Daniel Lira; Araújo-Júnior, João Xavier; da Silva Almeida, Jackson Roberto Guedes; Bonjardim, Leonardo Rigoldi; de Souza Araújo, Adriano Antunes; Quintans-Júnior, Lucindo José

    2013-01-01

    To assess the effects of medicinal plants (MPs) or related natural products (RNPs) on fibromyalgia (FM) patients, we evaluate the possible benefits and advantages of MP or RNP for the treatment of FM based on eight randomized placebo-controlled trials (RCTs) involving 475 patients. The methodological quality of all studies included was determined according to JADAD and “Risk of Bias” with the criteria in the Cochrane Handbook for Systematic Reviews of Interventions 5.1.0. Evidence suggests significant benefits of MP or RNP in sleep disruption, pain, depression, joint stiffness, anxiety, physical function, and quality of life. Our results demonstrated that MP or RNP had significant effects on improving the symptoms of FM compared to conventional drug or placebo; longer tests are required to determine the duration of the treatment and characterize the long-term safety of using MP, thus suggesting effective alternative therapies in the treatment of pain with minimized side effects. PMID:23861696

  15. Environmental Safety and Health Analytical Laboratory, Pantex Plant, Amarillo, Texas. Final Environmental Assessment

    SciTech Connect

    1995-06-01

    The US Department of Energy (DOE) has prepared an Environmental Assessment (EA) of the construction and operation of an Environmental Safety and Health (ES&H) Analytical Laboratory and subsequent demolition of the existing Analytical Chemistry Laboratory building at Pantex Plant near Amarillo, Texas. In accordance with the Council on Environmental Quality requirements contained in 40 CFR 1500--1508.9, the Environmental Assessment examined the environmental impacts of the Proposed Action and discussed potential alternatives. Based on the analysis of impacts in the EA, conducting the proposed action, construction of an analytical laboratory and demolition of the existing facility, would not significantly effect the quality of the human environment within the meaning of the National Environmental Policy Act of 1969 (NEPA) and the Council on Environmental Quality regulations in 40 CFR 1508.18 and 1508.27.

  16. Privatization of the gaseous diffusion plants and impacts on nuclear criticality safety administration

    SciTech Connect

    D`Aquila, D.M.; Holliday, R.T.; Dean, J.C.

    1996-12-31

    The Energy Policy Act of 1992 created the United States Enrichment Corporation (USEC) on July 1, 1993. The USEC is a government-owned business that leases those Gaseous Diffusion Plant (GDP) facilities at the Portsmouth, Ohio, and Paducah, Kentucky, sites from the U.S. Department of Energy (DOE) that are required for enriching uranium. Lockheed Martin Utility Services is the operating contractor for the USEC-leased facilities. The DOE has retained use of, and regulation over, some facilities and areas at the Portsmouth and Paducah sites for managing legacy wastes and environmental restoration activities. The USEC is regulated by the DOE, but is currently changing to regulation under the U.S. Nuclear Regulatory Commission (NRC). The USEC is also preparing for privatization of the uranium enrichment enterprise. These changes have significantly affected the nuclear criticality safety (NCS) programs at the sites.

  17. Pantex Plant final safety analysis report, Zone 4 magazines. Staging or interim storage for nuclear weapons and components: Issue D

    SciTech Connect

    Not Available

    1993-04-01

    This Safety Analysis Report (SAR) contains a detailed description and evaluation of the significant environmental, safety, and health (ES&H) issues associated with the operations of the Pantex Plant modified-Richmond and steel arch construction (SAC) magazines in Zone 4. It provides (1) an overall description of the magazines, the Pantex Plant, and its surroundings; (2) a systematic evaluations of the hazards that could occur as a result of the operations performed in these magazines; (3) descriptions and analyses of the adequacy of the measures taken to eliminate, control, or mitigate the identified hazards; and (4) analyses of potential accidents and their associated risks.

  18. Assessment of modular construction for safety-related structures at advanced nuclear power plants

    SciTech Connect

    Braverman, J.; Morante, R.; Hofmayer, C.

    1997-03-01

    Modular construction techniques have been successfully used in a number of industries, both domestically and internationally. Recently, the use of structural modules has been proposed for advanced nuclear power plants. The objective in utilizing modular construction is to reduce the construction schedule, reduce construction costs, and improve the quality of construction. This report documents the results of a program which evaluated the proposed use of modular construction for safety-related structures in advanced nuclear power plant designs. The program included review of current modular construction technology, development of licensing review criteria for modular construction, and initial validation of currently available analytical techniques applied to concrete-filled steel structural modules. The program was conducted in three phases. The objective of the first phase was to identify the technical issues and the need for further study in order to support NRC licensing review activities. The two key findings were the need for supplementary review criteria to augment the Standard Review Plan and the need for verified design/analysis methodology for unique types of modules, such as the concrete-filled steel module. In the second phase of this program, Modular Construction Review Criteria were developed to provide guidance for licensing reviews. In the third phase, an analysis effort was conducted to determine if currently available finite element analysis techniques can be used to predict the response of concrete-filled steel modules.

  19. PRB coal safety design considerations for new greenfield plants: an EPCC's perspective

    SciTech Connect

    Brown, J.H.

    2007-11-15

    The article reviews the design and safety aspects to consider in a new greenfield Powder River Basin (PRB) coal-fired power plant such as the 200 MW TS Power Plant (TSPP) in Nevada that Fluor is working on as an engineering, procurement and construction contractor (EPCC). PRB coals can become fragmented and form coal dust that is highly volatile and easily self-ignited. Coal handling systems incorporate features to minimise dust, such as totally enclosed chute works, 'spoon drops' to reduce impact turbulence, and overflow hoods. Conveyors have extended skirtboards and tight clearances between the wear plates and the belts. Storage piles are designed to have high compaction to deprive oxygen and dust suppression monitor hydrants to minimise dust and assist in compaction. The coal silo filling bay is designed to minimise dust once the coal is crushed, and attention is paid to cleaning and lighting. The silos are designed to ensure mass flow to the feeder and incorporate a carbon monoxide monitor and an F-500 fire suppressant. 3 photos.

  20. Regulatory analysis for the resolution of Generic Safety Issue 29: Bolting degradation or failure in nuclear power plants

    SciTech Connect

    Chang, T.Y.

    1991-09-01

    Generic Safety Issue (GSI)-29 deals with staff concerns about public risk due to degradation or failure of safety-related bolting in nuclear power plants. The issue was initiated in November 1982. Value-impact studies of a mandatory program on safety-related bolting for operating plants were inconclusive: therefore, additional regulatory requirements for operating plants could not be justified in accordance with provisions of 10 CFR 50.109. In addition, based on operating experience with bolting in both nuclear and conventional power plants, the actions already taken through bulletins, generic letters, and information notices, and the industry-proposed actions, the staff concluded that a sufficient technical basis exists for the resolution of GSI-29. The staff further concluded that leakage of bolted pressure joints is possible but catastrophic failure of a reactor coolant pressure boundary joint that will lead to significant accident sequences is highly unlikely. For future plants, it was concluded that a new Standard Review Plant section should be developed to codify existing bolting requirements and industry-developed initiatives. 9 refs., 1 tab.

  1. Hazardous organic compounds in biogas plant end products--soil burden and risk to food safety.

    PubMed

    Suominen, K; Verta, M; Marttinen, S

    2014-09-01

    The end products (digestate, solid fraction of the digestate, liquid fraction of the digestate) of ten biogas production lines in Finland were analyzed for ten hazardous organic compounds or compound groups: polychlorinated dibenzo-p-dioxins and furans (PCDD/Fs), polychlorinated biphenyls (PCB(7)), polyaromatic hydrocarbons (PAH(16)), bis-(2-ethylhexyl) phthalate (DEHP), perfluorinated alkyl compounds (PFCs), linear alkylbenzene sulfonates (LASs), nonylphenols and nonylphenol ethoxylates (NP+NPEOs), polybrominated diphenyl ethers (PBDEs), hexabromocyclododecane (HBCD) and tetrabromobisphenol A (TBBPA). Biogas plant feedstocks were divided into six groups: municipal sewage sludge, municipal biowaste, fat, food industry by-products, animal manure and others (consisting of milling by-products (husk) and raw former foodstuffs of animal origin from the retail trade). There was no clear connection between the origin of the feedstocks of a plant and the concentrations of hazardous organic compounds in the digestate. For PCDD/Fs and for DEHP, the median soil burden of the compound after a single addition of digestate was similar to the annual atmospheric deposition of the compound or compound group in Finland or other Nordic countries. For PFCs, the median soil burden was somewhat lower than the atmospheric deposition in Finland or Sweden. For NP+NPEOs, the soil burden was somewhat higher than the atmospheric deposition in Denmark. The median soil burden of PBDEs was 400 to 1000 times higher than the PBDE air deposition in Finland or in Sweden. With PBDEs, PFCs and HBCD, the impact of the use of end products should be a focus of further research. Highly persistent compounds, such as PBDE- and PFC-compounds may accumulate in agricultural soil after repeated use of organic fertilizers containing these compounds. For other compounds included in this study, agricultural use of biogas plant end products is unlikely to cause risk to food safety in Finland. PMID:24593894

  2. Safety assessment in plant layout design using indexing approach: implementing inherent safety perspective. Part 2-Domino Hazard Index and case study.

    PubMed

    Tugnoli, Alessandro; Khan, Faisal; Amyotte, Paul; Cozzani, Valerio

    2008-12-15

    The design of layout plans requires adequate assessment tools for the quantification of safety performance. The general focus of the present work is to introduce an inherent safety perspective at different points of the layout design process. In particular, index approaches for safety assessment and decision-making in the early stages of layout design are developed and discussed in this two-part contribution. Part 1 (accompanying paper) of the current work presents an integrated index approach for safety assessment of early plant layout. In the present paper (Part 2), an index for evaluation of the hazard related to the potential of domino effects is developed. The index considers the actual consequences of possible escalation scenarios and scores or ranks the subsequent accident propagation potential. The effects of inherent and passive protection measures are also assessed. The result is a rapid quantification of domino hazard potential that can provide substantial support for choices in the early stages of layout design. Additionally, a case study concerning selection among various layout options is presented and analyzed. The case study demonstrates the use and applicability of the indices developed in both parts of the current work and highlights the value of introducing inherent safety features early in layout design. PMID:18406517

  3. Implementation of Recommendations from the One System Comparative Evaluation of the Hanford Tank Farms and Waste Treatment Plant Safety Bases

    SciTech Connect

    Garrett, Richard L.; Niemi, Belinda J.; Paik, Ingle K.; Buczek, Jeffrey A.; Lietzow, J.; McCoy, F.; Beranek, F.; Gupta, M.

    2013-11-07

    A Comparative Evaluation was conducted for One System Integrated Project Team to compare the safety bases for the Hanford Waste Treatment and Immobilization Plant Project (WTP) and Tank Operations Contract (TOC) (i.e., Tank Farms) by an Expert Review Team. The evaluation had an overarching purpose to facilitate effective integration between WTP and TOC safety bases. It was to provide One System management with an objective evaluation of identified differences in safety basis process requirements, guidance, direction, procedures, and products (including safety controls, key safety basis inputs and assumptions, and consequence calculation methodologies) between WTP and TOC. The evaluation identified 25 recommendations (Opportunities for Integration). The resolution of these recommendations resulted in 16 implementation plans. The completion of these implementation plans will help ensure consistent safety bases for WTP and TOC along with consistent safety basis processes. procedures, and analyses. and should increase the likelihood of a successful startup of the WTP. This early integration will result in long-term cost savings and significant operational improvements. In addition, the implementation plans lead to the development of eight new safety analysis methodologies that can be used at other U.S. Department of Energy (US DOE) complex sites where URS Corporation is involved.

  4. Documentation of Hanford Site independent review of the Hanford Waste Vitrification Plant Preliminary Safety Analysis Report. Revision 3

    SciTech Connect

    Herborn, D.I.

    1993-11-01

    Westinghouse Hanford Company (WHC) is the Integrating Contractor for the Hanford Waste Vitrification Plant (HWVP) Project, and as such is responsible for preparation of the HWVP Preliminary Safety Analysis Report (PSAR). The HWVP PSAR was prepared pursuant to the requirements for safety analyses contained in US Department of Energy (DOE) Orders 4700.1, Project Management System (DOE 1987); 5480.5, Safety of Nuclear Facilities (DOE 1986a); 5481.lB, Safety Analysis and Review System (DOE 1986b) which was superseded by DOE order 5480-23, Nuclear Safety Analysis Reports, for nuclear facilities effective April 30, 1992 (DOE 1992); and 6430.lA, General Design Criteria (DOE 1989). The WHC procedures that, in large part, implement these DOE requirements are contained in WHC-CM-4-46, Nonreactor Facility Safety Analysis Manual. This manual describes the overall WHC safety analysis process in terms of requirements for safety analyses, responsibilities of the various contributing organizations, and required reviews and approvals.

  5. 10 CFR 50.49 - Environmental qualification of electric equipment important to safety for nuclear power plants.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 1 2014-01-01 2014-01-01 false Environmental qualification of electric equipment important to safety for nuclear power plants. 50.49 Section 50.49 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Standards for Licenses, Certifications, and Regulatory Approvals § 50.49...

  6. 77 FR 50722 - Software Unit Testing for Digital Computer Software Used in Safety Systems of Nuclear Power Plants

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-08-22

    ...The U.S. Nuclear Regulatory Commission (NRC or the Commission) is issuing for public comment draft regulatory guide (DG), DG-1208, ``Software Unit Testing for Digital Computer Software used in Safety Systems of Nuclear Power Plants.'' The DG-1208 is proposed Revision 1 of RG 1.171, dated September 1997. This revision endorses, with clarifications, the enhanced consensus practices for testing......

  7. 10 CFR 50.49 - Environmental qualification of electric equipment important to safety for nuclear power plants.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Environmental qualification of electric equipment important to safety for nuclear power plants. 50.49 Section 50.49 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Standards for Licenses, Certifications, and Regulatory Approvals § 50.49...

  8. 77 FR 50720 - Test Documentation for Digital Computer Software Used in Safety Systems of Nuclear Power Plants

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-08-22

    ...The U.S. Nuclear Regulatory Commission (NRC or the Commission) is issuing for public comment draft regulatory guide (DG), DG-1207, ``Test Documentation for Digital Computer Software used in Safety Systems of Nuclear Power Plants.'' The DG-1207 is proposed Revision 1 of RG 1.170, dated September 1997. This revision endorses, with clarifications, the enhanced consensus practices for test......

  9. 10 CFR 50.49 - Environmental qualification of electric equipment important to safety for nuclear power plants.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 1 2012-01-01 2012-01-01 false Environmental qualification of electric equipment important to safety for nuclear power plants. 50.49 Section 50.49 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Standards for Licenses, Certifications, and Regulatory Approvals § 50.49...

  10. 10 CFR 50.49 - Environmental qualification of electric equipment important to safety for nuclear power plants.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 1 2011-01-01 2011-01-01 false Environmental qualification of electric equipment important to safety for nuclear power plants. 50.49 Section 50.49 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Standards for Licenses, Certifications, and Regulatory Approvals § 50.49...

  11. 10 CFR 50.49 - Environmental qualification of electric equipment important to safety for nuclear power plants.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 1 2013-01-01 2013-01-01 false Environmental qualification of electric equipment important to safety for nuclear power plants. 50.49 Section 50.49 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Standards for Licenses, Certifications, and Regulatory Approvals § 50.49...

  12. Progress in Understanding Autism: 2007-2010

    ERIC Educational Resources Information Center

    Rutter, Michael L.

    2011-01-01

    Scientific progress is discussed in relation to clinical issues; genetic issues; environmental issues; and the state of play on psychological treatments. It is concluded that substantial gains in knowledge have been achieved during the last 3 years, and there have been some unexpected findings, but major puzzles remain. We should be hopeful of…

  13. Plutonium Finishing Plant (PFP) Final Safety Analysis Report (FSAR) [SEC 1 THRU 11

    SciTech Connect

    ULLAH, M K

    2001-02-26

    The Plutonium Finishing Plant (PFP) is located on the US Department of Energy (DOE) Hanford Site in south central Washington State. The DOE Richland Operations (DOE-RL) Project Hanford Management Contract (PHMC) is with Fluor Hanford Inc. (FH). Westinghouse Safety Management Systems (WSMS) provides management support to the PFP facility. Since 1991, the mission of the PFP has changed from plutonium material processing to preparation for decontamination and decommissioning (D and D). The PFP is in transition between its previous mission and the proposed D and D mission. The objective of the transition is to place the facility into a stable state for long-term storage of plutonium materials before final disposition of the facility. Accordingly, this update of the Final Safety Analysis Report (FSAR) reflects the current status of the buildings, equipment, and operations during this transition. The primary product of the PFP was plutonium metal in the form of 2.2-kg, cylindrical ingots called buttoms. Plutonium nitrate was one of several chemical compounds containing plutonium that were produced as an intermediate processing product. Plutonium recovery was performed at the Plutonium Reclamation Facility (PRF) and plutonium conversion (from a nitrate form to a metal form) was performed at the Remote Mechanical C (RMC) Line as the primary processes. Plutonium oxide was also produced at the Remote Mechanical A (RMA) Line. Plutonium processed at the PFP contained both weapons-grade and fuels-grade plutonium materials. The capability existed to process both weapons-grade and fuels-grade material through the PRF and only weapons-grade material through the RMC Line although fuels-grade material was processed through the line before 1984. Amounts of these materials exist in storage throughout the facility in various residual forms left from previous years of operations.

  14. Conceptual Software Reliability Prediction Models for Nuclear Power Plant Safety Systems

    SciTech Connect

    Johnson, G.; Lawrence, D.; Yu, H.

    2000-04-03

    The objective of this project is to develop a method to predict the potential reliability of software to be used in a digital system instrumentation and control system. The reliability prediction is to make use of existing measures of software reliability such as those described in IEEE Std 982 and 982.2. This prediction must be of sufficient accuracy to provide a value for uncertainty that could be used in a nuclear power plant probabilistic risk assessment (PRA). For the purposes of the project, reliability was defined to be the probability that the digital system will successfully perform its intended safety function (for the distribution of conditions under which it is expected to respond) upon demand with no unintended functions that might affect system safety. The ultimate objective is to use the identified measures to develop a method for predicting the potential quantitative reliability of a digital system. The reliability prediction models proposed in this report are conceptual in nature. That is, possible prediction techniques are proposed and trial models are built, but in order to become a useful tool for predicting reliability, the models must be tested, modified according to the results, and validated. Using methods outlined by this project, models could be constructed to develop reliability estimates for elements of software systems. This would require careful review and refinement of the models, development of model parameters from actual experience data or expert elicitation, and careful validation. By combining these reliability estimates (generated from the validated models for the constituent parts) in structural software models, the reliability of the software system could then be predicted. Modeling digital system reliability will also require that methods be developed for combining reliability estimates for hardware and software. System structural models must also be developed in order to predict system reliability based upon the reliability

  15. PROBABILISTIC SAFETY ASSESSMENT OF OPERATIONAL ACCIDENTS AT THE WASTE ISOLATION PILOT PLANT

    SciTech Connect

    Rucker, D.F.

    2000-09-01

    This report presents a probabilistic safety assessment of radioactive doses as consequences from accident scenarios to complement the deterministic assessment presented in the Waste Isolation Pilot Plant (WIPP) Safety Analysis Report (SAR). The International Council of Radiation Protection (ICRP) recommends both assessments be conducted to ensure that ''an adequate level of safety has been achieved and that no major contributors to risk are overlooked'' (ICRP 1993). To that end, the probabilistic assessment for the WIPP accident scenarios addresses the wide range of assumptions, e.g. the range of values representing the radioactive source of an accident, that could possibly have been overlooked by the SAR. Routine releases of radionuclides from the WIPP repository to the environment during the waste emplacement operations are expected to be essentially zero. In contrast, potential accidental releases from postulated accident scenarios during waste handling and emplacement could be substantial, which necessitates the need for radiological air monitoring and confinement barriers (DOE 1999). The WIPP Safety Analysis Report (SAR) calculated doses from accidental releases to the on-site (at 100 m from the source) and off-site (at the Exclusive Use Boundary and Site Boundary) public by a deterministic approach. This approach, as demonstrated in the SAR, uses single-point values of key parameters to assess the 50-year, whole-body committed effective dose equivalent (CEDE). The basic assumptions used in the SAR to formulate the CEDE are retained for this report's probabilistic assessment. However, for the probabilistic assessment, single-point parameter values were replaced with probability density functions (PDF) and were sampled over an expected range. Monte Carlo simulations were run, in which 10,000 iterations were performed by randomly selecting one value for each parameter and calculating the dose. Statistical information was then derived from the 10,000 iteration

  16. Chemical and Plant-Based Insect Repellents: Efficacy, Safety, and Toxicity.

    PubMed

    Diaz, James H

    2016-03-01

    Most emerging infectious diseases today are arthropod-borne and cannot be prevented by vaccinations. Because insect repellents offer important topical barriers of personal protection from arthropod-borne infectious diseases, the main objectives of this article were to describe the growing threats to public health from emerging arthropod-borne infectious diseases, to define the differences between insect repellents and insecticides, and to compare the efficacies and toxicities of chemical and plant-derived insect repellents. Internet search engines were queried with key words to identify scientific articles on the efficacy, safety, and toxicity of chemical and plant-derived topical insect repellants and insecticides to meet these objectives. Data sources reviewed included case reports; case series; observational, longitudinal, and surveillance studies; and entomological and toxicological studies. Descriptive analysis of the data sources identified the most effective application of insect repellents as a combination of topical chemical repellents, either N-diethyl-3-methylbenzamide (formerly N, N-diethyl-m-toluamide, or DEET) or picaridin, and permethrin-impregnated or other pyrethroid-impregnated clothing over topically treated skin. The insecticide-treated clothing would provide contact-level insecticidal effects and provide better, longer lasting protection against malaria-transmitting mosquitoes and ticks than topical DEET or picaridin alone. In special cases, where environmental exposures to disease-transmitting ticks, biting midges, sandflies, or blackflies are anticipated, topical insect repellents containing IR3535, picaridin, or oil of lemon eucalyptus (p-menthane-3, 8-diol or PMD) would offer better topical protection than topical DEET alone. PMID:26827259

  17. Mathematical aspects of assessing extreme events for the safety of nuclear plants

    NASA Astrophysics Data System (ADS)

    Potempski, Slawomir; Borysiewicz, Mieczyslaw

    2015-04-01

    In the paper the review of mathematical methodologies applied for assessing low frequencies of rare natural events like earthquakes, tsunamis, hurricanes or tornadoes, floods (in particular flash floods and surge storms), lightning, solar flares, etc., will be given in the perspective of the safety assessment of nuclear plants. The statistical methods are usually based on the extreme value theory, which deals with the analysis of extreme deviation from the median (or the mean). In this respect application of various mathematical tools can be useful, like: the extreme value theorem of Fisher-Tippett-Gnedenko leading to possible choices of general extreme value distributions, or the Pickands-Balkema-de Haan theorem for tail fitting, or the methods related to large deviation theory. In the paper the most important stochastic distributions relevant for performing rare events statistical analysis will be presented. This concerns, for example, the analysis of the data with the annual extreme values (maxima - "Annual Maxima Series" or minima), or the peak values, exceeding given thresholds at some periods of interest ("Peak Over Threshold"), or the estimation of the size of exceedance. Despite of the fact that there is a lack of sufficient statistical data directly containing rare events, in some cases it is still possible to extract useful information from existing larger data sets. As an example one can consider some data sets available from the web sites for floods, earthquakes or generally natural hazards. Some aspects of such data sets will be also presented taking into account their usefulness for the practical assessment of risk for nuclear power plants coming from extreme weather conditions.

  18. Hydraulic limits on maximum plant transpiration and the emergence of the safety-efficiency trade-off.

    PubMed

    Manzoni, Stefano; Vico, Giulia; Katul, Gabriel; Palmroth, Sari; Jackson, Robert B; Porporato, Amilcare

    2013-04-01

    Soil and plant hydraulics constrain ecosystem productivity by setting physical limits to water transport and hence carbon uptake by leaves. While more negative xylem water potentials provide a larger driving force for water transport, they also cause cavitation that limits hydraulic conductivity. An optimum balance between driving force and cavitation occurs at intermediate water potentials, thus defining the maximum transpiration rate the xylem can sustain (denoted as E(max)). The presence of this maximum raises the question as to whether plants regulate transpiration through stomata to function near E(max). To address this question, we calculated E(max) across plant functional types and climates using a hydraulic model and a global database of plant hydraulic traits. The predicted E(max) compared well with measured peak transpiration across plant sizes and growth conditions (R = 0.86, P < 0.001) and was relatively conserved among plant types (for a given plant size), while increasing across climates following the atmospheric evaporative demand. The fact that E(max) was roughly conserved across plant types and scales with the product of xylem saturated conductivity and water potential at 50% cavitation was used here to explain the safety-efficiency trade-off in plant xylem. Stomatal conductance allows maximum transpiration rates despite partial cavitation in the xylem thereby suggesting coordination between stomatal regulation and xylem hydraulic characteristics. PMID:23356378

  19. Environment, safety and Health Progress Assessment of the Rocky Flats Plant

    SciTech Connect

    Not Available

    1993-05-01

    This report documents the result of the US Department of Energy`s (DOE) Environment, Safety and Health (ES&H) Progress Assessment of the DOE Rocky Flats Plant (RFP) in Golden, Colorado. The assessment, which was conducted during the period of May 17 through May 28, 1993, included a selective review of the ES&H management systems and programs of the responsible DOE Headquarters Program Offices (Defense Programs (DP) and Environmental Restoration and Waste Management (EM)), the DOE Rocky Flats Office (RFO), and the site contractor, EG&G Rocky Flats, Inc. (EG&G). Despite the near constant state of flux under which RFP has been required to operate, the Progress Assessment Team has concluded that significant progress has been made in correcting the deficiencies identified in the 1989 Assessment and in responding responsibly to regulations, and DOE directives and guidance that have been issued since that time. The Team concluded that the improvements have been concentrated in the activities associated with plutonium facilities and in regulatory driven programs. Much remains to be done with respect to implementing on a sitewide basis those management systems that anchor an organization`s pursuit of continuous ES&H improvement. Furthermore the Team concluded that the pace of improvement has been constrained by a combination of factors that have limited the site`s ability to manage change in the pursuit of sitewide ES&H excellence.

  20. Structural Safety Analysis Based on Seismic Service Conditions for Butterfly Valves in a Nuclear Power Plant

    PubMed Central

    Han, Sang-Uk; Ahn, Dae-Gyun; Lee, Myeong-Gon

    2014-01-01

    The structural integrity of valves that are used to control cooling waters in the primary coolant loop that prevents boiling within the reactor in a nuclear power plant must be capable of withstanding earthquakes or other dangerous situations. In this study, numerical analyses using a finite element method, that is, static and dynamic analyses according to the rigid or flexible characteristics of the dynamic properties of a 200A butterfly valve, were performed according to the KEPIC MFA. An experimental vibration test was also carried out in order to verify the results from the modal analysis, in which a validated finite element model was obtained via a model-updating method that considers changes in the in situ experimental data. By using a validated finite element model, the equivalent static load under SSE conditions stipulated by the KEPIC MFA gave a stress of 135 MPa that occurred at the connections of the stem and body. A larger stress of 183 MPa was induced when we used a CQC method with a design response spectrum that uses 2% damping ratio. These values were lower than the allowable strength of the materials used for manufacturing the butterfly valve, and, therefore, its structural safety met the KEPIC MFA requirements. PMID:24955416

  1. Structural safety analysis based on seismic service conditions for butterfly valves in a nuclear power plant.

    PubMed

    Han, Sang-Uk; Ahn, Dae-Gyun; Lee, Myeong-Gon; Lee, Kwon-Hee; Han, Seung-Ho

    2014-01-01

    The structural integrity of valves that are used to control cooling waters in the primary coolant loop that prevents boiling within the reactor in a nuclear power plant must be capable of withstanding earthquakes or other dangerous situations. In this study, numerical analyses using a finite element method, that is, static and dynamic analyses according to the rigid or flexible characteristics of the dynamic properties of a 200A butterfly valve, were performed according to the KEPIC MFA. An experimental vibration test was also carried out in order to verify the results from the modal analysis, in which a validated finite element model was obtained via a model-updating method that considers changes in the in situ experimental data. By using a validated finite element model, the equivalent static load under SSE conditions stipulated by the KEPIC MFA gave a stress of 135 MPa that occurred at the connections of the stem and body. A larger stress of 183 MPa was induced when we used a CQC method with a design response spectrum that uses 2% damping ratio. These values were lower than the allowable strength of the materials used for manufacturing the butterfly valve, and, therefore, its structural safety met the KEPIC MFA requirements. PMID:24955416

  2. Enhanced-safety underground nuclear power plants based on the use of proven ship-building equipment and technology

    SciTech Connect

    Pashin, V.M.; Petrov, E.L.; Khazov, B.S.

    1995-10-01

    Investigations performed in the last few years by the State Science Center of the Russian Federation - Academician A. N. Krylov Central Scientific-Research Institute, together with specialized enterprises of the Ministry of Atomic Energy of the Russian Federation, Sudprom, and other agencies of Russia, have shown the promise of marine nuclear power plants for producing underground nuclear power plants with a higher degree of protection from external and internal actions of different intensity. The concept was developed on the basis of an analysis of the energy supply in different regions of Russia and the near-abroad using fossil fuels (lignite, oil, natural gas). The change in the international environment, which makes it possible to convert the military technology, frees the industrial potential and skilled workers in Russia for development of products for the national economy. Stricter international standards and rules for increased safety and protection of nuclear power plants made it necessary to develop a new generation of reactors for ground-based power plants, which under the modern economic conditions cannot be implemented within the time periods acceptable for economics for most of the countries surrounding Russia. In the development of a new generation of ground-based nuclear power plants, the intense improvement of the aviation and space technology must be taken into account. This is connected with the increase in the catastrophes and the threat they present to the safety of unprotected power plants. This article is an abstract of the entire report.

  3. Plant Operations. OSHA on Campus: Campus Safety Officers Discuss Problems and Potentials

    ERIC Educational Resources Information Center

    Kuchta, Joseph F.; And Others

    1973-01-01

    The Occupation Safety and Health Act (OSHA) has presented campus safety officers with new problems, but it is also offering them new potentials, which were explored at the recent national conference on Campus Security. (Editor)

  4. Integrated Safety Management System Phase I Verification for the Plutonium Finishing Plant (PFP) [VOL 1 & 2

    SciTech Connect

    SETH, S.S.

    2000-01-10

    U.S. Department of Energy (DOE) Policy 450.4, Safety Management System Policy commits to institutionalizing an Integrated Safety Management System (ISMS) throughout the DOE complex as a means of accomplishing its missions safely. DOE Acquisition Regulation 970.5204-2 requires that contractors manage and perform work in accordance with a documented safety management system.

  5. Safety provisions for UF{sub 6} handling in the design of a new UF{sub 6} conversion plant

    SciTech Connect

    Bannister, S.P.

    1991-12-31

    British Nuclear Fuels plc (BNFL) Fuel Division is currently undertaking the final design and construction of a new UF{sub 6} conversion plant at its production site at Springfields near Preston in the north of England. The Company has gained much experience in the handling of UF{sub 6} during operation of plants on site since 1961. The major hazard occurs during the liquefication cycle and the basis of the maximum credible incident scenario adopted for safety assessment and design purposes is discussed. This paper considers the design features which have been incorporated in the new plant to counter the hazards presented by the presence of UF{sub 6} in gaseous and liquid form and explains current thinking on operational procedures in areas of potential risk such as cylinder filling. The plant emergency response philosophy and systems are described and specific design provisions which have been included to satisfy the UK regulatory bodies are outlined in some detail.

  6. Seismic safety margins research program. Phase I. Final report: plant/site selection and data collection (Project I)

    SciTech Connect

    Chuang, T. Y.

    1981-05-01

    Project I of Phase I of the Seismic Safety Margins Research Program (SSMRP) comprised two parts: the selection of a representative nuclear power plant/site for study in Phase I and the collection of data needed by the other SSMRP projects. Unit 1 of the Zion Nuclear Power Plant in Zion, Illinois, was selected for the SSMRP Phase I studies. The Zion plant and its site were found to be reasonably representative of operating and future plants with regard to its nuclear steam supply system; the type of containment structure (prestressed concrete); its electrical capacity (1100 MWe); its location (the Midwest); the peak seismic accelaration used for design (0.17g); and the properties of the underlying soil (the low-strain shear-wave velocity is 1650 ft/s in a 50- to 100-ft-thick layer of soil overlying sedimentary bedrock).

  7. Technical basis for environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

    SciTech Connect

    Korsah, K.; Wood, R.T.; Hassan, M.; Tanaka, T.J.

    1998-01-01

    This document presents the results of studies sponsored by the Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. The studies were conducted by Oak Ridge National Laboratory (ORNL), Sandia National Laboratories (SNL), and Brookhaven National Laboratory (BNL). The studies address the following: (1) adequacy of the present test methods for qualification of digital I and C systems; (2) preferred (i.e., Regulatory Guide-endorsed) standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging for equipment to be located in a benign environment; and (5) determination of an appropriate approach for addressing the impact of smoke in digital equipment qualification programs. Significant findings from the studies form the technical basis for a recommended approach to the environmental qualification of microprocessor-based safety-related equipment in nuclear power plants.

  8. [Safety systems in nuclear power plants with pressurized water reactors and demonstration of their function in technical scale experiments. II].

    PubMed

    Hennies, H H

    1987-11-01

    Analyses and experiments carried out during the last decade on the sequence and consequences of accidents in German pressurized water reactors have shown that the functioning capability of the safety systems is guaranteed for the case of the MCA, the maximum credible accident. For the case of core meltdown, simulation experiments have also made it evident that the consequences remain largely restricted to the plant proper. PMID:3431585

  9. Generic Safety Issue (GSI) 171 -- Engineered Safety Feature (ESF) failure from a loop subsequent to LOCA: Assessment of plant vulnerability and CDF contributions

    SciTech Connect

    Martinez-Guridi, G.; Samanta, P.; Chu, L.; Yang, J.

    1998-03-01

    Generic Safety Issue 171 (GSI-171), Engineered Safety Feature (ESF) from a Loss Of Offsite Power (LOOP) subsequent to a Loss Of Coolant Accident (LOCA), deals with an accident sequence in which a LOCA is followed by a LOOP. This issue was later broadened to include a LOOP followed by a LOCA. Plants are designed to handle a simultaneous LOCA and LOOP. In this paper, the authors address the unique issues that are involved i LOCA with delayed LOOP (LOCA/LOOP) and LOOP with delayed LOCA (LOOP/LOCA) accident sequences. LOCA/LOOP accidents are analyzed further by developing event-tree/fault-tree models to quantify their contributions to core-damage frequency (CDF) in a pressurized water reactor and a boiling water reactor (PWR and a BWR). Engineering evaluation and judgments are used during quantification to estimate the unique conditions that arise in a LOCA/LOOP accident. The results show that the CDF contribution of such an accident can be a dominant contributor to plant risk, although BWRs are less vulnerable than PWRs.

  10. The ecosystem of the Mid-Atlantic Ridge at the sub-polar front and Charlie-Gibbs Fracture Zone; ECO-MAR project strategy and description of the sampling programme 2007-2010

    NASA Astrophysics Data System (ADS)

    Priede, Imants G.; Billett, David S. M.; Brierley, Andrew S.; Hoelzel, A. Rus; Inall, Mark; Miller, Peter I.; Cousins, Nicola J.; Shields, Mark A.; Fujii, Toyonobu

    2013-12-01

    The ECOMAR project investigated photosynthetically-supported life on the North Mid-Atlantic Ridge (MAR) between the Azores and Iceland focussing on the Charlie-Gibbs Fracture Zone area in the vicinity of the sub-polar front where the North Atlantic Current crosses the MAR. Repeat visits were made to four stations at 2500 m depth on the flanks of the MAR in the years 2007-2010; a pair of northern stations at 54°N in cold water north of the sub-polar front and southern stations at 49°N in warmer water influenced by eddies from the North Atlantic Current. At each station an instrumented mooring was deployed with current meters and sediment traps (100 and 1000 m above the sea floor) to sample downward flux of particulate matter. The patterns of water flow, fronts, primary production and export flux in the region were studied by a combination of remote sensing and in situ measurements. Sonar, tow nets and profilers sampled pelagic fauna over the MAR. Swath bathymetry surveys across the ridge revealed sediment-covered flat terraces parallel to the axis of the MAR with intervening steep rocky slopes. Otter trawls, megacores, baited traps and a suite of tools carried by the R.O.V. Isis including push cores, grabs and a suction device collected benthic fauna. Video and photo surveys were also conducted using the SHRIMP towed vehicle and the R.O.V. Isis. Additional surveying and sampling by landers and R.O.V. focussed on the summit of a seamount (48°44‧N, 28°10‧W) on the western crest of the MAR between the two southern stations.

