WorldWideScience

Sample records for safety datalink project

  1. Vaccine Safety Datalink

    Science.gov (United States)

    The Vaccine Safety Datalink is part of the National Immunization Program within the Centers for Disease Control and Prevention and was started in recognition of gaps in the scientific knowledge of rare vaccine side effects.

  2. The Vaccine Safety Datalink: successes and challenges monitoring vaccine safety.

    Science.gov (United States)

    McNeil, Michael M; Gee, Julianne; Weintraub, Eric S; Belongia, Edward A; Lee, Grace M; Glanz, Jason M; Nordin, James D; Klein, Nicola P; Baxter, Roger; Naleway, Allison L; Jackson, Lisa A; Omer, Saad B; Jacobsen, Steven J; DeStefano, Frank

    2014-09-22

    The Vaccine Safety Datalink (VSD) is a collaborative project between the Centers for Disease Control and Prevention (CDC) and 9 health care organizations. Established in 1990, VSD is a vital resource informing policy makers and the public about the safety of vaccines used in the United States. Large linked databases are used to identify and evaluate adverse events in over 9 million individuals annually. VSD generates rapid, important safety assessments for both routine vaccinations and emergency vaccination campaigns. VSD monitors safety of seasonal influenza vaccines in near-real time, and provided essential information on the safety of influenza A (H1N1) 2009 monovalent vaccine during the recent pandemic. VSD investigators have published important studies demonstrating that childhood vaccines are not associated with autism or other developmental disabilities. VSD prioritizes evaluation of new vaccines; searches for possible unusual health events after vaccination; monitors vaccine safety in pregnant women; and has pioneered development of biostatistical research methods. Published by Elsevier Ltd.

  3. Patterns in influenza antiviral medication use before and during the 2009 H1N1 pandemic, Vaccine Safety Datalink Project, 2000-2010.

    Science.gov (United States)

    Greene, Sharon K; Shay, David K; Yin, Ruihua; McCarthy, Natalie L; Baxter, Roger; Jackson, Michael L; Jacobsen, Steven J; Nordin, James D; Irving, Stephanie A; Naleway, Allison L; Glanz, Jason M; Lieu, Tracy A

    2012-11-01

    U.S. recommendations for using influenza antiviral medications changed in response to viral resistance (to reduce adamantane use) and during the 2009 H1N1 pandemic (to focus on protecting high-risk patients). Little information is available on clinician adherence to these recommendations. We characterized population-based outpatient antiviral medication usage, including diagnosis and testing practices, before and during the pandemic. Eight medical care organizations in the Vaccine Safety Datalink Project provided data on influenza antiviral medication dispensings from January 2000 through June 2010. Dispensing rates were explored in relation to changes in recommendations and influenza diagnosis and laboratory testing frequencies. Factors associated with oseltamivir dispensings in pandemic versus pre-pandemic periods were identified using multivariable logistic regression. Antiviral use changed coincident with recommendations to avoid adamantanes in 2006, to use alternatives to oseltamivir in 2008, and to use oseltamivir during the pandemic. Of 38,019 oseltamivir dispensings during the pandemic, 31% were to patients not assigned an influenza diagnosis, and 97% were to patients not tested for influenza. Oseltamivir was more likely to be dispensed in pandemic versus pre-pandemic periods to patients change antiviral prescribing based on resistance and to focus on high-risk patients during the pandemic. Medications were commonly dispensed to patients without influenza diagnoses and tests, suggesting that antiviral dispensings may offer useful supplemental data for monitoring influenza incidence. © 2012 Blackwell Publishing Ltd.

  4. Signal identification and evaluation for risk of febrile seizures in children following trivalent inactivated influenza vaccine in the Vaccine Safety Datalink Project, 2010-2011.

    Science.gov (United States)

    Tse, Alison; Tseng, Hung Fu; Greene, Sharon K; Vellozzi, Claudia; Lee, Grace M

    2012-03-02

    In fall 2010 in the southern hemisphere, an increased risk of febrile seizures was noted in young children in Australia in the 24 h after receipt of trivalent inactivated influenza vaccine (TIV) manufactured by CSL Biotherapies. Although the CSL TIV vaccine was not recommended for use in young children in the US, during the 2010-2011 influenza season near real-time surveillance was conducted for febrile seizures in the 0-1 days following first dose TIV in a cohort of 206,174 vaccinated children ages 6 through 59 months in the Vaccine Safety Datalink Project. On a weekly basis, surveillance was conducted with the primary approach of a self-controlled risk interval design and the secondary approach of a current vs. historical vaccinee design. Sequential statistical methods were employed to account for repeated analyses of accumulating data. Signals for seizures based on computerized data were identified in mid November 2010 using a current vs. historical design and in late December 2010 using a self-controlled risk interval design. Further signal evaluation was conducted with chart-confirmed febrile seizure cases using only data from the primary approach (i.e. self-controlled risk interval design). The magnitude of the incidence rate ratio and risk difference comparing risk of seizures in the 0-1 days vs. 14-20 days following TIV differed by receipt of concomitant 13-valent pneumococcal conjugate vaccine (PCV13). Among children 6-59 months of age, the incidence rate ratio (IRR) for TIV adjusted for concomitant PCV13 was 2.4 (95% CI 1.2, 4.7) while the IRR for PCV13 adjusted for concomitant TIV was 2.5 (95% CI 1.3, 4.7). The IRR for concomitant TIV and PCV13 was 5.9 (95% CI 3.1, 11.3). Risk difference estimates varied by age due to the varying baseline risk for seizures in young children, with the highest estimates occurring at 16 months (12.5 per 100,000 doses for TIV without concomitant PCV13, 13.7 per 100,000 doses for PCV13 without concomitant TIV, and 44.9 per

  5. Limited Evaluation of a Relative GPS Datalink Between Two C-12C Aircraft (Project "Lost Wingman")

    National Research Council Canada - National Science Library

    George, Benjamin E; Wilder, Bruce J; Pasanen, York W; Faulkner, Adam M; Sullivan, Scott T

    2005-01-01

    .... This project was a risk reduction step to test the stability of the datalink to provide relative position and attitude information from a lead aircraft to a trail aircraft for the potential purpose...

  6. White Paper on studying the safety of the childhood immunization schedule in the Vaccine Safety Datalink.

    Science.gov (United States)

    Glanz, Jason M; Newcomer, Sophia R; Jackson, Michael L; Omer, Saad B; Bednarczyk, Robert A; Shoup, Jo Ann; DeStefano, Frank; Daley, Matthew F

    2016-02-15

    While the large majority of parents in the U.S. vaccinate their children according to the recommended immunization schedule, some parents have refused or delayed vaccinating, often citing safety concerns. In response to public concern, the U.S. Institute of Medicine (IOM) evaluated existing research regarding the safety of the recommended immunization schedule. The IOM concluded that although available evidence strongly supported the safety of the currently recommended schedule as a whole, additional observational research was warranted to compare health outcomes between fully vaccinated children and those on a delayed or alternative schedule. In addition, the IOM identified the Vaccine Safety Datalink (VSD) as an important resource for conducting this research. Guided by the IOM findings, the Centers for Disease Control and Prevention (CDC) commissioned a White Paper to assess how the VSD could be used to study the safety of the childhood immunization schedule. Guided by subject matter expert engagement, the resulting White Paper outlines a 4 stage approach for identifying exposure groups of undervaccinated children, presents a list of health outcomes of highest priority to examine in this context, and describes various study designs and statistical methods that could be used to analyze the safety of the schedule. While it appears feasible to study the safety of the recommended immunization schedule in settings such as the VSD, these studies will be inherently complex, and as with all observational studies, will need to carefully address issues of confounding and bias. In light of these considerations, decisions about conducting studies of the safety of the schedule will also need to assess epidemiological evidence of potential adverse events that could be related to the schedule, the biological plausibility of an association between an adverse event and the schedule, and public concern about the safety of the schedule. Copyright © 2015 Elsevier Ltd. All rights

  7. Integration of data from a safety net health care system into the Vaccine Safety Datalink.

    Science.gov (United States)

    Hambidge, Simon J; Ross, Colleen; Shoup, Jo Ann; Wain, Kris; Narwaney, Komal; Breslin, Kristin; Weintraub, Eric S; McNeil, Michael M

    2017-03-01

    In 2013 the Institute of Medicine suggested that the Vaccine Safety DataLink (VSD) should broaden its population by including data of more patients from low income and racially and ethnically diverse backgrounds. In response, Kaiser Permanente Colorado (KPCO) partnered with Denver Health (DH), an integrated safety net health care system, to explore the integration of DH data. We compared three different methods (reference date of September 1, 2013): "Empanelment" (any patient who has had a primary care visit in the past 18months), "Proxy-enrollment" (two health care visits in 3years separated by 90days), and "Enrollment" in a managed care plan. For each of these methods, we compared cohort size, vaccination rates, socio-demographic characteristics, and health care utilization. The empaneled population at DH provided the best comparison to KPCO. DH's empaneled population was 111,330 (57,173 adults; 54,157 children), while KPCO had 436,290 empaneled patients (336,462 adults; 99,828 children). Vaccination rates in both health care systems for empaneled patients were comparable. Two year-old up-to-date coverage rates were 83.2% (KPCO) and 86.9% (DH); rates for adolescent Tdap and MCV4 were 85.5% (KPCO) and 90.6% (DH). There were significant differences in the two populations in age, gender, race, preferred language, and % Federal Poverty Level (FPL) (DH 70.7%safety net health care system that does not have a uniform managed care population into the VSD, and to compare vaccination rates, socio-demographic characteristics, and health care utilization across the two systems. The KPCO-DH collaboration may serve as a model for incorporating data from a safety net healthcare system into the VSD. Copyright © 2017 Elsevier Ltd. All rights reserved.

  8. Influenza Vaccination During Pregnancy: Influenza Seasons 2002-2012, Vaccine Safety Datalink.

    Science.gov (United States)

    Groom, Holly C; Henninger, Michelle L; Smith, Ning; Koppolu, Padma; Cheetham, T Craig; Glanz, Jason M; Hambidge, Simon J; Jackson, Lisa A; Kharbanda, Elyse O; Klein, Nicola P; McCarthy, Natalie L; Nordin, James D; Weintraub, Eric S; Naleway, Allison L

    2016-04-01

    Pregnant women are at risk for influenza-related complications and have been recommended for vaccination by the Advisory Committee on Immunization Practices (ACIP) since 1990. Annual rates of influenza coverage of pregnant women have been consistently low. The Vaccine Safety Datalink was used to assess influenza vaccine coverage over 10 consecutive years (2002-2012); assess patterns related to changes in ACIP recommendations; identify predictors of vaccination; and compare the results with those published by national U.S. surveys. Retrospective cohort study of 721,898 pregnancies conducted in 2014. Coverage rates were assessed for all pregnancies and for live births only. Multivariate regression analysis identified predictors associated with vaccination. Coverage increased from 8.8% to 50.9% in 2002-2012. Seasonal coverage rates increased slowly following the 2004 ACIP influenza vaccine recommendation (to remove the first trimester restriction), but spiked significantly during the 2009 H1N1 influenza pandemic. Significant predictors of vaccination during pregnancy included older age; vaccination in a previous season; high-risk conditions in addition to pregnancy; pregnancy during either the 2004-2005 or 2009-2010 seasons; entering the influenza season after the first trimester of pregnancy; and a pregnancy with longer overlap with the influenza season (pvaccination coverage among pregnant women increased between the 2002-2003 and 2011-2012 seasons, although it was still below the developmental Healthy People 2020 goal of 80%. The 2004 ACIP language change positively impacted first-trimester vaccination uptake. Vaccine Safety Datalink data estimates were consistent with U.S. estimates. Copyright © 2016 American Journal of Preventive Medicine. All rights reserved.

  9. Childhood vaccines and Kawasaki disease, Vaccine Safety Datalink, 1996-2006.

    Science.gov (United States)

    Abrams, Joseph Y; Weintraub, Eric S; Baggs, James M; McCarthy, Natalie L; Schonberger, Lawrence B; Lee, Grace M; Klein, Nicola P; Belongia, Edward A; Jackson, Michael L; Naleway, Allison L; Nordin, James D; Hambidge, Simon J; Belay, Ermias D

    2015-01-03

    Kawasaki disease is a childhood vascular disorder of unknown etiology. Concerns have been raised about vaccinations being a potential risk factor for Kawasaki disease. Data from the Vaccine Safety Datalink were collected on children aged 0-6 years at seven managed care organizations across the United States. Defining exposure as one of several time periods up to 42 days after vaccination, we conducted Poisson regressions controlling for age, sex, season, and managed care organization to determine if rates of physician-diagnosed and verified Kawasaki disease were elevated following vaccination compared to rates during all unexposed periods. We also performed case-crossover analyses to control for unmeasured confounding. A total of 1,721,186 children aged 0-6 years from seven managed care organizations were followed for a combined 4,417,766 person-years. The rate of verified Kawasaki disease was significantly lower during the 1-42 days after vaccination (rate ratio=0.50, 95% CL=0.27-0.92) and 8-42 days after vaccination (rate ratio=0.45, 95% CL=0.22-0.90) compared to rates during unexposed periods. Breaking down the analysis by vaccination category did not identify a subset of vaccines which was solely responsible for this association. The case-crossover analyses revealed that children with Kawasaki disease had lower rates of vaccination in the 42 days prior to symptom onset for both physician-diagnosed Kawasaki disease (rate ratio=0.79, 95% CL=0.64-0.97) and verified Kawasaki disease (rate ratio=0.38, 95% CL=0.20-0.75). Childhood vaccinations' studied did not increase the risk of Kawasaki disease; conversely, vaccination was associated with a transient decrease in Kawasaki disease incidence. Verifying and understanding this potential protective effect could yield clues to the underlying etiology of Kawasaki disease. Copyright © 2014. Published by Elsevier Ltd.