  11. Respiratory symptoms and pulmonary function tests in security and safety products plant workers

    PubMed Central

    Balbay, Ege Gulec; Toru, Umran; Arbak, Peri; Balbay, Oner; Suner, Kezban Ozmen; Annakkaya, Ali Nihat

    2014-01-01

    Objective: Lock and key factory workers are under the risk of metal pneumoconiosis and occupational asthma. In this cross-sectional study, it’s aimed to evaluate the relationship between metal dust exposure and respiratory symptoms, pulmonary function tests of workers in different section of lock and key factory. Methods: 54 male workers (mean age, 32.8 ± 5.4) in a security and safety products plant were evaluated for respiratory symptoms, pulmonary function tests and smoking habits. Results have been interpreted by comparison of the painting (28/54) and grinding group workers (26/54). Results: There was no significant difference between painting (32.1 ± 4.8) and grinding (33.6 ± 6.1) groups regarding mean age (P > 0.05). Smokers were in significantly higher in grinding group (18/26). Cough and sputum were reported 14.3% (4/28) in painting and 3.8% (1/26) in grinding workers (P > 0.05). Chest tightness was seen in 7.1% and 7.7% of painting and grinding workers, respectively (P > 0.05). But no chest tightness was reported in both groups when they were away work. Breathlessness was seen in 10.7% and 7.7% of painting and grinding workers, respectively (P > 0.05). Breathlessness was similar in both groups (7.1% vs. 3.8%) when they were away work. When comparing painting and grinding workers respiratory functions no significant difference observed. Chest radiography in painting and grinding workers showed hyperlucency (3.6% vs.11.4%), respectively. Conclusion: Painting groups in lock and key factory workers had more but statistically insignificantrespiratory complaints. Interestingly, chest tightness was only observed when both groups were at work. It was thought that ventilation and using personal protective equipment in factory could provide significant benefits. PMID:25126195

  12. Safety analysis -- 200 Area Savannah River Plant, F-Canyon Operations. Supplement 4

    SciTech Connect

    Beary, M.M.; Collier, C.D.; Fairobent, L.A.; Graham, R.F.; Mason, C.L.; McDuffee, W.T.; Owen, T.L.; Walker, D.H.

    1986-02-01

    The F-Canyon facility is located in the 200 Separations Area and uses the Purex process to recover plutonium from reactor-irradiated uranium. The irradiated uranium is normally in the form of solid or hollow cylinders called slugs. These slugs are encased in aluminum cladding and are sent to the F-Canyon from the Savannah River Plant (SRP) reactor areas or from the Receiving Basin for Offsite Fuels (RBOF). This Safety Analysis Report (SAR) documents an analysis of the F-Canyon operations and is an update to a section of a previous SAR. The previous SAR documented an analysis of the entire 200 Separations Area operations. This SAR documents an analysis of the F-Canyon and is one of a series of documents for the Separations Area as specified in the Savannah River Implementation Plans. A substantial amount of the information supporting the conclusions of this SAR is found in the Systems Analysis. Some F-Canyon equipment has been updated during the time between the Systems Analysis and this SAR and a complete description of this equipment is included in this report. The primary purpose of the analysis was to demonstrate that the F-Canyon can be operated without undue risk to onsite or offsite populations and to the environment. In this report, risk is defined as the expected frequency of an accident, multiplied by the resulting radiological consequence in person-rem. The units of risk for radiological dose are person-rem/year. Maximum individual exposure values have also been calculated and reported.

  13. Documentation of Hanford Site independent review of the Hanford Waste Vitrification Plant Preliminary Safety Analysis Report

    SciTech Connect

    Herborn, D.I.

    1991-10-01

    The requirements for Westinghouse Hanford independent review of the Preliminary Safety Analysis Report (PSAR) are contained in Section 1.0, Subsection 4.3 of WCH-CM-4-46. Specifically, this manual requires the following: (1) Formal functional reviews of the HWVP PSAR by the future operating organization (HWVP Operations), and the independent review organizations (HWVP and Environmental Safety Assurance, Environmental Assurance, and Quality Assurance); and (2) Review and approval of the HWVP PSAR by the Tank Waste Disposal (TWD) Subcouncil of the Safety and Environmental Advisory Council (SEAC), which provides independent advice to the Westinghouse Hanford President and executives on matters of safety and environmental protection. 7 refs.

  14. Recommended electromagnetic operating envelopes for safety-related I and C systems in nuclear power plants: Draft report for comment

    SciTech Connect

    Ewing, P.D.; Wood, R.T.

    1997-12-01

    This document presents recommendations for electromagnetic operating envelopes to augment test criteria and test methods addressing electromagnetic interference (EMI), radio-frequency interference (RFI), and power surges that are applicable to safety-related instrumentation and control (I and C) systems in nuclear power plants. The Oak Ridge National Laboratory (ORNL) was engaged by the US Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research to assist in developing the technical basis for regulatory guidance on EMI/RFI immunity and power surge withstand capability (SWC). Previous research has provided recommendations on electromagnetic compatibility (EMC) design and installation practices, endorsement of EMI/RFI immunity and SWC test criteria and test methods, and determination of ambient electromagnetic conditions at nuclear power plants. The present research involves development of recommended electromagnetic envelopes that are applicable to nuclear power plant locations where safety-related I and C systems either are or may be installed. These recommended envelopes establish both emissions criteria and the levels of radiated and conducted interference that I and C systems should be able to withstand without upset or malfunction. The EMI/RFI operating envelopes are derived from conditions in comparable military environments and are confirmed by comparison with the nuclear power plant electromagnetic environment based on measured plant emissions profiles. Detailed information on specific power surge conditions in nuclear power plants is not available, so industrial guidance on representative surge characteristics for susceptibility testing is adopted. An engineering assessment of the power surge environment in nuclear power plants leads to the recommendation of operating envelopes based on location categories and exposure levels defined in IEEE Std C62.41-1991, IEEE Recommended Practice on Surge Voltages in Low-Voltage AC Power Circuits.

  15. Contribution to the safety assessment of instrumentation and control software for nuclear power plants: Application to SPIN N4

    SciTech Connect

    Soubies, B.; Henry, J.Y.; Le Meur, M.

    1995-04-01

    1300 MWe pressurised water reactors (PWRs), like the 1400 MWe reactors, operate with microprocessor-based safety systems. This is particularly the case for the Digital Integrated Protection System (SPIN), which trips the reactor in an emergency and sets in action the safeguard functions. The softwares used in these systems must therefore be highly dependable in the execution of their functions. In the case of SPIN, three players are working at different levels to achieve this goal: the protection system manufacturer, Merlin Gerin; the designer of the nuclear steam supply system, Framatome; the operator of the nuclear power plants, Electricite de France (EDF), which is also responsible for the safety of its installations. Regulatory licenses are issued by the French safety authority, the Nuclear Installations Safety Directorate (French abbreviation DSIN), subsequent to a successful examination of the technical provisions adopted by the operator. This examination is carried out by the IPSN and the standing group on nuclear reactors. This communication sets out: the methods used by the manufacturer to develop SPIN software for the 1400 MWe PWRs (N4 series); the approach adopted by the IPSN to evaluate the safety software of the protection system for the N4 series of reactors.

  16. Review of nuclear power plant safety cable aging studies with recommendations for improved approaches and for future work.

    SciTech Connect

    Gillen, Kenneth Todd; Bernstein, Robert

    2010-11-01

    Many U. S. nuclear power plants are approaching 40 years of age and there is a desire to extend their life for up to 100 total years. Safety-related cables were originally qualified for nuclear power plant applications based on IEEE Standards that were published in 1974. The qualifications involved procedures to simulate 40 years of life under ambient power plant aging conditions followed by simulated loss of coolant accident (LOCA). Over the past 35 years or so, substantial efforts were devoted to determining whether the aging assumptions allowed by the original IEEE Standards could be improved upon. These studies led to better accelerated aging methods so that more confident 40-year lifetime predictions became available. Since there is now a desire to potentially extend the life of nuclear power plants way beyond the original 40 year life, there is an interest in reviewing and critiquing the current state-of-the-art in simulating cable aging. These are two of the goals of this report where the discussion is concentrated on the progress made over the past 15 years or so and highlights the most thorough and careful published studies. An additional goal of the report is to suggest work that might prove helpful in answering some of the questions and dealing with some of the issues that still remain with respect to simulating the aging and predicting the lifetimes of safety-related cable materials.

  17. 76 FR 35861 - Safety Culture at the Waste Treatment and Immobilization Plant

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-06-20

    ... facility. The Board is required by statute to investigate any event or practice at a defense nuclear facility which it determines may adversely affect public health and safety. The Board conducted this... healthy safety culture as identified by DOE's Energy Facility Contractors Group and endorsed by...

  18. Extraction and use of historical extreme climate databases for nuclear power plants safety assessment

    NASA Astrophysics Data System (ADS)

    Hamdi, Yasser; Bertin, Xavier; Bardet, Lise; Duluc, Claire-Marie; Rebour, Vincent

    2015-04-01

    Safety assessments of nuclear power plants (NPPs) related to natural hazards are a matter of major interest to the nuclear community in France and many European countries. Over the past fewer decades, France has experienced many of these events such as heat waves (2003 and 2006), heavy snowstorms (1958, 1990 and 1992), storms which have given rise to heavy rain and severe floods (1992, 1999, 2010), strong straight-line wind and extreme marine surges (1987, 1999 and 2010) much larger than the other local observations (outliers). These outliers had clearly illustrated the potential to underestimate the extreme surges calculated with the current statistical methods. The estimation of extreme surges then requires the use of a statistical analysis approach having a more solid theoretical framework and using more reliable databases for the assessment of hazards to design NPPs to low or extremely low probabilities of failure. These databases can be produced by collecting historical information (HI) about severe climatic events occurred over short and long timescales. As a matter of fact, natural hazards such as heat waves, droughts, floods, severe storms and snowstorms have affected France and many European countries since the dawn of time. These events would have been such horrific experiences that if they really occurred, there would be unmistakable traces of them. They must have left clues. These catastrophic events have been unforgettably engraved in people's minds and many of them have been traced in archives and history textbooks. The oldest events have certainly left clues and traces somewhere in the geological layers of the earth or elsewhere. The construction of the historical databases and developing probabilistic approaches capable of integrating them correctly is highly challenging for the scientific community (Translating these geological clues to historical data to build historical databases that can be used by the statistical models is a different

  19. Deep Sequencing of Plant and Animal DNA Contained within Traditional Chinese Medicines Reveals Legality Issues and Health Safety Concerns

    PubMed Central

    Coghlan, Megan L.; Haile, James; Houston, Jayne; Murray, Dáithí C.; White, Nicole E.; Moolhuijzen, Paula; Bellgard, Matthew I.; Bunce, Michael

    2012-01-01

    Traditional Chinese medicine (TCM) has been practiced for thousands of years, but only within the last few decades has its use become more widespread outside of Asia. Concerns continue to be raised about the efficacy, legality, and safety of many popular complementary alternative medicines, including TCMs. Ingredients of some TCMs are known to include derivatives of endangered, trade-restricted species of plants and animals, and therefore contravene the Convention on International Trade in Endangered Species (CITES) legislation. Chromatographic studies have detected the presence of heavy metals and plant toxins within some TCMs, and there are numerous cases of adverse reactions. It is in the interests of both biodiversity conservation and public safety that techniques are developed to screen medicinals like TCMs. Targeting both the p-loop region of the plastid trnL gene and the mitochondrial 16S ribosomal RNA gene, over 49,000 amplicon sequence reads were generated from 15 TCM samples presented in the form of powders, tablets, capsules, bile flakes, and herbal teas. Here we show that second-generation, high-throughput sequencing (HTS) of DNA represents an effective means to genetically audit organic ingredients within complex TCMs. Comparison of DNA sequence data to reference databases revealed the presence of 68 different plant families and included genera, such as Ephedra and Asarum, that are potentially toxic. Similarly, animal families were identified that include genera that are classified as vulnerable, endangered, or critically endangered, including Asiatic black bear (Ursus thibetanus) and Saiga antelope (Saiga tatarica). Bovidae, Cervidae, and Bufonidae DNA were also detected in many of the TCM samples and were rarely declared on the product packaging. This study demonstrates that deep sequencing via HTS is an efficient and cost-effective way to audit highly processed TCM products and will assist in monitoring their legality and safety especially when

  20. Individual plant examination program: Perspectives on reactor safety and plant performance. Part 6, appendices A, B, and C

    SciTech Connect

    1997-12-01

    This report provides perspectives gained by reviewing 75 Individual Plant Examination (IPE) submittals pertaining to 108 nuclear power plant units. IPEs are probabilistic analyses that estimate the core damage frequency (CDF) and containment performance for accidents initiated by internal events (including internal flooding, but excluding internal fire). The U.S. Nuclear Regulatory Commission (NRC), Office of Nuclear Regulatory Research, reviewed the WE submittals with the objective of gaining perspectives in three major areas: (1) improvements made to individual plants as a result of their IPEs and the collective results of the IPE program, (2) plant-specific design and operational features and modeling assumptions that significantly affect the estimates of CDF and containment performance, and (3) strengths and weaknesses of the models and methods used in the IPEs. These perspectives are gained by assessing the core damage and containment performance results, including overall CDF, accident sequences, dominant contributions to component failure and human error, and containment failure modes. In particular, these results are assessed in relation to the design and operational characteristics of the various reactor and containment types, and by comparing the IPEs to probabilistic risk assessment characteristics. Methods, data, boundary conditions, and assumptions used in the IPEs are considered in understanding the differences and similarities observed among the various types of plants.

  1. Guidelines for nuclear power plant safety issue prioritization information development. Supplement 2

    SciTech Connect

    Andrews, W.B.; Gallucci, R.H.V.; Konzek, G.J.; Heaberlin, S.W.; Fecht, B.A.; Allen, C.H.; Allen, R.D.; Bickford, W.E., Carbaugh, E.H.; Lewis, J.R.

    1983-12-01

    This is the third in a series of reports to document the use of a methodology developed by the Pacific Northwest Laboratory to calculate, for prioritization purposes, the risk, dose and cost impacts of implementing resolutions to reactor safety issues (NUREG/CR-2800, Andrews et al. 1983). This report contains results of issue-specific analyses for 31 issues. Each issue was considered within the constraints of available information as of summer 1983, and two staff-weeks of labor. The results are referenced, as one consideration in setting priorities for reactor safety issues, in NUREG-0933, A Prioritization of Generic Safety Issues.

  2. Guidelines for nuclear power plant safety issue prioritization information development. Supplement 4

    SciTech Connect

    Tabatabai, A.S.; Fecht, B.A.; Powers, T.B.; Bickford, W.E.; Andrews, W.B.; Gallucci, R.H.V.; Bian, S.H.; Daling, P.M.; Eschbach, E.J.; Allen, C.H.

    1986-07-01

    This is the fifth in a series of reports to document the use of a methodology developed by the Pacific Northwest Laboratory to calculate, for prioritization purposes, the risk, dose and cost impacts of implementing resolutions to reactor safety issues (NUREG/CR-2800, Andrews et al. 1983). This report contains results of issue-specific analyses for 23 issues. Each issue was considered within the constraints of available information as of winter 1986, and two staff-weeks of labor. The results are referenced, as one consideration in setting priorities for reactor safety issues, in NUREG-0933, ''A Prioritization of Generic Safety Issues.''

  3. Moving forward in plant food safety and security through NanoBioSensors: Adopt or adapt biomedical technologies?

    PubMed

    Sharma, Tarun K; Ramanathan, Rajesh; Rakwal, Randeep; Agrawal, Ganesh K; Bansal, Vipul

    2015-05-01

    Plant-based foods are integral part of our day-to-day diet. Increasing world population has put forth an ever increasing demand for plant-based foods, and food security remains a major concern. Similarly, biological, chemical, and physical threats to our food and increasing regulatory demands to control the presence of foreign species in food products have made food safety a growing issue. Nanotechnology has already established its roots in diverse disciplines. However, the food industry is yet to harness the full potential of the unique capabilities offered by this next-generation technology. While there might be safety concerns in regards to integration of nanoproducts with our food products, an aspect of nanotechnology that can make remarkable contribution to different elements of the food chain is the use of nanobiosensors and diagnostic platforms for monitoring food traceability, quality, safety, and nutritional value. This brings us to an important question that whether existing diagnostic platforms that have already been well developed for biomedical and clinical application are suitable for food industry or whether the demands of the food industry are altogether different that may not allow adoption/adaptation of the existing technology. This review is an effort to raise this important "uncomfortable" yet "timely" question. PMID:25727733

  4. Safety engineering: KTA code of practice. Lifting mechanisms in nuclear plant

    NASA Astrophysics Data System (ADS)

    Lifting mechanisms safety requirements are discussed in accordance with the present state of development of science and engineering for the protection of life, health, and assets against the dangers of nuclear energy and the ill effects of ionizing radiation.

  5. An investigation and analysis of safety issues in Polish small construction plants

    PubMed Central

    Dąbrowski, Andrzej

    2015-01-01

    The construction industry is a booming sector of the Polish economy; however, it is stigmatised by a lower classification due to high occupational risks and an unsatisfactory state of occupational safety. Safety on construction sites is compromised by small construction firms which dominate the market and have high accident rates. This article presents the results of studies (using a checklist) conducted in small Polish construction companies in terms of selected aspects of safety, such as co-operation with the general contractor, occupational health and safety documents, occupational risk assessment, organization of work, protective gear and general work equipment. The mentioned studies and analyses provided the grounds to establish the main directions of preventive measures decreasing occupational risk in small construction companies, e.g., an increase in engagement of investors and general contractors, improvement of occupational health and safety (OSH) documents, an increase in efficiency of construction site managers, better stability of employment and removal of opposing objectives between economic strategy and work safety. PMID:26694002

  6. An investigation and analysis of safety issues in Polish small construction plants.

    PubMed

    Dąbrowski, Andrzej

    2015-01-01

    The construction industry is a booming sector of the Polish economy; however, it is stigmatised by a lower classification due to high occupational risks and an unsatisfactory state of occupational safety. Safety on construction sites is compromised by small construction firms which dominate the market and have high accident rates. This article presents the results of studies (using a checklist) conducted in small Polish construction companies in terms of selected aspects of safety, such as co-operation with the general contractor, occupational health and safety documents, occupational risk assessment, organization of work, protective gear and general work equipment. The mentioned studies and analyses provided the grounds to establish the main directions of preventive measures decreasing occupational risk in small construction companies, e.g., an increase in engagement of investors and general contractors, improvement of occupational health and safety (OSH) documents, an increase in efficiency of construction site managers, better stability of employment and removal of opposing objectives between economic strategy and work safety. PMID:26694002

  7. The effects of electric power industry restructuring on the safety of nuclear power plants in the United States

    NASA Astrophysics Data System (ADS)

    Butler, Thomas S.

    Throughout the United States the electric utility industry is restructuring in response to federal legislation mandating deregulation. The electric utility industry has embarked upon an extraordinary experiment by restructuring in response to deregulation that has been advocated on the premise of improving economic efficiency by encouraging competition in as many sectors of the industry as possible. However, unlike the telephone, trucking, and airline industries, the potential effects of electric deregulation reach far beyond simple energy economics. This dissertation presents the potential safety risks involved with the deregulation of the electric power industry in the United States and abroad. The pressures of a competitive environment on utilities with nuclear power plants in their portfolio to lower operation and maintenance costs could squeeze them to resort to some risky cost-cutting measures. These include deferring maintenance, reducing training, downsizing staff, excessive reductions in refueling down time, and increasing the use of on-line maintenance. The results of this study indicate statistically significant differences at the .01 level between the safety of pressurized water reactor nuclear power plants and boiling water reactor nuclear power plants. Boiling water reactors exhibited significantly more problems than did pressurized water reactors.

  8. Identification of the impacts of maintenance and testing upon the safety of LWR power plants. Final report

    SciTech Connect

    Husseiny, A. A.; Sabri, Z. A.; Turnage, J. J.

    1980-04-01

    The present study was designed to identify the impact of maintenance and testing (M and T) upon the safety of LWR power plants. The study involved data extraction from various sources reporting safety-related and operation-related nuclear power plant experience. Primary sources reviewed, including Licensee Event Reports (LER's) submitted to the NRC, revealed that only ten percent of events reported could be identified as M and T problems. The collected data were collated in a manner that would allow identification of principal types of problems which are associated with the performance of M and T tasks in LWR power plants. Frequencies of occurrence of events and their general endemic nature were analyzed using data clustering and pattern recognition techniques, as well as chi-square analyses for sparse contingency tables. The results of these analyses identified seven major categories of M and T error modes which were related to individual facilities and reactor type. Data review indicated that few M and T problems were directly related to procedural inadequacies, with the majority of events being attributable to human error.

  9. Pinellas Plant site environmental report for calendar year 1989: Environmental Health and Safety Programs

    SciTech Connect

    Klein, R.D.

    1990-06-01

    The Pinellas Plant is a government-owned facility operated for the US Department of Energy (DOE) by the GE Neutron Devices (GEND). The plant's work force is approximately 1700 employees is engaged in the design, development and manufacture of special electronic and mechanical nuclear weapon components. The environmental monitoring programs maintained by the Pinellas Plant are designed to: determine the efficiencies of treatment and control mechanisms for environmental releases, provide measurements of discharge concentrations for comparison with applicable standards, assess the concentrations of these discharges in the on-site and off-site environment, and provide a data base for computer programs to calculate the potential dose to the public resulting from the operation of the Pinellas Plant. The environmental effects of radiological and nonradiological effluents from the operation of the Pinellas Plant have been demonstrated to be significant. This paper discussing the environmental monitoring programs at the Pinellas Plant. 29 refs., 12 figs., 15 tabs.

  10. Evaluation of station blackout accidents at nuclear power plants: Technical findings related to unresolved safety issue A-44: Final report

    SciTech Connect

    Not Available

    1988-06-01

    ''Station Blackout,'' which is the complete loss of alternating current (AC) electrical power in a nuclear power plant, has been designated as Unresolved Safety Issue A-44. Because many safety systems required for reactor core decay heat removal and containment heat removal depend on AC power, the consequences of a station blackout could be severe. This report documents the findings of technical studies performed as part of the program to resolve this issue. The important factors analyzed include: the fequency of loss of offsite power; the probability that emergency or onsite AC power supplies would be unavailable; the capability and reliability of decay heat removal systems independent of AC power; and the likelihood that offsite power would be restored before systems that cannot operate for extended periods without AC power fail, thus resulting in core damage. This report also addresses effects of different designs, locations, and operational features on the estimated frequency of core damage resulting from station blackout events.

  11. Cognitive decision errors and organization vulnerabilities in nuclear power plant safety management: Modeling using the TOGA meta-theory framework

    SciTech Connect

    Cappelli, M.; Gadomski, A. M.; Sepiellis, M.; Wronikowska, M. W.

    2012-07-01

    In the field of nuclear power plant (NPP) safety modeling, the perception of the role of socio-cognitive engineering (SCE) is continuously increasing. Today, the focus is especially on the identification of human and organization decisional errors caused by operators and managers under high-risk conditions, as evident by analyzing reports on nuclear incidents occurred in the past. At present, the engineering and social safety requirements need to enlarge their domain of interest in such a way to include all possible losses generating events that could be the consequences of an abnormal state of a NPP. Socio-cognitive modeling of Integrated Nuclear Safety Management (INSM) using the TOGA meta-theory has been discussed during the ICCAP 2011 Conference. In this paper, more detailed aspects of the cognitive decision-making and its possible human errors and organizational vulnerability are presented. The formal TOGA-based network model for cognitive decision-making enables to indicate and analyze nodes and arcs in which plant operators and managers errors may appear. The TOGA's multi-level IPK (Information, Preferences, Knowledge) model of abstract intelligent agents (AIAs) is applied. In the NPP context, super-safety approach is also discussed, by taking under consideration unexpected events and managing them from a systemic perspective. As the nature of human errors depends on the specific properties of the decision-maker and the decisional context of operation, a classification of decision-making using IPK is suggested. Several types of initial situations of decision-making useful for the diagnosis of NPP operators and managers errors are considered. The developed models can be used as a basis for applications to NPP educational or engineering simulators to be used for training the NPP executive staff. (authors)

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

    SciTech Connect

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

    1994-03-01

    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.

  13. Safety and nutritional assessment of GM plants and derived food and feed: the role of animal feeding trials.

    PubMed

    2008-03-01

    In this report the various elements of the safety and nutritional assessment procedure for genetically modified (GM) plant derived food and feed are discussed, in particular the potential and limitations of animal feeding trials for the safety and nutritional testing of whole GM food and feed. The general principles for the risk assessment of GM plants and derived food and feed are followed, as described in the EFSA guidance document of the EFSA Scientific Panel on Genetically Modified Organisms. In Section 1 the mandate, scope and general principles for risk assessment of GM plant derived food and feed are discussed. Products under consideration are food and feed derived from GM plants, such as maize, soybeans, oilseed rape and cotton, modified through the introduction of one or more genes coding for agronomic input traits like herbicide tolerance and/or insect resistance. Furthermore GM plant derived food and feed, which have been obtained through extensive genetic modifications targeted at specific alterations of metabolic pathways leading to improved nutritional and/or health characteristics, such as rice containing beta-carotene, soybeans with enhanced oleic acid content, or tomato with increased concentration of flavonoids, are considered. The safety assessment of GM plants and derived food and feed follows a comparative approach, i.e. the food and feed are compared with their non-GM counterparts in order to identify intended and unintended (unexpected) differences which subsequently are assessed with respect to their potential impact on the environment, safety for humans and animals, and nutritional quality. Key elements of the assessment procedure are the molecular, compositional, phenotypic and agronomic analysis in order to identify similarities and differences between the GM plant and its near isogenic counterpart. The safety assessment is focussed on (i) the presence and characteristics of newly expressed proteins and other new constituents and possible

  14. Precise plant breeding using new genome editing techniques: opportunities, safety and regulation in the EU.

    PubMed

    Hartung, Frank; Schiemann, Joachim

    2014-06-01

    Several new plant breeding techniques (NPBTs) have been developed during the last decade, and make it possible to precisely perform genome modifications in plants. The major problem, other than technical aspects, is the vagueness of regulation concerning these new techniques. Since the definition of eight NPBTs by a European expert group in 2007, there has been an ongoing debate on whether the resulting plants and their products are covered by GMO legislation. Obviously, cover by GMO legislation would severely hamper the use of NPBT, because genetically modified plants must pass a costly and time-consuming GMO approval procedure in the EU. In this review, we compare some of the NPBTs defined by the EU expert group with classical breeding techniques and conventional transgenic plants. The list of NPBTs may be shortened (or extended) during the international discussion process initiated by the Organization for Economic Co-operation and Development. From the scientific point of view, it may be argued that plants developed by NPBTs are often indistinguishable from classically bred plants and are not expected to possess higher risks for health and the environment. In light of the debate on the future regulation of NPBTs and the accumulated evidence on the biosafety of genetically modified plants that have been commercialized and risk-assessed worldwide, it may be suggested that plants modified by crop genetic improvement technologies, including genetic modification, NPBTs or other future techniques, should be evaluated according to the new trait and the resulting end product rather than the technique used to create the new plant variety. PMID:24330272

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

    SciTech Connect

    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.

  16. Management of the aging of critical safety-related concrete structures in light-water reactor plants

    SciTech Connect

    Naus, D.J.; Oland, C.B. ); Arndt, E.G. )

    1990-01-01

    The Structural Aging Program has the overall objective of providing the USNRC with an improved basis for evaluating nuclear power plant safety-related structures for continued service. The program consists of a management task and three technical tasks: materials property data base, structural component assessment/repair technology, and quantitative methodology for continued-service determinations. Objectives, accomplishments, and planned activities under each of these tasks are presented. Major program accomplishments include development of a materials property data base for structural materials as well as an aging assessment methodology for concrete structures in nuclear power plants. Furthermore, a review and assessment of inservice inspection techniques for concrete materials and structures has been complete, and work on development of a methodology which can be used for performing current as well as reliability-based future condition assessment of concrete structures is well under way. 43 refs., 3 tabs.

  17. Guidelines for nuclear-power-plant safety-issue-prioritization information development

    SciTech Connect

    Andrews, W.B.; Gallucci, R.H.V.; Heaberlin, S.W.; Bickford, W.E.; Konzek, G.J.; Strenge, D.L.; Smith, R.I.; Weakley, S.A.

    1983-02-01

    Pacific Northwest Laboratory has developed a methodology, with examples, to calculate - to an approximation serviceable for prioritization purposes - the risk, dose and cost impacts of implementing resolutions to reactor safety issues. This report is an applications guide to issue-specific calculations. A description of the approach, mathematical models, worksheets and step-by-step examples are provided. Analysis using this method is intended to provide comparable results for many issues at a cost of two staff-weeks per issue. Results will be used by the NRC to support decisions related to issue priorities in allocation of resources to complete safety issue resolutions.

  18. Guidelines for nuclear power plant safety issue prioritization information development. Supplement 5

    SciTech Connect

    Daling, P.M.; Lavender, J.C.

    1996-07-01

    This is the sixth in a series of reports to document the development and use of a methodology developed by the Pacific Northwest Laboratory (PNL) to calculate, for prioritization purposes, the risk, dose, and cost impacts of implementing potential resolutions to reactor safety issues (see NUREG/CR-2800, Andrews, et al., 1983). This report contains the results of issue-specific analyses for 34 generic issues. Each issue was considered within the constraints of available information at the time the issues were examined and approximately 2 staff-weeks of labor. The results are referenced as one consideration in NUREG-0933, A Prioritization of Generic Safety Issues (Emrit, et al., 1983).

  19. Guidelines for nuclear-power-plant safety-issue prioritization information development

    SciTech Connect

    Andrews, W.B.; Gallucci, R.H.V.; Konzek, G.J.

    1983-05-01

    This is the second in a series of reports to document the use of a methodology developed by the Pacific Northwest Laboratory to calculate, for prioritization purposes, the risk, dose and cost impacts of implementing resolutions to reactor safety issues. This report contains results of issue-specific analyses for 15 issues. Each issue was considered within the contraints of available information as of September 1982 and two staff-weeks of labor. The results will be referenced, as one consideration in setting priorities for reactor safety issues, in an NRC prioritization report to be published at a future date.

  20. Review guidelines on software languages for use in nuclear power plant safety systems. Final report

    SciTech Connect

    Hecht, H.; Hecht, M.; Graff, S.; Green, W.; Lin, D.; Koch, S.; Tai, A.; Wendelboe, D.

    1996-06-01

    Guidelines for the programming and auditing of software written in high level languages for safety systems are presented. The guidelines are derived from a framework of issues significant to software safety which was gathered from relevant standards and research literature. Language-specific adaptations of these guidelines are provided for the following high level languages: Ada, C/C++, Programmable Logic Controller (PLC) Ladder Logic, International Electrotechnical Commission (IEC) Standard 1131-3 Sequential Function Charts, Pascal, and PL/M. Appendices to the report include a tabular summary of the guidelines and additional information on selected languages.s

  1. Enteric Pathogen-Plant Interactions: Molecular Connections Leading to Colonization and Growth and Implications for Food Safety

    PubMed Central

    Martínez-Vaz, Betsy M.; Fink, Ryan C.; Diez-Gonzalez, Francisco; Sadowsky, Michael J.

    2014-01-01

    Leafy green vegetables have been identified as a source of foodborne illnesses worldwide over the past decade. Human enteric pathogens, such as Escherichia coli O157:H7 and Salmonella, have been implicated in numerous food poisoning outbreaks associated with the consumption of fresh produce. An understanding of the mechanisms responsible for the establishment of pathogenic bacteria in or on vegetable plants is critical for understanding and ameliorating this problem as well as ensuring the safety of our food supply. While previous studies have described the growth and survival of enteric pathogens in the environment and also the risk factors associated with the contamination of vegetables, the molecular events involved in the colonization of fresh produce by enteric pathogens are just beginning to be elucidated. This review summarizes recent findings on the interactions of several bacterial pathogens with leafy green vegetables. Changes in gene expression linked to the bacterial attachment and colonization of plant structures are discussed in light of their relevance to plant-microbe interactions. We propose a mechanism for the establishment and association of enteric pathogens with plants and discuss potential strategies to address the problem of foodborne illness linked to the consumption of leafy green vegetables. PMID:24859308

  2. Clinical Safety and Immunogenicity of Tumor-Targeted, Plant-Made Id-KLH Conjugate Vaccines for Follicular Lymphoma.

    PubMed

    Tusé, Daniel; Ku, Nora; Bendandi, Maurizio; Becerra, Carlos; Collins, Robert; Langford, Nyla; Sancho, Susana Inogés; López-Díaz de Cerio, Ascensión; Pastor, Fernando; Kandzia, Romy; Thieme, Frank; Jarczowski, Franziska; Krause, Dieter; Ma, Julian K-C; Pandya, Shan; Klimyuk, Victor; Gleba, Yuri; Butler-Ransohoff, John E

    2015-01-01

    We report the first evaluation of plant-made conjugate vaccines for targeted treatment of B-cell follicular lymphoma (FL) in a Phase I safety and immunogenicity clinical study. Each recombinant personalized immunogen consisted of a tumor-derived, plant-produced idiotypic antibody (Ab) hybrid comprising the hypervariable regions of the tumor-associated light and heavy Ab chains, genetically grafted onto a common human IgG1 scaffold. Each immunogen was produced in Nicotiana benthamiana plants using twin magnICON vectors expressing the light and heavy chains of the idiotypic Ab. Each purified Ab was chemically linked to the carrier protein keyhole limpet hemocyanin (KLH) to form a conjugate vaccine. The vaccines were administered to FL patients over a series of ≥6 subcutaneous injections in conjunction with the adjuvant Leukine (GM-CSF). The 27 patients enrolled in the study had previously received non-anti-CD20 cytoreductive therapy followed by ≥4 months of immune recovery prior to first vaccination. Of 11 patients who became evaluable at study conclusion, 82% (9/11) displayed a vaccine-induced, idiotype-specific cellular and/or humoral immune response. No patients showed serious adverse events (SAE) related to vaccination. The fully scalable plant-based manufacturing process yields safe and immunogenic personalized FL vaccines that can be produced within weeks of obtaining patient biopsies. PMID:26425548

  3. Clinical Safety and Immunogenicity of Tumor-Targeted, Plant-Made Id-KLH Conjugate Vaccines for Follicular Lymphoma

    PubMed Central

    Tusé, Daniel; Ku, Nora; Bendandi, Maurizio; Becerra, Carlos; Collins, Robert; Langford, Nyla; Sancho, Susana Inogés; López-Díaz de Cerio, Ascensión; Pastor, Fernando; Kandzia, Romy; Thieme, Frank; Jarczowski, Franziska; Krause, Dieter; Ma, Julian K.-C.; Pandya, Shan; Klimyuk, Victor; Gleba, Yuri; Butler-Ransohoff, John E.

    2015-01-01

    We report the first evaluation of plant-made conjugate vaccines for targeted treatment of B-cell follicular lymphoma (FL) in a Phase I safety and immunogenicity clinical study. Each recombinant personalized immunogen consisted of a tumor-derived, plant-produced idiotypic antibody (Ab) hybrid comprising the hypervariable regions of the tumor-associated light and heavy Ab chains, genetically grafted onto a common human IgG1 scaffold. Each immunogen was produced in Nicotiana benthamiana plants using twin magnICON vectors expressing the light and heavy chains of the idiotypic Ab. Each purified Ab was chemically linked to the carrier protein keyhole limpet hemocyanin (KLH) to form a conjugate vaccine. The vaccines were administered to FL patients over a series of ≥6 subcutaneous injections in conjunction with the adjuvant Leukine (GM-CSF). The 27 patients enrolled in the study had previously received non-anti-CD20 cytoreductive therapy followed by ≥4 months of immune recovery prior to first vaccination. Of 11 patients who became evaluable at study conclusion, 82% (9/11) displayed a vaccine-induced, idiotype-specific cellular and/or humoral immune response. No patients showed serious adverse events (SAE) related to vaccination. The fully scalable plant-based manufacturing process yields safe and immunogenic personalized FL vaccines that can be produced within weeks of obtaining patient biopsies. PMID:26425548

  4. Nuclear criticality safety controls for uranium deposits during D and D at the Oak Ridge Gaseous Diffusion Plant

    SciTech Connect

    Haire, M.J.; Jordan, W.C.; Jollay, L.J. III; Dahl, T.L.

    1997-02-01

    The US Department of Energy (DOE) Deputy Assistant Secretary of Energy for Environmental Management has issued a challenge to complete DOE environmental cleanup within a decade. The response for Oak Ridge facilities is in accordance with the DOE ten-year plan which calls for completion of > 95% of environmental management work by the year 2006. This will result in a 99% risk reduction and in a significant savings in base line costs in waste management (legacy waste); remedial action (groundwater, soil, etc.); and decontamination and decommissioning (D and D). It is assumed that there will be long-term institutional control of cascade equipment, i.e., there will be no walk away from sites, and that there will be firm radioactivity release limits by 1999 for recycle metals. An integral part of these plants is the removal of uranium deposits which pose nuclear criticality safety concerns in the shut down of the Oak Ridge Gaseous Diffusion Plant. DOE has initiated the Nuclear Criticality Stabilization Program to improve nuclear criticality safety by removing the larger uranium deposits from unfavorable geometry equipment. Nondestructive assay (NDA) measurements have identified the location of these deposits. The objective of the K-25 Site Nuclear Criticality Stabilization Program is to remove and place uranium deposits into safe geometry storage containers to meet the double contingency principle. Each step of the removal process results in safer conditions where multiple controls are present. Upon completion of the Program, nuclear criticality risks will be greatly reduced.

  5. Evaluation of operational safety at Babcock and Wilcox Plants: Volume 2, Thermal-hydraulic results

    SciTech Connect

    Wheatley, P.D.; Davis, C.B.; Callow, R.A.; Fletcher, C.D.; Dobbe, C.A.; Beelman, R.J.

    1987-11-01

    The Nuclear Regulatory Commission has initiated a research program to develop a methodology to assess the operational performance of Babcock and Wilcox plants and to apply this methodology on a trial basis. The methodology developed for analyzing Babcock and Wilcox plants integrated methods used in both thermal-hydraulics and human factors and compared results with information used in the assessment of risk. The integrated methodology involved an evaluation of a selected plant for each pressurized water reactor vendor during a limited number of transients. A plant was selected to represent each vendor, and three transients were identified for analysis. The plants were Oconee Unit 1 for Babcock and Wilcox, H.B. Robinson Unit 2 for Westinghouse, and Calvert Cliffs Unit 1 for Combustion Engineering. The three transients were a complete loss of all feedwater, a small-break loss-of-coolant accident, and a steam-generator overfill with auxiliary feedwater. Included in the integrated methodology was an assessment of the thermal-hydraulic behavior, including event timing, of the plants during the three transients. Thermal-hydraulic results are presented in this volume (Volume 2) of the report. 26 refs., 30 figs., 7 tabs.

  6. Caution! NRC as protector of worker health and safety at nuclear power plants.

    PubMed

    Dunn, M L

    1999-01-01

    Congress may soon face a decision about what agency will take responsibility for worker and facility safety at Department of Energy (DOE) sites as the DOE moves to external regulation. The Nuclear Regulatory Commission (NRC) occupies a prominent place on the short list of candidates. Thus, an examination of the NRC's historical record on health and safety, in particular, its record in protecting workers, is warranted. This look at the record shows that the NRC does not adopt a strong regulatory stance; exposure standards for workers have not changed despite evidence of harmful effects at low doses of radiation exposure; record-keeping and worker monitoring are lax; the NRC is blind to internal cultural problems; it appears more concerned about its public image than about entrenched problems; it is too lenient to the industry it is supposed to regulate. The NRC's history of recent problems has caused some critics to call for Congressional hearings or additional oversight of the agency. PMID:17208795

  7. Assessment of inservice conditions of safety-related nuclear plant structures

    SciTech Connect

    Ashar, H.; Bagchi, G.

    1995-06-01

    The report is a compilation from a number of sources of information related to the condition Of structures and civil engineering features at operating nuclear power plants in the United States. The most significant information came from the hands-on inspection of the six old plants (licensed prior to 1977) performed by the staff of the Civil Engineering and Geosciences Branch (ECGB) in the Division of Engineering of the Office of Nuclear Reactor Regulation. For the containment structures, most of the information related to the degraded conditions came from the licensees as part of the Licensing Event Report System (10 CFR 50.73), or as part of the requirement under limiting condition of operation of the plant-specific Technical Specifications. Most of the information related to the degradation of other Structures and civil engineering features was extracted from the industry survey, the reported incidents, and the plant visits. The report discusses the condition of the structures and civil engineering features at operating nuclear power plants and provides information that would help detect, alleviate, and correct the degraded conditions of the structures and civil engineering features.

  8. Activities in Support of Continuing the Service of Nuclear Power Plant Safety-Related Concrete Structures

    SciTech Connect

    Naus, Dan J

    2014-01-01

    Nuclear power plant (NPP) concrete structures are described. In-service inspection and testing requirements in the U.S. are summarized. The license renewal process in the U.S. is outlined and its current status provided. Operating experience related to performance of the concrete structures is presented. Basic components of a program to manage aging of the concrete structures are identified and described: (1) Degradation mechanisms, damage models, and material performance; (2) Assessment and remediation: i.e., component selection, in- service inspection, non-destructive examinations, and remedial actions; and (3) Estimation of performance at present or some future point in time: i.e., application of structural reliability theory to the design and optimization of in-service inspection/maintenance strategies, and determination of the effects of degradation on plant risk. Finally, areas are noted where additional research would be of benefit to aging management of nuclear power plant concrete structures.

  9. Activities in Support of Continuing the Service of Nuclear Power Plant Safety-Related Concrete Structures

    SciTech Connect

    Naus, Dan J

    2010-01-01

    Nuclear power plant concrete structures are described. In-service inspection and testing requirements in the U.S. are summarized. The license renewal process in the U.S. is outlined and its current status provided. Operating experience related to performance of the concrete structures is presented. Basic components of a program to manage aging of the concrete structures are identified and described: degradation mechanisms, damage models, and material performance; assessment and remediation (i.e., component selection, in-service inspection, non-destructive examinations, and remedial actions); and estimation of performance at present or some future point in time (i.e., application of structural reliability theory to the design and optimization of in-service inspection/maintenance strategies, and determination of the effects of degradation on plant risk). Finally, areas are noted where additional research would be of benefit to aging management of nuclear power plant concrete structures.

  10. A safety and regulatory assessment of generic BWR and PWR permanently shutdown nuclear power plants

    SciTech Connect

    Travis, R.J.; Davis, R.E.; Grove, E.J.; Azarm, M.A.

    1997-08-01

    The long-term availability of less expensive power and the increasing plant modification and maintenance costs have caused some utilities to re-examine the economics of nuclear power. As a result, several utilities have opted to permanently shutdown their plants. Each licensee of these permanently shutdown (PSD) plants has submitted plant-specific exemption requests for those regulations that they believe are no longer applicable to their facility. This report presents a regulatory assessment for generic BWR and PWR plants that have permanently ceased operation in support of NRC rulemaking activities in this area. After the reactor vessel is defueled, the traditional accident sequences that dominate the operating plant risk are no longer applicable. The remaining source of public risk is associated with the accidents that involve the spent fuel. Previous studies have indicated that complete spent fuel pool drainage is an accident of potential concern. Certain combinations of spent fuel storage configurations and decay times, could cause freshly discharged fuel assemblies to self heat to a temperature where the self sustained oxidation of the zircaloy fuel cladding may cause cladding failure. This study has defined four spent fuel configurations which encompass all of the anticipated spent fuel characteristics and storage modes following permanent shutdown. A representative accident sequence was chosen for each configuration. Consequence analyses were performed using these sequences to estimate onsite and boundary doses, population doses and economic costs. A list of candidate regulations was identified from a screening of 10 CFR Parts 0 to 199. The continued applicability of each regulation was assessed within the context of each spent fuel storage configuration and the results of the consequence analyses.

  11. Aging management of safety-related concrete structures in nuclear power plants

    SciTech Connect

    Naus, D.J.; Oland, C.B. ); Arndt, E.G. )

    1990-01-01

    The Structural Aging Program has the overall objective of providing the US Nuclear Regulatory Commission with an improved basis for evaluating nuclear power plants for continued service. In meeting this objective, a materials property data base is being developed as well as an aging assessment methodology for concrete structures in nuclear power plants. Furthermore, studies are well under way to review and assess inservice inspection techniques for concrete structures and to develop a methodology which can be used for performing current as well as reliability-based future conditions assessments of these structures. 16 refs., 2 tabs.

  12. INTERNATIONAL PROGRAM ON CHEMICAL SAFETY'S COLLABORATIVE STUDY ON PLANT TEST SYSTEMS

    EPA Science Inventory

    This article presents the status report on the International Program's Collaborative Study on Plant Test Systems. n the first phase of this program, 16 laboratories submitted data on the genetic effects of EMS evaluated in three bioassays; i.e., Vicia faba root hair, Tradescantia...

  13. Safety significance of inadvertent operation of motor operated valves in nuclear power plants

    SciTech Connect

    Ruger, C.J.; Higgins, J.C.; Carbonaro, J.F.; Hall, R.E.

    1994-05-01

    This report addresses concerns about the consequences of valve mispositioning which were brought to the forefront following an event at Davis Besse in 1985 (NRC, 1985a). The concern related to the ability to reposition ``position changeable`` motor operated valves (MOVs) in the event of their inadvertent operation from the control room and was documented in Nuclear Regulatory Commission (NRC) Bulletin 85-03 (NRC, 1985b) and Generic Letter (GL) 89-10 (NRC, 1989). The mispositioned MOVs may not be able to be returned to their required position due to high differential pressure (dP) or high flow conditions across the valves. The inability to reposition such valves may have significant safety consequences as in the Davis Besse event. However, full consideration of such mispositioning in safety analyses and in MOV test programs can be labor intensive and expensive. Industry raised concerns that consideration of position changeable valves under GL 89-10 would not decrease the probability of core damage to an extent which would justify licensee costs. As a response, Brookhaven National Laboratory (BNL) has conducted separate scoping studies for both Boiling Water Reactors (BWRS) and Pressurized Water Reactors (PWRs) using Probabilistic Risk Assessment (PRA) techniques to determine if such valve mispositioning by itself is significant to safety. The approach utilized internal events PRA models to survey the order of magnitude of the risk significance of valve mispositioning by considering the failure of selected position changeable MOVS. The change in core damage frequency (CDF) was determined for each valve considered and the results were presented as a risk increase ratio for each of four assumed MOV failure rates. The risk increase ratios resulting from this failure rate sensitivity study can be used as a basis for a judgement determination of the risk significance of the MOV mispositioning issue for BWRs and PWRS.

  14. Safety analysis report for packaging, Oak Ridge Y-12 Plant, model DC-1 package with HEU oxide contents. Change pages for Rev.1

    SciTech Connect

    1995-01-18

    This Safety Analysis Report for Packaging for the Oak Ridge Y-12 Plant for the Model DC-1 package with highly enriched uranium (HEU) oxide contents has been prepared in accordance with governing regulations form the Nuclear Regulatory Commission and the Department of Transportation and orders from the Department of energy. The fundamental safety requirements addressed by these regulations and orders pertain to the containment of radioactive material, radiation shielding, and nuclear subcriticality. This report demonstrates how these requirements are met.

  15. Process safety management (OSHA) and process risk management (CAA) application. Application to a coke plant

    SciTech Connect

    Graeser, W.C.; Mentzer, W.P.

    1995-12-01

    Risk Management Programs for Chemical Accidental Release Prevention is the name of the proposed rule for the RMP Risk Management Program. The RMP was written in response to several catastrophic releases of hazardous substances. The rule is applicable to facilities that store, process or use greater than threshold quantities of 62 listed flammable chemicals and another 100 listed toxic substances. Additionally, a Risk Management Plan is registered with the EPA, Chemical Safety and Hazardous Investigation Board, state governments and the local emergency planning commission. The Clean Air Act Amendments of 1990 (specifically Section 112r) required the EPA to develop a three phase Risk Management Plan for industry: prevention program; hazard assessment; and emergency response program. The Prevention Program closely follows the OSHA`s Process Safety Management Standard. The Hazard Assessment section requires facilities to develop plans for a worst case scenario. The Emergency Response section defines the steps the facility and each employee will take if a release occurs. This section also needs to be coordinated with the Local Emergency Planning Commission. These regulations are described using Clairton Works as an example of compliance.

  16. Cost update technology, safety, and costs of decommissioning a reference uranium hexafluoride conversion plant

    SciTech Connect

    Miles, T.L.; Liu, Y.

    1995-08-01

    The purpose of this study is to update the cost estimates developed in a previous report, NUREG/CR-1757 (Elder 1980) for decommissioning a reference uranium hexafluoride conversion plant from the original mid-1981 dollars to values representative of January 1993. The cost updates were performed by using escalation factors derived from cost index trends over the past 11.5 years. Contemporary price quotes wee used for costs that have increased drastically or for which is is difficult to find a cost trend. No changes were made in the decommissioning procedures or cost element requirements assumed in NUREG/CR-1757. This report includes only information that was changed from NUREG/CR-1757. Thus, for those interested in detailed descriptions and associated information for the reference uranium hexafluoride conversion plant, a copy of NUREG/CR-1757 will be needed.

  17. Aging and service wear of air-operated valves used in safety-related systems at nuclear power plants

    SciTech Connect

    Cox, D.F.; McElhaney, K.L.; Staunton, R.H.

    1995-05-01

    Air-operated valves (AOVs) are used in a variety of safety-related applications at nuclear power plants. They are often used where rapid stroke times are required or precise control of the valve obturator is required. They can be designed to operate automatically upon loss of power, which is often desirable when selecting components for response to design basis conditions. The purpose of this report is to examine the reported failures of AOVs and determine whether there are identifiable trends in the failures related to predictable causes. This report examines the specific components that comprise a typical AOV, how those components fail, when they fail, and how such failures are discovered. It also examines whether current testing frequencies and methods are effective in predicting such failures.

  18. Comparison of methods for uncertainty analysis of nuclear-power-plant safety-system fault-tree models. [PWR; BWR

    SciTech Connect

    Martz, H F; Beckman, R J; Campbell, K; Whiteman, D E; Booker, J M

    1983-04-01

    A comparative evaluation is made of several methods for propagating uncertainties in actual coupled nuclear power plant safety system faults tree models. The methods considered are Monte Carlo simulation, the method of moments, a discrete distribution method, and a bootstrap method. The Monte Carlo method is found to be superior. The sensitivity of the system unavailability distribution to the choice of basic event unavailability distribution is also investigated. The system distribution is also investigated. The system distribution is especially sensitive to the choice of symmetric versus asymmetric basic event distributions. A quick-and dirty method for estimating percentiles of the system unavailability distribution is developed. The method identifies the appropriate basic event distribution percentiles that should be used in evaluating the Boolean system equivalent expression for a given fault tree model to arrive directly at the 5th, 10th, 50th, 90th, and 95th percentiles of the system unavailability distribution.

  19. [PAHs concentrations in aquatic products and food safety evaluation in the coupled mangrove planting-aquaculture ecological system].

    PubMed

    Chen, Guan-Qiu; Li, Yao-Chu; Huang, Jin-Mu; Nan, Yan; Lin, Mao-Hong

    2012-06-01

    In order to know about the PAHs concentration in aquatic products from mangrove planting-aquaculture ecological system and to make sure of food quality and food safety, HPLC was used to determine concentrations of 13 polycyclic aromatic hydrocarbons (PAHs) in the Tilapia mossambica, Mugil cephalu and Concha ostreae from coupled mangrove planting-aquaculture ponds, food safety in aquatic products was also evaluated. The 13 PAHs were Fluorene (Flu), Phenanthrene (Phe), Anthracene (Ant), Fluoranthene (Fla), Pyrene (Pyr), Benz[a] anthraces (BaA), Chrysene (Chr), Benzo[b] fluoranthene (BbF), Benzo[k] fluoranthene (BkF), Benzo[a] Pyrene (BaP), Dibenzo [a, h] anthercene (DahA), Benzo [g, h, i] perylene (BghiP) and Indeno [1,2,3-c, d] pyrene (InP). Concentrations of PAHs were the highest in Concha ostreae which were in the range of 89.79-98.49 microg x kg(-1) dry weight, while those were in the range of 25.97-34.64 microg x kg(-1) in Mugil cephalu and 12.31-14.41 microg x kg(-1) in Tilapia mossambica. The content of fat affected the levels of PAHs content in different aquatic products. The individual composition of PAHs was characterized by 3 rings in samples with the range of 41.58% - 83.35%. Comparing with other areas, PAHs pollution of aquatic products in the studied area was in the mild level. Values of the total BaP(eq) concentration ranged from 0.0689 microg x kg(-1) to 1.0373 microg x kg(-1), which were lower than the maximum level set by European Union. PMID:22946164

  20. Application of the leak-before-break concept in nuclear power plant safety analysis

    SciTech Connect

    Kiselev, V.A.; Rivkin, E.Yu.

    1994-06-01

    The objective of this report was to attempt to justify the leak-before-break concept in reactor safety analyses, thus eliminating the need to show protection against the double-ended guillotine break in these analyses. The two assumptions of the concept: (1) A complete break would not occur, and (2) A leak via a through crack would be discovered before the crack size approached the critical value were discussed and conditions to insure validity of each assumption were outlined. Methods of analyses in various countries were also discussed. It was noted that the determination of the area of elastoplastic opening of a crack for a prescribed flow rate is a difficult problem, and it was recommended that testing be performed on full size pipes under postulated conditions.

  1. Occupational Health and Safety Issues in Ontario Sawmills and Veneer/Plywood Plants: A Pilot Study

    PubMed Central

    Verma, Dave K.; Demers, Cecil; Shaw, Don; Verma, Paul; Kurtz, Lawrence; Finkelstein, Murray; des Tombe, Karen; Welton, Tom

    2010-01-01

    A pilot study was conducted within the Ontario sawmill and veneer/plywood manufacturing industry. Information was collected by postal questionnaire and observational walk-through surveys. Industrial hygiene walk-through surveys were conducted at 22 work sites, and measurements for wood dust, noise, and bioaerosol were taken. The aim of the study was to obtain data on the current status regarding health and safety characteristics and an estimate of wood dust, noise, and bioaerosol exposures. The occupational exposure to wood dust and noise are similar to what has been reported in this industry in Canada and elsewhere. Airborne wood dust concentration ranged between 0.001 mg/m3 and 4.87 mg/m3 as total dust and noise exposure ranged between 55 and 117 dB(A). The study indicates the need for a more comprehensive industry-wide study of wood dust, noise, and bioaersols. PMID:21253473

  2. Occupational health and safety issues in Ontario sawmills and veneer/plywood plants: a pilot study.

    PubMed

    Verma, Dave K; Demers, Cecil; Shaw, Don; Verma, Paul; Kurtz, Lawrence; Finkelstein, Murray; des Tombe, Karen; Welton, Tom

    2010-01-01

    A pilot study was conducted within the Ontario sawmill and veneer/plywood manufacturing industry. Information was collected by postal questionnaire and observational walk-through surveys. Industrial hygiene walk-through surveys were conducted at 22 work sites, and measurements for wood dust, noise, and bioaerosol were taken. The aim of the study was to obtain data on the current status regarding health and safety characteristics and an estimate of wood dust, noise, and bioaerosol exposures. The occupational exposure to wood dust and noise are similar to what has been reported in this industry in Canada and elsewhere. Airborne wood dust concentration ranged between 0.001 mg/m³ and 4.87 mg/m³ as total dust and noise exposure ranged between 55 and 117 dB(A). The study indicates the need for a more comprehensive industry-wide study of wood dust, noise, and bioaersols. PMID:21253473

  3. Safety assessment of genetically modified organisms of plant origin in the Russian Federation.

    PubMed

    Tyshko, Nadezhda V; Aksyuk, Irina N; Tutelyan, Victor A

    2007-07-01

    The beginning of the 21st century is characterized by growing interest in the problems of biosafety, which are determined, on the one hand, by the wide use of novel biotechnologies and the necessity to develop the adequate precautionary measures, and, on the other hand, by the objective threat of bioterrorism. Therefore, improvement of the estimation system for genetically modified (GM) sources of food and strengthening the control of their circulation are the urgent problems of modern biology and medicine. Russia is one of the countries where the estimation system of food products obtained from the GM sources is rather efficient. The key features of this system are the complex toxicological and epidemiological examinations. One of the main parts of GM food safety assessment is based upon detection of their potentially toxic properties, which could provoke unintended effects of the genetic modification. PMID:17526054

  4. Safety assessment of plant varieties using transcriptomics profiling and a one-class classifier.

    PubMed

    van Dijk, Jeroen P; de Mello, Carla Souza; Voorhuijzen, Marleen M; Hutten, Ronald C B; Arisi, Ana Carolina Maisonnave; Jansen, Jeroen J; Buydens, Lutgarde M C; van der Voet, Hilko; Kok, Esther J

    2014-10-01

    An important part of the current hazard identification of novel plant varieties is comparative targeted analysis of the novel and reference varieties. Comparative analysis will become much more informative with unbiased analytical approaches, e.g. omics profiling. Data analysis estimating the similarity of new varieties to a reference baseline class of known safe varieties would subsequently greatly facilitate hazard identification. Further biological and eventually toxicological analysis would then only be necessary for varieties that fall outside this reference class. For this purpose, a one-class classifier tool was explored to assess and classify transcriptome profiles of potato (Solanum tuberosum) varieties in a model study. Profiles of six different varieties, two locations of growth, two year of harvest and including biological and technical replication were used to build the model. Two scenarios were applied representing evaluation of a 'different' variety and a 'similar' variety. Within the model higher class distances resulted for the 'different' test set compared with the 'similar' test set. The present study may contribute to a more global hazard identification of novel plant varieties. PMID:25046166

  5. The Belgian experience with the safety reassessment of nuclear power plants

    SciTech Connect

    Damsin, M. )

    1992-01-01

    Belgian utilities operate 7 PWR units distributed over 2 sites, Doel and Tihange. A. The first-generation plants (Doel 1 and 2, Tihange 1) are in operation for about 17 years: 1. Doel 1 and 2 are twin units of 400 MWe each, with a common turbine hall and control room, common nuclear auxiliaries and safeguards; it was built by ACECOWEN, a consortium formed by WESTINGHOUSE and the Belgian companies ACEC and COCKERILL. The architect- engineer was BELGATOM, 2. Tihange 1 is an 870MWe unit, the first 3 loop-PWR of Westinghouse design in Europe. It was built by the consortium ACECOWEN - CREUSOT LOIRE FRAMATOME: the architect-engineer was BELGATOM and EDF. These three units were connected to the grid between August 1974 and August 1975.

  6. Safety Assessment for Inertial Fusion Energy Power Plants: Methodology and Application to the Analysis of the HYLIFE-II and SOMBRERO Conceptual Designs

    NASA Astrophysics Data System (ADS)

    Reyes, S.; Latkowski, J. F.; Sanz, J.; Gomez del Rio, J.

    2001-06-01

    Although the safety and environmental (S & E) characteristics of fusion energy have long been emphasized, these benefits are not automatically achieved. To maximize the potential S & E attractiveness of the inertial fusion energy (IFE), analyses must be performed early in the designs so that lessons can be learned and intelligent decisions made. In this work we have introduced for the first time heat transfer and thermal-hydraulics calculations as part of a state-of-the-art set of codes and libraries in order to establish an updated methodology for IFE safety analysis. We have focused our efforts primarily on two IFE power plant conceptual designs: HYLIFE-II and SOMBRERO. To some degree, these designs represent the extremes in IFE power plant designs. Also, a preliminary safety assessment has been performed for a generic target fabrication facility producing various types of targets and using various production techniques. Although this study cannot address all issues and hazards posed by an IFE power plant, it advances our understanding of radiological safety of such facilities. This will enable better comparisons between IFE designs and competing technologies from the safety point of view.

  7. Florida Postsecondary Education Security Information Act. Annual Report of Campus Crime Statistics 1990-92 and Annual Assessment of Physical Plant Safety 1993.

    ERIC Educational Resources Information Center

    Florida State Dept. of Education, Tallahassee. Office of Postsecondary Education Coordination.

    This report contains campus crime statistics for 1990-92 of crimes reported to have occurred on the community colleges, state universities, and independent colleges and universities of Florida, as required by the Florida Postsecondary Education Security Information (FPESI) Act. It also includes an assessment of physical plant safety for 1993…

  8. Deliberation about the Safety of Industrial Wastewater Discharges into Wastewater Treatment Plants

    NASA Astrophysics Data System (ADS)

    Tolchinsky, Pancho; Aulinas, Montse; Cortés, Ulises; Poch, Manel

    The daily operation of Wastewater Treatment Plants (WWTPs) in industrialized areas is of particular concern because of the severe problems that can occur in the WWTP caused by the incoming inflow, which in turn may cause an ecological imbalance in the fluvial ecosystem. In order to minimize the environmental impact caused by the industrial wastewater discharges, guidelines and regulations exists. However, due to the complexity of the domain, there are still no golden standards by which to decide whether a WWTP can cope with wastewater discharges, and so strict adherence to regulations may not always be convenient. Special circumstances may motivate to accept discharges that are above established thresholds or to reject discharges that comply with guidelines. Nonetheless, because of the criticality of the actions to be taken, such decisions require to be well justified. Hence, in this work it is proposed the use of the argumentation-based model Pro- CLAIM to provide a more flexible decision making process, in which expertise can deliberate whether an industrial wastewater can safely be discharged into a WWTP, and thus adapt each decision to the particular circumstance. To ensure a safe decision, agents’ given arguments for or against the industrial spill are evaluated accounting for the domain guidelines and regulations, for similar past cases and for confidence in the expertise’s assessments.

  9. A 3-year hygiene and safety monitoring of a meat processing plant which uses raw materials of global origin.

    PubMed

    Manios, Stavros G; Grivokostopoulos, Nikolaos C; Bikouli, Vasiliki C; Doultsos, Dimitrios A; Zilelidou, Evangelia A; Gialitaki, Maria A; Skandamis, Panagiotis N

    2015-09-16

    A systematic approach in monitoring the hygiene of a meat processing plant using classical microbiological analyses combined with molecular characterization tools may assist in the safety of the final products. This study aimed: (i) to evaluate the total hygiene level and, (ii) to monitor and characterize the occurrence and spread of Salmonella spp. and Listeria monocytogenes in the environment and the final products of a meat industry that processes meat of global origin. In total, 2541 samples from the processing environment, the raw materials, and the final products were collected from a Greek meat industry in the period 2011-2013. All samples were subjected to enumeration of total viable counts (TVC), Escherichia coli (EC) and total coliforms (TCC) and the detection of Salmonella spp., while 709 of these samples were also analyzed for the presence L. monocytogenes. Pathogen isolates were serotyped and further characterized for their antibiotic resistance and subtyped by PFGE. Raw materials were identified as the primary source of contamination, while improper handling might have also favored the proliferation of the initial microbial load. The occurrence of Salmonella spp. and L. monocytogenes reached 5.5% and 26.9%, respectively. Various (apparent) cross-contamination or persistence trends were deduced based on PFGE analysis results. Salmonella isolates showed wide variation in their innate antibiotic resistance, contrary to L. monocytogenes ones, which were found susceptible to all antibiotics except for cefotaxime. The results emphasize the biodiversity of foodborne pathogens in a meat industry and may be used by meat processors to understand the spread of pathogens in the processing environment, as well as to assist the Food Business Operator (FBO) in establishing effective criteria for selection of raw materials and in improving meat safety and quality. This approach can limit the increase of microbial contamination during the processing steps observed in

  10. Lessons learned from Fukushima Daiichi nuclear power plant accident: efficient education items of radiation safety for general public.

    PubMed

    Ohno, K; Endo, K

    2015-07-01

    The Fukushima Daiichi nuclear power plant (FNP-1) accident, while as tragic as the tsunami, was a man-made disaster created by the ignorance of the effects of radiation and radioactive materials. Therefore, it is important that all specialists in radiation protection in medicine sympathize with the anxiety of the general public regarding the harmful effects of radiation and advise people accordingly. All questions and answers were collected related to inquiries from the general public that were posted to reliable websites, including those of the government and radiation-related organizations, from March 2011 to November 2012. The questions were summarized and classified by similarity of content. (1) The total number of questions is 372. The content was broadly classified into three categories: inquiries for radiation-related knowledge and about health effects and foods. The questions asked to obtain radiation-related knowledge were the most common, accounting for 38 %. Thirty-six percentage of the questions were related to health effects, and 26 % involved foods, whereas 18 % of the questions were related to children and pregnancy. (2) The change over time was investigated in 290 questions for which the time of inquiry was known. Directly after the earthquake, the questions were primarily from people seeking radiation-related knowledge. Later, questions related to health effects increased. The anxiety experienced by residents following the nuclear accident was caused primarily by insufficient knowledge related to radiation, concerns about health effects and uncertainties about food and water safety. The development of educational materials focusing on such content will be important for risk communication with the general public in countries with nuclear power plants. Physicians and medical physicist should possess the ability to respond to questions such as these and should continue with medical examinations and treatments in a safe and appropriate manner. PMID

  11. Evaluation of in vitro and in vivo safety profile of the Indian traditional medicinal plant Grewia tiliaefolia.

    PubMed

    Dicson, Sheeja Malar; Samuthirapandi, Muniasamy; Govindaraju, Archunan; Kasi, Pandima Devi

    2015-10-01

    Grewia tiliaefolia Vahl., is a subtropical tree used in Ayurvedic formulations and also by tribal communities in India for treatment of wounds, urinary infection and skin diseases. Despite of its medicinal use, the plant has not been previously tested for its safety. This study evaluated the toxicological profile of the methanolic extract of G. tiliaefolia leaves (MEGT) through in vitro (cytotoxic, mutagenic, genotoxic) and in vivo (acute and sub-acute) studies. In vitro assays conclude that there is no significant (p<0.05) level of cytotoxicity and genotoxicity at the tested concentrations (250-2000 μg/ml) in peripheral blood mononuclear cells. Ames assay in the tested Salmonella typhimurium strains revealed no significant (p<0.05) increase in the mutagenic index both in the presence and absence of metabolic activation. Alternatively, no change in mortality, physiological, behavioural, haematological and biochemical parameters were observed under in vivo acute (250, 500, 1000, 2000 mg/kg b.w) and sub-acute (100, 200, 1000 mg/kg b.w) toxicity studies in Wistar rats. Histopathological examinations of the animals did not reveal any treatment related changes and showed normal architecture, even at the highest concentration (1000 mg/kg b.w) following 28 days treatment. Overall, the results show that MEGT is non-toxic at the tested concentrations and is safe to be used as herbal medicine. PMID:26188119

  12. Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). Supplement No. 14

    SciTech Connect

    Tam, P.S.

    1994-12-01

    Supplement No. 14 to the Safety Evaluation Report for the application filed by the Tennessee Valley Authority for license to operate Watts Bar Nuclear Plant, Units 1 and 2, Docket Nos. 50-390 and 50-391, located in Rhea County, Tennessee, has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. The purpose of this supplement is to update the Safety Evaluation with additional information submitted by the applicant since Supplement No. 13 was issued, and matters that the staff had under review when Supplement No. 13 was issued.

  13. Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391): Supplement No. 19

    SciTech Connect

    1995-11-01

    Supplement No. 19 to the Safety Evaluation Report for the application filed by the Tennessee Valley Authority for license to operate Watts Bar Nuclear Plant, Units 1 and 2, Docket Nos. 50-390 and 50-391, located in Rhea County Tennessee, has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. The purpose of this supplement is to update the Safety Evaluation with (1) additional information submitted by the applicant since Supplement No. 18 was issued, and (2) matters that the staff had under review when Supplement No. 18 was issued.

  14. Safety Evaluation Report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). Supplement No. 12

    SciTech Connect

    Tam, P.S.

    1993-10-01

    Supplement No. 12 to the Safety Evaluation Report for the application filed by the Tennessee Valley Authority for license to operate Watts Bar Nuclear Plant, Units 1 and 2, Docket Nos. 50-390 and 50-391, located in Rhea County, Tennessee, has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. The purpose of this supplement is to update the Safety Evaluation of (1) additional information submitted by the applicant since Supplement No. 11 was issued, and (2) matters that the staff had under review when Supplement No. 11 was issued.

  15. Missouri Elementary Science Safety Manual.

    ERIC Educational Resources Information Center

    Lemons, Judith L.

    The purpose of this safety manual is to provide a resource to help manage and minimize potential risks in science classrooms where students spend up to 60% of instructional time engaged in hands-on activities. Information on general laboratory safety, science equipment safety, safety with plants, safety with animals, safety with chemicals, field…

  16. Phytotherapy in the management of psoriasis: a review of the efficacy and safety of oral interventions and the pharmacological actions of the main plants.

    PubMed

    Deng, Shiqiang; May, Brian H; Zhang, Anthony L; Lu, Chuanjian; Xue, Charlie C L

    2014-04-01

    This review provides assessments of the efficacy and safety of oral forms of phytotherapy in psoriasis management and discusses the pharmacological actions of the plants that have been frequently used in clinical trials. It employed the methods described in the Cochrane Handbook. Ten randomized controlled trials that compared a plant-based intervention with placebo or a pharmacotherapy in the treatment of psoriasis vulgaris and used Psoriasis Area Severity Index (PASI) as an outcome measure were included. Superiority to placebo was found in two out of three studies. In six out of seven studies, the effect of the phytotherapy was reported as comparable to the pharmacotherapy in the short term when assessed as PASI 50. The safety of the phytotherapies was discussed. The most commonly used plants were Oldenlandia diffusa, Rehmannia glutinosa and Salvia miltiorrhiza. Experimental studies on extracts and compounds derived from these plants have reported anti-inflammatory, anti-proliferative and other actions of relevance to psoriasis management. These properties may account for the apparent actions of some of the phytotherapies used in these clinical studies. These plants and their active constituents appear to warrant further research attention in the search for future medications for psoriasis. PMID:24253308

  17. Nuclear Powerplant Safety: Operations.

    ERIC Educational Resources Information Center

    Department of Energy, Washington, DC. Nuclear Energy Office.

    Powerplant systems and procedures that ensure the day-to-day health and safety of people in and around the plant is referred to as operational safety. This safety is the result of careful planning, good engineering and design, strict licensing and regulation, and environmental monitoring. Procedures that assure operational safety at nuclear…

  18. Weak tradeoff between xylem safety and xylem-specific hydraulic efficiency across the world's woody plant species.

    PubMed

    Gleason, Sean M; Westoby, Mark; Jansen, Steven; Choat, Brendan; Hacke, Uwe G; Pratt, Robert B; Bhaskar, Radika; Brodribb, Tim J; Bucci, Sandra J; Cao, Kun-Fang; Cochard, Hervé; Delzon, Sylvain; Domec, Jean-Christophe; Fan, Ze-Xin; Feild, Taylor S; Jacobsen, Anna L; Johnson, Daniel M; Lens, Frederic; Maherali, Hafiz; Martínez-Vilalta, Jordi; Mayr, Stefan; McCulloh, Katherine A; Mencuccini, Maurizio; Mitchell, Patrick J; Morris, Hugh; Nardini, Andrea; Pittermann, Jarmila; Plavcová, Lenka; Schreiber, Stefan G; Sperry, John S; Wright, Ian J; Zanne, Amy E

    2016-01-01

    The evolution of lignified xylem allowed for the efficient transport of water under tension, but also exposed the vascular network to the risk of gas emboli and the spread of gas between xylem conduits, thus impeding sap transport to the leaves. A well-known hypothesis proposes that the safety of xylem (its ability to resist embolism formation and spread) should trade off against xylem efficiency (its capacity to transport water). We tested this safety-efficiency hypothesis in branch xylem across 335 angiosperm and 89 gymnosperm species. Safety was considered at three levels: the xylem water potentials where 12%, 50% and 88% of maximal conductivity are lost. Although correlations between safety and efficiency were weak (r(2)  < 0.086), no species had high efficiency and high safety, supporting the idea for a safety-efficiency tradeoff. However, many species had low efficiency and low safety. Species with low efficiency and low safety were weakly associated (r(2)  < 0.02 in most cases) with higher wood density, lower leaf- to sapwood-area and shorter stature. There appears to be no persuasive explanation for the considerable number of species with both low efficiency and low safety. These species represent a real challenge for understanding the evolution of xylem. PMID:26378984

  19. Hand Safety

    MedlinePlus

    ... en gatillo See More... Hand Anatomy Hand Safety Fireworks Safety Lawnmower Safety Snowblower safety Pumpkin Carving Gardening ... en gatillo See More... Hand Anatomy Hand Safety Fireworks Safety Lawnmower Safety Snowblower safety Pumpkin Carving Gardening ...

  20. Hand Safety

    MedlinePlus

    ... Fireworks Safety Lawnmower Safety Snowblower safety Pumpkin Carving Gardening Safety Turkey Carving Removing a Ring Español Artritis ... Fireworks Safety Lawnmower Safety Snowblower safety Pumpkin Carving Gardening Safety Turkey Carving Removing a Ring Español Artritis ...

  1. The Influence of Individual and Team Cognitive Ability on Operators’ Task and Safety Performance: A Multilevel Field Study in Nuclear Power Plants

    PubMed Central

    Zhang, Jingyu; Li, Yongjuan; Wu, Changxu

    2013-01-01

    While much research has investigated the predictors of operators’ performance such as personality, attitudes and motivation in high-risk industries, its cognitive antecedents and boundary conditions have not been fully investigated. Based on a multilevel investigation of 312 nuclear power plant main control room operators from 50 shift teams, the present study investigated how general mental ability (GMA) at both individual and team level can influence task and safety performance. At the individual level, operators’ GMA was predictive of their task and safety performance and this trend became more significant as they accumulated more experience. At the team level, we found team GMA had positive influences on all three performance criteria. However, we also found a “big-fish-little-pond” effect insofar as team GMA had a relatively smaller effect and inhibited the contribution of individual GMA to workers’ extra-role behaviors (safety participation) compared to its clear beneficial influence on in-role behaviors (task performance and safety compliance). The possible mechanisms related to learning and social comparison processes are discussed. PMID:24391964

  2. The influence of individual and team cognitive ability on operators' task and safety performance: a multilevel field study in nuclear power plants.

    PubMed

    Zhang, Jingyu; Li, Yongjuan; Wu, Changxu

    2013-01-01

    While much research has investigated the predictors of operators' performance such as personality, attitudes and motivation in high-risk industries, its cognitive antecedents and boundary conditions have not been fully investigated. Based on a multilevel investigation of 312 nuclear power plant main control room operators from 50 shift teams, the present study investigated how general mental ability (GMA) at both individual and team level can influence task and safety performance. At the individual level, operators' GMA was predictive of their task and safety performance and this trend became more significant as they accumulated more experience. At the team level, we found team GMA had positive influences on all three performance criteria. However, we also found a "big-fish-little-pond" effect insofar as team GMA had a relatively smaller effect and inhibited the contribution of individual GMA to workers' extra-role behaviors (safety participation) compared to its clear beneficial influence on in-role behaviors (task performance and safety compliance). The possible mechanisms related to learning and social comparison processes are discussed. PMID:24391964

  3. Operational safety enhancement of Soviet-designed nuclear reactors via development of nuclear power plant simulators and transfer of related technology

    SciTech Connect

    Kohut, P.; Epel, L.G.; Tutu, N.K.