  10. Demographic characteristics of members of the Vaccine Safety Datalink (VSD): A comparison with the United States population.

    Science.gov (United States)

    Sukumaran, Lakshmi; McCarthy, Natalie L; Li, Rongxia; Weintraub, Eric S; Jacobsen, Steven J; Hambidge, Simon J; Jackson, Lisa A; Naleway, Allison L; Chan, Berwick; Tao, Biwen; Gee, Julianne

    2015-08-26

    The Vaccine Safety Datalink (VSD) is a collaboration between CDC and nine integrated health care systems that serves as a cornerstone of US post-licensure vaccine safety monitoring. Given concerns that potential differences between the insured VSD population and the US population could limit the generalizability of VSD study findings, we performed a comparison of the demographic characteristics between the two populations. We collected data from medical records and administrative files at VSD sites in 2010 to compare sex, age, race, ethnicity, income, and educational attainment to the 2010 US Census population. We also compared data on the 2012 VSD Medicaid population to 2012 US Medicaid data. The VSD population included over eight million individuals in 2010, which represented 2.6% of the total US population. All major demographic groups were represented in the VSD. We found no major differences in comparing sex, race, ethnicity, and educational attainment between the VSD and the US population. Middle income populations were comparable between the VSD and the US. While the percentage of lower income populations was less in the VSD compared to the US, the VSD had over two million individuals in this group. Additionally, there were over 600,000 Medicaid members in the VSD in 2012, which represented 1.1% of the US Medicaid population. We found that the VSD population is representative of the general US population on several key demographic and socioeconomic variables. Despite a few specific groups being underrepresented in the VSD compared to the US, the absolute number of VSD members is large enough to ensure significant representation of these groups in vaccine safety studies that use VSD data. Copyright © 2015 Elsevier Ltd. All rights reserved.

  11. Risk of venous thromboembolism following influenza vaccination in adults aged 50years and older in the Vaccine Safety Datalink.

    Science.gov (United States)

    Vickers, Elizabeth R; McClure, David L; Naleway, Allison L; Jacobsen, Steven J; Klein, Nicola P; Glanz, Jason M; Weintraub, Eric S; Belongia, Edward A

    2017-10-13

    Influenza-like illness and inflammation are known risk factors for venous thromboembolism (VTE), which includes deep vein thrombosis (DVT) and pulmonary embolism (PE). However, few studies have characterized the risk of VTE following influenza vaccination. We examined VTE risk after vaccination in adults 50years old and older within the Vaccine Safety Datalink (VSD). We used the self-controlled case series method to determine the risk of VTE among age-eligible adults who received influenza vaccine (with or without pandemic H1N1) and experienced a VTE during the months of September through December in 2007 through 2012. Presumptive VTE cases were identified among VSD participants using diagnostic codes, diagnostic tests, and oral anticoagulant prescription. Potential cases were validated by medical record review. The VTE incidence rate ratio was calculated among confirmed cases for the risk window 1 to 10days after vaccination relative to all other person-time from September through December. Of the 1,488 presumptive cases identified, 508 were reviewed, of which 492 (97%) were confirmed cases of VTE. The analysis included 396 incident, confirmed cases. Overall, there was no increased risk of VTE in the 1 to 10days after influenza vaccination (IRR=0.89, 95% CI 0.69-1.17) compared to the control period. Results were similar when all person-time was censored before vaccination. A post hoc analysis showed an increased risk among current tobacco smokers (IRR=2.57, 95% CI 1.06-6.23). No clustering of VTE was observed in the 1-42days after vaccination. Overall, there was no evidence that inactivated influenza vaccine was associated with VTE in adults ≥50years old. An increased risk was found among current smokers in a post hoc analysis. These findings are consistent with previous research and support the safety of annual vaccination in this population. Copyright © 2017 Elsevier Ltd. All rights reserved.

  12. Construction of a Multisite DataLink Using Electronic Health Records for the Identification, Surveillance, Prevention, and Management of Diabetes Mellitus: The SUPREME-DM Project

    Science.gov (United States)

    Desai, Jay; Elston Lafata, Jennifer; Lawrence, Jean M.; O’Connor, Patrick J.; Pathak, Ram D.; Raebel, Marsha A.; Reid, Robert J.; Selby, Joseph V.; Silverman, Barbara G.; Steiner, John F.; Stewart, W.F.; Vupputuri, Suma; Waitzfelder, Beth

    2012-01-01

    Introduction Electronic health record (EHR) data enhance opportunities for conducting surveillance of diabetes. The objective of this study was to identify the number of people with diabetes from a diabetes DataLink developed as part of the SUPREME-DM (SUrveillance, PREvention, and ManagEment of Diabetes Mellitus) project, a consortium of 11 integrated health systems that use comprehensive EHR data for research. Methods We identified all members of 11 health care systems who had any enrollment from January 2005 through December 2009. For these members, we searched inpatient and outpatient diagnosis codes, laboratory test results, and pharmaceutical dispensings from January 2000 through December 2009 to create indicator variables that could potentially identify a person with diabetes. Using this information, we estimated the number of people with diabetes and among them, the number of incident cases, defined as indication of diabetes after at least 2 years of continuous health system enrollment. Results The 11 health systems contributed 15,765,529 unique members, of whom 1,085,947 (6.9%) met 1 or more study criteria for diabetes. The nonstandardized proportion meeting study criteria for diabetes ranged from 4.2% to 12.4% across sites. Most members with diabetes (88%) met multiple criteria. Of the members with diabetes, 428,349 (39.4%) were incident cases. Conclusion The SUPREME-DM DataLink is a unique resource that provides an opportunity to conduct comparative effectiveness research, epidemiologic surveillance including longitudinal analyses, and population-based care management studies of people with diabetes. It also provides a useful data source for pragmatic clinical trials of prevention or treatment interventions. PMID:22677160

  13. Post licensure surveillance of influenza vaccines in the Vaccine Safety Datalink in the 2013-2014 and 2014-2015 seasons.

    Science.gov (United States)

    Li, Rongxia; Stewart, Brock; McNeil, Michael M; Duffy, Jonathan; Nelson, Jennifer; Kawai, Alison Tse; Baxter, Roger; Belongia, Edward A; Weintraub, Eric

    2016-08-01

    The changes in each year in influenza vaccine antigenic components as well as vaccine administration patterns may pose new risks of adverse events following immunization (AEs). To evaluate the safety of influenza vaccines annually administered to people ≥ 6 months, we conducted weekly post licensure surveillance for seven pre-specified adverse events following receipt of influenza vaccines during the 2013-2014 and 2014-2015 seasons in the Vaccine Safety Datalink (VSD). We used both a historically-controlled cohort design with the Poisson-based maximized sequential probability ratio test (maxSPRT) and a self-controlled risk interval (SCRI) design with the binomial-based maxSPRT. For each adverse event outcome, we defined the risk interval on the basis of biologic plausibility and prior literature. For the historical cohort design, numbers of expected adverse events were calculated from the prior seven seasons, adjusted for age and site. For the SCRI design, a comparison window was defined either before vaccination or after vaccination, depending on each specific outcome. An elevated risk of febrile seizures 0-1 days following trivalent inactivated influenza vaccine (IIV3) was identified in children aged 6-23 months during the 2014-2015 season using the SCRI design. We found the relative risk (RR) of febrile seizures following concomitant administration of IIV3 and PCV13 was 5.3 with a 95% CI 1.87-14.75. Without concomitant PCV 13 administration, the estimated risk decreased and was no longer statistically significant (RR: 1.4; CI: 0.54 - 3.61). No increased risks, other than for febrile seizures, were identified in influenza vaccine safety surveillance during 2013-2014 and 2014-2015 seasons in the VSD. Copyright © 2016 John Wiley & Sons, Ltd. Copyright © 2016 John Wiley & Sons, Ltd.

  14. Nuclear safety project

    International Nuclear Information System (INIS)

    Anon.

    1980-11-01

    The 17th semi-annual report 1980/1 is a description of work within the Nuclear Safety Project performed in the first six months of 1980 in the nuclear safety field by KfK institutes and departments and by external institutions on behalf of KfK. The chosen kind of this report is that of short summaries, containing the topics - work performed, results obtained, plans for future work. (orig.) [de

  15. Guillain-Barré Syndrome, Influenza Vaccination, and Antecedent Respiratory and Gastrointestinal Infections: A Case-Centered Analysis in the Vaccine Safety Datalink, 2009-2011.

    Directory of Open Access Journals (Sweden)

    Sharon K Greene

    Full Text Available Guillain-Barré Syndrome (GBS can be triggered by gastrointestinal or respiratory infections, including influenza. During the 2009 influenza A (H1N1 pandemic in the United States, monovalent inactivated influenza vaccine (MIV availability coincided with high rates of wildtype influenza infections. Several prior studies suggested an elevated GBS risk following MIV, but adjustment for antecedent infection was limited.We identified patients enrolled in health plans participating in the Vaccine Safety Datalink and diagnosed with GBS from July 2009 through June 2011. Medical records of GBS cases with 2009-10 MIV, 2010-11 trivalent inactivated influenza vaccine (TIV, and/or a medically-attended respiratory or gastrointestinal infection in the 1 through 141 days prior to GBS diagnosis were reviewed and classified according to Brighton Collaboration criteria for diagnostic certainty. Using a case-centered design, logistic regression models adjusted for patient-level time-varying sources of confounding, including seasonal vaccinations and infections in GBS cases and population-level controls.Eighteen confirmed GBS cases received vaccination in the 6 weeks preceding onset, among 1.27 million 2009-10 MIV recipients and 2.80 million 2010-11 TIV recipients. Forty-four confirmed GBS cases had infection in the 6 weeks preceding onset, among 3.77 million patients diagnosed with medically-attended infection. The observed-versus-expected odds that 2009-10 MIV/2010-11 TIV was received in the 6 weeks preceding GBS onset was odds ratio = 1.54, 95% confidence interval (CI, 0.59-3.99; risk difference = 0.93 per million doses, 95% CI, -0.71-5.16. The association between GBS and medically-attended infection was: odds ratio = 7.73, 95% CI, 3.60-16.61; risk difference = 11.62 per million infected patients, 95% CI, 4.49-26.94. These findings were consistent in sensitivity analyses using alternative infection definitions and risk intervals for prior

  16. CERN Safety Alarm Monitoring Project

    CERN Document Server

    Grau, S; Nunes, R W; Scibile, L; Soler, C

    2000-01-01

    The CERN Safety Alarm Monitoring (CSAM) system is the alarm transmission and supervision system for all CERN premises in the LHC era. Its objective is to help safeguard human life, property and the environment. The CSAM system consists of the acquisition, transmission, supervision and management of alarm-related data using state-of-the-art technology. It also includes some automatic safety actions to reduce hazardous events. As this is a large and multidisciplinary project a strategy based on three main issues was defined. First, the safety standards provide us with a technical framework for dealing systematically with safety-related activities in order to minimize system failures, optimize performance and obtain homogeneity with LHC site installations, maintenance and operation. Second, a rapid prototyping methodology leads to the best technical solutions; and, finally, we consider the commercial aspects required for a tendering procedure.

  17. Spent Nuclear Fuel Project Safety Management Plan

    International Nuclear Information System (INIS)

    Garvin, L.J.

    1996-02-01

    The Spent Nuclear Fuel Project Safety Management Plan describes the new nuclear facility regulatory requirements basis for the Spemt Nuclear Fuel (SNF) Project and establishes the plan to achieve compliance with this basis at the new SNF Project facilities

  18. National Ignition Facility Project Site Safety Program

    International Nuclear Information System (INIS)

    Dun, C

    2003-01-01

    This Safety Program for the National Ignition Facility (NIF) presents safety protocols and requirements that management and workers shall follow to assure a safe and healthful work environment during activities performed on the NIF Project site. The NIF Project Site Safety Program (NPSSP) requires that activities at the NIF Project site be performed in accordance with the ''LLNL ES and H Manual'' and the augmented set of controls and processes described in this NIF Project Site Safety Program. Specifically, this document: (1) Defines the fundamental NIF site safety philosophy. (2) Defines the areas covered by this safety program (see Appendix B). (3) Identifies management roles and responsibilities. (4) Defines core safety management processes. (5) Identifies NIF site-specific safety requirements. This NPSSP sets forth the responsibilities, requirements, rules, policies, and regulations for workers involved in work activities performed on the NIF Project site. Workers are required to implement measures to create a universal awareness that promotes safe practice at the work site and will achieve NIF management objectives in preventing accidents and illnesses. ES and H requirements are consistent with the ''LLNL ES and H Manual''. This NPSSP and implementing procedures (e.g., Management Walkabout, special work procedures, etc.,) are a comprehensive safety program that applies to NIF workers on the NIF Project site. The NIF Project site includes the B581/B681 site and support areas shown in Appendix B

  19. Effective Safety Management in Construction Project

    Science.gov (United States)

    Othman, I.; Shafiq, Nasir; Nuruddin, M. F.

    2017-12-01

    Effective safety management is one of the serious problems in the construction industry worldwide, especially in large-scale construction projects. There have been significant reductions in the number and the rate of injury over the last 20 years. Nevertheless, construction remains as one of the high risk industry. The purpose of this study is to examine safety management in the Malaysian construction industry, as well as to highlight the importance of construction safety management. The industry has contributed significantly to the economic growth of the country. However, when construction safety management is not implemented systematically, accidents will happen and this can affect the economic growth of the country. This study put the safety management in construction project as one of the important elements to project performance and success. The study emphasize on awareness and the factors that lead to the safety cases in construction project.

  20. Causal Models for Safety Assurance Technologies Project

    Data.gov (United States)

    National Aeronautics and Space Administration — Fulfillment of NASA's System-Wide Safety and Assurance Technology (SSAT) project at NASA requires leveraging vast amounts of data into actionable knowledge. Models...

  1. Nuclear Safety Project. Annual report 1983

    International Nuclear Information System (INIS)

    1984-06-01

    The annual report 1983 is a detailed description (in German language) of work within the Nuclear Safety Project performed in 1983 in the nuclear safety field by KfK institutes and departments and by external institutes on behalf of KfK. It includes for each individual research activity short summaries in English language on work performed, results obtained and plans for future work. This report was compiled by the project management. (orig.) [de

  2. Nuclear safety project. Annual report 1985

    International Nuclear Information System (INIS)

    1986-07-01

    The annual report 1985 is a detailed description (in German language) of work within the nuclear safety project performed in 1985 in the nuclear safety field by KfK institutes and departments and by external institutes on behalf of KfK. It includes for each individual research activity short summaries in English language on work performed, results obtained and plans for future work. This report was compiled by the project management. (orig./HP) [de

  3. Nordic projects concerning nuclear safety

    International Nuclear Information System (INIS)

    Soerensen, H.C.

    1988-11-01

    The report describes the nature of the work done in the first half of 1988 within the field of nuclear safety (1985-89) under the Nordic program for 1985-89. Five programmes and their documentation, are described and complete lists of addresses and of persons involved is given. (AB)

  4. Project safety studies - nuclear waste management (PSE)

    International Nuclear Information System (INIS)

    1981-10-01

    The project 'Safety Studies-Nuclear Waste Management' (PSE) is a research project performed by order of the Federal Minister for Research and Technology, the general purpose of which is to deepen and ensure the understanding of the safety aspects of the nuclear waste management and to prepare a risk analysis which will have to be established in the future. Owing to this the project is part of a series of projects which serve the further development of the concept of nuclear waste management and its safety, and which are set up in such a way as to accompany the realization of that concept. This report contains the results of the first stage of the project from 1978 to mid-1981. (orig./RW) [de

  5. Safety as a Foundation for Project Success

    International Nuclear Information System (INIS)

    Schepens, R.J.; Wiegman, S.A.; Shrader, T.; Coleman, S.J.

    2006-01-01

    This paper describes the importance of safety as a foundation for success on the largest and most complex cleanup project in the DOE complex. It describes the breadth of safety considerations ranging from design of systems to prevent low probability large consequence events to the day-to-day work hazard analysis and accident prevention. We are developing many first of a kind systems for handling, treating and disposing of the nation's largest volume of stored radioactive and hazardous waste. It is stored in aging underground tanks distributed across nearly 100 square miles. The project includes the development of retrieval and transfer systems, treatment and product handling, storage and disposal. When considering safety for a project of this magnitude it is necessary to include knowledge from almost every discipline as the breadth of hazard is large. Line ownership, worker involvement, and open communication are keys to safety success. (authors)

  6. Safety Culture in New Build Projects

    International Nuclear Information System (INIS)

    Reiman, T.

    2016-01-01

    The concept of culture emphasises the social factors that have an effect on the way hazards are perceived, risks are evaluated, risk management is conducted, the current safety level is interpreted, and what is considered normal and what abnormal. It also contributes to defining the correct ways to behave in situations and correct ways to talk about safety, risks or uncertainty. Culture is something the company has created for itself that then has an effect on the company. This effect is not necessarily perceived by the company itself, since the members of the organization consider all things that happen according to their cultural taken-for-granted assumptions (“business as usual”). Thus, safety culture can either hinder or advance nuclear safety. This depends on what the shared values and assumptions are, and how they are in line with, and influence, the organizational structures, practices, personnel and technology. Safety culture requires constant and systematic development, monitoring and review during the entire life-cycle of a nuclear facility. The pre-operational phase sets many unique requirements for nuclear safety culture. For example, some of the organizations and individuals involved in the project may have no insight on how safety culture relates to nuclear power plants. Companies that work in the conventional industry typically associate safety with occupational safety issues, not with nuclear safety. Further, it may be unclear how the construction phase affects nuclear safety of an operating plant. When workers are asked to perform their work differently than previously (e.g., in conventional construction sites), explanation has to be given. For example, structures, systems and components may have different functions during emergency that exceed or differ from their quality requirements during normal operation. The strict quality requirements and use of certain methods and procedures, documentation requirements, etc., may seem unimportant if

  7. Nuclear Safety Project - annual report 1980

    International Nuclear Information System (INIS)

    1981-08-01

    The Annual Report 1980 is a detailed description (in German language) of work within the Nuclear Safety Project performed in 1980 in the nuclear safety field by KfK institutes and departments and by external institutes on behalf of KfK. It includes for each individual research activity short summaries in English language on work completed, essential results, plans for the near future. (orig./RW) [de

  8. Nuclear safety research project. Annual report 1995

    International Nuclear Information System (INIS)

    Hueper, R.

    1996-08-01

    The reactor safety R and D work of the Karlsruhe Research Centre (FZK) has been part of the Nuclear Safety Research Project (PSF) since 1990. The present annual report 1995 summarizes the R and D results. The research tasks are coordinated in agreement with internal and external working groups. The contributions to this report correspond to the status of early 1996. An abstract in English precedes each of them, whenever the respective article is written in German. (orig.) [de

  9. UMTRA Project environmental, health, and safety plan

    International Nuclear Information System (INIS)

    1989-02-01

    The basic health and safety requirements established in this plan are designed to provide guidelines to be applied at all Uranium Mill Tailings Remedial Action (UMTRA) Project sites. Specific restrictions are given where necessary. However, an attempt has been made to provide guidelines which are generic in nature, and will allow for evaluation of site-specific conditions. Health and safety personnel are expected to exercise professional judgment when interpreting these guidelines to ensure the health and safety of project personnel and the general population. This UMTRA Project Environmental, Health, and Safety (EH ampersand S) Plan specifies the basic Federal health and safety standards and special DOE requirements applicable to this program. In addition, responsibilities in carrying out this plan are delineated. Some guidance on program requirements and radiation control and monitoring is also included. An Environmental, Health, and Safety Plan shall be developed as part of the remedial action plan for each mill site and associated disposal site. Special conditions at the site which may present potential health hazards will be described, and special areas that should should be addressed by the Remedial Action Contractor (RAC) will be indicated. Site-specific EH ampersand S concerns will be addressed by special contract conditions in RAC subcontracts. 2 tabs

  10. Outline of criticality safety research project

    International Nuclear Information System (INIS)

    Kobayashi, Iwao; Tachimori, Shoichi; Suzaki, Takenori; Takeshita, Isao; Miyoshi, Yoshinori; Nakajima, Ken; Sakurai, Satoshi; Yanagisawa, Hiroshi

    1987-01-01

    As the power generation capacity of LWRs in Japan increased, the establishment and development of nuclear fuel cycle have become the important subject. Conforming to the safety research project of the nation, the Japan Atomic Energy Research Institute has advanced the project of constructing a new research facility, that is, Nuclear Fuel Cycle Engineering Research Facility (NUCEF). In this facility, it is planned to carry out the research on criticality safety, upgraded reprocessing techniques, and the treatment and disposal of transuranium element wastes. In this paper, the subjects of criticality safety research and the research carried out with a criticality safety experiment facility which is expected to be installed in the NUCEF are briefly reported. The experimental data obtained from the criticality safety handbooks and published literatures in foreign countries are short of the data on the mixture of low enriched uranium and plutonium which is treated in the reprocessing of spent fuel from LWRs. The acquisition of the criticality data for various forms of fuel, the elucidation of the scenario of criticality accidents, and the soundness of the confinement system for gaseous fission products and plutonium are the main subjects. The Static Criticality Safety Facility, Transient Criticality Safety Facility and pulse column system are the main facilities. (Kako, I.)

  11. Software Defined Radio Datalink Implementation Using PC-Type Computers

    National Research Council Canada - National Science Library

    Zafeiropoulos, Georgios

    2003-01-01

    The objective of this thesis was to examine the feasibility of implementation and the performance of a Software Defined Radio datalink, using a common PC type host computer and a high level programming language...

  12. Not Your Daddy's Data Link: Musings on Datalink Communications

    Science.gov (United States)

    Branstetter, James

    2004-01-01

    Viewgraphs about musings on Datalink Communications are presented. Some of the topics include: 1) Keen Eye for a Straight Proposal (Next Gen Data Link); 2) So many datalinks so little funding!!!; 3) Brave New World; 4) Time marches on!; 5) Through the Looking Glass; 6) Dollars & Sense Cooking; 7) Economics 101; 8) The Missing Link(s); 9) Straight Shooting; and 10) All is not lost.

  13. Krsko periodic safety review project prioritization process

    International Nuclear Information System (INIS)

    Basic, I.; Vrbanic, I.; Spiler, J.; Lambright, J.

    2004-01-01

    Definition of a Krsko Periodic Safety Review (PSR) project is a comprehensive safety review of a plant after last ten years of operation. The objective is a verification by means of a comprehensive review using current methods that Krsko NPP remains safety when judged against current safety objectives and practices and that adequate arrangements are in place to maintain plant safety. This objective encompasses the three main criteria or goals: confirmation that the plant is as safe as originally intended, determination if there are any structures, systems or components that could limit the life of the plant in the foreseeable future, and comparison the plant against modern safety standards and to identify where improvements would be beneficial at justifiable cost. Krsko PSR project is structured in the three phases: Phase 1: Preparation of Detailed 10-years PSR Program, Phase 2: Performing of 10-years PSR Program and preparing of associated documents (2001-2003), and Phase 3: Implementation of the prioritized compensatory measures and modifications (development of associated EEAR, DMP, etc.) after agreement with the SNSA on the design, procedures and time-scales (2004-2008). This paper presents the NEK PSR results of work performed under Phase 2 focused on the ranking of safety issues and prioritization of corrective measures needed for establishing an efficient action plan. Safety issues were identified in Phase 2 during the following review processes: Periodic Safety Review (PSR) task; Krsko NPP Regulatory Compliance Program (RCP) review; Westinghouse Owner Group (WOG) catalog items screening/review; SNSA recommendations (including IAEA RAMP mission suggestions/recommendations).(author)

  14. Project safety as a sustainable competitive advantage.

    Science.gov (United States)

    Rechenthin, David

    2004-01-01

    To be consistently profitable, a construction company must complete projects in scope, on schedule, and on budget. At the same time, the nature of the often high-risk work performed by construction companies can result in high accident rates. Clients and other stakeholders are placing increasing pressure on companies to decrease those accident rates. Clients routinely demand copies of safety plans and evidence of past results at the "pre-qualification" or "request for proposal" stages of the procurement process. Are high accident rates and the associated costs just a part of business? Companies that deliver on scope, schedule, and budget have a competitive advantage. Is it possible for projects with low accident rates to use it as a competitive advantage? Is the value added by safety just a temporary or parity issue, or does a successful safety program offer significant advantage to the company and the client? This article concludes that in the case of a high-risk industry, such as the construction industry, an organization with a successful safety program can promote safety performance as a sustainable competitive advantage. It is a choice the company can make.

  15. UMTRA Project: Environment, Safety, and Health Plan

    Energy Technology Data Exchange (ETDEWEB)

    1995-02-01

    The US Department of Energy has prepared this UMTRA Project Environment, Safety, and Health (ES and H) Plan to establish the policy, implementing requirements, and guidance for the UMTRA Project. The requirements and guidance identified in this plan are designed to provide technical direction to UMTRA Project contractors to assist in the development and implementation of their ES and H plans and programs for UMTRA Project work activities. Specific requirements set forth in this UMTRA Project ES and H Plan are intended to provide uniformity to the UMTRA Project`s ES and H programs for processing sites, disposal sites, and vicinity properties. In all cases, this UMTRA Project ES and H Plan is intended to be consistent with applicable standards and regulations and to provide guidance that is generic in nature and will allow for contractors` evaluation of site or contract-specific ES and H conditions. This plan specifies the basic ES and H requirements applicable to UMTRA Project ES and H programs and delineates responsibilities for carrying out this plan. DOE and contractor ES and H personnel are expected to exercise professional judgment and apply a graded approach when interpreting these guidelines, based on the risk of operations.

  16. UMTRA Project: Environment, Safety, and Health Plan

    International Nuclear Information System (INIS)

    1995-02-01

    The US Department of Energy has prepared this UMTRA Project Environment, Safety, and Health (ES and H) Plan to establish the policy, implementing requirements, and guidance for the UMTRA Project. The requirements and guidance identified in this plan are designed to provide technical direction to UMTRA Project contractors to assist in the development and implementation of their ES and H plans and programs for UMTRA Project work activities. Specific requirements set forth in this UMTRA Project ES and H Plan are intended to provide uniformity to the UMTRA Project's ES and H programs for processing sites, disposal sites, and vicinity properties. In all cases, this UMTRA Project ES and H Plan is intended to be consistent with applicable standards and regulations and to provide guidance that is generic in nature and will allow for contractors' evaluation of site or contract-specific ES and H conditions. This plan specifies the basic ES and H requirements applicable to UMTRA Project ES and H programs and delineates responsibilities for carrying out this plan. DOE and contractor ES and H personnel are expected to exercise professional judgment and apply a graded approach when interpreting these guidelines, based on the risk of operations

  17. Data-link of autonomous CAMAC processor systems with a computer

    International Nuclear Information System (INIS)

    Brehmer, W.

    1978-08-01

    Employing CAMAC processor systems, a data-link, connecting the processor system and a host-computer, is often required. The functions for the data-link has been defined. The implementation of the data-link between a DEC-Computer PDP 11/4phi and an INCAA CAMAC processor system CAPRO-1 is described. The data-link includes procedures for dialog and datatransfer integrated into the executive of the processor system CAPRO-1. (orig.) [de

  18. Use of safety management practices for improving project performance.

    Science.gov (United States)

    Cheng, Eddie W L; Kelly, Stephen; Ryan, Neal

    2015-01-01

    Although site safety has long been a key research topic in the construction field, there is a lack of literature studying safety management practices (SMPs). The current research, therefore, aims to test the effect of SMPs on project performance. An empirical study was conducted in Hong Kong and the data collected were analysed with multiple regression analysis. Results suggest that 3 of the 15 SMPs, which were 'safety committee at project/site level', 'written safety policy', and 'safety training scheme' explained the variance in project performance significantly. Discussion about the impact of these three SMPs on construction was provided. Assuring safe construction should be an integral part of a construction project plan.