    1998-08-01

    The US Department of Energy (DOE), under the US government`s International Nuclear Safety Program (INSP), is implementing a program of developing and providing simulators for many of the Russian and Ukrainian Nuclear Power Plants (NPPs). Pacific Northwest National Laboratory (PNNL) and Brookhaven National Laboratory (BNL) manage and provide technical oversight of the various INSP simulator projects for DOE. The program also includes a simulator technology transfer process to simulator design organizations in Russia and Ukraine. Training programs, installation of new simulators, and enhancements in existing simulators are viewed as providing a relatively fast and cost-effective technology transfer that will result in measurable improvement in the safety culture and operation of NPPs. A review of this program, its present status, and its accomplishments are provided in this paper.

  4. Aging and service wear of spring-loaded pressure relief valves used in safety-related systems at nuclear power plants

    SciTech Connect

    Staunton, R.H.; Cox, D.F.

    1995-03-01

    Spring-loaded pressure relief valves (PRVS) are used in some safety-related applications at nuclear power plants. In general, they are used in systems where, during accidents, pressures may rise to levels where pressure safety relief is required for protection of personnel, system piping, and components. This report documents a study of PRV aging and considers the severity and causes of service wear and how it is discovered and corrected in various systems, valve sizes, etc. Provided in this report are results of the examination of the recorded failures and identification of trends and relationships/correlations in the failures when all failure-related parameters are considered. Components that comprise a typical PRV, how those components fail, when they fail, and the current testing frequencies and methods are also presented in detail.

  5. Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). Supplement No. 18

    SciTech Connect

    Tam, P.S.

    1995-10-01

    In June 1982, the Nuclear Regulatory Commission staff (NRC staff or staff) issued a Safety Evaluation Report, NUREG-0847, regarding the application by the Tennessee Valley Authority (TVA or the applicant) for licenses to operate the Watts Bar Nuclear Plant, Units 1 and 2. Each of the following sections and appendices of this supplement is numbered the same as the section or appendix of the SER that is being updated, and the discussions are supplementary to, and not in lieu of, the discussion in the SER, unless otherwise noted. Accordingly, Appendix A continues the chronology of the safety review. Appendix E lists principal contributors to this supplement. Appendix FF is added in this supplement. The other appendices are not changed by this supplement.

  6. Secondary Alveolar Bone Grafting (CLEFTSiS) 2007-2010.

    PubMed

    Paterson, Michael; Rae, Jennifer; Paterson, Paul; Gilgrass, Toby; Devlin, Mark; McIntyre, Grant

    2016-03-01

    Objective To determine whether alveolar bone graft outcomes for unilateral and bilateral cleft lip and palate patients have continued to improve since the reorganization of cleft services in Scotland in 2000. Design Retrospective analysis of postoperative anterior occlusal radiographs. Patients and Participants Eighty-one of 106 patients who were eligible for alveolar bone grafting between 2007 and 2010 had suitable postoperative radiographs available. Interventions Twenty-seven percent of the patients (n = 22) had presurgical orthodontic intervention. All patients underwent alveolar bone grafting with bone harvested from the iliac crest. Main Outcome Measures The Kindelan bone-fill index was used to evaluate success. Weighted kappa statistics were used to assess intra- and interobserver reproducibility. A comparison was made with results from 2000 to 2004 to assess any improvement. Chi-square tests (or Fisher exact test) were used to determine whether outcomes differed depending on the laterality of the cleft, use of presurgical expansion, or age at bone grafting. Results Interobserver scoring agreement was good (weighted kappa = .383). Intraobserver reproducibility was greater (weighted kappas of .835 and .620). Success was achieved in 99% of bone grafts, compared with 76% in the period from 2000 to 2004 (P < .001). There was no statistically significant relationship between the laterality of the cleft (P = 1.000), use of presurgical expansion (P = 1.000), or age at time of bone grafting and outcome (P = .259). Conclusion Scottish secondary alveolar bone graft outcomes improved during 2007 to 2010 in comparison to the 2000 to 2004 results. PMID:26914161

  7. Definition and Means of Maintaining the Emergency Notification and Evacuation System Portion of the Plutonium Finishing Plant (PFP) Safety Envelope

    SciTech Connect

    WHITE, W.F.

    2000-04-04

    The purpose of this document is to provide the definition and means of maintaining the safety envelope (SE) for the Emergency Notification and Evacuation System (ENES). Together with the appendices, it provides: (1) The system requirements for determining system operability (Section 3.0); (2) Evaluations of equipment to determine the safety boundary for the system (Section 4.0); (3) List of system drawings that are annotated to show the SE boundaries (Appendix A); (4) Identification of the SE equipment by reference to systems and drawings (Appendix B); (5) Requirements for the individual SE equipment (Section 4.0); and (6) A list of the operational and surveillance procedures necessary to operate and maintain the system equipment within the SE (Sections 5.0 and 6.0). The Private Automatic Exchange (PAX) phones and PAX switchers are outside the safety envelope defined in WHC-SD-CP-OSR-010, Section 5.4.10, ''Safety Communication and Alarm Systems,'' Section 5.4.1 0.1, ''Major Components and Operating Characteristics,'' and Section 5.4.10.1.12, ''PAX System.'' The PAX override microphone system maintains the safety envelope, and functions as a backup to the evacuation sirens during an emergency.

  8. [Health care safety should be focused on prevention. Lessons to be learned from aviation, nuclear power plants and offshore industries].

    PubMed

    Odegård, S

    1999-06-23

    In many respects the approach to questions of safety adopted in the aviation, nuclear energy and offshore oil industries is highly relevant to safety in the health care sector, even where legislation is concerned. Characteristic features are the emphasis on risk-factor identification, and such demands as risk analysis, knowledge checks, and the limitation of working hours. In addition, there is a need of disaster inquiries in cases of serious incidents, and of an organisation specifically responsible for safety issues. Regarding the development of an incident report system for use in health care, the importance of which increases with the risks involved, a commendable model is the risk report system adopted by civil aviation authorities in the USA, where those submitting reports are guaranteed immunity. PMID:10418254

  9. Review guidelines for software languages for use in nuclear power plant safety systems: Final report. Revision 1

    SciTech Connect

    Hecht, M.; Decker, D.; Graff, S.; Green, W.; Lin, D.; Dinsmore, G.; Koch, S.

    1997-10-01

    Guidelines for the programming and auditing of software written in high level languages for safety systems are presented. The guidelines are derived from a framework of issues significant to software safety which was gathered from relevant standards and research literature. Language-specific adaptations of these guidelines are provided for the following high level languages: Ada83 and Ada95; C and C++; International Electrochemical Commission (IEC) Standard 1131-3 Ladder Logic, Sequential Function Charts, Structured Text, and Function Block Diagrams; Pascal; and PL/M. Appendices to the report include a tabular summary of the guidelines and additional information on selected languages.

  10. Site plan safety submission for sampling, monitoring, decontamination of GB agent - north plant Rocky Mountain Arsenal. Volume 1

    SciTech Connect

    Not Available

    1988-10-01

    The scope of this site plan safety submission (SPSS), includes: sampling plan to determine if GB is a contaminant in equipment and piping used in the production and demil processes; monitoring plan for personnel involved in the sampling effort; decon plan for personnel, equipment, and piping should contamination be identified. Additional sections and appendices include: historical use of bldg 1501, 1503, 1504, 1506, 1601, 1602, 1603, 1606; chemical information on GB; safety requirements; medical requirements and first aid procedures; piping drawings; rma sop's for sampling, monitoring, and decon.

  11. Site plan safety submission for sampling, monitoring and decontamination of mustard agent, South Plant, Rocky Mountain Arsenal. Volume 1

    SciTech Connect

    Not Available

    1988-10-01

    The scope of this site plan safety submission (SPSS) includes: (1) Sampling plan to determine if H is a contaminant in Equipment and piping used in the 1970's for the H DEMIL program; (2) Monitoring plan for personnel involved in the sampling effort; and (3) Decon plan for personnel, equipment, and piping should contamination be identified. Additional sections and appendices include: (1) Historical use of Bld 637 and Bld 538; (2) Chemical information on H, HD, and HT; (3) Safety requirements; (4) Medical requirements and first aid procedures; (5) Piping drawings; and (6) RMA SOP's for sampling, monitoring, and decon.

  12. Meat Processing Plant Microbiome and Contamination Patterns of Cold-Tolerant Bacteria Causing Food Safety and Spoilage Risks in the Manufacture of Vacuum-Packaged Cooked Sausages

    PubMed Central

    Rahkila, Riitta; Ali, Javeria; Rousu, Juho; Björkroth, K. Johanna

    2015-01-01

    Refrigerated food processing facilities are specific man-made niches likely to harbor cold-tolerant bacteria. To characterize this type of microbiota and study the link between processing plant and product microbiomes, we followed and compared microbiota associated with the raw materials and processing stages of a vacuum-packaged, cooked sausage product affected by a prolonged quality fluctuation with occasional spoilage manifestations during shelf life. A total of 195 samples were subjected to culturing and amplicon sequence analyses. Abundant mesophilic psychrotrophs were detected within the microbiomes throughout the different compartments of the production plant environment. However, each of the main genera of food safety and quality interest, e.g., Leuconostoc, Brochothrix, and Yersinia, had their own characteristic patterns of contamination. Bacteria from the genus Leuconostoc, commonly causing spoilage of cold-stored, modified-atmosphere-packaged foods, were detected in high abundance (up to >98%) in the sausages studied. The same operational taxonomic units (OTUs) were, however, detected in lower abundances in raw meat and emulsion (average relative abundance of 2% ± 5%), as well as on the processing plant surfaces (<4%). A completely different abundance profile was found for OTUs phylogenetically close to the species Yersinia pseudotuberculosis. These OTUs were detected in high abundance (up to 28%) on the processing plant surfaces but to a lesser extent (<1%) in raw meat, sausage emulsion, and sausages. The fact that Yersinia-like OTUs were found on the surfaces of a high-hygiene packaging compartment raises food safety concerns related to their resilient existence on surfaces. PMID:26231646

  13. Meat Processing Plant Microbiome and Contamination Patterns of Cold-Tolerant Bacteria Causing Food Safety and Spoilage Risks in the Manufacture of Vacuum-Packaged Cooked Sausages.

    PubMed

    Hultman, Jenni; Rahkila, Riitta; Ali, Javeria; Rousu, Juho; Björkroth, K Johanna

    2015-10-01

    Refrigerated food processing facilities are specific man-made niches likely to harbor cold-tolerant bacteria. To characterize this type of microbiota and study the link between processing plant and product microbiomes, we followed and compared microbiota associated with the raw materials and processing stages of a vacuum-packaged, cooked sausage product affected by a prolonged quality fluctuation with occasional spoilage manifestations during shelf life. A total of 195 samples were subjected to culturing and amplicon sequence analyses. Abundant mesophilic psychrotrophs were detected within the microbiomes throughout the different compartments of the production plant environment. However, each of the main genera of food safety and quality interest, e.g., Leuconostoc, Brochothrix, and Yersinia, had their own characteristic patterns of contamination. Bacteria from the genus Leuconostoc, commonly causing spoilage of cold-stored, modified-atmosphere-packaged foods, were detected in high abundance (up to >98%) in the sausages studied. The same operational taxonomic units (OTUs) were, however, detected in lower abundances in raw meat and emulsion (average relative abundance of 2%±5%), as well as on the processing plant surfaces (<4%). A completely different abundance profile was found for OTUs phylogenetically close to the species Yersinia pseudotuberculosis. These OTUs were detected in high abundance (up to 28%) on the processing plant surfaces but to a lesser extent (<1%) in raw meat, sausage emulsion, and sausages. The fact that Yersinia-like OTUs were found on the surfaces of a high-hygiene packaging compartment raises food safety concerns related to their resilient existence on surfaces. PMID:26231646

  14. Weak tradeoff between xylem safety and xylem-specific hydraulic efficiency across the world’s woody plant species

    Technology Transfer Automated Retrieval System (TEKTRAN)

    • The evolution of lignified xylem allowed for the efficient transport of water under tension, but also exposed the vascular network to the risk of gas emboli and the spread of gas between xylem conduits, thus impeding sap transport to the leaves. A well-known hypothesis proposes that the safety of...

  15. Intervention technologies for food safety on minimally processed produce:Perspectives on food-borne and plant pathogens

    Technology Transfer Automated Retrieval System (TEKTRAN)

    Produce contamination associated with enteric pathogens such Escherichia coli O157:H7, salmonella spp., Listeria monocytogenes, Shigella and others are significant challenges to food safety. This is due to the illnesses and economic impacts resulting from the outbreaks. Innovative technologies for i...

  16. Evaluation of purity of certain pediatric preparations of plant origin and its significance for the safety of pharmacotherapy microbiological contamination of pediatric preparations of plant origin.

    PubMed

    Figura, Barbara; Pluta, Janusz

    2006-01-01

    Microorganisms inhabiting medicinal plants belong to either saprophytic or pathogenic flora. Even those microorganisms which are characterized by low pathogenicity, under favorable conditions may infect people who have had contact with them. Compound tea bags contain increased levels of bacteria in view of pharmacopoeic norms. Single plant tea bags contain less bacteria and granulated teas have the lowest content. On the other hand, the latter reveal higher level of fungal contamination. Processing of herbs, including brewing decreases the amount of microorganisms in herbal products. PMID:17438867

  17. Safety evaluation of the double mutant 5-enol pyruvylshikimate-3-phosphate synthase (2mEPSPS) from maize that confers tolerance to glyphosate herbicide in transgenic plants.

    PubMed

    Herouet-Guicheney, Corinne; Rouquié, David; Freyssinet, Martine; Currier, Thomas; Martone, Aris; Zhou, Junguo; Bates, Elizabeth E M; Ferullo, Jean-Marc; Hendrickx, Koen; Rouan, Dominique

    2009-07-01

    Glyphosate tolerance can be conferred by decreasing the herbicide's ability to inhibit the enzyme 5-enol pyruvylshikimate-3-phosphate synthase, which is essential for the biosynthesis of aromatic amino acids in all plants, fungi, and bacteria. Glyphosate tolerance is based upon the expression of the double mutant 5-enol pyruvylshikimate-3-phosphate synthase (2mEPSPS) protein. The 2mEPSPS protein, with a lower binding affinity for glyphosate, is highly resistant to the inhibition by glyphosate and thus allows sufficient enzyme activity for the plants to grow in the presence of herbicides that contain glyphosate. Based on both a review of published literature and experimental studies, the potential safety concerns related to the transgenic 2mEPSPS protein were assessed. The safety evaluation supports that the expressed protein is innocuous. The 2mEPSPS enzyme does not possess any of the properties associated with known toxins or allergens, including a lack of amino acid sequence similarity to known toxins and allergens, a rapid degradation in simulated gastric and intestinal fluids, and no adverse effects in mice after intravenous or oral administration (at 10 or 2000 mg/kg body weight, respectively). In conclusion, there is a reasonable certainty of no harm resulting from the inclusion of the 2mEPSPS protein in human food or in animal feed. PMID:19303906

  18. Health and safety plan for phase II of the Bear Creek Valley treatability study Oak Ridge Y-12 plant, Oak Ridge, Tennessee

    SciTech Connect

    1997-05-01

    This Health and Safety Plan (HASP) addresses the health and safety (H&S) concerns and requirements for the Bear Creek Valley (BCV) Treatability Study at the Oak Ridge Y-12 Plant. Samples will be collected from effluent following treatment tests of extraction columns, algal mats, and mature wetlands supplied by surface water locations and existing groundwater monitoring well locations. The project Sampling and Analysis Plan addresses the project description, technical objectives, procedures, and planned work activities in greater detail. It is the responsibility of the project managers, field manager, and site health and safety officer (SHSO) to determine that the requirements of this HASP are sufficiently protective. If it is determined that the requirements of this HASP are not sufficiently protective, a field change order(s) (FCO) will be prepared. FCOs will include a completed job hazard analysis or similar worksheet to ensure complete hazard assessment. FCOs must be approved by the Environmental Management and Enrichment Facilities (EMEF) project manager, EMEF H&S manager, subcontractor project or field manager, and subcontractor H&S representative. As a minimum, FCOs will be prepared if additional tasks will be performed or if contaminant exposure is anticipated.

  19. The relevance of gene transfer to the safety of food and feed derived from genetically modified (GM) plants.

    PubMed

    van den Eede, G; Aarts, H; Buhk, H-J; Corthier, G; Flint, H J; Hammes, W; Jacobsen, B; Midtvedt, T; van der Vossen, J; von Wright, A; Wackernagel, W; Wilcks, A

    2004-07-01

    In 2000, the thematic network ENTRANSFOOD was launched to assess four different topics that are all related to the testing or assessment of food containing or produced from genetically modified organisms (GMOs). Each of the topics was linked to a European Commission (EC)-funded large shared cost action (see http://www.entransfood.com). Since the exchange of genetic information through horizontal (lateral) gene transfer (HGT) might play a more important role, in quantity and quality, than hitherto imagined, a working group dealing with HGT in the context of food and feed safety was established. This working group was linked to the GMOBILITY project (GMOBILITY, 2003) and the results of the deliberations are laid down in this review paper. HGT is reviewed in relation to the potential risks of consuming food or feed derived from transgenic crops. First, the mechanisms for obtaining transgenic crops are described. Next, HGT mechanisms and its possible evolutionary role are described. The use of marker genes is presented in detail as a special case for genes that may pose a risk. Furthermore, the exposure to GMOs and in particular to genetically modified (GM) deoxyribonucleic acid (DNA) is discussed as part of the total risk assessment. The review finishes off with a number of conclusions related to GM food and feed safety. The aim of this paper is to provide a comprehensive overview to assist risk assessors as well as regulators and the general public in understanding the safety issues related to these mechanisms. PMID:15123384

  20. Aging and service wear of check valves used in engineered safety-feature systems of nuclear power plants: Aging assessments and monitoring method evaluations

    SciTech Connect

    Haynes, H.D. )

    1991-04-01

    Check valves are used extensively in nuclear power plant safety systems and balance-of-plant systems. The failures of these valves have resulted in significant maintenance efforts and, on occasion, have resulted in water hammer, overpressurization of low-pressure systems, and damage to flow system components. These failures have largely been attributed to severe degradation of internal parts (e.g., hinge pins, hinge arms, discs, and disc nut pins) resulting from instability (flutter) of check valve discs under normal plant operating conditions. Present surveillance requirements for nuclear power plant check valves have been inadequate for timely detection and trending of such degradation because neither the flutter nor the resulting wear can be detected prior to failure. Consequently, the US Nuclear Regulatory Commission has had a continuing strong interest in resolving check valve problems. In support of the Nuclear Plant Aging Research Program, Oak Ridge National Laboratory has carried out an evaluation of several developmental and/or commercially available check valve diagnostic monitoring methods, in particular, those based on measurements of acoustic emission, ultrasonics, and magnetic flux. In each case, the evaluations have been focused on the capability of each method to provide diagnostic information useful in determining check valve aging and service wear effects (degradation), check valve failures, and undesirable operating modes. A description of each monitoring method is provided in this report, including examples of test data acquired under controlled laboratory conditions. In some cases, field test data acquired in situ are also presented. The methods are compared, and suggested areas in need of further development are identified. 6 refs., 36 figs., 7 tabs.

  1. Reactor safety assessment system

    SciTech Connect

    Sebo, D.E.; Bray, M.A.; King, M.A.

    1987-01-01

    The Reactor Safety Assessment System (RSAS) is an expert system under development for the United States Nuclear Regulatory Commission (USNRC). RSA is designed for use at the USNRC Operations Center in the event of a serious incident at a licensed nuclear power plant. RSAS is a situation assessment expert system which uses plant parametric data to generate conclusions for use by the NRC Reactor Safety Team. RSAS uses multiple rule bases and plant specific setpoint files to be applicable to all licensed nuclear power plants in the United States. RSAS currently covers several generic reactor categories and multiple plants within each category.

  2. 76 FR 73737 - Notice of Opportunity for Public Comment on the Proposed Model Safety Evaluation for Plant...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-11-29

    ... Documents Access and Management System (ADAMS) under Accession Number ML111650552; the model application is available in ADAMS under Accession Number ML112850506. The proposed model SE for plant-specific adoption of TSTF-505, Revision 1, is available electronically under ADAMS Accession Number ML112690239....

  3. Nuclear safety

    NASA Technical Reports Server (NTRS)

    Buden, D.

    1991-01-01

    Topics dealing with nuclear safety are addressed which include the following: general safety requirements; safety design requirements; terrestrial safety; SP-100 Flight System key safety requirements; potential mission accidents and hazards; key safety features; ground operations; launch operations; flight operations; disposal; safety concerns; licensing; the nuclear engine for rocket vehicle application (NERVA) design philosophy; the NERVA flight safety program; and the NERVA safety plan.

  4. Medicinal Plants.

    ERIC Educational Resources Information Center

    Phillipson, J. David

    1997-01-01

    Highlights the demand for medicinal plants as pharmaceuticals and the demand for health care treatments worldwide and the issues that arise from this. Discusses new drugs from plants, anticancer drugs, antiviral drugs, antimalarial drugs, herbal remedies, quality, safety, efficacy, and conservation of plants. Contains 30 references. (JRH)

  5. Initial Assessment of Sulfur-Iodine Process Safety Issues and How They May Affect Pilot Plant Design and Operation

    SciTech Connect

    Robert S. Cherry

    2006-09-01

    The sulfur-iodine process to make hydrogen by the thermochemical splitting of water is under active development as part of a U.S. Department of Energy program. An integrated lab scale system is currently being designed and built. The next planned stage of development is a pilot plant with a thermal input of about 500 kW, equivalent to about 30,000 standard liters per hour of hydrogen production. The sulfur-iodine process contains a variety of hazards, including temperatures up to 850 ºC and hazardous chemical species including SO2, H2SO4, HI, I2, and of course H2. The siting and design of a pilot plant must consider these and other hazards. This report presents an initial analysis of the hazards that might affect pilot plant design and should be considered in the initial planning. The general hazards that have been identified include reactivity, flammability, toxicity, pressure, electrical hazards, and industrial hazards such as lifting and rotating equipment. Personnel exposure to these hazards could occur during normal operations, which includes not only running the process at the design conditions but also initial inventory loading, heatup, startup, shutdown, and system flushing before equipment maintenance. Because of the complexity and severity of the process, these ancillary operations are expected to be performed frequently. In addition, personnel could be exposed to the hazards during various abnormal situations which could include unplanned phase changes of liquids or solids, leaks of process fluids or cooling water into other process streams, unintentional introducion of foreign species into the process, and unexpected side reactions. Design of a pilot plant will also be affected by various codes and regulations such as the International Building Code, the International Fire Code, various National Fire Protection Association Codes, and the Emergency Planning and Community Right-to-Know Act.

  6. Risk-informed regulation and safety management of nuclear power plants--on the prevention of severe accidents.

    PubMed

    Himanen, Risto; Julin, Ari; Jänkälä, Kalle; Holmberg, Jan-Erik; Virolainen, Reino

    2012-11-01

    There are four operating nuclear power plant (NPP) units in Finland. The Teollisuuden Voima (TVO) power company has two 840 MWe BWR units supplied by Asea-Atom at the Olkiluoto site. The Fortum corporation (formerly IVO) has two 500 MWe VVER 440/213 units at the Loviisa site. In addition, a 1600 MWe European Pressurized Water Reactor supplied by AREVA NP (formerly the Framatome ANP--Siemens AG Consortium) is under construction at the Olkiluoto site. Recently, the Finnish Parliament ratified the government Decision in Principle that the utilities' applications to build two new NPP units are in line with the total good of the society. The Finnish utilities, Fenno power company, and TVO company are in progress of qualifying the type of the new nuclear builds. In Finland, risk-informed applications are formally integrated in the regulatory process of NPPs that are already in the early design phase and these are to run through the construction and operation phases all through the entire plant service time. A plant-specific full-scope probabilistic risk assessment (PRA) is required for each NPP. PRAs shall cover internal events, area events (fires, floods), and external events such as harsh weather conditions and seismic events in all operating modes. Special attention is devoted to the use of various risk-informed PRA applications in the licensing of Olkiluoto 3 NPP. PMID:23035957

  7. The (safety-related) heat exchangers aging management guideline for commercial nuclear power plants, and developments since 1994

    SciTech Connect

    Clauss, J.M.

    1998-08-01

    The US Department of Energy (DOE), in cooperation with the Electric Power Research Institute (EPRI) and US nuclear power plant utilities, is preparing a series of aging management guidelines (AMGs) for commodity types of components (e.g., heat exchangers, electrical cable and terminations, pumps). Commodities are included in this series based on their importance to continued nuclear plant operation and license renewal. The AMGs contain a detailed summary of operating history, stressors, aging mechanisms, and various types of maintenance and surveillance practices that can be combined to create an effective aging management program. Each AMG is intended for use by the systems engineers and plant maintenance staff (i.e., an AMG is intended to be a hands-on technical document rather than a licensing document). The heat exchangers AMG, published in June 1994, includes the following information of interest to nondestructive examination (NDE) personnel: aging mechanisms determined to be non-significant for all applications; aging mechanisms determined to be significant for some applications; effective conventional programs for managing aging; and effective unconventional programs for managing aging. Since the AMG on heat exchangers was published four years ago, a brief review has been conducted to identify emerging regulatory issues, if any. The results of this review and lessons learned from the collective set of AMGs are presented.

  8. Experimental investigations of thermal-hydraulic processes arising during operation of the passive safety systems used in new projects of nuclear power plants equipped with VVER reactors

    NASA Astrophysics Data System (ADS)

    Morozov, A. V.; Remizov, O. V.; Kalyakin, D. S.

    2014-05-01

    The results obtained from experimental investigations into thermal-hydraulic processes that take place during operation of the passive safety systems used in new-generation reactor plants constructed on the basis of VVER technology are presented. The experiments were carried out on the model rigs available at the Leipunskii Institute for Physics and Power Engineering. The processes through which interaction occurs between the opposite flows of saturated steam and cold water moving in the vertical steam line of the additional system for passively flooding the core from the second-stage hydro accumulators are studied. The specific features pertinent to undeveloped boiling of liquid on a single horizontal tube heated by steam and steam-gas mixture that is typical for of the condensing operating mode of a VVER reactor steam generator are investigated.

  9. Summary of the contractor information exchange meeting for improving the safety of Soviet-Designed Nuclear Power Plants, February 19, 1997

    SciTech Connect

    1997-04-01

    This report summarizes a meeting held on February 19, 1997, in Washington, D.C. The meeting was held primarily to exchange information among the contractors involved in the U.S. Department of Energy`s efforts to improve the safety of Soviet-designed nuclear power plants. Previous meetings have been held on December 5-6, 1995, and May 22, 1996. The meetings are sponsored by the U.S. Department of Energy and coordinated by the Pacific Northwest National Laboratory. The U.S. Department of Energy works with countries to increase the level of safety at 63 Soviet-designed nuclear reactors operating in Armenia, Bulgaria, the Czech Republic, Hungary, Lithuania, Russia, Slovakia, and Ukraine. The work is implemented largely by commercial companies and individuals who provide technologies and services to the countries with Soviet-designed nuclear power plants. Attending the meeting were 71 representatives of commercial contractors, the U.S. Department of Energy, the U.S. Department of State, national laboratories, and other federal agencies. The presentations and discussions that occurred during the exchange are summarized in this report. While this report captures the general presentation and discussion points covered at the meeting, it is not a verbatim, inclusive record. To make the report useful, information presented at the meeting has been expanded to clarify issues, respond to attendees` requests, or place discussion points in a broader programmatic context. Appendixes A through F contain the meeting agenda, list of attendees, copies of presentation visuals and handouts, the Strategy Document discussed at the meeting, and a summary of attendees` post-meeting evaluation comments. As with past information exchanges, the participants found this meeting valuable and useful. In response to the participant`s requests, a fourth information exchange will be held later in 1997.

  10. Food safety knowledge on the Bt mutant protein Cry8Ka5 employed in the development of coleopteran-resistant transgenic cotton plants.

    PubMed

    Farias, Davi F; Peijnenburg, Ad A C M; Grossi-de-Sá, Maria F; Carvalho, Ana F U

    2015-01-01

    Insecticidal Cry proteins from Bacillus thuringiensis (Bt) have been exploited in the development of genetically modified (GM) crops for pest control. However, several pests are still difficult to control such as the coleopteran boll weevil Anthonomus grandis. By applying in vitro molecular evolution to the cry8Ka1 gene sequence, variants were generated with improved activity against A. grandis. Among them, Cry8Ka5 mutant protein showed coleoptericidal activity 3-fold higher (LC50 2.83 μg/mL) than that of the original protein (Cry8Ka1). Cry8Ka5 has been used in breeding programs in order to obtain coleopteran-resistant cotton plants. Nevertheless, there is some concern in relation to the food safety of transgenic crops, especially to the heterologously expressed proteins. In this context, our research group has performed risk assessment studies on Cry8Ka5, using the tests recommended by Codex as well as tests that we proposed as alternative and/or complementary approaches. Our results on the risk analysis of Cry8Ka5 taken together with those of other Cry proteins, point out that there is a high degree of certainty on their food safety. It is reasonable to emphasize that most safety studies on Cry proteins have essentially used the Codex approach. However, other methodologies would potentially provide additional information such as studies on the effects of Cry proteins and derived peptides on the indigenous gastrointestinal microbiota and on intestinal epithelial cells of humans. Additionally, emerging technologies such as toxicogenomics potentially will offer sensitive alternatives for some current approaches or methods. PMID:26513483

  11. Recommendations from the workshop on Comparative Approaches to Safety Assessment of GM Plant Materials: A road toward harmonized criteria?

    PubMed

    Bartholomaeus, Andrew; Batista, Juan Carlos; Burachik, Moisés; Parrott, Wayne

    2015-01-01

    An international meeting of genetically modified (GM) food safety assessors from the main importing and exporting countries from Asia and the Americas was held in Buenos Aires, Argentina, between June 26(th) and 28(th), 2013. Participants shared their evaluation approaches, identified similarities and challenges, and used their experience to propose areas for future work. Recommendations for improving risk assessment procedures and avenues for future collaboration were also discussed. The deliberations of the meeting were also supported by a survey of participants which canvassed risk assessment approaches across the regions from which participants came. This project was initiated by Argentine Agri-Food Health and Quality National Service (SENASA, Ministry of Agriculture, Argentina), with the support of the International Life Sciences Institute (ILSI) and other partner institutions. The importance of making all possible efforts toward more integrated and harmonized regulatory oversight for GM organisms (GMOs) was strongly emphasized. This exercise showed that such harmonization is a feasible goal that would contribute to sustain a fluid trade of commodities and ultimately enhance food security. Before this can be achieved, key issues identified in this meeting will have to be addressed in the near future to enable regulatory collaboration or joint work. The authors propose that the recommendations coming out of the meeting should be used as a basis for continuing work, follow up discussions and concrete actions. PMID:25706477

  12. Food Safety by Using Machine Learning for Automatic Classification of Seeds of the South-American Incanut Plant

    NASA Astrophysics Data System (ADS)

    Lemanzyk, Thomas; Anding, Katharina; Linss, Gerhard; Rodriguez Hernández, Jorge; Theska, René

    2015-02-01

    The following paper deals with the classification of seeds and seed components of the South-American Incanut plant and the modification of a machine to handle this task. Initially the state of the art is being illustrated. The research was executed in Germany and with a relevant part in Peru and Ecuador. Theoretical considerations for the solution of an automatically analysis of the Incanut seeds were specified. The optimization of the analyzing software and the separation unit of the mechanical hardware are carried out with recognition results. In a final step the practical application of the analysis of the Incanut seeds is held on a trial basis and rated on the bases of statistic values.

  13. Summary and bibliography of safety-related events at boiling-water nuclear power plants as reported in 1980

    SciTech Connect

    McCormack, K.E.; Gallaher, R.B.

    1982-03-01

    This document presents a bibliography that contains 100-word abstracts of event reports submitted to the US Nuclear Regulatory Commission concerning operational events that occurred at boiling-water-reactor nuclear power plants in 1980. The 1547 abstracts included on microfiche in this bibliography describe incidents, failures, and design or construction deficiencies that were experienced at the facilities. These abstracts are arranged alphabetically by reactor name and then chronologically for each reactor. Full-size keyword and permuted-title indexes to facilitate location of individual abstracts are provided following the text. Tables that summarize the information contained in the bibliography are also provided. The information in the tables includes a listing of the equipment items involved in the reported events and the associated number of reports for each item. Similar information is given for the various kinds of instrumentation and systems, causes of failures, deficiencies noted, and the time of occurrence (i.e., during refueling, operation, testing, or construction).

  14. Thermal reactor safety

    SciTech Connect

    Not Available

    1980-06-01

    Information is presented concerning new trends in licensing; seismic considerations and system structural behavior; TMI-2 risk assessment and thermal hydraulics; statistical assessment of potential accidents and verification of computational methods; issues with respect to improved safety; human factors in nuclear power plant operation; diagnostics and activities in support of recovery; LOCA transient analysis; unresolved safety issues and other safety considerations; and fission product transport.

  15. Aerosol Formation from High-Pressure Sprays for Supporting the Safety Analysis for the Hanford Waste Treatment and Immobilization Plant

    SciTech Connect

    Gauglitz, Phillip A.; Mahoney, Lenna A.; Schonewill, Philip P.; Bontha, Jagannadha R.; Blanchard, Jeremy; Kurath, Dean E.; Daniel, Richard C.; Song, Chen

    2013-03-05

    The Waste Treatment and Immobilization Plant (WTP) at Hanford is being designed and built to pretreat and vitrify waste currently stored in underground tanks at Hanford. One of the postulated events in the hazard analysis for the WTP is a breach in process piping that produces a pressurized spray with small droplets that can be transported into ventilation systems. Literature correlations are currently used for estimating the generation rate and size distribution of aerosol droplets in postulated spray releases. These correlations, however, are based on results obtained from small engineered nozzles using Newtonian liquids that do not contain slurry particles and thus do not accurately represent the fluids and breaches in the WTP. A test program was developed to measure the generation rate of droplets suspended in a test chamber and droplet size distribution from a range of prototypic sprays. A novel test method was developed to allow measurement of sprays from small to very large breaches and also includes the effect of aerosol generation from splatter when the spray impacts on walls. Results show that the aerosol generation rate increases with increasing the orifice area, though with a weaker dependence on orifice area than the currently-used correlation. A comparison of water sprays to slurry sprays with 8 to 20 wt% gibbsite or boehmite particles shows that the presence of slurry particles depresses the release fraction compared to water for droplets above 10 μm and increases the release fraction below this droplet size.

  16. Results of an Analysis of Field Studies of the Intrinsic Dynamic Characteristics Important for the Safety of Nuclear Power Plant Equipment

    SciTech Connect

    Kaznovsky, A. P. Kasiyanov, K. G.; Ryasnyj, S. I.

    2015-01-15

    A classification of the equipment important for the safety of nuclear power plants is proposed in terms of its dynamic behavior under seismic loading. An extended bank of data from dynamic tests over the entire range of thermal and mechanical equipment in generating units with VVER-1000 and RBMK-1000 reactors is analyzed. Results are presented from a study of the statistical behavior of the distribution of vibrational frequencies and damping decrements with the “small perturbation” factor that affects the measured damping decrements taken into account. A need to adjust the regulatory specifications for choosing the values of the damping decrements with specified inertial loads on equipment owing to seismic effects during design calculations is identified. Minimum values of the decrements are determined and proposed for all types of equipment as functions of the directions and natural vibration frequencies of the dynamic interactions to be adopted as conservative standard values in the absence of actual experimental data in the course of design studies of seismic resistance.

  17. Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). Supplement No. 15

    SciTech Connect

    Tam, P.S.

    1995-06-01

    This report supplements the Safety Evaluation Report (SER), NUREG-0847 (June 1982), Supplement No. 1 (September 1982), Supplement No. 2 (January 1984), Supplement No. 3 (January 1985), Supplement No. 4 (March 1985), Supplement No. 5 (November 1990), Supplement No. 6 (April 1991), Supplement No. 7 (September 1991), Supplement No. 8 (January 1992), Supplement No. 9 (June 1992), Supplement No. 10 (October 1992), Supplement No. 11 (April 1993), Supplement No. 12 (October 1993), Supplement No. 13 (April 1994), and Supplement No. 14 (December 1994) issued by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by the Tennessee Valley Authority, as applicant and owner, for licenses to operate the Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). The facility is located in Rhea County, Tennessee, near the Watts Bar Dam on the Tennessee River. This supplement provides recent information regarding resolution of some of the outstanding and confirmatory items, and proposed license conditions identified in the SER.

  18. The European ASAMPSA_E project : towards guidance to model the impact of high amplitude natural hazards in the probabilistic safety assessment of nuclear power plants. Information on the project progress and needs from the geosciences.

    NASA Astrophysics Data System (ADS)

    Raimond, Emmanuel; Decker, Kurt; Guigueno, Yves; Klug, Joakim; Loeffler, Horst

    2015-04-01

    The Fukushima nuclear accident in Japan resulted from the combination of two correlated extreme external events (earthquake and tsunami). The consequences, in particular flooding, went beyond what was considered in the initial engineering design design of nuclear power plants (NPPs). Such situations can in theory be identified using probabilistic safety assessment (PSA) methodology. PSA results may then lead industry (system suppliers and utilities) or Safety Authorities to take appropriate decisions to reinforce the defence-in-depth of the NPP for low probability event but high amplitude consequences. In reality, the development of such PSA remains a challenging task. Definitions of the design basis of NPPs, for example, require data on events with occurrence probabilities not higher than 10-4 per year. Today, even lower probabilities, down to 10-8, are expected and typically used for probabilistic safety analyses (PSA) of NPPs and the examination of so-called design extension conditions. Modelling the combinations of natural or man-made hazards that can affect a NPP and affecting some meaningful probability of occurrence seems to be difficult. The European project ASAMPSAE (www.asampsa.eu) gathers more than 30 organizations (industry, research, safety control) from Europe, US and Japan and aims at identifying some meaningful practices to extend the scope and the quality of the existing probabilistic safety analysis developed for nuclear power plants. It offers a framework to discuss, at a technical level, how "extended PSA" can be developed efficiently and be used to verify if the robustness of Nuclear Power Plants (NPPs) in their environment is sufficient. The paper will present the objectives of this project, some first lessons and introduce which type of guidance is being developed. It will explain the need of expertise from geosciences to support the nuclear safety assessment in the different area (seismotectonic, hydrological, meteorological and biological

  19. Technical evaluation of the susceptibility of safety-related systems to flooding caused by the failure of non-category 1 systems for the San Onofre Nuclear Power Plant, Unit 1

    SciTech Connect

    Latorre, V.R.; Victor, R.A.

    1980-11-01

    This report documents the technical evaluation of Southern California Edison Company's San Onofre Nuclear Power Plant, Unit 1, to determine whether the failure of any non-Category 1 (seismic) equipment could result in a condition, such as flooding, that might potentially adversely affect the performance of safety-related equipment required for the safe shutdown of the facility or to mitigate the consequences of an accident. Criteria developed by the US Nuclear Regulatory Commission were used to evaluate the acceptability of the existing protection as well as measures taken by Southern California Edison Company to minimize the danger of flooding and to protect safety-related equipment.

  20. Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). Supplement No. 17

    SciTech Connect

    Tam, P.S.

    1995-10-01

    This report supplements the Safety Evaluation Report (SER), NUREG-0847 (June 1982), Supplement No. 1 (September 1982), Supplement No. 2 (January 1984), Supplement No. 3 (January 1985), Supplement No. 4 (March 1985), Supplement No. 5 (November 1990), Supplement No. 6 (April 1991), Supplement No. 7 (September 1991), 1991), Supplement No. 8 (January 1992), Supplement No. 9 (June 1992), Supplement No. 10 (October 1992), Supplement No. 11 (April.1993), Supplement No. 12 (October 1993), Supplement No. 13 (April 1994), Supplement No. 14 (December 1994), Supplement No. 15 (June 1995), and Supplement No. 16 (September 1995) issued by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by the Tennessee Valley Authority, as applicant and owner, for licenses to operate the Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50--390 and 50--391). The facility is located in Rhea county, Tennessee, near the Watts Bar Dam on the Tennessee River. In this supplement, NRC examines the significant problems of construction quality and quality assurance effectiveness that led TVA to withdraw its certification in 1985 that Watts Bar Unit I was ready to load fuel. Also discussed are the extensive corrective actions performed by TVA according to its nuclear performance plans and other supplemental programs, and NRC`s extensive oversight to determine whether the Watts Bar Unit 1 construction quality and TVA`s operational readiness and quality assurance effectiveness are adequate for a low-power operating license to be issued. SSER 17 does not address Watts Bar Unit 2, except for the systems which are necessary to support Unit 1 operation.

  1. Evaluation of the Safety Analysis Report for the Waste Isolation Pilot Plant Project. [Summary of the more significant EEG comments and the associated DOE responses

    SciTech Connect

    Little, M.S.

    1985-05-01

    The Safety Analysis Report (SAR) for the Waste Isolation Pilot Plant (WIPP) Project was first published by the US Department of Energy (DOE), WIPP Project Office (WPO) in 1980. Since that time a total of eight amendments to this Report have been published. As part of its independent evaluation of the WIPP Project for the State of New Mexico, the Environmental Evaluation Group (EEG) maintains a continuing technical assessment of the information in this Report and its amendments. Beginning with the initial publication, and following the amendments, the EEG prepares detailed written comments and recommendations which are submitted to the WPO for consideration in future amendments. The WPO has made many substantial changes to the SAR in response to the EEG's comments. On frequent occasions, meetings between the two groups have been held in an effort to reach an accord on some of the more controversial issues. These meetings generally have been very constructive, but several important areas of conflict remain. In many instances, these areas represent changes which are to be considered by the WPO at some future date, rather than irreconcilable issues. The most important issues remaining to be resolved are included in the discussions of this report, and could be summarized as follows: (1) An amendment of the topical content to be more in accord with the DOE Order 5481.1A and AL 5481.1A. (2) Substantial revisions of the classification of components, structures and systems, and related quality assurance. (3) Revisions to the site geological and hydrologic data based on studies agreed to between DOE and the State.

  2. Pharmacokinetics, Safety, and Antiviral Effects of Hypericin, a Derivative of St. John's Wort Plant, in Patients with Chronic Hepatitis C Virus Infection

    PubMed Central

    Jacobson, Jeffrey M.; Feinman, Lawrence; Liebes, Leonard; Ostrow, Nancy; Koslowski, Victoria; Tobia, Alfonso; Cabana, Bernard E.; Lee, Dong-Hun; Spritzler, John; Prince, Alfred M.

    2001-01-01

    Hypericin is a natural derivative of the common St. Johns wort plant, Hypericum perforatum. It has in vitro activity against several viruses, including bovine diarrhea virus, a pestivirus with structural similarities to hepatitis C virus (HCV). We conducted a phase I dose escalation study to determine the safety and antiviral activity of hypericin in patients with chronic HCV infection. The first 12 patients received an 8-week course of 0.05 mg of hypericin per kg of body weight orally once a day; 7 patients received an 8-week course of 0.10 mg/kg orally once a day. At the end of the 8-week period of treatment, no subject had a change of plasma HCV RNA level of more than 1.0 log10. Five of 12 subjects receiving the 0.05-mg/kg/day dosing schedule and 6 of 7 subjects receiving the 0.10-mg/kg/day dosing schedule developed phototoxic reactions. No other serious adverse events associated with hypericin use occurred. The pharmacokinetic data revealed a long elimination half-life (mean values of 36.1 and 33.8 h, respectively, for the doses of 0.05 and 0.1 mg/kg) and mean area under the curve determinations of 1.5 and 3.1 μg/ml × hr, respectively. In sum, hypericin given orally in doses of 0.05 and 0.10 mg/kg/d caused considerable phototoxicity and had no detectable anti-HCV activity in patients with chronic HCV infection. PMID:11158749

  3. Investigation of the radiological safety concerns and medical history of the late Joseph T. Harding, former employee of the Paducah Gaseous Diffusion Plant

    SciTech Connect

    Vallario, E.J.; Wolfe, H.R.

    1981-03-01

    An ex-employee's claims that inadequate enforcement of radiation safety regulations allowed excess radiation exposure thereby causing his deteriorating health was not substantiated by a thorough investigation.

  4. Summertime Safety

    MedlinePlus

    ... Violence & Safety Life Stages & Populations Travelers' Health Workplace Safety & Health Features Media Sign up for Features Get Email Updates ... Submit What's this? Submit Button Past Emails CDC Features Summertime Safety Recommend on Facebook Tweet Share Compartir The feature ...

  5. Drug Safety

    MedlinePlus

    ... over-the-counter drug. The FDA evaluates the safety of a drug by looking at Side effects ... clinical trials The FDA also monitors a drug's safety after approval. For you, drug safety means buying ...

  6. Safety Education.

    ERIC Educational Resources Information Center

    Daniels, James H.; And Others

    1980-01-01

    Five articles in this issue focus on safety education in agricultural laboratories. Topics discussed include teacher liability; elements of a safety instruction program; state and federal safety standards; ground fault current protection; and eye protection requirements and equipment. (SK)

  7. Delivering safety

    SciTech Connect

    Baldwin, N.D.; Spooner, K.G.; Walkden, P.

    2007-07-01

    In the United Kingdom there have been significant recent changes to the management of civil nuclear liabilities. With the formation in April 2005 of the Nuclear Decommissioning Authority (NDA), ownership of the civil nuclear licensed sites in the UK, including the Magnox Reactor Stations, passed to this new organisation. The NDAs mission is to seek acceleration of the nuclear clean up programme and deliver increased value for money and, consequently, are driving their contractors to seek more innovative ways of performing work. British Nuclear Group manages the UK Magnox stations under contract to the NDA. This paper summarises the approach being taken within its Reactor Sites business to work with suppliers to enhance working arrangements at sites, improve the delivery of decommissioning programmes and deliver improvements in safety and environmental performance. The UK Magnox stations are 1. generation gas-graphite reactors, constructed in the 1950's and 1960's. Two stations are currently still operating, three are shut-down undergoing defueling and the other five are being decommissioned. Despite the distractions of industry restructuring, an uncompromising policy of demanding improved performance in conjunction with improved safety and environmental standards has been adopted. Over the past 5 years, this policy has resulted in step-changes in performance at Reactor Sites, with increased electrical output and accelerated defueling and decommissioning. The improvements in performance have been mirrored by improvements in safety (DACR of 0 at 5 sites); environmental standards (reductions in energy and water consumption, increased waste recycling) and the overall health of the workforce (20% reduction in sickness absence). These achievements have, in turn, been recognised by external bodies, resulting in several awards, including: the world's first ISRS and IERS level 10 awards (Sizewell, 2006), the NUMEX plant maintenance award (Bradwell, 2006), numerous Ro

  8. A Safety Program that Integrated Behavior-Based Safety and Traditional Safety Methods and Its Effects on Injury Rates of Manufacturing Workers

    ERIC Educational Resources Information Center

    Hermann, Jaime A.; Ibarra, Guillermo V.; Hopkins, B. L.

    2010-01-01

    The present research examines the effects of a complex safety program that combined Behavior-Based Safety (BBS) and traditional safety methods. The study was conducted in an automobile parts plant in Mexico. Two sister plants served as comparison. Some of the components of the safety programs addressed behaviors of managers and included methods…

  9. PRELIMINARY ENVIRONMENTAL, HEALTH AND SAFETY RISK ASSESSMENT ON THE INTEGRATION OF A PROCESS UTILIZING LOW-ENERGY SOLVENTS FOR CARBON DIOXIDE CAPTURE ENABLED BY A COMBINATION OF ENZYMES AND VACUUM REGENERATION WITH A SUBCRITICAL PC POWER PLANT

    SciTech Connect

    Fitzgerald, David; Vidal, Rafael; Russell, Tania; Babcock, Doosan; Freeman, Charles; Bearden, Mark; Whyatt, Greg; Liu, Kun; Frimpong, Reynolds; Lu, Kunlei; Salmon, Sonja; House, Alan; Yarborough, Erin

    2014-12-31

    The results of the preliminary environmental, health and safety (EH&S) risk assessment for an enzyme-activated potassium carbonate (K2CO3) solution post-combustion CO2 capture (PCC) plant, integrated with a subcritical pulverized coal (PC) power plant, are presented. The expected emissions during normal steady-state operation have been estimated utilizing models of the PCC plant developed in AspenTech’s AspenPlus® software, bench scale test results from the University of Kentucky, and industrial experience of emission results from a slipstream PCC plant utilizing amine based solvents. A review of all potential emission species and their sources was undertaken that identified two credible emission sources, the absorber off-gas that is vented to atmosphere via a stack and the waste removed from the PCC plant in the centrifuge used to reclaim enzyme and solvent. The conditions and compositions of the emissions were calculated and the potential EH&S effects were considered as well as legislative compliance requirements. Potential mitigation methods for emissions during normal operation have been proposed and solutions to mitigate uncontrolled releases of species have been considered. The potential emissions were found to pose no significant EH&S concerns and were compliant with the Federal legislation reviewed. The limitations in predicting full scale plant performance from bench scale tests have been noted and further work on a larger scale test unit is recommended to reduce the level of uncertainty.

  10. Safety system status monitoring

    SciTech Connect

    Lewis, J.R.; Morgenstern, M.H.; Rideout, T.H.; Cowley, P.J.

    1984-03-01

    The Pacific Northwest Laboratory has studied the safety aspects of monitoring the preoperational status of safety systems in nuclear power plants. The goals of the study were to assess for the NRC the effectiveness of current monitoring systems and procedures, to develop near-term guidelines for reducing human errors associated with monitoring safety system status, and to recommend a regulatory position on this issue. A review of safety system status monitoring practices indicated that current systems and procedures do not adequately aid control room operators in monitoring safety system status. This is true even of some systems and procedures installed to meet existing regulatory guidelines (Regulatory Guide 1.47). In consequence, this report suggests acceptance criteria for meeting the functional requirements of an adequate system for monitoring safety system status. Also suggested are near-term guidelines that could reduce the likelihood of human errors in specific, high-priority status monitoring tasks. It is recommended that (1) Regulatory Guide 1.47 be revised to address these acceptance criteria, and (2) the revised Regulatory Guide 1.47 be applied to all plants, including those built since the issuance of the original Regulatory Guide.

  11. Safety Equipment in the Lab.

    ERIC Educational Resources Information Center

    Denham, Willard A.S.

    1964-01-01

    Findings of two recent surveys on safety equipment in laboratory facilities are presented. The first survey was a pilot study of emergency shower and eye wash equipment. This study was followed by a more comprehensive random survey of safety equipment in 2,820 labs. Among other findings, the surveys indicate that many plants are underequipped, or…

  12. Guide for Science Laboratory Safety.

    ERIC Educational Resources Information Center

    McDermott, John J.

    General and specific safety procedures and recommendations for secondary school science laboratories are provided in this guide. Areas of concern include: (1) chemicals (storage, disposal, toxicity, unstable and incompatible chemicals); (2) microorganisms; (3) plants; (4) animals; (5) electricity; (6) lasers; (7) rockets; (8) eye safety and…

  13. Vaccine Safety

    MedlinePlus

    ... During Pregnancy Frequently Asked Questions about Vaccine Recalls Historical Vaccine Safety Concerns FAQs about GBS and Menactra ... CISA Resources for Healthcare Professionals Evaluation Current Studies Historical Background 2001-12 Publications Technical Reports Vaccine Safety ...

  14. Safety Handbook.

    ERIC Educational Resources Information Center

    Montgomery County Public Schools, Rockville, MD.

    Safety policies, procedures, and related information are presented in this manual to assist school personnel in a continuing program of accident prevention. Chapter 1 discusses safety education and accident prevention in general. Chapter 2 covers traffic regulations relating to school safety patrols, school bus transportation, bicycles, and…

  15. Safety climate practice in Korean manufacturing industry.

    PubMed

    Baek, Jong-Bae; Bae, Sejong; Ham, Byung-Ho; Singh, Karan P

    2008-11-15

    Safety climate survey was sent to 642 plants in 2003 to explore safety climate practices in the Korean manufacturing plants, especially in hazardous chemical treating plants. Out of 642 plants contacted 195 (30.4%) participated in the surveys. Data were collected by e-mail using SQL-server and mail. The main objective of this study was to explore safety climate practices (level of safety climate and the underlying problems). In addition, the variables that may influence the level of safety climate among managers and workers were explored. The questionnaires developed by health and safety executive (HSE) in the UK were modified to incorporate differences in Korean culture. Eleven important factors were summarized. Internal reliability of these factors was validated. Number of employees in the company varied from less than 30 employees (9.2%) to over 1000 employees (37.4%). Both managers and workers showed generally high level of safety climate awareness. The major underlying problems identified were inadequate health and safety procedures/rules, pressure for production, and rule breaking. The length of employment was a significant contributing factor to the level of safety climate. In this study, participants showed generally high level of safety climate, and length of employment affected the differences in the level of safety climate. Managers' commitment to comply safety rules, procedures, and effective safety education and training are recommended. PMID:18060692

  16. Research Update - Intervention Technologies for Enhancing the Safety and Security of Fresh and Minimally Processed Produce and Solid Plant-Derived Foods

    Technology Transfer Automated Retrieval System (TEKTRAN)

    The produce safety research objectives of Research Project 1935-41420-011 are to 1) understand pathogen microbial ecology and its effects on decontamination efficacy; 2) develop biological-based intervention strategies for pathogen reduction; and 3) develop new effective chemical and physical decont...

  17. National Safety Council

    MedlinePlus

    ... Introduction Safety Management Systems Workplace Safety Consulting Employee Perception Surveys Research Journey to Safety Excellence Join the ... Safety Safety Management Systems Workplace Safety Consulting Employee Perception Surveys Research Journey to Safety Excellence Join the ...

  18. Bromine Safety

    SciTech Connect

    Meyers, B

    2001-04-09

    The production and handling in 1999 of about 200 million kilograms of bromine plus substantial derivatives thereof by Great Lakes Chemical Corp. and Albemarle Corporation in their southern Arkansas refineries gave OSHA Occupational Injury/Illness Rates (OIIR) in the range of 0.74 to 1.60 reportable OIIRs per 200,000 man hours. OIIRs for similar industries and a wide selection of other U.S. industries range from 1.6 to 23.9 in the most recent OSHA report. Occupational fatalities for the two companies in 1999 were zero compared to a range in the U.S.of zero for all computer manufacturing to 0.0445 percent for all of agriculture, forestry and fishing in the most recent OSHA report. These results show that bromine and its compounds can be considered as safe chemicals as a result of the bromine safety standards and practices at the two companies. The use of hydrobromic acid as an electrical energy storage medium in reversible PEM fuel cells is discussed. A study in 1979 of 20 megawatt halogen working fluid power plants by Oronzio de Nora Group found such energy to cost 2 to 2.5 times the prevailing base rate at that time. New conditions may reduce this relative cost. The energy storage aspect allows energy delivery at maximum demand times where the energy commands premium rates. The study also found marginal cost and performance advantages for hydrobromic acid over hydrochloric acid working fluid. Separate studies in the late 70s by General Electric also showed marginal performance advantages for hydrobromic acid.

  19. Health and safety plan for the removal action at the former YS-860 Firing Ranges, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    SciTech Connect

    1998-03-24

    This health and safety plan sets forth the requirements and procedures to protect the personnel involved in the removal action project at the former YS-860 Firing Ranges. This project will be conducted in a manner that ensures the protection of the safety and health of workers, the public, and the environment. The purpose of this removal action is to address lead-contaminated soil and reduce a potential risk to human health and the environment. This site is an operable unit within the Upper East Fork Poplar Creek watershed. The removal action will contribute to early source actions within the watershed. The project will accomplish this through the removal of lead-contaminated soil in the target areas of the two small arms firing ranges. The primary hazards include temperature extremes, equipment operation, noise, potential lead exposure, uneven and slippery working surfaces, and insects.

  20. Florida Postsecondary Education Security Information Act. Annual Report of Campus Crime Statistics 1991-93 and Annual Assessment of Physical Plant Safety 1994.

    ERIC Educational Resources Information Center

    Florida State Dept. of Education, Tallahassee. Office of Postsecondary Education Coordination.

    This state-mandated report presents crime statistics at higher education institutions in Florida and an assessment of physical plant security. The crime data list numbers of homicides, forcible sex offenses, robberies, aggravated assaults, burglaries/breaking and entering, larcenies and thefts, and motor vehicle thefts for each state university,…

  1. Safety Systems

    ERIC Educational Resources Information Center

    Halligan, Tom

    2009-01-01

    Colleges across the country are rising to the task by implementing safety programs, response strategies, and technologies intended to create a secure environment for teachers and students. Whether it is preparing and responding to a natural disaster, health emergency, or act of violence, more schools are making campus safety a top priority. At…

  2. Solidifying Safety

    NASA Technical Reports Server (NTRS)

    Covault, Craig

    2003-01-01

    Contents include the following: 1. Solidifying Safety: NASA s new safety organization spools up, as the 1SS program grapples with long-term risk. 2. Earth to Orbit O'Keefe telling skeptical lawmakers Orbital Space Plan (OSP) will cover exploration vision. China's rapid pace.

  3. Safety First

    ERIC Educational Resources Information Center

    Taft, Darryl

    2011-01-01

    Ned Miller does not take security lightly. As director of campus safety and emergency management at the Des Moines Area Community College (DMACC), any threat requires serious consideration. As community college administrators adopt a more proactive approach to campus safety, many institutions are experimenting with emerging technologies, including…

  4. Health and safety plan for the removal action at the former YS-860 Firing Ranges, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    SciTech Connect

    1998-04-28

    This health and safety plan sets forth the requirements and procedures to protect the personnel involved in the Lead Source Removal Project at the Former YS-86O Firing Ranges. This project will be conducted in a manner that ensures the protection of the safety and health of workers, the public, and the environment. The purpose of this removal action is to address lead contaminated soil and reduce a potential risk to human health and the environment. This site is an operable unit within the Upper East Fork Poplar Creek watershed. The removal action will contribute to early source actions within the watershed. The project will accomplish this through the removal of lead-contaminated soil in the target areas of the two small arms firing ranges. This plan covers the removal actions at the Former YS-86O Firing Ranges. These actions involve the excavation of lead-contaminated soils, the removal of the concrete trench and macadam (asphalt) paths, verification/confirmation sampling, grading and revegetation. The primary hazards include temperature extremes, equipment operation, noise, potential lead exposure, uneven and slippery working surfaces, and insects.

  5. Investigation: revelations about Three Mile Island disaster raise doubts over nuclear plant safety: a special facing south investigation by Sue Sturgis.

    PubMed

    Sturgis, Sue

    2009-01-01

    A series of mishaps in a reactor at the Three Mile Island (TMI) nuclear plant led to the 1979 meltdown of almost half the uranium fuel and uncontrolled releases of radiation into the air and surrounding Susquehanna River. It was the single worst disaster ever to befall the U.S. nuclear power industry. Health physics technician Randall Thompson's story about what he witnessed while monitoring radiation there after the incident is being publicly disclosed for the first time. It is supported by a growing body of evidence and it contradicts the U.S. government's contention that the TMI accident posed no threat to the public. Thompson and his wife, a nuclear health physicist who also worked at TMI in the disaster's wake, warn that the government's failure to acknowledge the full scope of the disaster is leading officials to underestimate the risks posed by a new generation of nuclear power plants. PMID:20129905

  6. Industrial water supply for the Kursk TETs-1 heating and electric power plant with the ecological safety of the River Seim taken into account

    SciTech Connect

    Kyakk, V. A.

    2009-09-15

    The Kursk TETs-1 heating and electric power plant is discussed as an illustration of preventing thermal contamination of its water supply (River Seim) by circulating water. An effective water supply system is taken to be one for which the overheating of the water at a monitoring site (near the outlet location) does not exceed an approved level for the water use conditions. The required cooling capacity of a spray pond for circulating and flow-through water supplies is determined.

  7. Software safety

    NASA Technical Reports Server (NTRS)

    Leveson, Nancy

    1987-01-01

    Software safety and its relationship to other qualities are discussed. It is shown that standard reliability and fault tolerance techniques will not solve the safety problem for the present. A new attitude requires: looking at what you do NOT want software to do along with what you want it to do; and assuming things will go wrong. New procedures and changes to entire software development process are necessary: special software safety analysis techniques are needed; and design techniques, especially eliminating complexity, can be very helpful.

  8. Safety Tips.

    ERIC Educational Resources Information Center

    Nagel, Miriam C., Ed.

    1984-01-01

    Outlines a cooperative effort in Iowa to eliminate dangerous or unwanted chemicals from school science storerooms. Also reviews the Council of State Science Supervisor's safety program and discusses how to prevent cuts and punctures from jagged glass tubing. (JN)

  9. Food Safety

    MedlinePlus

    ... are four basic steps to food safety at home: Clean - always wash your fruits and vegetables, hands, counters, and cooking utensils. Separate - keep raw foods to themselves. Germs can spread from one food ...

  10. 10 CFR 76.87 - Technical safety requirements.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false Technical safety requirements. 76.87 Section 76.87 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safety § 76.87 Technical safety requirements. (a) The Corporation shall establish technical safety requirements....

  11. 10 CFR 76.87 - Technical safety requirements.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 2 2012-01-01 2012-01-01 false Technical safety requirements. 76.87 Section 76.87 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safety § 76.87 Technical safety requirements. (a) The Corporation shall establish technical safety requirements....

  12. 10 CFR 76.87 - Technical safety requirements.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Technical safety requirements. 76.87 Section 76.87 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safety § 76.87 Technical safety requirements. (a) The Corporation shall establish technical safety requirements....

  13. State-of-the-art of non-destructive testing methods and technologies for application to nuclear power plant safety-related concrete structures

    NASA Astrophysics Data System (ADS)

    Wiggenhauser, Herbert; Naus, Dan J.

    2014-02-01

    The inspection of nuclear power plant concrete structures presents challenges different from conventional civil engineering structures. Wall thicknesses can be in excess of one meter and the structures often have increased steel reinforcement density with more complex detailing. The accessibility for any testing method may be limited due to the presence of liners and other components and there can be a number of penetrations or cast-in-place items present. The objective of the report is to present the state-of-the art of non-destructive testing methods and technologies for the inspection of thick, heavily-reinforced nuclear power plant concrete cross-sections with particular respect to: •locating steel reinforcement and identification of its cover depth •locating tendon ducts and identification of the condition of the grout materials •detection of cracking, voids, delamination, and honeycombing in concrete structures •detection of inclusions of different materials or voids adjacent to the concrete side of the containment liner •methods capable of identification of corrosion occurrence on the concrete side of the containment liner

  14. State-of-the-art of non-destructive testing methods and technologies for application to nuclear power plant safety-related concrete structures

    SciTech Connect

    Wiggenhauser, Herbert; Naus, Dan J.

    2014-02-18

    The inspection of nuclear power plant concrete structures presents challenges different from conventional civil engineering structures. Wall thicknesses can be in excess of one meter and the structures often have increased steel reinforcement density with more complex detailing. The accessibility for any testing method may be limited due to the presence of liners and other components and there can be a number of penetrations or cast-in-place items present. The objective of the report is to present the state-of-the art of non-destructive testing methods and technologies for the inspection of thick, heavily-reinforced nuclear power plant concrete cross-sections with particular respect to: •locating steel reinforcement and identification of its cover depth •locating tendon ducts and identification of the condition of the grout materials •detection of cracking, voids, delamination, and honeycombing in concrete structures •detection of inclusions of different materials or voids adjacent to the concrete side of the containment liner •methods capable of identification of corrosion occurrence on the concrete side of the containment liner.

  15. State-of-the-Art of Non-Destructive Testing Methods and Technologies for Application to Nuclear Power Plant Safety-Related Concrete Structures

    SciTech Connect

    Wiggenhauser, Dr. Herbert; Naus, Dan J

    2014-01-01

    The inspection of nuclear power plant concrete structures presents challenges different from conventional civil engineering structures. Wall thicknesses can be in excess of one meter and the structures often have increased steel reinforcement density with more complex detailing. The accessibility for any testing method may be limited due to the presence of liners and other components and there can be a number of penetrations or cast-in-place items present. The objective of the report is to present the state-of-the art of non-destructive testing methods and technologies for the inspection of thick, heavily-reinforced nuclear power plant concrete cross-sections with particular respect to: locating steel reinforcement and identification of its cover depth locating tendon ducts and identification of the condition of the grout materials detection of cracking, voids, delamination, and honeycombing in concrete structures detection of inclusions of different materials or voids adjacent to the concrete side of the containment liner methods capable of identification of corrosion occurrence on the concrete side of the containment liner

  16. System safety education focused on flight safety

    NASA Technical Reports Server (NTRS)

    Holt, E.

    1971-01-01

    The measures necessary for achieving higher levels of system safety are analyzed with an eye toward maintaining the combat capability of the Air Force. Several education courses were provided for personnel involved in safety management. Data include: (1) Flight Safety Officer Course, (2) Advanced Safety Program Management, (3) Fundamentals of System Safety, and (4) Quantitative Methods of Safety Analysis.

  17. Occupational Safety Review of High Technology Facilities

    SciTech Connect

    Lee Cadwallader

    2005-01-31

    This report contains reviews of operating experiences, selected accident events, and industrial safety performance indicators that document the performance of the major US DOE magnetic fusion experiments and particle accelerators. These data are useful to form a basis for the occupational safety level at matured research facilities with known sets of safety rules and regulations. Some of the issues discussed are radiation safety, electromagnetic energy exposure events, and some of the more widespread issues of working at height, equipment fires, confined space work, electrical work, and other industrial hazards. Nuclear power plant industrial safety data are also included for comparison.

  18. First Aid and Safety

    MedlinePlus

    ... First-Aid Kit Food Safety for Your Family Gun Safety Halloween Candy Hints Household Safety Checklists Household ... Climbing, and Grabbing Household Safety: Preventing Injuries From Firearms Household Safety: Preventing Injuries in the Crib Household ...

  19. Aerosol Formation from High-Pressure Sprays for Supporting the Safety Analysis for the Hanford Waste Treatment and Immobilization Plant - 13183

    SciTech Connect

    Gauglitz, P.A.; Mahoney, L.A.; Schonewill, P.P.; Bontha, J.R.; Blanchard, J.; Kurath, D.E.; Daniel, R.C.; Song, C.

    2013-07-01

    The Waste Treatment and Immobilization Plant (WTP) at Hanford is being designed and built to pretreat and vitrify waste currently stored in underground tanks at Hanford. One of the postulated events in the hazard analysis for the WTP is a breach in process piping that produces a pressurized spray with small droplets that can be transported into ventilation systems. Literature correlations are currently used for estimating the generation rate and size distribution of aerosol droplets in postulated releases. These correlations, however, are based on results obtained from small engineered nozzles using Newtonian liquids that do not contain slurry particles and thus do not represent the fluids and breaches in the WTP. A test program was developed to measure the generation rate, and the release fraction which is the ratio of generation rate to spray flow rate, of droplets suspended in a test chamber and droplet size distribution from prototypic sprays. A novel test method was developed to allow measurement of sprays from small to large breaches and also includes the effect of aerosol generation from splatter when the spray impacts on walls. Results show that the release fraction decreases with increasing orifice area, though with a weaker dependence on orifice area than the currently-used correlation. A comparison of water sprays to slurry sprays with 8 to 20 wt% gibbsite or boehmite particles shows that the presence of slurry particles depresses the release fraction compared to water for droplets above 10 μm and increases the release fraction below this droplet size. (authors)

  20. Playground Safety.

    ERIC Educational Resources Information Center

    Sipes, James L.

    2000-01-01

    Discusses the issues of risk, liability, and fun when landscaping playgrounds with safety in mind. The importance of playground surfaces and several preventive measures landscapers can use to reduce the risk of injury are discussed. Concluding comments address playground design features and liability. (GR)

  1. School Safety.

    ERIC Educational Resources Information Center

    The Newsletter of the Comprehensive Center-Region VI, 1999

    1999-01-01

    The articles in this issue dealing with school safety discusses what rural and small urban settings are doing to prevent violence and to educate young people about prosocial alternatives to violence. The research is quite clear that female, minority, and gay students are the targets of a disproportionate amount of harassment and violence, both in…

  2. Safety First!

    ERIC Educational Resources Information Center

    Longfield, Judith

    2006-01-01

    In this article, the author relates how a hands-on chemistry investigation provided her the inspiration to develop an effective safety lesson for her third grade chemistry class. She began the lesson by demonstrating the use of pH indicator paper to show that ordinary household (white) vinegar was an acid. With the students, she wondered aloud…

  3. Art Safety.

    ERIC Educational Resources Information Center

    BCATA Journal for Art Teachers, 1991

    1991-01-01

    Advocating that Canadian art programs should use and model environmentally safe practices, the articles in this journal focus on issues of safe practices in art education. Articles are: (1) "What is WHMIS?"; (2) "Safety Precautions for Specific Art Processes"; (3) "Toxic Substances"; (4) "Using Clay, Glazes, and Kilns Safely in the Classroom"…

  4. Rekindling Longwood University's Rhetoric and Professional Writing Concentration and Minor, 2007-2010

    ERIC Educational Resources Information Center

    Welch, Kristen Dayle

    2011-01-01

    The challenges of redesigning and reviving Longwood University's Rhetoric and Professional Writing program involved skills in collaboration, negotiation, and advertisement. While unexpected obstacles arose, taking an honest look at the existing program design and working to maintain the focus on rhetoric helped to circumvent failure. Finally,…

  5. Calories Consumed from Alcoholic Beverages by U.S. Adults, 2007-2010

    MedlinePlus

    ... and Nutrition Examination Survey. Are there differences by poverty level in mean calories consumed from alcoholic beverages? ... those living at or above 350% of the poverty level, higher than the average of just over ...

  6. Residue control of coccidiostats in food of animal origin in Poland during 2007-2010.

    PubMed

    Olejnik, Małgorzata; Szprengier-Juszkiewicz, Teresa; Jedziniak, Piotr; Sledzińska, Edyta; Szymanek-Bany, Iwona; Korycińska, Beata; Pietruk, Konrad; Zmudzki, Jan

    2011-01-01

    Coccidiostats are widely used as feed additives to prevent coccidiosis. The off-label use of anticoccidials or feeding non-target animals with cross-contaminated feedingstuffs may result in the occurrence of coccidiostat residues in animal tissues and eggs. In EU countries, food of animal origin is subjected to official control of residues according to Council Directive 96/23/EC. In Poland, within the framework of the National Residue Control Plan, 3718 samples (3533 targeted and 185 suspect) of animal liver, eggs, drinking water and feed were tested for coccidiostats between 2007 and 2010. Violative residues of nicarbazin, lasalocid, maduramicin, salinomycin, semduramicin and robenidine were detected in 77 food samples (53 samples of chicken liver, 23 samples of eggs and 1 sample of turkey liver). A high percentage (31%) of non-compliant feed samples collected during follow-up investigations was observed, which confirms that feed cross-contamination may be the reason of the occurrence of coccidiostat residues in food. PMID:24786249

  7. Variability of aerosol properties during the 2007-2010 spring seasons over central Europe

    NASA Astrophysics Data System (ADS)

    Pietruczuk, Aleksander; Chaikovsky, Anatoli

    2012-10-01

    Aerosol optical properties have been studied for spring seasons when increased values of PM10 are registered. Measurements of aerosol optical properties were taken by collocated lidar and sun-photometers at Belsk, Poland, and Minsk, Belarus. A significant increase of registered aerosol optical thickness (AOT) was found during episodes with elevated PM10 concentrations. An increase of AOT at 1020 nm amounted to 50% in the case of Minsk and 18% in the case of Belsk, while an increase of AOT at 400 nm was 66% and 33%, respectively. We noted an increase of Ångström exponent by 6% at both stations and no significant increase of single scattering albedo. The LIDAR measurements together with NAAPS model results and backtrajectory analysis suggest that both the biomass burning products and the Saharan dust are responsible for increased PM10 concentrations and large AOT values during spring time. The smoke aerosol is transported over Central Europe mainly in the boundary layer, increasing both PM10 concentration and AOT. The dust aerosol transported in the free troposphere slightly affects the AOT values only. Statistically significant correlation between PM10 concentration and AOT was found during reporting period.

  8. Corotating Interaction Regions as Seen by the STEREO Heliospheric Imagers 2007 - 2010

    NASA Astrophysics Data System (ADS)

    Conlon, T. M.; Milan, S. E.; Davies, J. A.; Williams, A. O.

    2015-08-01

    NASA's Solar Terrestrial Relations Observatory (STEREO) mission has coincided with a pronounced solar minimum. This allowed for easier detection of corotating interaction regions (CIRs). CIRs are formed by the interaction between fast and slow solar-wind streams ejected from source regions on the solar surface that rotate with the Sun. High-density plasma blobs that have become entrained at the stream interface can be tracked out to large elongations in data from the Heliospheric Imager (HI) instruments onboard STEREO. These blobs act as tracers of the CIR itself such that their HI signatures can be used to estimate CIR source location and radial speed. We estimate the kinematic properties of solar-wind transients associated with 40 CIRs detected by the HI instrument onboard the STEREO-A spacecraft between 2007 and 2010. We identify in-situ signatures of these transients at L1 using the Advanced Composition Explorer (ACE) and compare the in-situ parameters with the HI results. We note that solar-wind transients associated with CIRs appear to travel at or close to the slow solar-wind speed preceding the event as measured in situ. We also highlight limitations in the commonly used analysis techniques of solar-wind transients by considering variability in the solar wind.

  9. An inverse modeling study of circulation in the Eastern Bering Sea during 2007-2010

    NASA Astrophysics Data System (ADS)

    Panteleev, Gleb; Yaremchuk, Max; Francis, Oceana; Stabeno, Phyllis J.; Weingartner, T.; Zhang, J.

    2016-06-01

    A two-way nested 4d-variational data assimilation system is implemented in the Eastern Bering Sea (EBS) to investigate changes in circulation and thermodynamic state for a 3.8 year period. Assimilated observations include data from 19 moorings deployed on the shelf and in the Bering Strait, 1705 hydrographic stations occupied during eight surveys, and remotely sensed sea surface temperature and sea surface height (SSH) data. Validation of the presented 4dVar reanalysis against the output of two sequential data-assimilative systems (the Bering Ecosystem Study ice-ocean Modeling and Assimilation System (BESTMAS) and the Arctic Cap Nowcast-Forecast System (ACNFS)) has shown that the product is more consistent with the observed transports in the Bering Strait and in the EBS interior both in terms of their magnitude and time variability. Analysis of the data-optimized solution quantifies a sequence of wind-forced events that resulted in the anomalous heat and freshwater transports through the Bering Strait, including a 28 day long flow reversal that occurred in November 2009 and carried Siberian Coastal Current water down to the Gulf of Anadyr. Lagrangian study of the Arctic-bound Pacific waters indicates the extreme importance of the cross-shelf exchange along the path of the Bering Slope Current and quantifies the spectrum of residence times for the waters entering EBS through Unimak Pass and through Aleutian passages. Residence times in the EBS cold pool are diagnosed to be 2-3 times longer than those in the surrounding waters.