  19. The Citizenship Safety Project: a pilot study.

    Science.gov (United States)

    Frederick, K; Barlow, J

    2006-02-01

    The Government White Paper Saving Lives: Our Healthier Nation (1999) provides a clear indication that accidents are a serious public health problem and have been targeted by the Department of Health as a key area for prevention over the next 10 years. School-based injury prevention programmes have been identified as one of the key settings for the implementation of the White Paper's heath promotion strategies. The Citizen Safety Project (CSP) is a peer-delivered injury prevention programme for Year 10 students (14-15 years) and Year 2 pupils (6-7 years). This paper summarizes the findings of a pilot study that assessed the feasibility of implementing the CSP in schools and of conducting a larger study. Working as part of their Personal Social Health Education lessons, 11 pairs (n = 22) of Year 10 students developed a project to take one accident prevention theme of their choice into a primary school to teach small groups of five or six Year 2 pupils (n = 55). A formative evaluation was conducted, based on interviews with Year 2 and Year 10 teachers (n = 2), and the diaries of Year 10 students. Knowledge of accident prevention and risk awareness was measured in Year 2 pupils using the Draw and Write technique, and impact on Year 10 students was measured using self-esteem and locus of control inventories. Using both statistical and thematic analysis the study concludes that the CSP is well accepted, improves knowledge in Year 2 pupils and boosts confidence in Year 10 students, while concurrently achieving key stage attainment targets. Implications of the study are discussed in terms of future research, as are recommendations with regard to modifications to the project.

  20. Optimization of safety on pavement preservation projects.

    Science.gov (United States)

    2011-01-01

    To achieve a goal of reducing highway crash fatalities by 4% each year to improve roadway safety, the Georgia Department of Transportation (GDOT) is actively seeking opportunities to incorporate safety improvements into its current pavement preservat...

  1. Expediting Clinician Adoption of Safety Practices: The UCSF Venous Access Patient Safety Interdisciplinary Education Project

    National Research Council Canada - National Science Library

    Donaldson, Nancy E; Plank, Rosemary K; Williamson, Ann; Pearl, Jeffrey; Kellogg, Jerry; Ryder, Marcia

    2005-01-01

    ...) Venous Access Device (VAD) Patient Safety Interdisciplinary Education Project was to develop a 30-hour/one clinical academic unit VAD patient safety course with the aim of expediting clinician adoption of critical concepts...

  2. Enhancing Safety Culture in Complex Nuclear Industry Projects

    International Nuclear Information System (INIS)

    Gotcheva, N.

    2016-01-01

    This paper presents an on-going research project “Management principles and safety culture in complex projects” (MAPS), supported by the Finnish Research Programme on Nuclear Power Plant Safety 2015-2018. The project aims at enhancing safety culture and nuclear safety by supporting high quality execution of complex projects in the nuclear industry. Safety-critical industries are facing new challenges, related to increased outsourcing and complexity in technology, work tasks and organizational structures (Milch and Laumann, 2016). In the nuclear industry, new build projects, as well as modernisation projects are temporary undertakings often carried out by networks of companies. Some companies may have little experience in the nuclear industry practices or consideration of specific national regulatory requirements. In large multinational subcontractor networks, the challenge for assuring nuclear safety arises partly from the need to ensure that safety and quality requirements are adequately understood and fulfilled by each partner. Deficient project management practices and unsatisfactory nuclear safety culture in project networks have been recognised as contributing factors to these challenges (INPO, 2010). Prior evidence indicated that many recent major projects have experienced schedule, quality and financial challenges both in the nuclear industry (STUK, 2011) and in the non-nuclear domain (Ahola et al., 2014; Brady and Davies, 2010). Since project delays and quality issues have been perceived mainly as economic problems, project management issues remain largely understudied in safety research. However, safety cannot be separated from other performance aspects if a systemic view is applied. Schedule and quality challenges may reflect deficiencies in coordination, knowledge and competence, distribution of roles and responsibilities or attitudes among the project participants. It is increasingly understood that the performance of the project network in all

  3. Present status of International Criticality Safety Benchmark Evaluation Project (ICSBEP)

    International Nuclear Information System (INIS)

    Miyoshi, Yoshinori

    2000-01-01

    The International Criticality Safety Evaluation Project, ICSBEP was designed to identify and evaluate a comprehensive set of critical experiment benchmark data. Compilation of the data into a standardized format are made by reviewing original and subsequently revised documentation for calculating each experiment with standard criticality safety codes. Five handbooks of evaluated criticality safety benchmark experiments have been published since 1995. (author)

  4. Hotel and Motel Fire Safety Project - USFA

    Data.gov (United States)

    Department of Homeland Security — Provides a listing of properties compliant with the requirements of the Hotel and Motel Fire Safety Act of 1990. Users may search for compliant properties and submit...

  5. Surface Map Traffic Intent Displays and Net-Centric Data-link Communications for NextGen

    Science.gov (United States)

    Shelton, Kevin J.; Prinzel, Lawrence J., III; Jones, Denise R.; Allamandola, Angela S.; Arthur, Jarvis J., III; Bailey, Randall E.

    2009-01-01

    By 2025, U.S. air traffic is predicted to increase three fold and may strain the current air traffic management system, which may not be able to accommodate this growth. In response to this challenge, a revolutionary new concept has been proposed for U.S. aviation operations, termed the Next Generation Air Transportation System or "NextGen". Many key capabilities are being identified to enable NextGen, including the use of data-link communications. Because NextGen represents a radically different approach to air traffic management and requires a dramatic shift in the tasks, roles, and responsibilities for the flight deck, there are numerous research issues and challenges that must be overcome to ensure a safe, sustainable air transportation system. Flight deck display and crew-vehicle interaction concepts are being developed that proactively investigate and overcome potential technology and safety barriers that might otherwise constrain the full realization of NextGen. The paper describes simulation research, conducted at National Aeronautics and Space Administration (NASA) Langley Research Center, examining data-link communications and traffic intent data during envisioned four-dimensional trajectory (4DT)-based and equivalent visual (EV) surface operations. Overall, the results suggest that controller pilot data-link communications (CPDLC) with the use of mandatory pilot read-back of all clearances significantly enhanced situation awareness for 4DT and EV surface operations. The depiction of graphical traffic state and intent information on the surface map display further enhanced off-nominal detection and pilot qualitative reports of safety and awareness.

  6. Environmental Restoration Disposal Facility (Project W-296) Safety Assessment

    International Nuclear Information System (INIS)

    Armstrong, D.L.

    1994-08-01

    This Safety Assessment is based on information derived from the Conceptual Design Report for the Environmental Restoration Disposal Facility (DOE/RL 1994) and ancillary documentation developed during the conceptual design phase of Project W-296. The Safety Assessment has been prepared to support the Solid Waste Burial Ground Interim Safety Basis document. The purpose of the Safety Assessment is to provide an evaluation of the design to determine if the process, as proposed, will comply with US Department of Energy (DOE) Limits for radioactive and hazardous material exposures and be acceptable from an overall health and safety standpoint. The evaluation considered affects on the worker, onsite personnel, the public, and the environment

  7. Project W-030 safety class upgrade summary report

    Energy Technology Data Exchange (ETDEWEB)

    Kriskovich, J.R.

    1998-02-13

    This document presents a summary of safety class criteria for the 241-AY/AZ Tank Farm primary ventilation system upgrade under Project W-030, and recommends acceptance of the system as constructed, based on a review of supporting documentation.

  8. Automation of Safety Analysis with SysML Models Project

    Data.gov (United States)

    National Aeronautics and Space Administration — This project was a small proof-of-concept case study, generating SysML model information as a side effect of safety analysis. A prototype FMEA Assistant was...

  9. SNF fuel retrieval sub project safety analysis document

    Energy Technology Data Exchange (ETDEWEB)

    BERGMANN, D.W.

    1999-02-24

    This safety analysis is for the SNF Fuel Retrieval (FRS) Sub Project. The FRS equipment will be added to K West and K East Basins to facilitate retrieval, cleaning and repackaging the spent nuclear fuel into Multi-Canister Overpack baskets. The document includes a hazard evaluation, identifies bounding accidents, documents analyses of the accidents and establishes safety class or safety significant equipment to mitigate accidents as needed.

  10. Network management tools for a GPS datalink network

    Science.gov (United States)

    Smyth, Padhraic; Chauvin, Todd; Oliver, Gordon; Statman, Joseph

    1991-01-01

    The availability of GPS (Global Position Satellite) information in real-time via a datalink system is shown to significantly increase the capacity of flight test and training ranges in terms of missions supported. This increase in mission activity. imposes demands on mission planning in the range-operations environment. In this context, network management tools which can improve the capability of range personnel to plan, monitor, and control network resources, are of significant interest. The application of both simulation and artificial intelligence techniques is described to develop such network managements tools.

  11. ELECTRICAL SAFETY IMPROVEMENT PROJECT A COMPLEX WIDE TEAMING INITIATIVE

    Energy Technology Data Exchange (ETDEWEB)

    GRAY BJ

    2007-11-26

    This paper describes the results of a year-long project, sponsored by the Energy Facility Contractors Group (EFCOG) and designed to improve overall electrical safety performance throughout Department of Energy (DOE)-owned sites and laboratories. As evidenced by focused metrics, the Project was successful primarily due to the joint commitment of contractor and DOE electrical safety experts, as well as significant support from DOE and contractor senior management. The effort was managed by an assigned project manager, using classical project-management principles that included execution of key deliverables and regular status reports to the Project sponsor. At the conclusion of the Project, the DOE not only realized measurable improvement in the safety of their workers, but also had access to valuable resources that will enable them to do the following: evaluate and improve electrical safety programs; analyze and trend electrical safety events; increase electrical safety awareness for both electrical and non-electrical workers; and participate in ongoing processes dedicated to continued improvement.

  12. Radiation safety at the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    Hoffman, R.L.

    1997-01-01

    This is a report on the Radiation Safety Program at the West Valley Demonstration Project (WVDP). This Program covers a number of activities that support high-level waste solidification, stabilization of facilities, and decontamination and decommissioning activities at the Project. The conduct of the Program provides confidence that all occupational radiation exposures received during operational tasks at the Project are within limits, standards, and program requirements, and are as low as reasonably achievable

  13. Study of system safety evaluation on LTO of national project. NISA safety research project on system safety of nuclear power plants

    International Nuclear Information System (INIS)

    Takizawa, Masayuki; Sekimura, Naoto; Miyano, Hiroshi; Aoyama, Katsunobu

    2012-01-01

    Japanese safety regulatory body, that is, Nuclear and Industrial Safety Agency (NISA) started a 5-year national safety research project as 'the first stage' from 2006 FY to 2010 FY whose objective is 'Improve the technical information basis in order to utilize knowledge as well as information related to ageing management and maintenance of NPPs. Fukushima disaster happened in March 2011, and the priority of research needs for ageing management dramatically changed in Japan. The second-stage national project started in October 2011 with the concept of 'system safety' of NNPs where not only ageing management on degradation phenomena of important components but also safety management on total plant systems are paid attention to. The second-stage project is so called 'Japanese Ageing Management Program for System Safety (JAMPSS)'. (author)

  14. A root cause analysis project in a medication safety course.

    Science.gov (United States)

    Schafer, Jason J

    2012-08-10

    To develop, implement, and evaluate team-based root cause analysis projects as part of a required medication safety course for second-year pharmacy students. Lectures, in-class activities, and out-of-class reading assignments were used to develop students' medication safety skills and introduce them to the culture of medication safety. Students applied these skills within teams by evaluating cases of medication errors using root cause analyses. Teams also developed error prevention strategies and formally presented their findings. Student performance was assessed using a medication errors evaluation rubric. Of the 211 students who completed the course, the majority performed well on root cause analysis assignments and rated them favorably on course evaluations. Medication error evaluation and prevention was successfully introduced in a medication safety course using team-based root cause analysis projects.

  15. Transport fire safety engineering in the European Union - project TRANSFEU

    Directory of Open Access Journals (Sweden)

    Jolanta Maria RADZISZEWSKA-WOLIŃSKA

    2011-01-01

    Full Text Available Article presents European Research project (of FP7-SST-2008-RTD-1 for Surface transportation TRANSFEU. Projects undertakes to deliver both a reliable toxicity measurement methodology and a holistic fire safety approach for all kind of surface transport. It bases on a harmonized Fire Safety Engineering methodology which link passive fire security with active fire security mode. This all embracing system is the key to attain optimum design solutions in respect to fire safety objectives as an alternative to the prescriptive approach. It will help in the development of innovative solutions (design and products used for the building of the surface transport which will better respect the environment.In order to reach these objectives new toxicity measurement methodology and related classification of materials, new numerical fire simulation tools, fire test methodology (laboratory and full scale and a decisive tool to optimize or explore new design in accordance to the fire safety requirements will be developed.