  10. Aerosol variability and atmospheric transport in the Himalayan region from CALIOP 2007-2010 observations

    NASA Astrophysics Data System (ADS)

    Bucci, S.; Cagnazzo, C.; Cairo, F.; Di Liberto, L.; Fierli, F.

    2014-05-01

    This work quantifies the spatial distribution of different aerosol types, their seasonal variability and sources.The analysis of four years of CALIOP (Cloud-Aerosol LIdar with Orthogonal Polarization) vertically resolved aerosol data allows the identification of spatial patterns of desert dust and carbonaceous particles in different atmospheric layers. Clusters of Lagrangian back trajectories highlight the transport pathways from source regions during the dusty spring season. The analysis shows a prevalence of dust; at low heights it occurs frequently (up to 70% of available observations) and is distributed north of the Tibetan Plateau with a main contribution from the Gobi and Taklamakan deserts, and west of the Tibetan Plateau, originating from the deserts of southwest Asia and advected by the Westerlies. Above the Himalayas the dust amount is minor but still not negligible (occurrence around 20%) and mainly affected by the transport from more distant deserts sources (Sahara and Arabian Peninsula). Carbonaceous aerosol, produced mainly in northern India and eastern China, is subject to shorter-range transport and is indeed observed closer to the sources, while there is a limited amount reaching the top of the plateau. Data analysis reveals a clear seasonal variability in the frequencies of occurrence for the main aerosol types; dust is regulated principally by the monsoon dynamics, with maximal occurrence in spring. We also highlight relevant interannual differences, showing a larger presence of aerosol in the region during 2007 and 2008. The characterization of the aerosol spatial and temporal distribution in terms of observational frequency is a key piece of information that can be directly used for the evaluation of global aerosol models.

  11. Very-long-period seismicity at Kilauea Volcano, Hawai`i, 2007-2010 (Invited)

    NASA Astrophysics Data System (ADS)

    Dawson, P. B.; Benítez, M. C.; Chouet, B. A.

    2010-12-01

    On 19 March, 2008 eruptive activity returned to the summit of Kilauea Volcano, Hawai‘i with the formation of a new vent within the Halema‘uma‘u pit crater. The new vent has been gradually increasing in size, and exhibiting sustained degassing and the episodic bursting of gas slugs at the surface of a lava pond ~200 m below the floor of Halema‘uma‘u. The observation of broadband seismicity recorded within Kilauea Caldera provides an unprecedented view into the processes leading up to and beyond the renewal of eruptive activity at the summit. Resonant features in the Very-Long-Period spectra begin to appear in October, 2007, and by the end of November, 2007 the magma transport system sustained continuous oscillations that persist through 31 January, 2010. The lowest observed frequency, at about 0.04 Hz, represents the breathing mode of the shallow magmatic system with a source centroid located 1 km beneath the caldera floor and ~500 m north-northeast of the new pit in Halema‘uma‘u. Spectral peaks seen at 0.2 and 0.45 Hz are inferred to represent higher modes of resonance in the system. The marked shifts in frequencies over time are due to the complex interaction between the slowly changing magma-static head, conduit structure, and the acoustic properties of the magmatic fluid. Rockfall and collapse signals appear as random processes statistically disassociated from the degassing burst signals. These events have a frequency content ranging from 5 to 20 Hz. The spectral characteristics, source location obtained by radial semblance, and Hidden Markov Model pattern recognition of the degassing burst signals are consistent with an increase in gas content in the magma transport system beginning in October, 2007. This increase plateaus between March-September 2008, and exhibits a fluctuating pattern until 31 January, 2010, suggesting that the release of gas is slowly diminishing over time.

  12. Caloric Intake from Fast Food among Adults: United States, 2007-2010

    MedlinePlus

    ... to poverty. The U.S. Department of Health and Human Services' poverty guidelines were used as the poverty measure to calculate this index ( 8 ). The cut point for participation in the Supplemental Nutrition Assistance Program is 130% of the poverty level. ...

  13. Consumption of pizza in the United States, What We Eat in America, NHANES 2007-2010

    Technology Transfer Automated Retrieval System (TEKTRAN)

    Pizza is recognized as a high consumption food and a contributor of nutrients of public significance in the American diet including fat, calcium, and sodium. This research presents results on pizza consumption among U.S. children (2-19 years) and adults (20 years and over) and details nutrient cont...

  14. Coalbed natural gas exploration, drilling activities, and geologic test results, 2007-2010

    USGS Publications Warehouse

    Clark, Arthur C.

    2014-01-01

    The U.S. Geological Survey, in partnership with the U.S. Bureau of Land Management, the North Slope Borough, and the Arctic Slope Regional Corporation conducted a four-year study designed to identify, define, and delineate a shallow coalbed natural gas (CBNG) resource with the potential to provide locally produced, affordable power to the community of Wainwright, Alaska. From 2007 through 2010, drilling and testing activities conducted at three sites in or near Wainwright, identified and evaluated an approximately 7.5-ft-thick, laterally continuous coalbed that contained significant quantities of CBNG. This coalbed, subsequently named the Wainwright coalbed, was penetrated at depths ranging from 1,167 ft to 1,300 ft below land surface. Core samples were collected from the Wainwright coalbed at all three drill locations and desorbed-gas measurements were taken from seventeen 1-ft-thick sections of the core. These measurements indicate that the Wainwright coalbed contains enough CBNG to serve as a long-term energy supply for the community. Although attempts to produce viable quantities of CBNG from the Wainwright coalbed proved unsuccessful, it seems likely that with proper well-field design and by utilizing currently available drilling and reservoir stimulation techniques, this CBNG resource could be developed as a long-term economically viable energy source for Wainwright.

  15. A Strategic Action Plan for Advancing Math and Science Education in New Mexico 2007-2010

    ERIC Educational Resources Information Center

    New Mexico Public Education Department, 2007

    2007-01-01

    This Strategic Action Plan for Advancing Math and Science Education is an initial outline of strategies, actions, measures of progress, resources needed, timelines, and responsible parties. The Plan focuses on these three main goals: (1) increasing student interest, participation, and achievement in math and science; (2) raising public support and…

  16. The Expanding Burden of Elevated Blood Pressure in China: Evidence From Jiangxi Province, 2007-2010.

    PubMed

    Xu, Gang; Liu, Junxiu; Liu, Shiwei; Zhou, Haiming; Orekoya, Olubunmi; Liu, Jie; Li, Yichong; Tang, Ji; Zhou, Chunlian; Huang, Jiuling

    2015-09-01

    Elevated blood pressure (BP) as a risk factor accounts for the biggest burden of disease worldwide and in China. This study aimed to estimate attributed mortality and life expectancy (LE) to elevated BP in Jiangxi province between 2007 and 2010. BP and mortality data (2007 and 2010 inclusive) were obtained from the National Chronic Diseases and Risk Factors Surveillance Survey and Disease Surveillance Points system, respectively. Population-attributable fraction used in comparative risk assessment of the Global Burden of Disease study 2010 were followed to quantify the attributed mortality to elevated BP, subsequently life table methods were applied to estimate its effects on LE. Uncertainty analysis was conducted to get 95% uncertainty intervals (95% uncertainty interval [UI]) for each outcome. There are 35,482 (95% UI: 31,389-39,928) and 47,842 (42,323-53,837) deaths in Jiangxi province were caused by elevated BP in 2007 and 2010, respectively. 2.24 (1.87-2.65) years of LE would be gained if all the attributed deaths were eliminated in 2007, and increased to 3.04 (2.52-3.48) in 2010. If the mean value of elevated BP in 2010 was decreased by 5 and 10 mm Hg, 5324 (4710-5991) and 11,422 (10,104-12,853) deaths would be avoided, with 0.41 (0.37-0.48) and 0.85 (0.71-1.09) years of LE gained, respectively. The deaths attributable to elevated BP in Jiangxi province has increased by 35% from 2007 to 2010, with 0.8 years of LE loss, suggesting the necessity to take actions to control BP in Chinese population. PMID:26426647

  17. Medical bill problems steady for U.S. families, 2007-2010.

    PubMed

    Sommers, Anna; Cunningham, Peter J

    2011-12-01

    More than one in five Americans were in families reporting problems paying medical bills in 2010--about the same proportion as in 2007, according to a new national study by the Center for Studying Health System Change (HSC). Given the severe 2007-09 recession, the sluggish economic recovery and health care costs continuing to increase faster than incomes, it is somewhat surprising that the rate of medical bill problems did not increase between 2007 and 2010. The steady rate of medical bill problems may be a byproduct of decreased use of medical care--both by people who lost jobs and health insurance during the recession and others who cut back on medical care in the face of uncertain economic times. While problems paying medical bills stabilized in recent years, the proportion of Americans in families with medical bill problems remained significantly higher in 2010 compared with 2003--20.9 percent vs. 15.1 percent. And, in 2010, many people in families with problems paying medical bills continued to experience severe financial consequences, with about two-thirds reporting problems paying for other necessities and a quarter considering bankruptcy. PMID:22207915

  18. Changing Epidemiology of Common Cancers in Southern Iran, 2007-2010: A Cross Sectional Study

    PubMed Central

    Masoompour, Seyed Masoom; Lankarani, Kamran B.; Honarvar, Behnam; Tabatabaee, Seyed Hamidreza; Moghadami, Mohsen; Khosravizadegan, Zahra

    2016-01-01

    We have evaluated the ever changing epidemiology of cancers in Fars province, Iran since the re-establishment of Fars cancer registry. Based on the collected data from all related sources in Fars province from 2007–2010 we calculated the cancer age-standardized rates per 100,000 person-years (ASRs). The results are presented as incidence rates of cases by site according to the International Classification of Diseases for Oncology (ICD-O), sex, age, crude rate, and ASRs. In women the total ASR was 41.70 per 100,000 from 1985–1989 which had increased to 55.50 and 95.46 during 1998–2002 and 2007–2010. The incidence of breast cancer in women during 2007–2010 was about two and four times higher than 1998–2002 and 1985–1989. The incidence of colorectal cancer in women during 2007–2010 was about three and five times higher than 1998–2002 and 1985–1989. In men the total ASR was 62.9 per 100,000 in 1985–1989 that increased to 64.50 and 101.48 during 1998–2002 and 2007–2010. Although stomach cancer was the most common cancer among men during 1985–1989 and 1998–2002, but in recent study bladder cancer was the most common cancer among men in Fars province. The incidence of colorectal cancer in men during 2007–2010 was about three times higher than 1998–2002 and 1985–1989. This study shows growing incidence of cancer in southern Iran. The colorectal cancer in both genders had increased and its pattern is similar to western countries. In men, bladder and prostate cancers had a growing rate and the incidences of these cancers in the present study were greater than stomach cancer. PMID:27219458

  19. Three Years of on Orbit ISS Oxygen Generation System Operation 2007-2010

    NASA Technical Reports Server (NTRS)

    Diderich, Greg S.; Polis, Pete; VanKeuren, Steven P.; Erickson, Bob

    2010-01-01

    The International Space Station (ISS) United States Orbital Segment (USOS) Oxygen Generation System (OGS) has accumulated 240 days of continuous operation at varied oxygen production rates within the US Laboratory Module (LAB) since it was first activated in July 2007. OGS relocated from the ISS LAB to Node 3 during 20A Flight (February 2010). The OGS rack delivery was accelerated for on-orbit checkout in the LAB, and it was launched to ISS in July of 2006. During the on-orbit checkout interval within the LAB from July 2007 to October 2008, OGS operational times were limited by the quantity of feedwater in a Payload Water Reservoir (PWR) bag. Longer runtimes are now achievable due to the continuous feedwater availability after ULF2 delivery and activation of the USOS Water Recovery System (WRS) racks. OGS is considered a critical function to maintaining six crew capability. There have been a number of failures which interrupted or threatened to interrupt oxygen production. Filters in the recirculation loop have clogged and have been replaced, Hydrogen sensors have fallen out of specifications, a pump delta pressure sensor failed, a pump failed to start, and the voltage on the cell stack increased out of tolerance. This paper will discuss the operating experience and characteristics of the OGS, as well as operational issues and their resolution.

  20. Some views on nuclear reactor safety

    SciTech Connect

    Tanguy, P.Y.

    1995-04-01

    This document is the text of a speech given by Pierre Y. Tanguy (Electricite de France) at the 22nd Water Reactor Safety Meeting held in Bethesda, MD in 1994. He describes the EDF nuclear program in broad terms and proceeds to discuss operational safety results with EDF plants. The speaker also outlines actions to enhance safety planned for the future, and he briefly mentions French cooperation with the Chinese on the Daya Bay project.

  1. Pantex: safety in nuclear weapons processing.

    PubMed

    Johannesen, R E; Farrell, L M

    2000-11-01

    The Pantex Plant, located in the Texas panhandle near Amarillo, is a major Department of Energy (DOE) participant in maintaining the safety of the nation's nuclear weapons resources and protecting the employees, public, and environment. With more than 168,000 person-years of operations involving nuclear materials, explosives, and hazardous chemicals, Pantex has maintained a notable safety record. This article overviews the nuclear weapon activities at Pantex and describes their safety culture. PMID:11045518

  2. Safety in the Elementary Science Classroom.

    ERIC Educational Resources Information Center

    National Science Teachers Association, Arlington, VA.

    This guide gives elementary school teachers suggestions for providing a safe environment for their students and covers general safety concerns in the science classroom. Information is printed in a flip chart format for easy reference. Safety areas covered include: (1) In Case of Accident; (2) Eye Protection; (3) Plants in the Classroom; (4) First…

  3. Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2, Docket Nos. 50-390 and 50-391, Tennessee Valley Authority. Supplement number 20

    SciTech Connect

    1996-02-01

    This report supplements the Safety Evaluation Report (SER), NUREG-0847 (June 1982), Supplement No. 1 (September 1982), Supplement No. 2 (January 1984), Supplement No. 3 (January 1985), Supplement No. 4 (March 1985), Supplement No. 5 (November 1990), Supplement No. 6 (April 1991), Supplement No. 7 (September 1991), Supplement No. 8 (January 1992), Supplement No. 9 (June 1992), Supplement No. 10 (October 1992), Supplement No. 11 (April 1993), Supplement No. 12 (October 1993), Supplement No. 13 (April 1994), Supplement No. 14 (December 1994), Supplement No. 15 (June 1995), Supplement No. 16 (September 1995), Supplement No. 17 (October 1995), Supplement No. 18 (October 1995), and Supplement No. 19 (November 1995) issued by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by the Tennessee Valley Authority, as applicant and owner, for licenses to operate the Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). The facility is located in Rhea County, Tennessee, near the Watts Bar Dam on the Tennessee River. This supplement provides recent information regarding resolution of some of the issues identified in the SER.

  4. Nuclear criticality safety engineer qualification program utilizing SAT

    SciTech Connect

    Baltimore, C.J.; Dean, J.C.; Henson, T.L.

    1996-12-31

    As part of the privatization process of the U.S. uranium enrichment plants, the Paducah Gaseous Diffusion Plant (PGDP) and the Portsmouth Gaseous Diffusion Plant (PORTS) have been in transition from U.S. Department of Energy (DOE) regulatory oversight to U.S. Nuclear Regulatory Commission (NRC) oversight since July 1993. One of the focus areas of this transition has been training and qualification of plant personnel who perform tasks important to nuclear safety, such as nuclear criticality safety (NCS) engineers.

  5. Safety harness

    DOEpatents

    Gunter, Larry W.

    1993-01-01

    A safety harness to be worn by a worker, especially a worker wearing a plastic suit thereunder for protection in a radioactive or chemically hostile environment, which safety harness comprises a torso surrounding portion with at least one horizontal strap for adjustably securing the harness about the torso, two vertical shoulder straps with rings just forward of the of the peak of the shoulders for attaching a life-line and a pair of adjustable leg supporting straps releasibly attachable to the torso surrounding portion. In the event of a fall, the weight of the worker, when his fall is broken and he is suspended from the rings with his body angled slightly back and chest up, will be borne by the portion of the leg straps behind his buttocks rather than between his legs. Furthermore, the supporting straps do not restrict the air supplied through hoses into his suit when so suspended.

  6. Safety valve

    DOEpatents

    Bergman, Ulf C.

    1984-01-01

    The safety valve contains a resilient gland to be held between a valve seat and a valve member and is secured to the valve member by a sleeve surrounding the end of the valve member adjacent to the valve seat. The sleeve is movable relative to the valve member through a limited axial distance and a gap exists between said valve member and said sleeve.

  7. Farm Safety

    PubMed Central

    Wilson, G. S.

    1966-01-01

    Accident and safety are related terms; the higher the accident rate in any industry, the greater is the need for safety measures designed to prevent accidents. This article discusses the accident and safety problems in agriculture, which includes horticulture and forestry. There is still a tendency among townspeople to think of the countryside as peaceful and tranquil, a place where nothing happens very quickly and far removed from violent death or crippling injury. This pleasant rustic picture has undergone a striking change in the last 30 years owing to considerable agricultural mechanization and the development of chemical pesticides, which have brought new dangers to those who live and work on the land. Although men have readily adapted themselves to new machines and methods, they have not proved as able to recognize new dangers and learn how to guard against them. In consequence, accidents have increased to such an extent that the whole industry has realized the need for positive preventive measures. In this country, it is generally accepted that an employer of labour has a responsibility to provide safe working conditions for those he employs. Farm safety legislation goes a little further and usually requires an employer to provide necessary safeguards, with the added requirement on a worker to make use of them. It is a feature of accident prevention work that it never reaches a stage when it can be regarded as complete. Even when a reduction in accidents has been achieved, the effort must be sustained or the trend will be quickly reversed. Images PMID:5904095

  8. Immunotherapy of plant viral diseases.

    PubMed

    Benvenuto, E; Tavladoraki, P

    1995-07-01

    The stable expression of antibodies in plants is one recent strategy for the unconventional control of plant viruses that is undergoing development. The advantages of this approach are its wide applicability and intrinsic safety; however, to be successful, the 'genetic immunization' of plants requires careful antibody design, efficient expression and targeting to appropriate cell compartments. PMID:7551641

  9. Safety culture evaluation and asset root cause analysis

    SciTech Connect

    Okrent, D.; Xiong, Y.

    1995-12-31

    This paper examines the role of organizational and management factors in nuclear power plant safety through the use of operating experiences. The ASSET (Assessment of Safety Significant Events Team) reports of thirteen plants (total thirty events) have been analyzed in term of twenty organizational dimensions (factors) identified by Brookhaven National Laboratory and Pennsylvania State University. For three plants detailed results are reported in this paper. The results of thirteen plants are summarized in the form of a table. The study tends to confirm that organizational and management factors play an important role in plant safety. The twenty organizational dimensions and their definitions, in general, were adequate in this study. Formalization, Safety Culture, Technical Knowledge, Training, Roles-Responsibilities and Problem Identification appear to be key organizational factors which influence the safety of nuclear power plants studied.

  10. Safety and Liability.

    ERIC Educational Resources Information Center

    Berthelot, Ronald J.; And Others

    1982-01-01

    This series of five articles highlights Pensacola Junior College's occupational safety course, involving simulated emergencies, Florida's standards for teacher liability, electrical safety in the classroom and laboratory, color coding for machine safety, and Florida industrial arts safety instructional materials. (SK)

  11. Implement proper furnace safety interlocks

    SciTech Connect

    Thomas, C.D.; Schoenmaker, G.J.W.

    1996-07-01

    Cracking furnaces are among some of the most complex operations in chemical process industries (CPI) plants. Consider, for example, the cracking furnaces in ethylene plants. Furnace explosions can occur during the light-off process or from accumulations of unburned fuel, incomplete combustion, or introduction of flammable products into the combustion spaces of the furnace. Over half of all furnace explosions occur during the initial light-off process for the furnace. The deficiencies that cause these events can be grouped into three broad categories: (1) human error; (2) incorrect or incomplete safety controls and equipment arrangement; and (3) equipment malfunction. This article presents a safety system that helps address all three of these categories for light-off events. No system is totally foolproof, but the use of a safety system, along with strict operating discipline, will reduce the number of furnace events encountered over the lifetime of the equipment. (Note that the controls typically referred to as ``combustion control,`` which include process temperature control, fuel-gas control, oxygen trim/draft control, and the like, are not part of the control described here.) Note also that although this system was developed for cracking furnaces in ethylene plants, it is equally applicable to other types of radiant-wall multiple-burner furnaces. It can be used for both new installations and retrofit situations. This safety system is not applicable to boilers or other devices with only one or two burners.

  12. Safety Grooving

    NASA Technical Reports Server (NTRS)

    1985-01-01

    Safety grooving, the cutting of grooves in concrete to increase traction and prevent injury, was first developed to reduce aircraft accidents on wet runways. Represented by the International Grooving and Grinding Association (IG&GA), the industry expanded into highway and pedestrian applications. The technique originated at Langley, which assisted in testing the grooving at airports and on highways. Skidding was reduced, stopping distance decreased, and a vehicle's cornering ability on curves was increased. The process has been extended to animal holding pens, steps, parking lots and other potentially slippery surfaces.

  13. 10 CFR 76.87 - Technical safety requirements.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Technical safety requirements. 76.87 Section 76.87 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safety § 76.87... analysis; (11) Chemical safety; (12) Sharing of facilities, structures, systems and components;...

  14. Innovative modeling approaches for risk assessment in food safety

    Technology Transfer Automated Retrieval System (TEKTRAN)

    Food safety involves preventing foodborne illness by describing ways to properly handle, prepare and store food. Regulation of food safety is applied to companies that produce food. Thus, the goal of food safety regulation is to reduce human pathogens to acceptable levels at the processing plant t...

  15. [Agricultural biotechnology safety assessment].

    PubMed

    McClain, Scott; Jones, Wendelyn; He, Xiaoyun; Ladics, Gregory; Bartholomaeus, Andrew; Raybould, Alan; Lutter, Petra; Xu, Haibin; Wang, Xue

    2015-01-01

    Genetically modified (GM) crops were first introduced to farmers in 1995 with the intent to provide better crop yield and meet the increasing demand for food and feed. GM crops have evolved to include a thorough safety evaluation for their use in human food and animal feed. Safety considerations begin at the level of DNA whereby the inserted GM DNA is evaluated for its content, position and stability once placed into the crop genome. The safety of the proteins coded by the inserted DNA and potential effects on the crop are considered, and the purpose is to ensure that the transgenic novel proteins are safe from a toxicity, allergy, and environmental perspective. In addition, the grain that provides the processed food or animal feed is also tested to evaluate its nutritional content and identify unintended effects to the plant composition when warranted. To provide a platform for the safety assessment, the GM crop is compared to non-GM comparators in what is typically referred to as composition equivalence testing. New technologies, such as mass spectrometry and well-designed antibody-based methods, allow better analytical measurements of crop composition, including endogenous allergens. Many of the analytical methods and their intended uses are based on regulatory guidance documents, some of which are outlined in globally recognized documents such as Codex Alimentarius. In certain cases, animal models are recommended by some regulatory agencies in specific countries, but there is typically no hypothesis or justification of their use in testing the safety of GM crops. The quality and standardization of testing methods can be supported, in some cases, by employing good laboratory practices (GLP) and is recognized in China as important to ensure quality data. Although the number of recommended, in some cases, required methods for safety testing are increasing in some regulatory agencies, it should be noted that GM crops registered to date have been shown to be

  16. Autoclave nuclear criticality safety analysis

    SciTech Connect

    D`Aquila, D.M.; Tayloe, R.W. Jr.

    1991-12-31

    Steam-heated autoclaves are used in gaseous diffusion uranium enrichment plants to heat large cylinders of UF{sub 6}. Nuclear criticality safety for these autoclaves is evaluated. To enhance criticality safety, systems are incorporated into the design of autoclaves to limit the amount of water present. These safety systems also increase the likelihood that any UF{sub 6} inadvertently released from a cylinder into an autoclave is not released to the environment. Up to 140 pounds of water can be held up in large autoclaves. This mass of water is sufficient to support a nuclear criticality when optimally combined with 125 pounds of UF{sub 6} enriched to 5 percent U{sup 235}. However, water in autoclaves is widely dispersed as condensed droplets and vapor, and is extremely unlikely to form a critical configuration with released UF{sub 6}.

  17. Safety analysis

    NASA Technical Reports Server (NTRS)

    Knight, John C.

    1995-01-01

    We are engaged in a research program in safety-critical computing that is based on two case studies. We use these case studies to provide application-specific details of the various research issues, and as targets for evaluation of research ideas. The first case study is the Magnetic Stereotaxis System (MSS), an investigational device for performing human neurosurgery being developed in a joint effort between the Department of Physics at the University of Virginia and the Department of Neurosurgery at the University of Iowa. The system operates by manipulating a small permanent magnet (known as a 'seed') within the brain using an externally applied magnetic field. By varying the magnitude and gradient of the external magnetic field, the seed can be moved along a non-linear path and positioned at a site requiring therapy, e.g., a tumor. The magnetic field required for movement through brain tissue is extremely high, and is generated by a set of six superconducting magnets located in a housing surrounding the patient's head. The system uses two X-ray cameras positioned at right angles to detect in real time the locations of the seed and of X-ray opaque markers affixed to the patient's skull. the X-ray images are used to locate the objects of interest in a canonical frame of reference. the second case study is the University of Virginia Research Nuclear Reactor (UVAR). It is a 2 MW thermal, concrete-walled pool reactor. The system operates using 20 to 25 plate-type fuel assemblies placed on a rectangular grid plate. There are three scramable safety rods, and one non-scramable regulating rod that can be put in automatic mode. It was originally constructed in 1959 as a 1 MW system, and it was upgraded to 2 MW in 1973. Though only a research reactor rather than a power reactor, the issues raised are significant and can be related to the problems faced by full-scale reactor systems.

  18. Rebuilding a safety culture

    NASA Astrophysics Data System (ADS)

    Rodney, George A.

    1991-11-01

    The development of a culture of safety and NASA since the Challenger accident is reviewed. The technical elements of the strengthened NASA safety program are described, including problem reporting, risk/assessment/risk management, operational safety, and safety assurance are addressed. Future directions in the development of safety are considered.

  19. Safety in the Workplace.

    ERIC Educational Resources Information Center

    Shaw, Richard

    1999-01-01

    Addresses workplace safety needs and tips for helping an organization achieve a high level of safety. Tips include showing administration commitment, establishing retribution-free reporting of safety problems and violations, rewarding excellent safety effort, and allowing no compromises in following safety procedures. (GR)

  20. Rebuilding a safety culture

    NASA Technical Reports Server (NTRS)

    Rodney, George A.

    1991-01-01

    The development of a culture of safety and NASA since the Challenger accident is reviewed. The technical elements of the strengthened NASA safety program are described, including problem reporting, risk/assessment/risk management, operational safety, and safety assurance are addressed. Future directions in the development of safety are considered.

  1. Attentional bias toward safety predicts safety behaviors.

    PubMed

    Xu, Yaoshan; Li, Yongjuan; Wang, Guangxi; Yuan, Xiao; Ding, Weidong; Shen, Zhongxiang

    2014-10-01

    Safety studies have primarily focused on how explicit processes and measures affect safety behavior and subsequent accidents and injuries. Recently, safety researchers have paid greater attention to the role of implicit processes. Our research focuses on the role of attentional bias toward safety (ABS) in workplace safety. ABS is a basic, early-stage cognitive process involving the automatic and selective allocation of attentional resources toward safety cues, which reflect the implicit motivational state of employees regarding safety goal. In this study, we used two reaction time-based paradigms to measure the ABS of employees in three studies: two modified Stroop tasks (Studies 1 and 2) and a visual dot-probe task (Study 3). Results revealed that employees with better safety behavior showed significant ABS (Study 2), and greater ABS than employees with poorer safety behavior (Studies 1 and 2). Moreover, ABS was positively associated with the perceived safety climate and safety motivation of employees, both of which mediate the effect of ABS on safety behavior (Study 3). These results contributed to a deeper understanding of how early-stage automatic perceptual processing affects safety behavior. The practical implications of these results were also discussed. PMID:24922613

  2. Workplace Safety and Health Topics: Safety & Prevention

    MedlinePlus

    ... message, please visit this page: About CDC.gov . Workplace Safety and Health Topics Industries & Occupations Hazards & Exposures Diseases & ... Pinterest Twitter YouTube NIOSH Homepage NIOSH A-Z Workplace Safety & Health Topics Publications and Products Programs Contact NIOSH ...

  3. Food safety.

    PubMed

    Borchers, Andrea; Teuber, Suzanne S; Keen, Carl L; Gershwin, M Eric

    2010-10-01

    Food can never be entirely safe. Food safety is threatened by numerous pathogens that cause a variety of foodborne diseases, algal toxins that cause mostly acute disease, and fungal toxins that may be acutely toxic but may also have chronic sequelae, such as teratogenic, immunotoxic, nephrotoxic, and estrogenic effects. Perhaps more worrisome, the industrial activities of the last century and more have resulted in massive increases in our exposure to toxic metals such as lead, cadmium, mercury, and arsenic, which now are present in the entire food chain and exhibit various toxicities. Industrial processes also released chemicals that, although banned a long time ago, persist in the environment and contaminate our food. These include organochlorine compounds, such as 1,1,1-trichloro-2,2-bis(p-chlorophenyl)ethane (dichlorodiphenyl dichloroethene) (DDT), other pesticides, dioxins, and dioxin-like compounds. DDT and its breakdown product dichlorophenyl dichloroethylene affect the developing male and female reproductive organs. In addition, there is increasing evidence that they exhibit neurodevelopmental toxicities in human infants and children. They share this characteristic with the dioxins and dioxin-like compounds. Other food contaminants can arise from the treatment of animals with veterinary drugs or the spraying of food crops, which may leave residues. Among the pesticides applied to food crops, the organophosphates have been the focus of much regulatory attention because there is growing evidence that they, too, affect the developing brain. Numerous chemical contaminants are formed during the processing and cooking of foods. Many of them are known or suspected carcinogens. Other food contaminants leach from the packaging or storage containers. Examples that have garnered increasing attention in recent years are phthalates, which have been shown to induce malformations in the male reproductive system in laboratory animals, and bisphenol A, which negatively

  4. Probabilistic Safety Assessment of Tehran Research Reactor

    SciTech Connect

    Hosseini, Seyed Mohammad Hadi; Nematollahi, Mohammad Reza; Sepanloo, Kamran

    2004-07-01

    Probabilistic Safety Assessment (PSA) application is found to be a practical tool for research reactor safety due to intense involvement of human interactions in an experimental facility. In this paper the application of the Probabilistic Safety Assessment to the Tehran Research Reactor (TRR) is presented. The level 1 PSA application involved: Familiarization with the plant, selection of accident initiators, mitigating functions and system definitions, event tree constructions and quantification, fault tree constructions and quantification, human reliability, component failure data base development and dependent failure analysis. Each of the steps of the analysis given above is discussed with highlights from the selected results. Quantification of the constructed models is done using SAPHIRE software. This Study shows that the obtained core damage frequency for Tehran Research Reactor (8.368 E-6 per year) well meets the IAEA criterion for existing nuclear power plants (1E-4). But safety improvement suggestions are offered to decrease the most probable accidents. (authors)

  5. Principles of providing inherent self-protection and passive safety characteristics of the SVBR-75/100 type modular reactor installation for nuclear power plants of different capacity and purpose

    SciTech Connect

    Toshinsky, G.I.; Komlev, O.G.; Novikova, N.N.; Tormyshev, I.V.; Stepanov, V.S.; Klimov, N.N.; Dedoul, A.V.

    2007-07-01

    The report presents a brief description of the reactor installation SVBR-75/100, states a concept of providing the RI safety and presents the basic results of the analysis of the most dangerous pre-accidental situations and beyond the design basis accidents, which have been obtained in the process of validating the RI safety. It has been shown that the safety functions concerning the accidental shutdown of the reactor, total blacking out of the NPP and localization of the accidental situation relating to the postulated simultaneous rupture of several steam-generator tubes are not subject to influence of the human factor and are entirely realized in a passive way. (authors)

  6. Nuclear criticality safety guide

    SciTech Connect

    Pruvost, N.L.; Paxton, H.C.

    1996-09-01

    This technical reference document cites information related to nuclear criticality safety principles, experience, and practice. The document also provides general guidance for criticality safety personnel and regulators.

  7. Farm Health and Safety

    MedlinePlus

    ... jobs in the United States. Farms have many health and safety hazards, including Chemicals and pesticides Machinery, ... equipment can also reduce accidents. Occupational Safety and Health Administration

  8. Medical Device Safety

    MedlinePlus

    ... Vaccines, Blood & Biologics Animal & Veterinary Cosmetics Tobacco Products Medical Devices Home Medical Devices Medical Device Safety Medical Device Safety Share Tweet Linkedin Pin it More sharing ...

  9. The Future of Plant Biotechnology

    Technology Transfer Automated Retrieval System (TEKTRAN)

    Plant biotechnology has been wildly successful and has literally transformed plant agriculture. There are still undulating concerns about safety and sustainability that critics demand to be addressed. In that light, there are some biotechnoloogies that are being developed that might not only improve...

  10. Elements of Successful Plant Management.

    ERIC Educational Resources Information Center

    Sweitzer, John H.

    The physical plant administrator manages men, money and materials to create the best possible physical environment for the educational processes at his institution. Areas of concern of the plant administrator are administration, building maintenance, janitorial services, traffic, security and safety, utilities, grounds, alterations, and…

  11. RISK-INFORMED SAFETY MARGIN CHARACTERIZATION

    SciTech Connect

    Nam Dinh; Ronaldo Szilard

    2009-07-01

    The concept of safety margins has served as a fundamental principle in the design and operation of commercial nuclear power plants (NPPs). Defined as the minimum distance between a system’s “loading” and its “capacity”, plant design and operation is predicated on ensuring an adequate safety margin for safety-significant parameters (e.g., fuel cladding temperature, containment pressure, etc.) is provided over the spectrum of anticipated plant operating, transient and accident conditions. To meet the anticipated challenges associated with extending the operational lifetimes of the current fleet of operating NPPs, the United States Department of Energy (USDOE), the Idaho National Laboratory (INL) and the Electric Power Research Institute (EPRI) have developed a collaboration to conduct coordinated research to identify and address the technological challenges and opportunities that likely would affect the safe and economic operation of the existing NPP fleet over the postulated long-term time horizons. In this paper we describe a framework for developing and implementing a Risk-Informed Safety Margin Characterization (RISMC) approach to evaluate and manage changes in plant safety margins over long time horizons.

  12. Food Safety Practices in the Egg Products Industry.

    PubMed

    Viator, Catherine L; Cates, Sheryl C; Karns, Shawn A; Muth, Mary K; Noyes, Gary

    2016-07-01

    We conducted a national census survey of egg product plants (n = 57) to obtain information on the technological and food safety practices of the egg products industry and to assess changes in these practices from 2004 to 2014. The questionnaire asked about operational and sanitation practices, microbiological testing practices, food safety training for employees, other food safety issues, and plant characteristics. The findings suggest that improvements were made in the industry's use of food safety technologies and practices between 2004 and 2014. The percentage of plants using advanced pasteurization technology and an integrated, computerized processing system increased by almost 30 percentage points. Over 90% of plants voluntarily use a written hazard analysis and critical control point (HACCP) plan to address food safety for at least one production step. Further, 90% of plants have management employees who are trained in a written HACCP plan. Most plants (93%) conduct voluntary microbiological testing. The percentage of plants conducting this testing on egg products before pasteurization has increased by almost 30 percentage points since 2004. The survey findings identify strengths and weaknesses in egg product plants' food safety practices and can be used to guide regulatory policymaking and to conduct required regulatory impact analysis of potential regulations. PMID:27357041

  13. Evaluation of reliability assurance approaches to operational nuclear safety

    SciTech Connect

    Mueller, C.J.; Bezella, W.A.

    1984-01-01

    This report discusses the results of research to evaluate existing and/or recommended safety/reliability assurance activities among nuclear and other high technology industries for potential nuclear industry implementation. Since the Three Mile Island (TMI) accident, there has been increased interest in the use of reliability programs (RP) to assure the performance of nuclear safety systems throughout the plant's lifetime. Recently, several Nuclear Regulatory Commission (NRC) task forces or safety issue review groups have recommended RPs for assuring the continuing safety of nuclear reactor plants. 18 references.

  14. DEINVENTORY THE CRITICALITY SAFETY ENDGAME

    SciTech Connect

    ROGERS, C.A.