  16. Offshore safety research and development programme. Project handbook 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-02-01

    The Offshore Safety Division (OSD) of the Health and Safety Executive (HSE) undertakes Research and Development (R and D) in support of its regulatory responsibility for the safety of the offshore workforce and installations. The R and D programme undertaken has a broad technical scope ranging from `Collisions` to `Wells and Well Operations`. A strategy for this Research Programme has been published. The aim of this Handbook is to provide information on R and D projects which are currently in progress or have recently been completed. A similar handbook was published last year. To assist in the search for information, projects are grouped into sections according to their strategy area: collisions; decommissioning; diving operations; diver physiology; evacuation, escape and rescue; fire and blast; floating stability; human factors; materials performance; miscellaneous; moorings failure; occupational health; oceanography and fluid loading; pipelines; process systems and process control; safety systems; structural failure (concrete); structural failure (steel); and wells and well operations. (author)

  17. Evaluation of Mixed-Mode Data-Link Communications for NextGen 4DT and Equivalent Visual Surface Operations

    Science.gov (United States)

    Prinzel, Lawrence J., III; Shelton, Kevin J.; Jones, Denise R.; Allamandola, Angela S.; Arthur, Jarvis, J., III; Bailey, Randall E.

    2010-01-01

    By 2025, U.S. air traffic is predicted to increase 3-fold and may strain the current air traffic management system, which may not be able to accommodate this growth. In response to this challenge, a revolutionary new concept has been proposed for U.S. aviation operations, termed the Next Generation Air Transportation System or NextGen. Many key capabilities are being identified to enable NextGen, including the use of data-link communications. Because NextGen represents a radically different approach to air traffic management and requires a dramatic shift in the tasks, roles, and responsibilities for the flight deck, there are numerous research issues and challenges that must be overcome to ensure a safe, sustainable air transportation system. Flight deck display and crew-vehicle interaction concepts are being developed that proactively investigate and overcome potential technology and safety barriers that might otherwise constrain the full realization of NextGen. The paper describes simulation research examining data-link communications during 4DT and equivalent visual surface operations.

  18. Proceedings of the first annual Nuclear Criticality Safety Technology Project

    International Nuclear Information System (INIS)

    Rutherford, D.A.

    1994-09-01

    This document represents the published proceedings of the first annual Nuclear Criticality Safety Technology Project (NCSTP) Workshop, which took place May 12--14, 1992, in Gaithersburg, Md. The conference consisted of four sessions, each dealing with a specific aspect of nuclear criticality safety issues. The session titles were ''Criticality Code Development, Usage, and Validation,'' ''Experimental Needs, Facilities, and Measurements,'' ''Regulation, Compliance, and Their Effects on Nuclear Criticality Technology and Safety,'' and ''The Nuclear Criticality Community Response to the USDOE Regulations and Compliance Directives.'' The conference also sponsored a Working Group session, a report of the NCSTP Working Group is also presented. Individual papers have been cataloged separately

  19. Overview of DOE/ONS criticality safety projects

    International Nuclear Information System (INIS)

    Barber, R.W.; Brown, B.P.; Hopper, C.M.

    1985-01-01

    The evolution of Federal involvement with nuclear criticality safety has traversed through the 1940's and early 1950's with the Manhattan Engineering District, the 1950's and 1960's with the Atomic Energy Commission, the early 1970's with the Energy Research and Development Administration, and the late 1970's to date with the US Department of Energy. The importance of nuclear criticality safety has been maintained throughout these periods; however, criticality safety has received shifting emphases in research/applications, promulgations of regulations/standards, origins of fiscal support and organization. In June 1981 the Office of Nuclear Safety was established in response to a Department of Energy study of the impact of the March 1979 Three Mile Island accident. The organizational structure of the ONS, its program for establishing and maintaining a progressive nuclear criticality safety program, and associated projects, and current history of ONS's fiscal support of program projects is presented. With the establishment of the ONS came concomitant missions to develop and maintain nuclear safety policy and requirements, to provide independent assurance that nuclear operations are performed safely, to provide resources and management for DOE responses to nuclear accidents, and to provide technical support. In the past four years, ONS has developed and initiated a continuing Department Nuclear Criticality Safety Program in such areas as communications and information, physics of criticality, knowledge of factors affecting criticality, and computational capability

  20. Understanding lean & safety projects: analysis of case studies

    Directory of Open Access Journals (Sweden)

    Maria Crema

    2017-12-01

    Full Text Available Facing the current socio-economic contingency while guaranteeing a high level of care quality is particularly challenging in the field of healthcare. Through an integrated adoption of emerging managerial solutions, projects that allow organizations to achieve both efficiency and patient safety improvements could be implemented, thereby transposing policy directives towards a safer and more sustainable healthcare system. Therefore, the purpose of this paper is to investigate the features of Lean & Safety (L&S projects. Three Health Lean Management (HLM projects that had unexpected patient safety results were selected from the same region. Differences and similarities among the cases have been highlighted and interesting points of evidence have been noted. Despite the fact that the projects were pursuing similar objectives and benefiting from comparable support, the obtained changes had direct impact on patient safety enhancement in the cases that involved the front-office processes, and an indirect impact on patient safely for the L&S project that focused on back-office activities. The implementation processes and the Information and Communication Technologies (ICT adoption of the cases are also different.

  1. From initial safety considerations to a final safety case: forms and purposes of safety analysis during a disposal project's lifetime

    International Nuclear Information System (INIS)

    Vigfusson, J.

    2008-01-01

    During preparation and realisation of a radioactive waste disposal project a multitude of decisions are taken which require input from an assessment of the radiological safety of the disposal facility. Depending on the stage of the project and the purpose of the assessment, the safety assessments that are needed or are possible vary in comprehensiveness and in the choice of safety indicators. The paper compares the suite of safety considerations employed from the beginning of the search for a suitable radioactive waste repository site until the final closure of the repository. The reference material mostly derives from the regulatory basis and actual planning of the Swiss repository projects but illustrative examples are also taken from other national programmes. (author)

  2. The Nordic nuclear safety program 1994-1997. Project handbook

    International Nuclear Information System (INIS)

    1997-06-01

    This is a new revision of the handbook for administrators of the Nordic reactor safety program NKS. The most important administrative functions in project management are described, which should secure a uniform management approach in all the projects. The description of the organizational scheme of the NKS and distribution of responsibilities is followed by examples of various administrative routines and document forms. In the annex the names and addresses of the staff involved in administration of the NKS program are listed. (EG)

  3. Data-linked pilot reply time on controller workload and communication in a simulated terminal option

    Science.gov (United States)

    2001-05-01

    This report describes an analysis of air traffic control communication and workload in a simulated terminal radar approach : control environment. The objective of this study was to investigate how pilot-to-controller data-link acknowledgment time : m...

  4. Software qualification for digital safety system in KNICS project

    International Nuclear Information System (INIS)

    Kwon, Kee-Choon; Lee, Dong-Young; Choi, Jong-Gyun

    2012-01-01

    In order to achieve technical self-reliance in the area of nuclear instrumentation and control, the Korea Nuclear Instrumentation and Control System (KNICS) project had been running for seven years from 2001. The safety-grade Programmable Logic Controller (PLC) and the digital safety system were developed by KNICS project. All the software of the PLC and digital safety system were developed and verified following the software development life cycle Verification and Validation (V and V) procedure. The main activities of the V and V process are preparation of software planning documentations, verification of the Software Requirement Specification (SRS), Software Design Specification (SDS) and codes, and a testing of the software components, the integrated software, and the integrated system. In addition, a software safety analysis and a software configuration management are included in the activities. For the software safety analysis at the SRS and SDS phases, the software Hazard Operability (HAZOP) was performed and then the software fault tree analysis was applied. The software fault tree analysis was applied to a part of software module with some critical defects identified by the software HAZOP in SDS phase. The software configuration management was performed using the in-house tool developed in the KNICS project. (author)

  5. does road safety projects relate to community capacity building?

    African Journals Online (AJOL)

    USER

    Key words: AARSI road safety projects, capacity building, capacity building interventions, community ... claimed that their CSR based programmes are toward community capacity building-. CCB. The CSR practices by these ... promote sustainable community development-SCD by connecting social capital to community and ...

  6. Assuring health and safety performance on construction projects ...

    African Journals Online (AJOL)

    The key finding was that, generally, client H&S culture impacted on project H&S performance. The influence of clients was ... Keywords: Botswana, construction, culture, health and safety, improvement, influence, performance, South Africa .... The first source was the CIB W099 register of members on the CIB W099 website.

  7. Proceedings of the Nuclear Criticality Technology and Safety Project Workshop

    International Nuclear Information System (INIS)

    Sanchez, R.G.

    1994-01-01

    This report is the proceedings of the annual Nuclear Criticality Technology and Safety Project (NCTSP) Workshop held in Monterey, California, on April 16--28, 1993. The NCTSP was sponsored by the Department of Energy and organized by the Los Alamos Critical Experiments Facility. The report is divided into six sections reflecting the sessions outlined on the workshop agenda

  8. Proceedings of the Nuclear Criticality Technology and Safety Project Workshop

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez, R.G. [comp.

    1994-01-01

    This report is the proceedings of the annual Nuclear Criticality Technology and Safety Project (NCTSP) Workshop held in Monterey, California, on April 16--28, 1993. The NCTSP was sponsored by the Department of Energy and organized by the Los Alamos Critical Experiments Facility. The report is divided into six sections reflecting the sessions outlined on the workshop agenda.

  9. Safety culture and subcontractor network governance in a complex safety critical project

    International Nuclear Information System (INIS)

    Oedewald, Pia; Gotcheva, Nadezhda

    2015-01-01

    In safety critical industries many activities are currently carried out by subcontractor networks. Nevertheless, there are few studies where the core dimensions of resilience would have been studied in safety critical network activities. This paper claims that engineering resilience into a system is largely about steering the development of culture of the system towards better ability to anticipate, monitor, respond and learn. Thus, safety culture literature has relevance in resilience engineering field. This paper analyzes practical and theoretical challenges in applying the concept of safety culture in a complex, dynamic network of subcontractors involved in the construction of a new nuclear power plant in Finland, Olkiluoto 3. The concept of safety culture is in focus since it is widely used in nuclear industry and bridges the scientific and practical interests. This paper approaches subcontractor networks as complex systems. However, the management model of the Olkiluoto 3 project is to a large degree a traditional top-down hierarchy, which creates a mismatch between the management approach and the characteristics of the system to be managed. New insights were drawn from network governance studies. - Highlights: • We studied a relevant topical subject safety culture in nuclear new build project. • We integrated safety science challenges and network governance studies. • We produced practicable insights in managing safety of subcontractor networks

  10. Proceedings of the nuclear criticality technology safety project

    International Nuclear Information System (INIS)

    Sanchez, R.G.

    1997-06-01

    This document contains summaries of the most of the papers presented at the 1994 Nuclear Criticality Technology Safety Project (NCTSP) meeting, which was held May 10 and 11 at Williamsburg, Va. The meeting was broken up into seven sessions, which covered the following topics: (1) Validation and Application of Calculations; (2) Relevant Experiments for Criticality Safety; (3) Experimental Facilities and Capabilities; (4) Rad-Waste and Weapons Disassembly; (5) Criticality Safety Software and Development; (6) Criticality Safety Studies at Universities; and (7) Training. The minutes and list of participants of the Critical Experiment Needs Identification Workgroup meeting, which was held on May 9 at the same venue, has been included as an appendix. A second appendix contains the names and addresses of all NCTSP meeting participants. Separate abstracts have been indexed to the database for contributions to this proceedings

  11. Proceedings of the nuclear criticality technology safety project

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez, R.G. [comp.

    1997-06-01

    This document contains summaries of the most of the papers presented at the 1994 Nuclear Criticality Technology Safety Project (NCTSP) meeting, which was held May 10 and 11 at Williamsburg, Va. The meeting was broken up into seven sessions, which covered the following topics: (1) Validation and Application of Calculations; (2) Relevant Experiments for Criticality Safety; (3) Experimental Facilities and Capabilities; (4) Rad-Waste and Weapons Disassembly; (5) Criticality Safety Software and Development; (6) Criticality Safety Studies at Universities; and (7) Training. The minutes and list of participants of the Critical Experiment Needs Identification Workgroup meeting, which was held on May 9 at the same venue, has been included as an appendix. A second appendix contains the names and addresses of all NCTSP meeting participants. Separate abstracts have been indexed to the database for contributions to this proceedings.

  12. Recognising Kawasaki disease in UK primary care: a descriptive study using the Clinical Practice Research Datalink.

    Science.gov (United States)

    Moore, Abigail; Harnden, Anthony; Mayon-White, Richard

    2014-08-01

    Kawasaki disease is a rare childhood illness that can present non-specifically, making it a diagnostic challenge. The clinical presentation of Kawasaki disease has not been previously described in primary care. To describe how children with an eventual diagnosis of Kawasaki disease initially present to primary care in the UK. The Clinical Practice Research Datalink was used to find cases coded as Kawasaki disease. Hospital Episode Statistics, hospital admissions, and hospital outpatient attendances were used to identify the children with a convincing diagnosis of Kawasaki disease. Questionnaires and a request for copies of relevant hospital summaries, discharge letters, and reports were sent to GPs of the 104 children with a diagnosis of Kawasaki disease between 2007 and 2011. Most children presented with few clinical features typical of Kawasaki disease. Of those with just one feature, a fever or a polymorphous rash were the most common. By the time that most children were admitted to hospital they had a more recognisable syndrome, with three or more clinical features diagnostic of Kawasaki disease. Most GPs did not consider Kawasaki disease among their differential diagnoses, but some GPs did suspect that the child's illness was unusual. The study highlighted the difficulty of early diagnosis, with most children having a non-specific presentation to primary care. GPs are encouraged to implement good safety netting, and to keep Kawasaki disease in mind when children present with fever and rashes. © British Journal of General Practice 2014.

  13. International Criticality Safety Benchmark Evaluation Project (ICSBEP) - ICSBEP 2015 Handbook

    International Nuclear Information System (INIS)

    Bess, John D.

    2015-01-01

    The Criticality Safety Benchmark Evaluation Project (CSBEP) was initiated in October of 1992 by the United States Department of Energy (DOE). The project quickly became an international effort as scientists from other interested countries became involved. The International Criticality Safety Benchmark Evaluation Project (ICSBEP) became an official activity of the Nuclear Energy Agency (NEA) in 1995. This handbook contains criticality safety benchmark specifications that have been derived from experiments performed at various critical facilities around the world. The benchmark specifications are intended for use by criticality safety engineers to validate calculation techniques used to establish minimum subcritical margins for operations with fissile material and to determine criticality alarm requirements and placement. Many of the specifications are also useful for nuclear data testing. Example calculations are presented; however, these calculations do not constitute a validation of the codes or cross-section data. The evaluated criticality safety benchmark data are given in nine volumes. These volumes span approximately 69000 pages and contain 567 evaluations with benchmark specifications for 4874 critical, near-critical or subcritical configurations, 31 criticality alarm placement/shielding configurations with multiple dose points for each, and 207 configurations that have been categorised as fundamental physics measurements that are relevant to criticality safety applications. New to the handbook are benchmark specifications for neutron activation foil and thermoluminescent dosimeter measurements performed at the SILENE critical assembly in Valduc, France as part of a joint venture in 2010 between the US DOE and the French Alternative Energies and Atomic Energy Commission (CEA). A photograph of this experiment is shown on the front cover. Experiments that are found unacceptable for use as criticality safety benchmark experiments are discussed in these

  14. Safety Culture Enhancement Project. Final Report. A Field Study on Approaches to Enhancement of Safety Culture

    International Nuclear Information System (INIS)

    Lowe, Andrew; Hayward, Brent

    2006-08-01

    This report documents a study with the objective of enhancing safety culture in the Swedish nuclear power industry. A primary objective of this study was to ensure that the latest thinking on human factors principles was being recognised and applied by nuclear power operators as a means of ensuring optimal safety performance. The initial phase of the project was conducted as a pilot study, involving the senior management group at one Swedish nuclear power-producing site. The pilot study enabled the project methodology to be validated after which it was repeated at other Swedish nuclear power industry sites, providing a broad-ranging analysis of opportunities across the industry to enhance safety culture. The introduction to this report contains an overview of safety culture, explains the background to the project and sets out the project rationale and objectives. The methodology used for understanding and analysing the important safety culture issues at each nuclear power site is then described. This section begins with a summary of the processes used in the information gathering and data analysis stage. The six components of the Management Workshops conducted at each site are then described. These workshops used a series of presentations, interactive events and group exercises to: (a) provide feedback to site managers on the safety culture and safety leadership issues identified at their site, and (b) stimulate further safety thinking and provide 'take-away' information and leadership strategies that could be applied to promote safety culture improvements. Section 3, project Findings, contains the main observations and output from the project. These include: - a brief overview of aspects of the local industry operating context that impinge on safety culture; - a summary of strengths or positive attributes observed within the safety culture of the Swedish nuclear industry; - a set of identified opportunities for further improvement; - the aggregated results of the

  15. Safety Culture Enhancement Project. Final Report. A Field Study on Approaches to Enhancement of Safety Culture

    Energy Technology Data Exchange (ETDEWEB)

    Lowe, Andrew; Hayward, Brent (Dedale Asia Pacific, Albert Park VIC 3206 (Australia))

    2006-08-15

    This report documents a study with the objective of enhancing safety culture in the Swedish nuclear power industry. A primary objective of this study was to ensure that the latest thinking on human factors principles was being recognised and applied by nuclear power operators as a means of ensuring optimal safety performance. The initial phase of the project was conducted as a pilot study, involving the senior management group at one Swedish nuclear power-producing site. The pilot study enabled the project methodology to be validated after which it was repeated at other Swedish nuclear power industry sites, providing a broad-ranging analysis of opportunities across the industry to enhance safety culture. The introduction to this report contains an overview of safety culture, explains the background to the project and sets out the project rationale and objectives. The methodology used for understanding and analysing the important safety culture issues at each nuclear power site is then described. This section begins with a summary of the processes used in the information gathering and data analysis stage. The six components of the Management Workshops conducted at each site are then described. These workshops used a series of presentations, interactive events and group exercises to: (a) provide feedback to site managers on the safety culture and safety leadership issues identified at their site, and (b) stimulate further safety thinking and provide 'take-away' information and leadership strategies that could be applied to promote safety culture improvements. Section 3, project Findings, contains the main observations and output from the project. These include: - a brief overview of aspects of the local industry operating context that impinge on safety culture; - a summary of strengths or positive attributes observed within the safety culture of the Swedish nuclear industry; - a set of identified opportunities for further improvement; - the aggregated

  16. The International Criticality Safety Benchmark Evaluation Project on the Internet

    International Nuclear Information System (INIS)

    Briggs, J.B.; Brennan, S.A.; Scott, L.

    2000-01-01

    The International Criticality Safety Benchmark Evaluation Project (ICSBEP) was initiated in October 1992 by the US Department of Energy's (DOE's) defense programs and is documented in the Transactions of numerous American Nuclear Society and International Criticality Safety Conferences. The work of the ICSBEP is documented as an Organization for Economic Cooperation and Development (OECD) handbook, International Handbook of Evaluated Criticality Safety Benchmark Experiments. The ICSBEP Internet site was established in 1996 and its address is http://icsbep.inel.gov/icsbep. A copy of the ICSBEP home page is shown in Fig. 1. The ICSBEP Internet site contains the five primary links. Internal sublinks to other relevant sites are also provided within the ICSBEP Internet site. A brief description of each of the five primary ICSBEP Internet site links is given

  17. The International Criticality Safety Benchmark Evaluation Project (ICSBEP)

    International Nuclear Information System (INIS)

    Briggs, J.B.

    2003-01-01

    The International Criticality Safety Benchmark Evaluation Project (ICSBEP) was initiated in 1992 by the United States Department of Energy. The ICSBEP became an official activity of the Organisation for Economic Cooperation and Development (OECD) - Nuclear Energy Agency (NEA) in 1995. Representatives from the United States, United Kingdom, France, Japan, the Russian Federation, Hungary, Republic of Korea, Slovenia, Yugoslavia, Kazakhstan, Israel, Spain, and Brazil are now participating. The purpose of the ICSBEP is to identify, evaluate, verify, and formally document a comprehensive and internationally peer-reviewed set of criticality safety benchmark data. The work of the ICSBEP is published as an OECD handbook entitled 'International Handbook of Evaluated Criticality Safety Benchmark Experiments.' The 2003 Edition of the Handbook contains benchmark model specifications for 3070 critical or subcritical configurations that are intended for validating computer codes that calculate effective neutron multiplication and for testing basic nuclear data. (author)

  18. Safety related physics activities in the DEBENE-FBR-Project

    International Nuclear Information System (INIS)

    Froehlich, R.; Helm, F.; Kesler, G.; Kiefhaber, E.

    1980-12-01

    The physics research and development activities in the DEBENE-Fast-Breeder-Project related to core disruptive accidents are discussed. These activities are placed into the context of an overall plant safety concept for a future commercial size LMFBR plant, which is strongly influenced by construction and licensing of the prototype reactor SNR-300. This paper starts with a presentation of the overall LMFBR (e.g. SNR-300) safety design concept, reviews the present core disruptive accident analysis procedure for SNR-300 and describes the present status of phasics design and analysis for the future commercial-size SNR-1300. Based on this review key issues of physics related safety research for core disruptive accidents are discussed and the necessity of more research and development effort to resolve these issues for commercial-sized plants is indicated. (orig.) [de

  19. Nordic projects in the field of nuclear safety

    International Nuclear Information System (INIS)

    Soerensen, H.C.

    1988-05-01

    This report deseribes the work in 1987 within the Nordic program concerning nuclear safety 1985-1989. The report has the form of a handbook meant for those in Scandinavia who are involved in nuclear safety, and it is based on statements from the constituent subject fields of the program. The first chapter is a short summary of the work and results over the year. In the next chapter an account is given of the ongoing projects within each of the subject fields. An economic survey of the entire program and a list of the reports and articles published in 1987 is included in the publication as well. Chapter 5 is a complete list of adresses comprising participants, project managers, program coordinators and members of the advisory group. (SH) 74 refs

  20. Nordic projects in the field of nuclear safety

    International Nuclear Information System (INIS)

    Soerensen, H.C.

    1989-07-01

    This report describes the work in 1988 within the Nordic program concerning nuclear safety 1985-1989. The report has the form of a handbook meant for those in Scandinavia who are involeved in nuclear safety, and it is based on statements from the constituent subject fields of the program. The first chapter is a short summary of the work and results over the year. In the next chapter an account is given of the ongoing projects within each of the subject fields. An economic survey of the entire program and a list of the reports and articles published in 1988 is included in the publicaltion as well. Chapter 5 is a complete list of adresses comprising participants, project managers, program coordinators and members of the advirosy group. (SH)

  1. How to communicate safety? Some reflections from European project studies

    International Nuclear Information System (INIS)

    Richardson, Philip; Galson, Daniel

    2009-12-01

    Attempts to site geological disposal facilities for radioactive waste - and associated public reactions - indicate that communicating safety and demonstrating safety are very different things. The three different approaches to stakeholder engagement undertaken in the context of the PAMINA, ARGONA and CIP projects have provided valuable insights into how risk communication processes and tools can be improved. The approaches used in these projects all involve the participation of interested stakeholders in identifying concerns and issues, which are then examined in a co-operative fashion between stakeholders and developers acting in partnership. Such approaches offer avenues for dialogue and confidence building where such channels were previously not well developed, Full results from the projects will be available in late 2009 for PAMINA and ARGONA and in early 2010 for CIP. The comments and interim insights outlined here will be developed further and incorporated in the overall project outputs, and help inform developing European policy in this area. It is already clear, however, that the approaches used in these projects offer great promise in helping to develop the trust in the institutions and organisations involved that is essential in gaining support and acceptance for the waste management activities now underway across Europe

  2. Data Resource Profile: Clinical Practice Research Datalink (CPRD)

    Science.gov (United States)

    Herrett, Emily; Gallagher, Arlene M; Bhaskaran, Krishnan; Forbes, Harriet; Mathur, Rohini; van Staa, Tjeerd; Smeeth, Liam

    2015-01-01

    The Clinical Practice Research Datalink (CPRD) is an ongoing primary care database of anonymised medical records from general practitioners, with coverage of over 11.3 million patients from 674 practices in the UK. With 4.4 million active (alive, currently registered) patients meeting quality criteria, approximately 6.9% of the UK population are included and patients are broadly representative of the UK general population in terms of age, sex and ethnicity. General practitioners are the gatekeepers of primary care and specialist referrals in the UK. The CPRD primary care database is therefore a rich source of health data for research, including data on demographics, symptoms, tests, diagnoses, therapies, health-related behaviours and referrals to secondary care. For over half of patients, linkage with datasets from secondary care, disease-specific cohorts and mortality records enhance the range of data available for research. The CPRD is very widely used internationally for epidemiological research and has been used to produce over 1000 research studies, published in peer-reviewed journals across a broad range of health outcomes. However, researchers must be aware of the complexity of routinely collected electronic health records, including ways to manage variable completeness, misclassification and development of disease definitions for research. PMID:26050254

  3. Technical safety appraisal of the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    1989-09-01

    This report presents the results of one in a series of Technical Safety Appraisals (TSAs) being conducted of DOE nuclear operations by the Assistant Secretary for Environment, Safety, and Health Office of Safety Appraisals TSAs are one of the ititiatives announced by the Secretary of Energy on September 18, 1985, to enhance the DOE environment, safety and health program. This report presents the results of a TSA of the West Valley Demonstration Project (WVDP). The appraisal was conducted by a team of exerts assembled by the DOE Office of Safety Appraisal and was conducted during onsite visits of June 26-30 and July 10-21, 1989. West Valley, about 30 miles south of Buffalo, New York is the location of the only commercial nuclear fuel reprocessing facility operated in the United States. Nuclear Fuels Services, Inc. (NFS) operated the plant from 1966 to 1972 and processed about 640 metric tons of spent reactor fuel. The reprocessing operation generated about 560,000 gallons of high-level radioactive waste, which was transferred into underground tanks for storage. In 1972 NFS closed the plant and subsequently decided not to reopen it

  4. Bayesian-network-based safety risk analysis in construction projects

    International Nuclear Information System (INIS)

    Zhang, Limao; Wu, Xianguo; Skibniewski, Miroslaw J.; Zhong, Jingbing; Lu, Yujie

    2014-01-01

    This paper presents a systemic decision support approach for safety risk analysis under uncertainty in tunnel construction. Fuzzy Bayesian Networks (FBN) is used to investigate causal relationships between tunnel-induced damage and its influential variables based upon the risk/hazard mechanism analysis. Aiming to overcome limitations on the current probability estimation, an expert confidence indicator is proposed to ensure the reliability of the surveyed data for fuzzy probability assessment of basic risk factors. A detailed fuzzy-based inference procedure is developed, which has a capacity of implementing deductive reasoning, sensitivity analysis and abductive reasoning. The “3σ criterion” is adopted to calculate the characteristic values of a triangular fuzzy number in the probability fuzzification process, and the α-weighted valuation method is adopted for defuzzification. The construction safety analysis progress is extended to the entire life cycle of risk-prone events, including the pre-accident, during-construction continuous and post-accident control. A typical hazard concerning the tunnel leakage in the construction of Wuhan Yangtze Metro Tunnel in China is presented as a case study, in order to verify the applicability of the proposed approach. The results demonstrate the feasibility of the proposed approach and its application potential. A comparison of advantages and disadvantages between FBN and fuzzy fault tree analysis (FFTA) as risk analysis tools is also conducted. The proposed approach can be used to provide guidelines for safety analysis and management in construction projects, and thus increase the likelihood of a successful project in a complex environment. - Highlights: • A systemic Bayesian network based approach for safety risk analysis is developed. • An expert confidence indicator for probability fuzzification is proposed. • Safety risk analysis progress is extended to entire life cycle of risk-prone events. • A typical

  5. Preprimary Traffic Safety Curriculum Demonstration Project, Evaluation Report, 1979-80.

    Science.gov (United States)

    Claus, Richard N.; Quimper, Barry E.