    2005-03-15

    Criticality safety begins with the design and evaluation of a fissionable material operation and continues even after the operation has been shut down. An interest in criticality safety is maintained until all fissionable material has been removed. This paper examines the process of removing fissionable material with the goal of no longer requiring criticality safety control. The word ''de-inventory'' (usually written deinventory) was coined at the Plutonium Finishing Plant on the Hanford Atomic Reservation to describe this process. The cleanout of gloveboxes at the Plutonium Finishing Plant illustrates typical deinventory operations. Although tanks may have been previously drained of their solutions, residual contents remain for which the plutonium content must be estimated. Normally, this is accomplished using Non-Destructive Assay (NDA) techniques that require conservative correction factors to compensate for tank wall shielding apparatus geometry, fissile material distribution, detector efficiencies, and detector locations. The plutonium inventory is usually overestimated. A Kickoff Meeting is held to review planned operations. Then a criticality safety evaluation of the operations is written, and limits and controls are established. In practice, an evaluation may turn out to be significantly more difficult than it at first appeared, primarily due to uncertainties in the quantity and distribution of the residual plutonium and liquid. The evaluation process can sometimes be streamlined by taking advantage of similarities in design, plutonium inventory, and operations to a glovebox previously evaluated. If an existing Criticality Safety Evaluation Report (CSER) can be shown to bound the new operations, it may be used as the basis for establishing limits and controls for the new operations. Otherwise, a new CSER must be completed and approved.

  15. Molten salt safety study. Final report

    SciTech Connect

    Not Available

    1980-01-01

    The considerations concerning safety in using molten salt (40% potassium nitrate, 60% sodium nitrate) in a solar central receiver plant are addressed. The considerations are of a general nature and do not cover any details of equipment or plant operation. The study includes salt chemical reaction, experiments with molten salt, dry storage and handling constraints, and includes data from the National Fire Protection Association. The contents of this report were evaluated by two utility companies and they concluded that no major safety problems exist in using a molten salt solar system.

  16. Vibration of safety injection pump motors

    SciTech Connect

    Wattrelos, D.

    1996-12-01

    This paper covers a fault encountered in the safety injection pump motors of the French 900 MWe unit nuclear power stations. This fault was not revealed either during the low pressure safety injection and containment spray system pump qualification tests under accident conditions or during the special tests on a test bench carried out to attempt to replicate the fault and to identify ways of remedying it. This constitutes a potential common mode of failure of the safety injection system and the containment spray system pumps. The vibration phenomena illustrate the importance of carrying out tests in the plants under conditions as close as possible to those of actual accident situations.

  17. Safety assessment of the tritium recovery system

    SciTech Connect

    Not Available

    1994-09-01

    This Safety Assessment (SA) contains descriptions and evaluations of the environmental, health, and safety issues associated with the Tritium Recovery System (TRS) at the Pinellas Plant. It provides: 1. site and facility descriptions, 2. an overall description of the TRS and its operations, 3. an evaluation of the hazards associated with TRS operations, 4. descriptions and analyses of the adequacy of measures taken to eliminate, control, or mitigate identified hazards, and 5. assessment of potential accidents and their associated risks. This SA contains the results of safety evaluations of TRS operations, equipment, and supplied systems. The evaluations include, as appropriate, preliminary hazards listings, qualitative risk assessments, and quantitative risk assessments.

  18. CRITICALITY SAFETY CONTROLS AND THE SAFETY BASIS AT PFP

    SciTech Connect

    Kessler, S

    2009-04-21

    With the implementation of DOE Order 420.1B, Facility Safety, and DOE-STD-3007-2007, 'Guidelines for Preparing Criticality Safety Evaluations at Department of Energy Non-Reactor Nuclear Facilities', a new requirement was imposed that all criticality safety controls be evaluated for inclusion in the facility Documented Safety Analysis (DSA) and that the evaluation process be documented in the site Criticality Safety Program Description Document (CSPDD). At the Hanford site in Washington State the CSPDD, HNF-31695, 'General Description of the FH Criticality Safety Program', requires each facility develop a linking document called a Criticality Control Review (CCR) to document performance of these evaluations. Chapter 5, Appendix 5B of HNF-7098, Criticality Safety Program, provided an example of a format for a CCR that could be used in lieu of each facility developing its own CCR. Since the Plutonium Finishing Plant (PFP) is presently undergoing Deactivation and Decommissioning (D&D), new procedures are being developed for cleanout of equipment and systems that have not been operated in years. Existing Criticality Safety Evaluations (CSE) are revised, or new ones written, to develop the controls required to support D&D activities. Other Hanford facilities, including PFP, had difficulty using the basic CCR out of HNF-7098 when first implemented. Interpretation of the new guidelines indicated that many of the controls needed to be elevated to TSR level controls. Criterion 2 of the standard, requiring that the consequence of a criticality be examined for establishing the classification of a control, was not addressed. Upon in-depth review by PFP Criticality Safety staff, it was not clear that the programmatic interpretation of criterion 8C could be applied at PFP. Therefore, the PFP Criticality Safety staff decided to write their own CCR. The PFP CCR provides additional guidance for the evaluation team to use by clarifying the evaluation criteria in DOE-STD-3007-2007. In

  19. Transportation Safety Excellence in Operations Through Improved Transportation Safety Document

    SciTech Connect

    Dr. Michael A. Lehto; MAL

    2007-05-01

    A recent accomplishment of the Idaho National Laboratory (INL) Materials and Fuels Complex (MFC) Nuclear Safety analysis group was to obtain DOE-ID approval for the inter-facility transfer of greater-than-Hazard-Category-3 quantity radioactive/fissionable waste in Department of Transportation (DOT) Type A drums at MFC. This accomplishment supported excellence in operations through safety analysis by better integrating nuclear safety requirements with waste requirements in the Transportation Safety Document (TSD); reducing container and transport costs; and making facility operations more efficient. The MFC TSD governs and controls the inter-facility transfer of greater-than-Hazard-Category-3 radioactive and/or fissionable materials in non-DOT approved containers. Previously, the TSD did not include the capability to transfer payloads of greater-than-Hazard-Category-3 radioactive and/or fissionable materials using DOT Type A drums. Previous practice was to package the waste materials to less-than-Hazard-Category-3 quantities when loading DOT Type A drums for transfer out of facilities to reduce facility waste accumulations. This practice allowed operations to proceed, but resulted in drums being loaded to less than the Waste Isolation Pilot Plant (WIPP) waste acceptance criteria (WAC) waste limits, which was not cost effective or operations friendly. An improved and revised safety analysis was used to gain DOE-ID approval for adding this container configuration to the MFC TSD safety basis. In the process of obtaining approval of the revised safety basis, safety analysis practices were used effectively to directly support excellence in operations. Several factors contributed to the success of MFC’s effort to obtain approval for the use of DOT Type A drums, including two practices that could help in future safety basis changes at other facilities. 1) The process of incorporating the DOT Type A drums into the TSD at MFC helped to better integrate nuclear safety

  20. Passive Safety Features for Small Modular Reactors

    SciTech Connect

    Ingersoll, Daniel T

    2010-01-01

    The rapid growth in the size and complexity of commercial nuclear power plants in the 1970s spawned an interest in smaller, simpler designs that are inherently or intrinsically safe through the use of passive design features. Several designs were developed, but none were ever built, although some of their passive safety features were incorporated into large commercial plant designs that are being planned or built today. In recent years, several reactor vendors are actively redeveloping small modular reactor (SMR) designs with even greater use of passive features. Several designs incorporate the ultimate in passive safety they completely eliminate specific accident initiators from the design. Other design features help to reduce the likelihood of an accident or help to mitigate the accident s consequences, should one occur. While some passive safety features are common to most SMR designs, irrespective of the coolant technology, other features are specific to water, gas, or liquid-metal cooled SMR designs. The extensive use of passive safety features in SMRs promise to make these plants highly robust, protecting both the general public and the owner/investor. Once demonstrated, these plants should allow nuclear power to be used confidently for a broader range of customers and applications than will be possible with large plants alone.

  1. Integrating Safety Assessment Methods using the Risk Informed Safety Margins Characterization (RISMC) Approach

    SciTech Connect

    Curtis Smith; Diego Mandelli

    2013-03-01

    Safety is central to the design, licensing, operation, and economics of nuclear power plants (NPPs). As the current light water reactor (LWR) NPPs age beyond 60 years, there are possibilities for increased frequency of systems, structures, and components (SSC) degradations or failures that initiate safety significant events, reduce existing accident mitigation capabilities, or create new failure modes. Plant designers commonly “over-design” portions of NPPs and provide robustness in the form of redundant and diverse engineered safety features to ensure that, even in the case of well-beyond design basis scenarios, public health and safety will be protected with a very high degree of assurance. This form of defense-in-depth is a reasoned response to uncertainties and is often referred to generically as “safety margin.” Historically, specific safety margin provisions have been formulated primarily based on engineering judgment backed by a set of conservative engineering calculations. The ability to better characterize and quantify safety margin is important to improved decision making about LWR design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margin management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved. In addition, as research and development (R&D) in the LWR Sustainability (LWRS) Program and other collaborative efforts yield new data, sensors, and improved scientific understanding of physical processes that govern the aging and degradation of plant SSCs needs and opportunities to better optimize plant safety and performance will become known. To support decision making related to economics, readability, and safety, the RISMC Pathway provides methods and tools that enable mitigation options known as margins management strategies. The purpose of the RISMC Pathway R&D is to support plant decisions for risk

  2. Safety: An Attitude

    ERIC Educational Resources Information Center

    Smith, Harry T.

    1978-01-01

    Describes eight safety concepts developed by the author to teach safety and accident prevention in industrial arts shops and to promote more positive student attitudes toward shop safety. Stressing several general safety concepts instead of requiring dozens of rules has been found to work. (MF)

  3. Launch Services Safety Overview

    NASA Technical Reports Server (NTRS)

    Loftin, Charles E.

    2008-01-01

    NASA/KSC Launch Services Division Safety (SA-D) services include: (1) Assessing the safety of the launch vehicle (2) Assessing the safety of NASA ELV spacecraft (S/C) / launch vehicle (LV) interfaces (3) Assessing the safety of spacecraft processing to ensure resource protection of: - KSC facilities - KSC VAFB facilities - KSC controlled property - Other NASA assets (4) NASA personnel safety (5) Interfacing with payload organizations to review spacecraft for adequate safety implementation and compliance for integrated activities (6) Assisting in the integration of safety activities between the payload, launch vehicle, and processing facilities

  4. Periodic Safety Review on Safety Analyses of Kori Nuclear Units 3,4

    SciTech Connect

    Jong Woon Park; Sung Heum Han; Byoung Hwan Bae

    2004-07-01

    In order to maintain the operating plant safety at current safety standards, Periodic Safety Review (PSR) is legislated in 2001 in Korea as a 10-year-basis safety evaluation process. One of the eleven topics addressed in the PSR is safety analysis, in which the compliance of plants' safety analyses with current standards on initiating events and scope, methods and assumptions are evaluated. This paper describes the methods and results of the PSR on safety analysis of the Kori nuclear units 3,4, 3-Loop pressurized water reactors in operation from 1984. The review areas are design-basis, beyond-design basis and severe accidents. Evaluation of design basis accidents (DBA) in the Kori units 3,4 Final Safety Analysis Report (FSAR) issued a lack of consideration of loss of offsite power (LOOP) in some DBAs. To resolve this, electric power system stability analysis has been performed to show that sufficient time delay of reactor coolant pump trip after LOOP makes the current FSAR DBA analyses still valid with additional assumption of LOOP as an initiating event. Also, to get confidence on defense-in-depth safety, thermal hydraulic analyses are performed for beyond-design basis and severe accidents. A typical high-pressure scenario, total loss of feedwater event, is selected and analyzed by using RELAP5/MOD3 and MAAP4 computer codes for recovered and un-recovered cases, respectively. It is shown that using safety-grade pressurizer relief valves, the two cases meet the criteria that are applied to the new Korean Standard Nuclear Plants (KSNP) in Korea. It is thus concluded that the Kori units 3,4 have good design capabilities to prevent and mitigate broad spectrum of reactor accidents from design basis to severe accidents. (authors)

  5. TWRS safety program plan

    SciTech Connect

    Calderon, L.M., Westinghouse Hanford

    1996-08-01

    Management of Nuclear Safety, Industrial Safety, Industrial Hygiene, and Fire Protection programs, functions, and field support resources for Tank Waste Remediation Systems (TWRS) has, until recently, been centralized in TWRS Safety, under the Emergency, Safety, and Quality organization. Industrial hygiene technician services were also provided to support operational needs related to safety basis compliance. Due to WHC decentralization of safety and reengineering efforts in West Tank Farms, staffing and safety responsibilities have been transferred to the facilities. Under the new structure, safety personnel for TWRS are assigned directly to East Tank Farms, West Tank Farms, and a core Safety Group in TWRS Engineering. The Characterization Project Operations (CPO) safety organization will remain in tact as it currently exists. Personnel assigned to East Tank Farms, West Tank Farms, and CPO will perform facility-specific or project-specific duties and provide field implementation of programs. Those assigned to the core group will focus on activities having a TWRS-wide or programmatic focus. Hanford-wide activities will be the responsibility of the Safety Center of Expertise. In order to ensure an effective and consistent safety program for TWRS under the new organization program functions, goals, organizational structure, roles, responsibilities, and path forward must be clearly established. The purpose of the TWRS Safety Program Plan is to define the overall safety program, responsibilities, relationships, and communication linkages for safety personnel under the new structure. In addition, issues associated with reorganization transition are addressed, including training, project ownership, records management, and dissemination of equipment. For the purpose of this document ``TWRS Safety`` refers to all safety professionals and technicians (Industrial Safety, Industrial Hygiene, Fire Protection, and Nuclear Safety) within the TWRS organization, regardless of their

  6. Seismic Safety Study

    SciTech Connect

    Tokarz, F J; Coats, D W

    2006-05-16

    During the past three decades, the Laboratory has been proactive in providing a seismically safe working environment for its employees and the general public. Completed seismic upgrades during this period have exceeded $30M with over 24 buildings structurally upgraded. Nevertheless, seismic questions still frequently arise regarding the safety of existing buildings. To address these issues, a comprehensive study was undertaken to develop an improved understanding of the seismic integrity of the Laboratory's entire building inventory at the Livermore Main Site and Site 300. The completed study of February 2005 extended the results from the 1998 seismic safety study per Presidential Executive Order 12941, which required each federal agency to develop an inventory of its buildings and to estimate the cost of mitigating unacceptable seismic risks. Degenkolb Engineers, who performed the first study, was recontracted to perform structural evaluations, rank order the buildings based on their level of seismic deficiencies, and to develop conceptual rehabilitation schemes for the most seriously deficient buildings. Their evaluation is based on screening procedures and guidelines as established by the Interagency Committee on Seismic Safety in Construction (ICSSC). Currently, there is an inventory of 635 buildings in the Laboratory's Facility Information Management System's (FIMS's) database, out of which 58 buildings were identified by Degenkolb Engineers that require seismic rehabilitation. The remaining 577 buildings were judged to be adequate from a seismic safety viewpoint. The basis for these evaluations followed the seismic safety performance objectives of DOE standard (DOE STD 1020) Performance Category 1 (PC1). The 58 buildings were ranked according to three risk-based priority classifications (A, B, and C) as shown in Figure 1-1 (all 58 buildings have structural deficiencies). Table 1-1 provides a brief description of their expected performance and damage state

  7. Study Gives Good Odds on Nuclear Reactor Safety

    ERIC Educational Resources Information Center

    Russell, Cristine

    1974-01-01

    Summarized is data from a recent study on nuclear reactor safety completed by Norman C. Rasmussen and others. Non-nuclear events are about 10,000 times more likely to produce large accidents than nuclear plants. (RH)

  8. Fast reactor safety program. Progress report, January-March 1980

    SciTech Connect

    1980-05-01

    The goal of the DOE LMFBR Safety Program is to provide a technology base fully responsive to safety considerations in the design, evaluation, licensing, and economic optimization of LMFBRs for electrical power generation. A strategy is presented that divides safety technology development into seven program elements, which have been used as the basis for the Work Breakdown Structure (WBS) for the Program. These elements include four lines of assurance (LOAs) involving core-related safety considerations, an element supporting non-core-related plant safety considerations, a safety R and D integration element, and an element for the development of test facilities and equipment to be used in Program experiments: LOA-1 (prevent accidents); LOA-2 (limit core damage); LOA-3 (maintain containment integrity); LOA-4 (attenuate radiological consequences); plant considerations; R and D integration; and facility development.

  9. Space engine safety system

    NASA Technical Reports Server (NTRS)

    Maul, William A.; Meyer, Claudia M.

    1991-01-01

    A rocket engine safety system is designed to initiate control procedures which will minimize damage to the engine and vehicle or test stand in the event of an engine failure. This report describes the features and the implementation issues associated with rocket engine safety systems. Specific concerns of safety systems applied to a space-based engine and long duration space missions are discussed. Examples of safety system features and architectures are given from recent safety monitoring investigations conducted for the Space Shuttle Main Engine and for future liquid rocket engines. Also, a general design and implementation process for rocket engine safety systems is presented.

  10. Space engine safety system

    NASA Technical Reports Server (NTRS)

    Maul, William A.; Meyer, Claudia M.

    1991-01-01

    A rocket engine safety system was designed to initiate control procedures to minimize damage to the engine or vehicle or test stand in the event of an engine failure. The features and the implementation issues associated with rocket engine safety systems are discussed, as well as the specific concerns of safety systems applied to a space-based engine and long duration space missions. Examples of safety system features and architectures are given, based on recent safety monitoring investigations conducted for the Space Shuttle Main Engine and for future liquid rocket engines. Also, the general design and implementation process for rocket engine safety systems is presented.

  11. Regulatory views on current criticality safety issues

    SciTech Connect

    Conde, J.M.; Recio, M.

    1996-12-31

    The nuclear facilities in Spain of interest from the stand-point of criticality are a fuel fabrication facility, handling only fresh fuel; seven pressurized water reactor (PWR) plants with different nuclear steam supply system designs; two boiling water reactor (BWR) plants; and an ongoing program of dual-purpose casks (storage and transport) for spent fuel. Given the spent-fuel storage space problems with the original rack designs, a plan was developed and started in 1990 to incorporate high-density racks (borated steel or Boral) in the spent-fuel storage of all plants, giving credit for fuel burnup. Following this plan, five PWR units have licensed burnup-credited criticality safety analyses using a two-zone approach (fresh and spent fuel) for the spent-fuel pool. The two BWR plants have also licensed a criticality safety analysis with credit for the reactivity reduction provided by the gadolinia rods. The only spent-fuel cask yet licensed has followed the expected fresh fuel assumption for the criticality safety evaluation. However, it can be expected that the industry will submit burnup-credit safety analyses for the future casks designs.

  12. New generation of NPP with boiling water reactor of improved safety

    SciTech Connect

    Adamov, E.O.; Kuklin, A.N.; Mityaev, Yu.I.; Mikhan, V.I.; Tokarev, Yu.I.; Cherkashov, Yu.M.; Sokolov, I.N.; Iljin, Yu.V.; Pakh, E.E.; Abramov, V.I.

    1993-12-31

    The nuclear power plants with boiling water reactors of improved safety are being developed. There is 26 years of operating experience with the plant VK-50 in Dimitrovgrad. The design and operation of the BWR reactors are described.

  13. A risk-informed approach to safety margins analysis

    SciTech Connect

    Curtis Smith; Diego Mandelli

    2013-07-01

    The Risk Informed Safety Margins Characterization (RISMC) Pathway is a systematic approach developed to characterize and quantify safety margins of nuclear power plant structures, systems and components. The model has been tested on the Advanced Test Reactor (ATR) at Idaho National Lab.

  14. 76 FR 34773 - Final Safety Culture Policy Statement

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-06-14

    ... Power Plant Operations'' (54 FR 3424; January 24, 1989), applies to all individuals engaged in... of Employees in the Nuclear Industry to Raise Safety Concerns Without Fear of Retaliation'' (61 FR..., Federal Register notice (FRN) (74 FR 6433) entitled ``Safety Culture Policy Statement Development:...

  15. 9 CFR 113.38 - Guinea pig safety test.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 9 Animals and Animal Products 1 2012-01-01 2012-01-01 false Guinea pig safety test. 113.38 Section 113.38 Animals and Animal Products ANIMAL AND PLANT HEALTH INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE VIRUSES, SERUMS, TOXINS, AND ANALOGOUS PRODUCTS; ORGANISMS AND VECTORS STANDARD REQUIREMENTS Standard Procedures § 113.38 Guinea pig safety...

  16. Information Services at the Nuclear Safety Analysis Center.

    ERIC Educational Resources Information Center

    Simard, Ronald

    This paper describes the operations of the Nuclear Safety Analysis Center. Established soon after an accident at the Three Mile Island nuclear power plant near Harrisburg, Pennsylvania, its efforts were initially directed towards a detailed analysis of the accident. Continuing functions include: (1) the analysis of generic nuclear safety issues,…

  17. SAFETY MANUAL FOR WASTEWATER TREATMENT WITH OXYGEN AERATION

    EPA Science Inventory

    This safety manual provides design, operating, and safety personnel of municipal wastewater treatment plants which use oxygen aeration of activated sludge systems with the knowledge to prevent hazards due to the interaction of the oxygen with combustibles and other hazardous mate...

  18. Vocational Education Safety Instruction Manual.

    ERIC Educational Resources Information Center

    Cropley, Russell, Ed.; Doherty, Susan Sloan, Ed.

    This manual describes four program areas in vocational education safety instruction: (1) introduction to a safety program; (2) resources to ensure laboratory safety; (3) safety program implementation; and (4) safety rules and safety tests. The safety rules and tests included in section four are for the most common tools and machines used in…

  19. Medicine safety and children

    MedlinePlus

    ... this page: //medlineplus.gov/ency/patientinstructions/000619.htm Medicine safety and children To use the sharing features ... especially careful if you have toddlers around. Keep Medicines out of Reach and Sight Safety tips: DO ...

  20. Water safety and drowning

    MedlinePlus

    ... among people of all ages. Learning and practicing water safety is important to prevent drowning accidents. ... Water safety tips for all ages include: Learn CPR Never swim alone Never dive into water unless ...

  1. Safety organizations and experts

    NASA Technical Reports Server (NTRS)

    Mandel, G.; Rubinstein, R. I.; Pinto, J. J.; Meschkow, S. Z.

    1977-01-01

    Handbook lists organizations and experts in specific, well defined areas of safety technology. Special emphasis is given to relevant safety information sources on aircraft fire hazards and aircraft interior flammability.

  2. Motor Vehicle Safety

    MedlinePlus

    ... these crashes is one part of motor vehicle safety. Here are some things you can do to ... speed or drive aggressively Don't drive impaired Safety also involves being aware of others. Share the ...

  3. Farm Health and Safety

    MedlinePlus

    ... the United States. Farms have many health and safety hazards, including Chemicals and pesticides Machinery, tools and ... inspection and maintenance can help prevent accidents. Using safety gloves, goggles and other protective equipment can also ...

  4. Safety in Science Laboratories.

    ERIC Educational Resources Information Center

    Education in Science, 1978

    1978-01-01

    Presents 12 amendments to the second edition of Safety in Science Laboratories. Covers topics such as regular inspection of equipment, wearing safety glasses, dating stock chemicals, and safe use of chemicals. (MA)

  5. Security vs. Safety.

    ERIC Educational Resources Information Center

    Sturgeon, Julie

    1999-01-01

    Provides administrative advice on how some safety experts have made college campuses safer and friendlier without breaking the budget. Tips on security and advice on safety management that encompasses the whole environment are highlighted. (GR)

  6. Facility safety study

    NASA Technical Reports Server (NTRS)

    1979-01-01

    The safety of NASA's in house microelectronics facility is addressed. Industrial health standards, facility emission control requirements, operation and safety checklists, and the disposal of epitaxial vent gas are considered.

  7. Spacecraft Fire Safety

    NASA Technical Reports Server (NTRS)

    Margle, Janice M. (Editor)

    1987-01-01

    Fire detection, fire standards and testing, fire extinguishment, inerting and atmospheres, fire-related medical science, aircraft fire safety, Space Station safety concerns, microgravity combustion, spacecraft material flammability testing, and metal combustion are among the topics considered.

  8. Electrical safety guidelines

    SciTech Connect

    Not Available

    1993-09-01

    The Electrical Safety Guidelines prescribes the DOE safety standards for DOE field offices or facilities involved in the use of electrical energy. It has been prepared to provide a uniform set of electrical safety standards and guidance for DOE installations in order to affect a reduction or elimination of risks associated with the use of electrical energy. The objectives of these guidelines are to enhance electrical safety awareness and mitigate electrical hazards to employees, the public, and the environment.

  9. Safety analysts training

    SciTech Connect

    Bolton, P.

    2000-10-01

    The purpose of this task was to support ESH-3 in providing Airborne Release Fraction and Respirable Fraction training to safety analysts at LANL who perform accident analysis, hazard analysis, safety analysis, and/or risk assessments at nuclear facilities. The task included preparation of materials for and the conduct of two 3-day training courses covering the following topics: safety analysis process; calculation model; aerosol physic concepts for safety analysis; and overview of empirically derived airborne release fractions and respirable fractions.

  10. DOE handbook electrical safety

    SciTech Connect

    1998-01-01

    Electrical Safety Handbook presents the Department of Energy (DOE) safety standards for DOE field offices or facilities involved in the use of electrical energy. It has been prepared to provide a uniform set of electrical safety guidance and information for DOE installations to effect a reduction or elimination of risks associated with the use of electrical energy. The objectives of this handbook are to enhance electrical safety awareness and mitigate electrical hazards to employees, the public, and the environment.

  11. Radiation Safety Compliance.

    PubMed

    Koth, Jana; Smith, Marcia Hess

    2016-05-01

    This article discusses radiation safety programs, including the members of the radiation safety team, their roles, and the challenges they face, with a focus on the radiation safety officer's duties. Agencies that regulate radiation safety also are described. The importance of minimizing patient dose, ensuring that dosimetry badges are worn correctly, and using therapeutic radioactive materials safely are addressed. Finally, radiologic technologists' role in using radiation safely is discussed, and the principles of time, distance, and shielding are reviewed. PMID:27146175

  12. Generic safety documentation model

    SciTech Connect

    Mahn, J.A.

    1994-04-01

    This document is intended to be a resource for preparers of safety documentation for Sandia National Laboratories, New Mexico facilities. It provides standardized discussions of some topics that are generic to most, if not all, Sandia/NM facilities safety documents. The material provides a ``core`` upon which to develop facility-specific safety documentation. The use of the information in this document will reduce the cost of safety document preparation and improve consistency of information.

  13. Aviation Safety Issues Database

    NASA Technical Reports Server (NTRS)

    Morello, Samuel A.; Ricks, Wendell R.

    2009-01-01

    The aviation safety issues database was instrumental in the refinement and substantiation of the National Aviation Safety Strategic Plan (NASSP). The issues database is a comprehensive set of issues from an extremely broad base of aviation functions, personnel, and vehicle categories, both nationally and internationally. Several aviation safety stakeholders such as the Commercial Aviation Safety Team (CAST) have already used the database. This broader interest was the genesis to making the database publically accessible and writing this report.

  14. HSE's safety assessment principles for criticality safety.

    PubMed

    Simister, D N; Finnerty, M D; Warburton, S J; Thomas, E A; Macphail, M R

    2008-06-01

    The Health and Safety Executive (HSE) published its revised Safety Assessment Principles for Nuclear Facilities (SAPs) in December 2006. The SAPs are primarily intended for use by HSE's inspectors when judging the adequacy of safety cases for nuclear facilities. The revised SAPs relate to all aspects of safety in nuclear facilities including the technical discipline of criticality safety. The purpose of this paper is to set out for the benefit of a wider audience some of the thinking behind the final published words and to provide an insight into the development of UK regulatory guidance. The paper notes that it is HSE's intention that the Safety Assessment Principles should be viewed as a reflection of good practice in the context of interpreting primary legislation such as the requirements under site licence conditions for arrangements for producing an adequate safety case and for producing a suitable and sufficient risk assessment under the Ionising Radiations Regulations 1999 (SI1999/3232 www.opsi.gov.uk/si/si1999/uksi_19993232_en.pdf). PMID:18495990

  15. Virtual Safety Training.

    ERIC Educational Resources Information Center

    Fuller, Scott; Davis, Jason

    2003-01-01

    The Multimedia Tool Box Talk is a web-based quick reference safety guide and training tool for construction personnel. An intended outcome of this effort was to provide an efficient and effective way to locate and interpret crucial safety information while at the job site. The tool includes information from the Occupational Safety and Health…

  16. School Safety Audit Protocol.

    ERIC Educational Resources Information Center

    DeMary, Jo Lynne; Owens, Marsha; Ramnarain, A. K. Vijay

    The 1997 Virginia General Assembly passed legislation directing school boards to require all schools to conduct safety audits. This audit is designed to assess the safety conditions in each public school to: (1) identify and, if necessary, develop solutions for physical safety concerns, including building security issues; and (2) identify and…

  17. Safety in the Preschool.

    ERIC Educational Resources Information Center

    Settles, Mimi

    Guidelines for safety in the cooperative preschool are outlined, emphasizing control of the physical environment to insure maximum freedom for the children compatible with maximum safety. Building standards are set for stairways, rooms, lavatories, parking lots, harmful supplies, and wading pools. Orientation for safety is discussed in regard to…

  18. Revitalizing Nuclear Safety Research.

    ERIC Educational Resources Information Center

    National Academy of Sciences - National Research Council, Washington, DC.

    This report covers the general issues involved in nuclear safety research and points out the areas needing detailed consideration. Topics included are: (1) "Principles of Nuclear Safety Research" (examining who should fund, who should conduct, and who should set the agenda for nuclear safety research); (2) "Elements of a Future Agenda for Nuclear…

  19. School Bus Safety.

    ERIC Educational Resources Information Center

    Stroup, Karen Bruner; And Others

    1991-01-01

    Equipment to allow safe transportation of disabled children is reviewed. Such equipment includes infant car seats, child safety seats, safety vests, and accommodations for children in casts and/or braces. Five principles for evaluation and selection of safe seating options are given as are safety rules and information on standards and resources.…

  20. SNTP environmental, safety, and health

    NASA Technical Reports Server (NTRS)

    Harmon, Charles D.

    1993-01-01

    Viewgraphs on space nuclear thermal propulsion (SNTP) environmental, safety, and health are presented. Topics covered include: program safety policy; program safety policies; and DEIS public hearing comments.

  1. Power Plant Construction

    NASA Technical Reports Server (NTRS)

    1985-01-01

    Stone & Webster Engineering Corporation utilized TAP-A, a COSMIC program originally developed as part of a NASA investigation into the potential of nuclear power for space launch vehicles. It is useful in nuclear power plant design to qualify safety-related equipment at the temperatures it would experience should an accident occur. The program is easy to use, produces accurate results, and is inexpensive to run.

  2. Good housekeeping: Safety and order in the scientific laboratory

    SciTech Connect

    Sims, B. H.

    2002-01-01

    Laboratory safety might not seem, at first, to be very profoundly related to scientific knowledge. Of course safety is a relatively trivial issue in many scientific settings, especially in comparison to the kind of safety concerns found, say, at a construction site or a chemical plant. However, as scientific work has come to involve more exotic chemicals, biological organisms, and forms of radiation, and generally become more industrial in character, safety has become more of a concern. This has occurred alongside a general expansion of government regulation of workplace safety during the 20thc entury, and a recent trend toward extending work lace safety efforts to new kinds of work, including administrative and professional tasks. As a result of these trends, scientists find that they are increasingly being held responsible for following safety regulations in their re{approx}earc

  3. Safety and IVHM

    NASA Technical Reports Server (NTRS)

    Goebel, Kai

    2012-01-01

    When we address safety in a book on the business case for IVHM, the question arises whether safety isn t inherently in conflict with the need of operators to run their systems as efficiently (and as cost effectively) as possible. The answer may be that the system needs to be just as safe as needed, but not significantly more. That begs the next question: How safe is safe enough? Several regulatory bodies provide guidelines for operational safety, but irrespective of that, operators do not want their systems to be known as lacking safety. We illuminate the role of safety within the context of IVHM.

  4. Safety after cardiac catheterization.

    PubMed

    Huber, Charlotte

    2009-08-01

    The Pennsylvania Patient Safety Authority's reporting system is a confidential, statewide Internet reporting system to which all Pennsylvania hospitals, outpatient-surgery facilities, and birthing centers, as well as some abortion facilities, must file information on medical errors. Safety Monitor is a column from the authority that informs nurses on issues that can affect patient safety and presents strategies they can easily integrate into practice. For more information on the authority, visit www.patientsafetyauthority.org. For the original article discussed in this column or for other articles on patient safety, click on "Patient Safety Advisories" and then "Advisory Library" in the left-hand navigation menu. PMID:19641415

  5. NASA Safety Manual. Volume 3: System Safety

    NASA Technical Reports Server (NTRS)

    1970-01-01

    This Volume 3 of the NASA Safety Manual sets forth the basic elements and techniques for managing a system safety program and the technical methods recommended for use in developing a risk evaluation program that is oriented to the identification of hazards in aerospace hardware systems and the development of residual risk management information for the program manager that is based on the hazards identified. The methods and techniques described in this volume are in consonance with the requirements set forth in NHB 1700.1 (VI), Chapter 3. This volume and future volumes of the NASA Safety Manual shall not be rewritten, reprinted, or reproduced in any manner. Installation implementing procedures, if necessary, shall be inserted as page supplements in accordance with the provisions of Appendix A. No portion of this volume or future volumes of the NASA Safety Manual shall be invoked in contracts.

  6. Safety Tips: Safety Is No Laughing Matter.

    ERIC Educational Resources Information Center

    Hill, Patricia S.; Greco, Thomas G.

    1995-01-01

    Presents the script of a skit designed to engage beginning students in a contest to identify and list the most safety violations they observe during the skit. Includes a list of 37 safe laboratory practices. (MKR)

  7. Subsystem fragility: Seismic Safety Margins Research Program (Phase I)

    SciTech Connect

    Kennedy, R. P.; Campbell, R. D.; Hardy, G.; Banon, H.

    1981-10-01

    Seismic fragility levels of safety related equipment are developed for use in a seismic oriented Probabilistic Risk Assessment (PRA) being conducted as part of the Seismic Safety Margins Research Program (SSMRP). The Zion Nuclear Power Plant is being utilized as a reference plant and fragility descriptions are developed for specific and generic safety related equipment groups in Zion. Both equipment fragilities and equipment responses are defined in probabilistic terms to be used as input to the SSMRP event tree/fault tree models of the Zion systems. 65 refs., 14 figs., 11 tabs.

  8. Complementary safety assessments of the French nuclear facilities

    NASA Astrophysics Data System (ADS)

    Pouget-Abadie, Xavier

    2012-05-01

    EDF has conducted, after the Fukushima event, complementary safety assessments of its nuclear facilities. The aim of this in-depth review was to assess the resilience of each plant to extreme external hazards, situations that could lead to severe accident conditions. These analyses demonstrate a good level of safety for all of EDF's nuclear facilities. Supplementary measures post-Fukushima have been put forward to the ASN with the aim of continuing to improve the level of safety at the plants. Once the ASN position is issued, EDF will develop an action plan over several years, covering both supplementary studies and modifications that have been identified.

  9. SAFR: a marriage of safety and innovation in LMR design

    SciTech Connect

    Lancet, R.T.; Mills, J.C.

    1985-11-01

    The Sodium Advanced Fast Reactor (SAFR) is a natural evolution of earlier designs, given the current economic and licensing environment. Stringent safety and economic goals have been established for the SAFR plant. This paper describes how these goals are being satisfied, with the primary emphasis being placed on safety. The top level safety goals are: (a) to provide inherently safe responses to all credible events (b) to minimize the potential for severe accidents, and (c) to eliminate the need for evacuation, (d) limited financial risk, (e) assured investment protection, (f) minimum development risk, (g) high capacity factor, (h) long plant life, and (i) low personnel radiation exposure.

  10. Convergence of plant-rich and plant-only diets.

    PubMed

    Dwyer, J

    1999-09-01

    Discussants at the Third International Congress on Vegetarian Nutrition considered the nutritional adequacy, benefits, and health outcomes of plant-only (e.g., vegan and fruitarian), plant-based (e.g., macrobiotic, lactovegetarian, semivegetarian, and meatless), and omnivorous dietary patterns. The increased availability of a variety of plant foods, the advent of nutrient-fortified plant foods, the use of vitamin and mineral supplements, and the widespread dissemination of sound information on dietary patterns mean that convergence between the essential nutrient profiles of plant-only and plant-rich, plant-based diets is possible. Special attention should be paid to nutrition among vulnerable groups by age or physiologic status if they consume diets based solely on plants. Research has shown that both plant-only and plant-based eating patterns have health benefits, most notably in reducing the risk of chronic, degenerative diseases. The panel concluded that evidence for a convergence of scientific opinion on the safety and healthfulness of plant-only diets that are appropriately planned to meet all nutrient requirements compared with plant-based diets is considerable. PMID:10479241

  11. Considering Plants.

    ERIC Educational Resources Information Center

    Flannery, Maura C.

    1991-01-01

    Examples from research that incorporate plants to illustrate biological principles are presented. Topics include dried pea shape, homeotic genes, gene transcription in plants that are touched or wounded, production of grasslands, seaweed defenses, migrating plants, camouflage, and family rivalry. (KR)

  12. NASA Software Safety Standard

    NASA Technical Reports Server (NTRS)

    Rosenberg, Linda

    1997-01-01

    If software is a critical element in a safety critical system, it is imperative to implement a systematic approach to software safety as an integral part of the overall system safety programs. The NASA-STD-8719.13A, "NASA Software Safety Standard", describes the activities necessary to ensure that safety is designed into software that is acquired or developed by NASA, and that safety is maintained throughout the software life cycle. A PDF version, is available on the WWW from Lewis. A Guidebook that will assist in the implementation of the requirements in the Safety Standard is under development at the Lewis Research Center (LeRC). After completion, it will also be available on the WWW from Lewis.