    The Preprimary Traffic Safety Curriculum (PTSC) Demonstration Project is a three year project to develop, pilot test, and disseminate a traffic safety curriculum for young children. The PTSC Project has two general goals: to develop appropriate safety habits and attitudes in children, and to establish cooperation between home and school so that…

  6. Assessment of Contributions to Patient Safety Knowledge by the Agency for Healthcare Research and Quality-Funded Patient Safety Projects

    Science.gov (United States)

    Sorbero, Melony E S; Ricci, Karen A; Lovejoy, Susan; Haviland, Amelia M; Smith, Linda; Bradley, Lily A; Hiatt, Liisa; Farley, Donna O

    2009-01-01

    Objective To characterize the activities of projects funded in Agency for Healthcare Research and Quality (AHRQ)' patient safety portfolio and assess their aggregate potential to contribute to knowledge development. Data Sources Information abstracted from proposals for projects funded in AHRQ' patient safety portfolio, information on safety practices from the AHRQ Evidence Report on Patient Safety Practices, and products produced by the projects. Study Design This represented one part of the process evaluation conducted as part of a longitudinal evaluation based on the Context–Input–Process–Product model. Principal Findings The 234 projects funded through AHRQ' patient safety portfolio examined a wide variety of patient safety issues and extended their work beyond the hospital setting to less studied parts of the health care system. Many of the projects implemented and tested practices for which the patient safety evidence report identified a need for additional evidence. The funded projects also generated a substantial body of new patient safety knowledge through a growing number of journal articles and other products. Conclusions The projects funded in AHRQ' patient safety portfolio have the potential to make substantial contributions to the knowledge base on patient safety. The full value of this new knowledge remains to be confirmed through the synthesis of results. PMID:21456108

  7. The SISIFO project: Seismic Safety at High Schools

    Science.gov (United States)

    Peruzza, Laura; Barnaba, Carla; Bragato, Pier Luigi; Dusi, Alberto; Grimaz, Stefano; Malisan, Petra; Saraò, Angela; Mucciarelli, Marco

    2014-05-01

    For many years, the Italian scientific community has faced the problem of the reduction of earthquake risk using innovative educational techniques. Recent earthquakes in Italy and around the world have clearly demonstrated that seismic codes alone are not able to guarantee an effective mitigation of risk. After the tragic events of San Giuliano di Puglia (2002), where an earthquake killed 26 school children, special attention was paid in Italy to the seismic safety of schools, but mainly with respect to structural aspects. Little attention has been devoted to the possible and even significant damage to non-structural elements (collapse of ceilings, tipping of cabinets and shelving, obstruction of escape routes, etc..). Students and teachers trained on these aspects may lead to a very effective preventive vigilance. Since 2002, the project EDURISK (www.edurisk.it) proposed educational tools and training programs for schools, at primary and middle levels. More recently, a nationwide campaign aimed to adults (www.iononrischio.it) was launched with the extensive support of civil protection volounteers. There was a gap for high schools, and Project SISIFO was designed to fill this void and in particular for those schools with technical/scientific curricula. SISIFO (https://sites.google.com/site/ogssisifo/) is a multidisciplinary initiative, aimed at the diffusion of scientific culture for achieving seismic safety in schools, replicable and can be structured in training the next several years. The students, helped by their teachers and by experts from scientific institutions, followed a course on specialized training on earthquake safety. The trial began in North-East Italy, with a combination of hands-on activities for the measurement of earthquakes with low-cost instruments and lectures with experts in various disciplines, accompanied by specifically designed teaching materials, both on paper and digital format. We intend to raise teachers and students knowledge of the

  8. Surveillance and Datalink Communication Performance Analysis for Distributed Separation Assurance System Architectures

    Science.gov (United States)

    Chung, William W.; Linse, Dennis J.; Alaverdi, Omeed; Ifarraguerri, Carlos; Seifert, Scott C.; Salvano, Dan; Calender, Dale

    2012-01-01

    This study investigates the effects of two technical enablers: Automatic Dependent Surveillance - Broadcast (ADS-B) and digital datalink communication, of the Federal Aviation Administration s Next Generation Air Transportation System (NextGen) under two separation assurance (SA) system architectures: ground-based SA and airborne SA, on overall separation assurance performance. Datalink performance such as successful reception probability in both surveillance and communication messages, and surveillance accuracy are examined in various operational conditions. Required SA performance is evaluated as a function of subsystem performance, using availability, continuity, and integrity metrics to establish overall required separation assurance performance, under normal and off-nominal conditions.

  9. Practice and innovation on safety management of Haiyang Nuclear Power Project

    International Nuclear Information System (INIS)

    Wei Guohu

    2011-01-01

    From the perspective of owner, this article has introduced the safety management model and practice of Haiyang Nuclear Power Project, one of AP1000 Self-reliance Program supporting projects of China. And the article has summarized characteristics of the safety management of Haiyang Project for reference and communication with nuclear or other projects. (author)

  10. Natural Gas Vehicle Cylinder Safety, Training and Inspection Project

    Energy Technology Data Exchange (ETDEWEB)

    Hank Seiff

    2008-12-31

    Under the auspices of the National Energy Technology Laboratory and the US Department of Energy, the Clean Vehicle Education Foundation conducted a three-year program to increase the understanding of the safe and proper use and maintenance of vehicular compressed natural gas (CNG) fuel systems. High-pressure fuel systems require periodic inspection and maintenance to insure safe and proper operation. The project addressed the needs of CNG fuel containers (cylinders) and associated high-pressure fuel system components related to existing law, codes and standards (C&S), available training and inspection programs, and assured coordination among vehicle users, public safety officials, fueling station operators and training providers. The program included a public and industry awareness campaign, establishment and administration of a cylinder inspector certification training scholarship program, evaluation of current safety training and testing practices, monitoring and investigation of CNG vehicle incidents, evaluation of a cylinder recertification program and the migration of CNG vehicle safety knowledge to the nascent hydrogen vehicle community.

  11. Project plan for resolution of the organic waste tank safety issues at the Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Meacham, J.E.

    1996-10-03

    A multi-year project plan for the Organic Safety Project has been developed with the objective of resolving the organic safety issues associated with the High Level Waste (HLW) in Hanford`s single-shell tanks (SSTS) and double-shell tanks (DSTs). The objective of the Organic Safety Project is to ensure safe interim storage until retrieval for pretreatment and disposal operations begins, and to resolve the organic safety issues by September 2001. Since the initial identification of organics as a tank waste safety issue, progress has been made in understanding the specific aspects of organic waste combustibility, and in developing and implementing activities to resolve the organic safety issues.

  12. System Safety Program Plan for Project W-314, tank farm restoration and safe operations

    International Nuclear Information System (INIS)

    Boos, K.A.

    1996-01-01

    This System Safety Program Plan (SSPP) outlines the safety analysis strategy for project W-314, ''Tank Farm Restoration and Safe Operations.'' Project W-314 will provide capital improvements to Hanford's existing Tank Farm facilities, with particular emphasis on infrastructure systems supporting safe operation of the double-shell activities related to the project's conceptual Design Phase, but is planned to be updated and maintained as a ''living document'' throughout the life of the project to reflect the current safety analysis planning for the Tank Farm Restoration and Safe Operations upgrades. This approved W-314 SSPP provides the basis for preparation/approval of all safety analysis documentation needed to support the project

  13. Vandellos 1 decommissioning project. Safety before, during and after

    International Nuclear Information System (INIS)

    Rodriguez, A.

    2002-01-01

    The Nuclear Power Plant of Vandellos 1, a gas-graphite reactor (GCR), started operation in the 70's after 17 years running the decommissioning process began in 1998, and is expected to finish at the end of 2002 with the level 2 of decommissioning with a practically total scope reached, except the concrete reactor vessel and its internals that will remain for another 25 years in surveillance state (dormancy) until their total dismantling. During the last four years the activities related to decontamination and disassembly of the power plant system as well as the management of all this material have been carried out. One of the last phases of the project that will be performed this year, without doubt, one of the most representative of the operative difficulty of the task is the disassembly of some buildings which are more than 80 meters high and with some structures weighing more than 3.000 t, an operation, which is spectacular in terms of volume and mass involved. However one has to keep in mind that it has been preceded by the of clearance process of all these structures to be disassembled this summer. Hundred of thousands of radiological measures will confirm with guarantee that the destination of the dismantled materials is the correct one, assuring the protection of people and the environment. This is a process which has to integrate the principles of radiological safety and industrial safety. First, it has to be guaranteed that structures and components are below the values authorised by authorities for their free release, and, secondly, that the planned sequence of the process and manoeuvres in the disassembly of these colossal structures assures safety. (author)

  14. A series of student design projects for improving and modernizing safety helmets

    NARCIS (Netherlands)

    Beurden, van K.M.M. (Karin); Boer, de J. (Johannes); Stilma, M. (Margot); Teeuw, W.B. (Wouter)

    2014-01-01

    The Saxion Research Centre for Design and Technology employs many students during research projects. This paper discusses a series of student design projects on safety helmets in the Safety@Work project. At construction sites workers are required to wear personal protective equipment during their

  15. Safety equipment list for the 241-SY-101 RAPID mitigation project

    International Nuclear Information System (INIS)

    Morris, K.L.

    1999-01-01

    This document provides the safety classification for the safety (safety class and safety RAPID Mitigation Project. This document is being issued as the project SEL until the supporting authorization basis documentation, this document will be superseded by the TWRS SEL (LMHC 1999), documentation istlralized. Upon implementation of the authorization basis significant) structures, systems, and components (SSCS) associated with the 241-SY-1O1 which will be updated to include the information contained herein

  16. Safety equipment list for the 241-SY-101 RAPID mitigation project

    Energy Technology Data Exchange (ETDEWEB)

    MORRIS, K.L.

    1999-06-29

    This document provides the safety classification for the safety (safety class and safety RAPID Mitigation Project. This document is being issued as the project SEL until the supporting authorization basis documentation, this document will be superseded by the TWRS SEL (LMHC 1999), documentation istlralized. Upon implementation of the authorization basis significant) structures, systems, and components (SSCS) associated with the 241-SY-1O1 which will be updated to include the information contained herein.

  17. Seismic safety margins research program. Project I SONGS 1 AFWS Project

    International Nuclear Information System (INIS)

    Chuang, T.Y.; Smith, P.D.; Dong, R.G.; Bernreuter, D.L.; Bohn, M.P.; Cummings, G.E.; Wells, J.E.

    1981-01-01

    The seismic qualification requirements of auxiliary feedwater systems (AFWS) of Pressurized Water Reactors (PWR) were developed over a number of years. These are formalized in the publication General Design Criteria (Appendix A to 10CFR50). The full recognition of the system as an engineered safety feature did not occur until publication of the Standard Review Plan (1975). Efforts to determine how to backfit seismic requirements to earlier plants has been undertaken primarily in the Systematic Evaluation Program (SEP) for a limited number of operating reactors. Nuclear Reactor Research (RES) and NRR have requested LLNL to perform a probabilistic study on the AFWS of San Onofre Nuclear Generating Station (SONGS) Unit 1 utilizing the tools developed by the Seismic Safety Margins Research Program (SSMRP). The main objectives of this project are to: identify the weak links of AFWS; compare the failure probabilities of SONGS 1 and Zion 1 AFWS: and compare the seismic responses due to different input spectra and design values

  18. The International Criticality Safety Benchmark Evaluation Project (ICSBEP) and The International Reactor Reactor Physics Experiment Evaluation Project (IRPhEP)

    Energy Technology Data Exchange (ETDEWEB)

    Briggs, J.B.; Bess, J. [Idaho National Laboratory (INL), Idaho Falls, ID (United States); Gulliford, J. [Organization for Economic Cooperation and Development (OECD),Nuclear Energy Agency, Paris, (France)

    2011-07-01

    The International Reactor Physics Experiment Evaluation Project (IRPhEP) and the International Criticality Safety Benchmark Evaluation Project (ICSBEP) are sources of evaluated integral benchmark data that may be used for validation of reactor physics / nuclear criticality safety analytical methods and data, nuclear data testing, and safety analysis licensing activities. The IRPhEP is patterned after its predecessor, the ICSBEP, but focuses on other integral measurements such as buckling, spectral characteristics, reactivity effects, reactivity coefficients, kinetics measurements, reaction-rate and power distributions, nuclide compositions and other miscellaneous types of measurements in addition to the critical configuration. Both projects will be discussed.

  19. Using historical crash data as part of traffic work zone safety planning and project management strategies.

    Science.gov (United States)

    2014-07-01

    This funding enabled the project entitled, USING HISTORICAL CRASH DATA AS PART OF TRAFFIC WORK ZONE SAFETY : PLANNING AND PROJECT MANAGEMENT STRATEGIES to address the following: : Evaluate current organizational strategies with respect to w...

  20. Drinking-driving patterns at night : baseline roadside survey of the Fairfax Alcohol Safety Action Project.

    Science.gov (United States)

    1974-01-01

    As part of the Fairfax Alcohol Safety Action Project (ASAP), staff members of the Virginia Highway Research Council, acting in their role as evaluators of the project, conducted a baseline survey of the nighttime drinking-driving patterns in Fairfax,...