  13. 9 CFR 590.650 - Exempted plant registration number.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 9 Animals and Animal Products 2 2013-01-01 2013-01-01 false Exempted plant registration number. 590.650 Section 590.650 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF... Egg Products Plants § 590.650 Exempted plant registration number. Each plant processing egg...

  14. 9 CFR 590.650 - Exempted plant registration number.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 9 Animals and Animal Products 2 2014-01-01 2014-01-01 false Exempted plant registration number. 590.650 Section 590.650 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF... Egg Products Plants § 590.650 Exempted plant registration number. Each plant processing egg...

  15. Highway Safety Program Manual: Volume 14: Pedestrian Safety.

    ERIC Educational Resources Information Center

    National Highway Traffic Safety Administration (DOT), Washington, DC.

    Volume 14 of the 19-volume Highway Safety Program Manual (which provides guidance to State and local governments on preferred highway safety practices) concentrates on pedestrian safety. The purpose and objectives of a pedestrian safety program are outlined. Federal authority in the area of pedestrian safety and policies regarding a safety program…

  16. Health Education and Safety for High Quality Performance.

    ERIC Educational Resources Information Center

    Bulo, Apollos

    2000-01-01

    Discusses the methodologies successfully used at the University of Michigan Plant Building Services for the maintenance of the safety and health of almost 400 management and custodial staff, and which may be extended to cover all the more than 1,500 workers throughout the university's Plant Operations Department. The establishing of departmental…

  17. Tiger Team assessment of the Pinellas Plant

    SciTech Connect

    Not Available

    1990-05-01

    This Document contains findings identified during the Tiger Team Compliance Assessment of the Department of Energy's (DOE's) Pinellas Plant, Pinellas County, Florida. The assessment wa directed by the Department's Office of Environment, Safety, and Health (ES H) from January 15 to February 2, 1990. The Pinellas Tiger Team Compliance Assessment is comprehensive in scope. It covers the Environment Safety and Health, and Management areas and determines the plant's compliance with applicable Federal (including DOE), State, and local regulations and requirements.

  18. Modular HTGR Safety Basis and Approach

    SciTech Connect

    Thomas Hicks

    2011-08-01

    The Next Generation Nuclear Plant (NGNP) will be a licensed commercial high temperature gas-cooled reactor (HTGR) capable of producing electricity and/or high temperature process heat for industrial markets supporting a range of end-user applications. The NGNP Project has adopted the 10 CFR 52 Combined License (COL) process, as recommended in the NGNP Licensing Strategy - A Report to Congress, dated August 2008, as the foundation for the NGNP licensing strategy [DOE/NRC 2008]. Nuclear Regulatory Commission (NRC) licensing of the NGNP plant utilizing this process will demonstrate the efficacy for licensing future HTGRs for commercial industrial applications. This information paper is one in a series of submittals that address key generic issues of the priority licensing topics as part of the process for establishing HTGR regulatory requirements. This information paper provides a summary level introduction to HTGR history, public safety objectives, inherent and passive safety features, radionuclide release barriers, functional safety approach, and risk-informed safety approach. The information in this paper is intended to further the understanding of the modular HTGR safety approach with the NRC staff and public stakeholders. The NGNP project does not expect to receive comments on this information paper because other white papers are addressing key generic issues of the priority licensing topics in greater detail.

  19. International Nuclear Safety Center (INSC) database

    SciTech Connect

    Sofu, T.; Ley, H.; Turski, R.B.

    1997-08-01

    As an integral part of DOE`s International Nuclear Safety Center (INSC) at Argonne National Laboratory, the INSC Database has been established to provide an interactively accessible information resource for the world`s nuclear facilities and to promote free and open exchange of nuclear safety information among nations. The INSC Database is a comprehensive resource database aimed at a scope and level of detail suitable for safety analysis and risk evaluation for the world`s nuclear power plants and facilities. It also provides an electronic forum for international collaborative safety research for the Department of Energy and its international partners. The database is intended to provide plant design information, material properties, computational tools, and results of safety analysis. Initial emphasis in data gathering is given to Soviet-designed reactors in Russia, the former Soviet Union, and Eastern Europe. The implementation is performed under the Oracle database management system, and the World Wide Web is used to serve as the access path for remote users. An interface between the Oracle database and the Web server is established through a custom designed Web-Oracle gateway which is used mainly to perform queries on the stored data in the database tables.

  20. Safety and the Human Factor.

    ERIC Educational Resources Information Center

    Smith, Ann

    1982-01-01

    Discusses four elements of safety programs: (1) safety training; (2) safety inspections; (3) accident investigations; and (4) protective safety equipment. Also discusses safety considerations in water/wastewater treatment facilities focusing on falls, drowning hazards, trickling filters, confined space entry, collection/distribution system safety,…

  1. Principles of Safety Pharmacology

    PubMed Central

    Pugsley, M K; Authier, S; Curtis, M J

    2008-01-01

    Safety Pharmacology is a rapidly developing discipline that uses the basic principles of pharmacology in a regulatory-driven process to generate data to inform risk/benefit assessment. The aim of Safety Pharmacology is to characterize the pharmacodynamic/pharmacokinetic (PK/PD) relationship of a drug's adverse effects using continuously evolving methodology. Unlike toxicology, Safety Pharmacology includes within its remit a regulatory requirement to predict the risk of rare lethal events. This gives Safety Pharmacology its unique character. The key issues for Safety Pharmacology are detection of an adverse effect liability, projection of the data into safety margin calculation and finally clinical safety monitoring. This article sets out to explain the drivers for Safety Pharmacology so that the wider pharmacology community is better placed to understand the discipline. It concludes with a summary of principles that may help inform future resolution of unmet needs (especially establishing model validation for accurate risk assessment). Subsequent articles in this issue of the journal address specific aspects of Safety Pharmacology to explore the issues of model choice, the burden of proof and to highlight areas of intensive activity (such as testing for drug-induced rare event liability, and the challenge of testing the safety of so-called biologics (antibodies, gene therapy and so on.). PMID:18604233

  2. Traceability of Software Safety Requirements in Legacy Safety Critical Systems

    NASA Technical Reports Server (NTRS)

    Hill, Janice L.

    2007-01-01

    How can traceability of software safety requirements be created for legacy safety critical systems? Requirements in safety standards are imposed most times during contract negotiations. On the other hand, there are instances where safety standards are levied on legacy safety critical systems, some of which may be considered for reuse for new applications. Safety standards often specify that software development documentation include process-oriented and technical safety requirements, and also require that system and software safety analyses are performed supporting technical safety requirements implementation. So what can be done if the requisite documents for establishing and maintaining safety requirements traceability are not available?

  3. Austrian contributions to reactor safety research

    NASA Astrophysics Data System (ADS)

    Sdouz, Gert

    1992-03-01

    An overview of Austrian contributions to reactor safety research is given. Starting with licensing for the power plant Zwenkendorf and participation in the safety projects PBF (Power Burst Facility) and LOFT (Loss Of Fluid Test), the work shifted later to participation in the study of international standard problems of the OECD and the IAEA. Since 1988 the center of activity is the calculation of the source term behavior of accident sequences, especially for reactors of Russian types. As an illustration the results of a source term calculation for a TMLB' sequence are presented.

  4. Evaluation of safety assessment methodologies in Rocky Flats Risk Assessment Guide (1985) and Building 707 Final Safety Analysis Report (1987)

    SciTech Connect

    Walsh, B.; Fisher, C.; Zigler, G.; Clark, R.A.

    1990-11-09

    FSARs. Rockwell International, as operating contractor at the Rocky Flats plant, conducted a safety analysis program during the 1980s. That effort resulted in Final Safety Analysis Reports (FSARs) for several buildings, one of them being the Building 707 Final Safety Analysis Report, June 87 (707FSAR) and a Plant Safety Analysis Report. Rocky Flats Risk Assessment Guide, March 1985 (RFRAG85) documents the methodologies that were used for those FSARs. Resources available for preparation of those Rocky Flats FSARs were very limited. After addressing the more pressing safety issues, some of which are described below, the present contractor (EG&G) intends to conduct a program of upgrading the FSARs. This report presents the results of a review of the methodologies described in RFRAG85 and 707FSAR and contains suggestions that might be incorporated into the methodology for the FSAR upgrade effort.

  5. Intranet-based safety documentation in management of major hazards and occupational health and safety.

    PubMed

    Leino, Antti

    2002-01-01

    In the European Union, Council Directive 96/82/EC requires operators producing, using, or handling significant amounts of dangerous substances to improve their safety management systems in order to better manage the major accident potentials deriving from human error. A new safety management system for the Viikinmäki wastewater treatment plant in Helsinki, Finland, was implemented in this study. The system was designed to comply with both the new safety liabilities and the requirements of OHSAS 18001 (British Standards Institute, 1999). During the implementation phase experiences were gathered from the development processes in this small organisation. The complete documentation was placed in the intranet of the plant. Hyperlinks between documents were created to ensure convenience of use. Documentation was made accessible for all workers from every workstation. PMID:12189104

  6. Hydrogen Technologies Safety Guide

    SciTech Connect

    Rivkin, C.; Burgess, R.; Buttner, W.

    2015-01-01

    The purpose of this guide is to provide basic background information on hydrogen technologies. It is intended to provide project developers, code officials, and other interested parties the background information to be able to put hydrogen safety in context. For example, code officials reviewing permit applications for hydrogen projects will get an understanding of the industrial history of hydrogen, basic safety concerns, and safety requirements.

  7. TWRS safety management plan

    SciTech Connect

    Popielarczyk, R.S., Westinghouse Hanford

    1996-08-01

    The Tank Waste Remediation System (TWRS) Safety Management Program Plan for development, implementation and maintenance of the tank farm authorization basis is described. The plan includes activities and procedures for: (a) Updating the current Interim Safety Basis, (b) Development,implementation and maintenance of a Basis for Interim Operations, (c) Development, implementation and maintenance of the Final Safety Analyses Report, (d) Development and implementation of a TWRS information Management System for monitoring the authorization basis.

  8. IAEA Activities in the Area of Safety Analysis and Accident Management

    SciTech Connect

    Lee, S.; El-Shanawany, M.

    2006-07-01

    Safety analysis is a means of demonstrating how critical safety functions, the integrity of barriers against the release of radioactive materials, and various other safety requirements are fulfilled for a broad range of operating conditions and initiating events. Accordingly, performing safety analysis for a nuclear power plant is one of the most important safety principles. Thermal-hydraulic computer codes are extensively used worldwide for safety analysis by utilities, regulatory authorities, power plant designers and vendors, nuclear fuel companies, research organizations, and technical support organizations. Safety analysis methodology and computer codes have seen a significant development over the last two decades. This fact is also reflected in the work of the International Atomic Energy Agency (IAEA) that aims at increasing the quality and international harmonization of the approaches used in safety analysis. The paper provides an overview of activities and of examples of results obtained recently or planned in the near future in the IAEA's Division of Nuclear Installation Safety in the field of safety analysis for both design basis accidents and beyond design basis accidents as well as accident management. In this paper, specific technical guidance on the safety assessments in the IAEA Safety Standards such as safety analysis methodologies, probabilistic safety assessment, and development of accident management programmes are described. Future trends and related activities in safety analysis and accident management are also introduced. (authors)

  9. Proceedings of the international meeting on thermal nuclear reactor safety. Vol. 1

    SciTech Connect

    1983-02-01

    Separate abstracts are included for each of the papers presented concerning current issues in nuclear power plant safety; national programs in nuclear power plant safety; radiological source terms; probabilistic risk assessment methods and techniques; non LOCA and small-break-LOCA transients; safety goals; pressurized thermal shocks; applications of reliability and risk methods to probabilistic risk assessment; human factors and man-machine interface; and data bases and special applications.

  10. Technical Seminar: "Crash Safety"""

    NASA Video Gallery

    This seminar addresses the history and successful progress in predicting and improving the crash safety characteristics of vehicles, with particular emphasis on rotary wing aircraft and composite s...

  11. Lift truck safety review

    SciTech Connect

    Cadwallader, L.C.

    1997-03-01

    This report presents safety information about powered industrial trucks. The basic lift truck, the counterbalanced sit down rider truck, is the primary focus of the report. Lift truck engineering is briefly described, then a hazard analysis is performed on the lift truck. Case histories and accident statistics are also given. Rules and regulations about lift trucks, such as the US Occupational Safety an Health Administration laws and the Underwriter`s Laboratories standards, are discussed. Safety issues with lift trucks are reviewed, and lift truck safety and reliability are discussed. Some quantitative reliability values are given.

  12. Aerospace Safety Advisory Panel

    NASA Technical Reports Server (NTRS)

    1992-01-01

    The results of the Panel's activities are presented in a set of findings and recommendations. Highlighted here are both improvements in NASA's safety and reliability activities and specific areas where additional gains might be realized. One area of particular concern involves the curtailment or elimination of Space Shuttle safety and reliability enhancements. Several findings and recommendations address this area of concern, reflecting the opinion that safety and reliability enhancements are essential to the continued successful operation of the Space Shuttle. It is recommended that a comprehensive and continuing program of safety and reliability improvements in all areas of Space Shuttle hardware/software be considered an inherent component of ongoing Space Shuttle operations.

  13. Helicopter Safety Research

    NASA Technical Reports Server (NTRS)

    Hart, Sandra G.; Rutkowski, Michael

    1999-01-01

    In response to the President's challenge to reduce civil aviation accidents by a factor of 10 by the year 2022, NASA has embarked on an ambitious safety program in partnership with other government agencies and industry. The helicopter element of the NASA initiative has been guided by a series of accident analyses aimed at identifying the most frequent causes and consequences and initiating research to prevent or mitigate these factors. This talk will summarize the key findings of three of the accident analyses, the major elements of the safety program, and how helicopter safety research relates to the safety program.

  14. Constantly evolving safety assessment protocols for GM foods.

    PubMed

    Sesikeran, B; Vasanthi, Siruguri

    2008-01-01

    he introduction of GM foods has led to the evolution of a food safety assessment paradigm that establishes safety of the GM food relative to its conventional counterpart. The GM foods currently approved and marketed in several countries have undergone extensive safety testing under a structured safety assessment framework evolved by international organizations like FAO, WHO, Codex and OECD. The major elements of safety assessment include molecular characterization of inserted genes and stability of the trait, toxicity and allergenicity potential of the expressed substances, compositional analysis, potential for gene transfer to gut microflora and unintentional effects of the genetic modification. As more number and type of food crops are being brought under the genetic modification regime, the adequacy of existing safety assessment protocols for establishing safety of these foods has been questioned. Such crops comprise GM crops with higher agronomic vigour, nutritional or health benefit/ by modification of plant metabolic pathways and those expressing bioactive substances and pharmaceuticals. The safety assessment challenges of these foods are the potential of the methods to detect unintentional effects with higher sensitivity and rigor. Development of databases on food compositions, toxicants and allergens is currently seen as an important aid to development of safety protocols. With the changing global trends in genetic modification technology future challenge would be to develop GM crops with minimum amount of inserted foreign DNA so as to reduce the burden of complex safety assessments while ensuring safety and utility of the technology. PMID:18296346

  15. Integrated radar and lidar analysis reveals extensive loss of remaining intact forest on Sumatra 2007-2010

    NASA Astrophysics Data System (ADS)

    Collins, M. B.; Mitchard, E. T. A.

    2015-06-01

    Forests with high above ground biomass (AGB), including those growing on peat swamps, have historically not been thought suitable for biomass mapping and change detection using Synthetic Aperture Radar (SAR). However, by integrating L-band (λ = 0.23 m) SAR with lidar data from the ALOS and ICESat earth-observing satellites respectively, and 56 forest plots, we were able to create a forest biomass and change map for a 10.7 Mha section of eastern Sumatra that still contains high AGB peat swamp forest. Using a time series of SAR data we estimated changes in both forest area and AGB. We estimate that there were 274 ± 68 Tg AGB remaining in natural forest (≥ 20 m height) in the study area in 2007, with this stock reducing by approximately 11.4% over the subsequent 3 years. A total of 137.4 kha of the study area were deforested between 2007 and 2010; an average rate of 3.8% yr-1. The ability to attribute forest loss to different initial biomass values allows for far more effective monitoring and baseline modelling for avoided deforestation projects than traditional, optical-based remote sensing. Furthermore, given SAR's ability to penetrate the smoke and cloud which normally obscure land cover change in this region, SAR-based forest monitoring can be relied on to provide frequent imagery. This study demonstrates that even at L-band, which typically saturates at medium biomass levels (ca. 150 Mg ha-1), it is possible to make reliable estimates of not just the area but the carbon emissions resulting from land use change.

  16. Beyond the Gallery: Interactions between Audiences, Artists, and Their Art through the Kampala Art Tour 2007-2010

    ERIC Educational Resources Information Center

    Nagawa, Margaret

    2012-01-01

    When one walks into an art gallery in Kampala, the capital city of Uganda, one sees a predominantly non-Ugandan audience. Visitors to homes of Ugandans, even those wealthy enough to afford art, find typically bare walls. This begs broader questions: (1) What is it about the education and presentation of contemporary art that excludes local…

  17. Surface deformation and stress interactions during the 2007-2010 sequence of earthquake, dyke intrusion and eruption in northern Tanzania

    NASA Astrophysics Data System (ADS)

    Biggs, Juliet; Chivers, Michael; Hutchinson, Michael C.

    2013-10-01

    Magma movement and fault slip alter the magnitude and orientation of the stress in the surrounding crust. Observations of a sequence of events clustered in space and time provide information about the triggering mechanism and stress interactions between magma intrusion, earthquakes and eruptions. We investigate the syn- and post-intrusion stress changes associated with the 2007 Gelei dyke intrusion episode and subsequent eruption of nearby Oldonyo Lengai. Previous studies produced a kinematic model of the 2007 June-August sequence involving ˜1 m slip on a normal fault followed by the intrusion of the 7-10-km long Gelei dyke, collapse of a shallow graben and the deflation of the Gelei magma chamber. Immediately following this, the volcano Oldoinyo Lengai (<10 km away) experienced a new phase of explosive activity lasting for several months. Here, we present new geodetic observations covering Gelei and Oldoinyo Lengai in 2008 September-2010. We show continued slip on graben-bounding faults above the Gelei dyke. The eruption of Oldoinyo Lengai was accompanied by the intrusion of a 4 km-long E-W-trending dyke followed by deflation of a shallow source directly below the summit of the volcano. Next, we use stress calculations to investigate a number of hypotheses linking these events. (1) Before the onset of surface deformation, a dyke sufficiently deep and narrow to be geodetically undetectable could still have produced sufficient stress changes to trigger slip on the normal fault (i.e. the sequence could have been magmatically driven). (2) Stresses at the dyke tip would have been sufficient to overcome the effect of continued slip on the normal fault, allowing the dyke to propagate upwards into a region of clamping. (3) The Gelei sequence would have produced a significant stress change on the chamber beneath Oldoinyo Lengai. These static stress calculations allow us to discuss the roles played by dynamic stress, deeper magmatic changes and background stresses throughout the sequence with implications for the stress triggering of both seismic and volcanic hazards.

  18. Comparative Analysis of the Development of Multicultural Library Services in the Spanish Public Library Network (2007-2010)

    ERIC Educational Resources Information Center

    Garcia Lopez, Fatima; Caridad Sebastian, Mercedes; Morales Garcia, Ana Maria

    2012-01-01

    Introduction: The percentage of foreign-born residents in Spain has multiplied almost fourfold over the last decade. Immigration has changed our society, both from a demographic and economic perspective, and from a cultural and political prospective. The Spanish public library network, a democratic institution that provides services, initially, of…

  19. Integrated radar and lidar analysis reveals extensive loss of remaining intact forest on Sumatra 2007-2010

    NASA Astrophysics Data System (ADS)

    Collins, M. B.; Mitchard, E. T. A.

    2015-11-01

    Forests with high above-ground biomass (AGB), including those growing on peat swamps, have historically not been thought suitable for biomass mapping and change detection using synthetic aperture radar (SAR). However, by integrating L-band (λ = 0.23 m) SAR from the ALOS and lidar from the ICESat Earth-Observing satellites with 56 field plots, we were able to create a forest biomass and change map for a 10.7 Mha section of eastern Sumatra that still contains high AGB peat swamp forest. Using a time series of SAR data we estimated changes in both forest area and AGB. We estimate that there was 274 ± 68 Tg AGB remaining in natural forest (≥ 20 m height) in the study area in 2007, with this stock reducing by approximately 11.4 % over the subsequent 3 years. A total of 137.4 kha of the study area was deforested between 2007 and 2010, an average rate of 3.8 % yr-1. The ability to attribute forest loss to different initial biomass values allows for far more effective monitoring and baseline modelling for avoided deforestation projects than traditional, optical-based remote sensing. Furthermore, given SAR's ability to penetrate the smoke and cloud which normally obscure land cover change in this region, SAR-based forest monitoring can be relied on to provide frequent imagery. This study demonstrates that, even at L-band, which typically saturates at medium biomass levels (ca. 150 Mg ha-1), in conjunction with lidar data, it is possible to make reliable estimates of not just the area but also the carbon emissions resulting from land use change.

  20. Survey of sulfites in wine and various Turkish food and food products intended for export, 2007-2010.

    PubMed

    Ulca, P; Öztürk, Y; Senyuva, H Z

    2011-01-01

    Surveys were carried out between 2007 and 2010 to determine the total levels of sulfites in 1245 samples of wines, dried apricots, dried vegetables, nuts, juices and purees, frozen foods and cereals containing dried fruit supplied by food inspectors and by food producers for testing or for export certification. Sulfite analysis of wine was carried out using the Ripper method with an LOQ of 5 mg l(-1) and for dried and other foods the Monier-Williams distillation procedure was employed with an LOQ of 10 mg kg(-1). In the survey all wines contained measurable sulfites, but with the exception of one sample of white wine they were otherwise below Turkish Food Codex limits of 160 mg kg(-1) for red wine, 210 mg kg(-1) to white wine and 235 mg kg(-1) for sparkling wine. None of the cereal products, frozen foods, juices or purees contained sulfites above 10 mg kg(-1). However, all dried apricot samples contained significant levels of sulfite with around 40% having levels exceeding the Turkish limit of 2000 mg kg(-1). Significant levels of sulfite were found in other samples of dried fruit with even a fruit and nut bar containing 1395 mg kg(-1) of sulfite, suggesting the dried fruit ingredients contained levels above regulatory limits. PMID:24786011

  1. Emerging issues and current trends in assistive technology use 2007-2010: practising, assisting and enabling learning for all.

    PubMed

    Abbott, Chris; Brown, David; Evett, Lindsay; Standen, Penny

    2014-11-01

    Following an earlier review in 2007, a further review of the academic literature relating to the uses of assistive technology (AT) by children and young people was completed, covering the period 2007-2011. As in the earlier review, a tripartite taxonomy: technology uses to train or practise, technology uses to assist learning and technology uses to enable learning, was used in order to structure the findings. The key markers for research in this field and during these three years were user involvement, AT on mobile mainstream devices, the visibility of AT, technology for interaction and collaboration, new and developing interfaces and inclusive design principles. The paper concludes by locating these developments within the broader framework of the Digital Divide. PMID:24083780

  2. Campaign Expenditures in School Levy Referenda and Their Relationship to Voter Approval: Evidence from Ohio, 2007-2010

    ERIC Educational Resources Information Center

    Ingle, William Kyle; Johnson, Paul Andrew; Givens, Matt Ryan; Rampelt, Jerry

    2013-01-01

    Using logistic regression, this study sought to understand the relationship between district characteristics, district finances, levy characteristics, and campaign expenditures with new operating levy outcomes. We found that employee benefits as a percentage of the district's budget were negatively associated with levy outcomes, while salaries…

  3. Review of Doctoral Research in English Language Education in the Philippines, Singapore and Malaysia (2007-2010)

    ERIC Educational Resources Information Center

    Rubdy, Rani; Tupas, T. Ruanni F.; Villareal, Corazon D.; David, Maya Khemlani; Dumanig, Francisco Perlas

    2012-01-01

    This review highlights recent doctoral research in English language education and related areas completed between 2007 and 2010 in three countries in Southeast Asia: Singapore, Malaysia and the Philippines. Out of sixty dissertations initially chosen from major universities in these countries, five from the Philippines, four from Malaysia and…

  4. The possession game? A comparative analysis of ball retention and team success in European and international football, 2007-2010.

    PubMed

    Collet, Christian

    2013-01-01

    Possession is thought of as central to success in modern football, but questions remain about its impact on positive team outcomes (Bate, 1988; Hughes & Franks, 2005; Pollard & Reep, 1997; Stanhope, 2001). Recent studies (e.g. Bloomfield, Polman, & O'Donoghue, 2005; Carling, Williams, & Reilly, 2005; James, Mellallieu, & Holley, 2002; Jones, James, & Mellalieu, 2004; Lago, 2009; Lago & Martin, 2007; Lago-Peñas & Dellal, 2010; Lago-Peñas, Lago-Ballesteros, Dellal, & Gómez, 2010; Taylor, Mellalieu, & James, 2005; Tucker, Mellalieu, James, & Taylor, 2005) that have examined these questions have often been constrained by an exclusive focus on English or Spanish domestic play. Using data from five European leagues, UEFA and FIFA tournaments, the study found that while possession time and passing predicted aggregated team success in domestic league play, both variables were poor predictors at the individual match level once team quality and home advantage were accounted for. In league play, the effect of greater possession was consistently negative; in the Champions League, it had virtually no impact. In national team tournaments, possession failed to reach significance when offensive factors were accounted for. Much of the success behind the 'possession game' was thus a function of elite teams confined in geographic and competitive space. That ball hegemony was not consistently tied to success suggests that a nuanced approach to possession is needed to account for variant strategic environments (e.g. James et al., 2002) and compels match analysts to re-examine the metric's overall value. PMID:23067001

  5. Plant maintenance and plant life extension issue, 2007

    SciTech Connect

    Agnihotri, Newal

    2007-03-15

    The focus of the March-April issue is on plant maintenance and plant life extension. Major articles/reports in this issue include: Three proposed COLs expected in 2007, by Dale E. Klein, U.S. Nuclear Regulatory Commission; Delivering behaviors that our customers value, by Jack Allen, Westinghouse Electric Company; Facilitating high-level and fuel waste disposal technologies, by Malcolm Gray, IAEA, Austria; Plant life management and long-term operation, by Pal Kovacs, OECD-NEA, France; Measuring control rod position, by R. Taymanov, K. Sapozhnikova, I. Druzhinin, D.I. Mendeleyev, Institue for Metrology, Russia; and, 'Modernization' means higher safety, by Svetlana Genova, Kozluduy NPP plc, Bulgaria.

  6. Development Trends in Nuclear Technology and Related Safety Aspects

    SciTech Connect

    Kuczera, B.; Juhn, P.E.; Fukuda, K.

    2002-07-01

    The IAEA Safety Standards Series include, in a hierarchical manner, the categories of Safety Fundamentals, Safety Requirements and Safety Guides, which define the elements necessary to ensure the safety of nuclear installations. In the same way as nuclear technology and scientific knowledge advance continuously, also safety requirements may change with these advances. Therefore, in the framework of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) one important aspect among others refers to user requirements on the safety of innovative nuclear installations, which may come into operation within the next fifty years. In this respect, the major objectives of the INPRO sub-task 'User Requirements and Nuclear Energy Development Criteria in the Area of Safety' have been: a. to overview existing national and international requirements in the safety area, b. to define high level user requirements in the area of safety of innovative nuclear technologies, c. to compile and to analyze existing innovative reactor and fuel cycle technology enhancement concepts and approaches intended to achieve a high degree of safety, and d. to identify the general areas of safety R and D needs for the establishment of these technologies. During the discussions it became evident that the application of the defence in depth strategy will continue to be the overriding approach for achieving the general safety objective in nuclear power plants and fuel cycle facilities, where the emphasis will be shifted from mitigation of accident consequences more towards prevention of accidents. In this context, four high level user requirements have been formulated for the safety of innovative nuclear reactors and fuel cycles. On this basis safety strategies for innovative reactor designs are highlighted in each of the five levels of defence in depth and specific requirements are discussed for the individual components of the fuel cycle. (authors)

  7. Fires: what plant locations should we really protect

    SciTech Connect

    Berry, D.L.

    1980-01-01

    A fire protection analysis technique was developed from earlier work involving the protection of nuclear power plants against acts of sabotage. Characteristics unique to fire phenomena were used to modify the sabotage analysis methodology. These characteristics include the effects of fuel loads, ventilation rates, heat loss areas, barrier ratings, and plant locations. The new fire analysis technique was applied to an example nuclear power plant having 85 different plant areas. It was found that some safety and nonsafety areas were both highly vulnerable to fire spread and important to overall safety, while other areas were found to be of marginal importance to fire safety.

  8. A Silent Safety Program

    NASA Technical Reports Server (NTRS)

    Goodin, James Ronald

    2006-01-01

    NASA's Columbia Accident Investigation Board (CAIB) referred 8 times to the NASA "Silent Safety Program." This term, "Silent Safety Program" was not an original observation but first appeared in the Rogers Commission's Investigation of the Challenger Mishap. The CAIB on page 183 of its report in the paragraph titled 'Encouraging Minority Opinion,' stated "The Naval Reactor Program encourages minority opinions and "bad news." Leaders continually emphasize that when no minority opinions are present, the responsibility for a thorough and critical examination falls to management. . . Board interviews revealed that it is difficult for minority and dissenting opinions to percolate up through the agency's hierarchy. . ." The first question and perhaps the only question is - what is a silent safety program? Well, a silent safety program may be the same as the dog that didn't bark in Sherlock Holmes' "Adventure of the Silver Blaze" because system safety should behave as a devil's advocate for the program barking on every occasion to insure a critical review inclusion. This paper evaluates the NASA safety program and provides suggestions to prevent the recurrence of the silent safety program alluded to in the Challenger Mishap Investigation. Specifically targeted in the CAM report, "The checks and balances the safety system was meant to provide were not working." A silent system safety program is not unique to NASA but could emerge in any and every organization. Principles developed by Irving Janis in his book, Groupthink, listed criteria used to evaluate an organization's cultural attributes that allows a silent safety program to evolve. If evidence validates Jams's criteria, then Jams's recommendations for preventing groupthink can also be used to improve a critical evaluation and thus prevent the development of a silent safety program.

  9. Highway Safety Program Manual: Volume 3: Motorcycle Safety.

    ERIC Educational Resources Information Center

    National Highway Traffic Safety Administration (DOT), Washington, DC.

    Volume 3 of the 19-volume Highway Safety Program Manual (which provides guidance to State and local governments on preferred highway safety practices) concentrates on aspects of motorcycle safety. The purpose and specific objectives of a State motorcycle safety program are outlined. Federal authority in the highway safety area and general policies…

  10. Safety of Decommissioning of Nuclear Facilities

    SciTech Connect

    Batandjieva, B.; Warnecke, E.; Coates, R.

    2008-01-15

    Full text of publication follows: ensuring safety during all stages of facility life cycle is a widely recognised responsibility of the operators, implemented under the supervision of the regulatory body and other competent authorities. As the majority of the facilities worldwide are still in operation or shutdown, there is no substantial experience in decommissioning and evaluation of safety during decommissioning in majority of Member States. The need for cooperation and exchange of experience and good practices on ensuring and evaluating safety of decommissioning was one of the outcomes of the Berlin conference in 2002. On this basis during the last three years IAEA initiated a number of international projects that can assist countries, in particular small countries with limited resources. The main IAEA international projects addressing safety during decommissioning are: (i) DeSa Project on Evaluation and Demonstration of Safety during Decommissioning; (ii) R{sup 2}D{sup 2}P project on Research Reactors Decommissioning Demonstration Project; and (iii) Project on Evaluation and Decommissioning of Former Facilities that used Radioactive Material in Iraq. This paper focuses on the DeSa Project activities on (i) development of a harmonised methodology for safety assessment for decommissioning; (ii) development of a procedure for review of safety assessments; (iii) development of recommendations on application of the graded approach to the performance and review of safety assessments; and (iv) application of the methodology and procedure to the selected real facilities with different complexities and hazard potentials (a nuclear power plant, a research reactor and a nuclear laboratory). The paper also outlines the DeSa Project outcomes and planned follow-up activities. It also summarises the main objectives and activities of the Iraq Project and introduces the R{sup 2}D{sup 2} Project, which is a subject of a complementary paper.

  11. Carlsbad Area Office vehicle safety program

    SciTech Connect

    1996-12-01

    The Carlsbad Area Office (CAO) Vehicle Safety Program (VSP) establishes the minimum requirements for CAO personnel to safely operate government vehicles and provides direction to effectively reduce the number of vehicle accidents, reduce the severity of vehicle accidents, and minimize vehicular property damage. This Program covers the operations of Government Services Administration (GSA) vehicles, rental or leased vehicles, and special purpose vehicles used at the Waste Isolation Pilot Plant (WIPP) in the performance of work. Additionally, this Program encourages CAO employees to use safe driving habits while operating their privately owned vehicles, motorcycles, or bicycles, or, as pedestrians, to be aware of the hazards associated with traffic in and around CAO facilities. Vehicle safety is a shared responsibility in this organization. At anytime a CAO employee witnesses an unsafe act relating to the operation of a motor vehicle, it is their responsibility to notify their Team Leader (TL) or Assistant Manager (AM), or contact the CAO Safety and Occupational Health Manager (SOHM). Employees are encouraged to participate in the Carlsbad Area Office Federal Employees Safety Committee (FESC) activities and goals in order to address vehicle safety concerns. The FESC is designed to be a forum for all federal employees to improve the health and safety of the organization. The VSP is an effective method of ensuring the health and safety of CAO employees during the operation of government vehicles. The human resources of the CAO are the most valuable assets of this organization and any lost manhours are difficult to replace. Safe driving habits and defensive driving methods should always be practiced to preserve the health and safety of all employees.

  12. Safety for Older Consumers. Home Safety Checklist.

    ERIC Educational Resources Information Center

    Consumer Product Safety Commission, Washington, DC.

    A home safety checklist geared to the needs of older adults is presented in this document. The beginning of the checklist highlights potential hazards which may need to be checked in more than one area of the home, such as electric cords, smoke detectors, rugs, telephone areas, and emergency exit plans. The rest of the checklist is organized…

  13. Safety and Excellence. Safety in the Schools

    ERIC Educational Resources Information Center

    Merrow, John

    2004-01-01

    As far as schools are concerned, there are three kinds of safety: physical, emotional, and intellectual. Excellence demands all three, while "good enough" schools are simply physically safe. How can parents and others determine whether a school is physically safe? It's always good to find out how many students were suspended at a particular…

  14. Plant Risk Status Information Management System.

    Energy Science and Technology Software Center (ESTSC)

    1990-12-12

    Version 00 PRISIM allows inspectors to quickly access probabilistic risk assessment (PRA) information and use it to update risk analysis results, reflecting a nuclear plant's status at any time. PRISIM also allows regulators to access PRA information and modify the information to assess the impact the changes may have on plant safety.

  15. Bicycle Safety in Action.

    ERIC Educational Resources Information Center

    National Commission on Safety Education, Washington, DC.

    This material was designed to assist schools in teaching bicycle safety. As the population grows and competition for road space increases, it is more imperative than ever that we concentrate attention on the need for caution among pupil cyclists. The pamphlet: (1) discusses the role of bicycle safety in classroom instruction and in student…

  16. Improving Student Safety.

    ERIC Educational Resources Information Center

    Dorn, Michael; Trump, Kenneth S.; Nichols, R. Leslie

    2001-01-01

    Presents the latest information on how schools can keep their students safe. Safety oriented actions discussed cover incident reporting and tracking, tactical site surveys, school safety and emergency operations planning, staff development efforts, and facility design. Explains the need to review and test specific prevention concepts and emergency…

  17. Introducing Laboratory Safety.

    ERIC Educational Resources Information Center

    DeLorenzo, Ronald

    1985-01-01

    Presents a simple, 10-item quiz designed to make students aware that they must learn laboratory safety. The items include questions on acid/base accidents, several types of fire extinguishers, and safety glassses. Answers and some explanations are included. (DH)

  18. Idaho Safety Manual.

    ERIC Educational Resources Information Center

    Idaho State Dept. of Education, Boise. Div. of Vocational Education.

    This manual is intended to help teachers, administrators, and local school boards develop and institute effective safety education as a part of all vocational instruction in the public schools of Idaho. This guide is organized in 13 sections that cover the following topics: introduction to safety education, legislation, levels of responsibility,…

  19. Science Safety Procedure Handbook.

    ERIC Educational Resources Information Center

    Lynch, Mervyn A.; Offet, Lorna

    This booklet outlines general safety procedures in the areas of: (1) student supervision; (2) storage safety regulations, including lists of incompatible chemicals, techniques of disposal and storage; (3) fire; and (4) first aid. Specific sections exist for elementary, junior high school, senior high school, in which special procedures are…

  20. Workplace Health and Safety.

    ERIC Educational Resources Information Center

    Massachusetts Career Development Inst., Springfield.

    This booklet is one of six texts from a workplace literacy curriculum designed to assist learners in facing the increased demands of the workplace. It is a short guide to workplace health and safety issues, laws, and regulations, especially in Massachusetts. Topics covered include the following: (1) safety issues--workplace ergonomics, the…