  1. Bayesian-network-based safety risk assessment for steel construction projects.

    Science.gov (United States)

    Leu, Sou-Sen; Chang, Ching-Miao

    2013-05-01

    There are four primary accident types at steel building construction (SC) projects: falls (tumbles), object falls, object collapse, and electrocution. Several systematic safety risk assessment approaches, such as fault tree analysis (FTA) and failure mode and effect criticality analysis (FMECA), have been used to evaluate safety risks at SC projects. However, these traditional methods ineffectively address dependencies among safety factors at various levels that fail to provide early warnings to prevent occupational accidents. To overcome the limitations of traditional approaches, this study addresses the development of a safety risk-assessment model for SC projects by establishing the Bayesian networks (BN) based on fault tree (FT) transformation. The BN-based safety risk-assessment model was validated against the safety inspection records of six SC building projects and nine projects in which site accidents occurred. The ranks of posterior probabilities from the BN model were highly consistent with the accidents that occurred at each project site. The model accurately provides site safety-management abilities by calculating the probabilities of safety risks and further analyzing the causes of accidents based on their relationships in BNs. In practice, based on the analysis of accident risks and significant safety factors, proper preventive safety management strategies can be established to reduce the occurrence of accidents on SC sites. Copyright © 2013 Elsevier Ltd. All rights reserved.

  2. Safety cases for the co-ordinated research project on improvement of safety assessment methodologies for near surface radioactive waste disposal facilities (ISAM)

    International Nuclear Information System (INIS)

    Kozak, M.W.; Torres-Vidal, C.; Kelly, E.; Guskov, A.; Blerk, J. van

    2002-01-01

    A Co-ordinated Research Project (CRP) has recently been completed on the Improvement of Safety Assessment Methodologies for Near-Surface Radioactive Waste Disposal Facilities (ISAM). A major aspect of the project was the use of safety cases for the practical application of safety assessment. An overview of the ISAM safety cases is given in this paper. (author)

  3. 25 CFR 170.144 - What are eligible highway safety projects?

    Science.gov (United States)

    2010-04-01

    ... RESERVATION ROADS PROGRAM Indian Reservation Roads Program Policy and Eligibility Highway Safety Functions...-related deaths, injuries and accidents; (j) Impaired driver initiatives; (k) Child safety seat programs... 25 Indians 1 2010-04-01 2010-04-01 false What are eligible highway safety projects? 170.144...

  4. Integrated Environment and Safety and Health Management System (ISMS) Implementation Project Plan

    Energy Technology Data Exchange (ETDEWEB)

    MITCHELL, R.L.

    2000-01-10

    The Integrated Environment, Safety and Health Management System (ISMS) Implementation Project Plan serves as the project document to guide the Fluor Hanford, Inc (FHI) and Major Subcontractor (MSC) participants through the steps necessary to complete the integration of environment, safety, and health into management and work practices at all levels.

  5. Integrated Environment and Safety and Health Management System (ISMS) Implementation Project Plan

    International Nuclear Information System (INIS)

    MITCHELL, R.L.

    2000-01-01

    The Integrated Environment, Safety and Health Management System (ISMS) Implementation Project Plan serves as the project document to guide the Fluor Hanford, Inc (FHI) and Major Subcontractor (MSC) participants through the steps necessary to complete the integration of environment, safety, and health into management and work practices at all levels

  6. 76 FR 53054 - Safety Zone; TriMet Bridge Project, Willamette River; Portland, OR

    Science.gov (United States)

    2011-08-25

    ... SECURITY Coast Guard 33 CFR Part 165 RIN 1625-AA00 Safety Zone; TriMet Bridge Project, Willamette River... safety zone during the construction of the TriMet Bridge on the Willamette River, in Portland, OR. This... close proximity to cranes and overhead work associated with this construction project. During the...

  7. System safety and the Coast Guard Lighter-Than-Air system project

    OpenAIRE

    Danaher, Patrick Joseph

    1983-01-01

    Approved for public release; distribution is unlimited The Coast Guard is evaluating the potential of Lighter-Than-Air (LTA) vehicles for possible future Coast Guard utilization. Progress of the project is explored. Safety science is an emerging field particularly of value in the historically hazardous realm of aviation. The System Safety Concept as applicable to major project development is examined. One of the fundamental tasks of system safety management is to identify possible haza...

  8. Safety risk assessment using analytic hierarchy process (AHP) during planning and budgeting of construction projects.

    Science.gov (United States)

    Aminbakhsh, Saman; Gunduz, Murat; Sonmez, Rifat

    2013-09-01

    The inherent and unique risks on construction projects quite often present key challenges to contractors. Health and safety risks are among the most significant risks in construction projects since the construction industry is characterized by a relatively high injury and death rate compared to other industries. In construction project management, safety risk assessment is an important step toward identifying potential hazards and evaluating the risks associated with the hazards. Adequate prioritization of safety risks during risk assessment is crucial for planning, budgeting, and management of safety related risks. In this paper, a safety risk assessment framework is presented based on the theory of cost of safety (COS) model and the analytic hierarchy process (AHP). The main contribution of the proposed framework is that it presents a robust method for prioritization of safety risks in construction projects to create a rational budget and to set realistic goals without compromising safety. The framework provides a decision tool for the decision makers to determine the adequate accident/injury prevention investments while considering the funding limits. The proposed safety risk framework is illustrated using a real-life construction project and the advantages and limitations of the framework are discussed. Copyright © 2013 National Safety Council and Elsevier Ltd. All rights reserved.

  9. Project for the completion of a probabilistic safety analysis of an industrial irradiation

    International Nuclear Information System (INIS)

    Ferro, R.; Troncoso, M.

    1995-01-01

    The probabilistic safety analysis is a very valuable instrument in safety studies of facilities with potential risk for the personnel, population and environment. One of the possible field of use of PSA techniques in the safety studies for industrial irradiation where serious accidents have occurred. For this reason a project has been undertaken to carry out the PSA in the Irradiation Plant of Research Institute of the Food Industry, which complements the safety studies of this facility

  10. Relational approach in managing construction project safety: a social capital perspective.

    Science.gov (United States)

    Koh, Tas Yong; Rowlinson, Steve

    2012-09-01

    Existing initiatives in the management of construction project safety are largely based on normative compliance and error prevention, a risk management approach. Although advantageous, these approaches are not wholly successful in further lowering accident rates. A major limitation lies with the approaches' lack of emphasis on the social and team processes inherent in construction project settings. We advance the enquiry by invoking the concept of social capital and project organisational processes, and their impacts on project safety performance. Because social capital is a primordial concept and affects project participants' interactions, its impact on project safety performance is hypothesised to be indirect, i.e. the impact of social capital on safety performance is mediated by organisational processes in adaptation and cooperation. A questionnaire survey was conducted within Hong Kong construction industry to test the hypotheses. 376 usable responses were received and used for analyses. The results reveal that, while the structural dimension is not significant, the mediational thesis is generally supported with the cognitive and relational dimensions affecting project participants' adaptation and cooperation, and the latter two processes affect safety performance. However, the cognitive dimension also directly affects safety performance. The implications of these results for project safety management are discussed. Copyright © 2011 Elsevier Ltd. All rights reserved.

  11. SAFETY IMPROVES DRAMATICALLY IN FLUOR HANFORD SOIL AND GROUNDWATER REMEDIATION PROJECT

    Energy Technology Data Exchange (ETDEWEB)

    GERBER MS

    2007-12-05

    This paper describes dramatic improvements in the safety record of the Soil and Groundwater Remediation Project (SGRP) at the Hanford Site in southeast Washington state over the past four years. During a period of enormous growth in project work and scope, contractor Fluor Hanford reduced injuries, accidents, and other safety-related incidents and enhanced a safety culture that earned the SGRP Star Status in the Department of Energy's (DOE's) Voluntary Protection Program (VPP) in 2007. This paper outlines the complex and multi-faceted work of Fluor Hanford's SGRP and details the steps taken by the project's Field Operations and Safety organizations to improve safety. Holding field safety meetings and walkdowns, broadening safety inspections, organizing employee safety councils, intensively flowing down safety requirements to subcontractors, and adopting other methods to achieve remarkable improvement in safety are discussed. The roles of management, labor and subcontractors are detailed. Finally, SGRP's safety improvements are discussed within the context of overall safety enhancements made by Fluor Hanford in the company's 11 years of managing nuclear waste cleanup at the Hanford Site.

  12. SAFETY IMPROVES DRAMATICALLY IN FLUOR HANFORD SOIL AND GROUNDWATER REMEDIATION PROJECT

    International Nuclear Information System (INIS)

    GERBER MS

    2007-01-01

    This paper describes dramatic improvements in the safety record of the Soil and Groundwater Remediation Project (SGRP) at the Hanford Site in southeast Washington state over the past four years. During a period of enormous growth in project work and scope, contractor Fluor Hanford reduced injuries, accidents, and other safety-related incidents and enhanced a safety culture that earned the SGRP Star Status in the Department of Energy's (DOE's) Voluntary Protection Program (VPP) in 2007. This paper outlines the complex and multi-faceted work of Fluor Hanford's SGRP and details the steps taken by the project's Field Operations and Safety organizations to improve safety. Holding field safety meetings and walkdowns, broadening safety inspections, organizing employee safety councils, intensively flowing down safety requirements to subcontractors, and adopting other methods to achieve remarkable improvement in safety are discussed. The roles of management, labor and subcontractors are detailed. Finally, SGRP's safety improvements are discussed within the context of overall safety enhancements made by Fluor Hanford in the company's 11 years of managing nuclear waste cleanup at the Hanford Site

  13. Safety evaluation report. Fast Flux Test Facility. Project No. 448

    Energy Technology Data Exchange (ETDEWEB)

    1978-08-01

    Information on the safety of the FFTF Reactor is presented under the following chapter headings: site characteristics; design of structures, components, equipment, and systems; reactor; reactor coolant system and connected systems; engineered safety features; electric power; auxiliary systems; radioactive waste management systems; radiation protection; conduct of operations; initial test programs; accident analysis; and quality assurance.

  14. Impact of Construction Health & Safety Regulations on Project ...

    African Journals Online (AJOL)

    The effectiveness of the construction industry can only be enhanced by repositioning the construction health and safety regulations to safeguard the health of the workers and the entire community. This paper seeks to assess the views of consultants and contractors about the impact of construction health and safety ...

  15. Safety evaluation report. Fast Flux Test Facility. Project No. 448

    International Nuclear Information System (INIS)

    1978-01-01

    Information on the safety of the FFTF Reactor is presented under the following chapter headings: site characteristics; design of structures, components, equipment, and systems; reactor; reactor coolant system and connected systems; engineered safety features; electric power; auxiliary systems; radioactive waste management systems; radiation protection; conduct of operations; initial test programs; accident analysis; and quality assurance

  16. Experience of Hungarian model project: 'Strengthening training for operational safety at Paks NPP'

    International Nuclear Information System (INIS)

    Kiss, I.

    1998-01-01

    Training of Operational Safety at Paks NPP is described including all the features of the project including namely: description of Paks NPP, its properties and performances; reasons for establishing Hungarian Model Project, its main goals, mentioning Hungarian and IAEA experts involved in the Project, its organization, operation, budget, current status together with its short term and long term impact

  17. Analysis of Aviation Safety Reporting System Incident Data Associated With the Technical Challenges of the Vehicle Systems Safety Technology Project

    Science.gov (United States)

    Withrow, Colleen A.; Reveley, Mary S.

    2014-01-01

    This analysis was conducted to support the Vehicle Systems Safety Technology (VSST) Project of the Aviation Safety Program (AVsP) milestone VSST4.2.1.01, "Identification of VSST-Related Trends." In particular, this is a review of incident data from the NASA Aviation Safety Reporting System (ASRS). The following three VSST-related technical challenges (TCs) were the focus of the incidents searched in the ASRS database: (1) Vechicle health assurance, (2) Effective crew-system interactions and decisions in all conditions; and (3) Aircraft loss of control prevention, mitigation, and recovery.

  18. Inventory of Federal energy-related environment and safety research for FY 1977. Volume II. Project listings

    Energy Technology Data Exchange (ETDEWEB)

    1978-07-01

    This volume contains Biomedical and Environmental Research, Environmental Control Technology Research, and Operational and Environmental Safety Research project listings. The projects are ordered numerically by log number.

  19. Automated Flight Safety Inference Engine (AFSIE) System Project

    Data.gov (United States)

    National Aeronautics and Space Administration — We propose to develop an innovative Autonomous Flight Safety Inference Engine (AFSIE) system to autonomously and reliably terminate the flight of an errant launch...

  20. Safety Design Strategy for the Advanced Test Reactor Diesel Bus (E-3) and Switchgear Replacement Project

    Energy Technology Data Exchange (ETDEWEB)

    Noel Duckwitz

    2011-06-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3B, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3B and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Advanced Test Reactor Reliability Sustainment Project. While this project does not introduce new hazards to the ATR, it has the potential for significant impacts to safety-related systems, structures, and components that are credited in the ATR safety basis and are being replaced. Thus the project has been determined to meet the definition of a major modification and is being managed accordingly.

  1. Safety Design Strategy for the Advanced Test Reactor Emergency Firewater Injection System Replacement Project

    Energy Technology Data Exchange (ETDEWEB)

    Noel Duckwitz

    2011-06-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3B, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3B and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Advanced Test Reactor Reliability Sustainment Project. While this project does not introduce new hazards to the ATR, it has the potential for significant impacts to safety-related systems, structures, and components that are credited in the ATR safety basis and are being replaced. Thus the project has been determined to meet the definition of a major modification and is being managed accordingly.

  2. Safety Design Strategy for the Advanced Test Reactor Primary Coolant Pump and Motor Replacement Project

    Energy Technology Data Exchange (ETDEWEB)

    Noel Duckwitz

    2011-06-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3B, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3B and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Advanced Test Reactor Reliability Sustainment Project. While this project does not introduce new hazards to the ATR, it has the potential for significant impacts to safety-related systems, structures, and components that are credited in the ATR safety basis and are being replaced. Thus the project has been determined to meet the definition of a major modification and is being managed accordingly.

  3. Safety Design Strategy for the Advanced Test Reactor Diesel Bus (E-3) and Switchgear Replacement Project

    International Nuclear Information System (INIS)

    Duckwitz, Noel

    2011-01-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3B, 'Program and Project Management for the Acquisition of Capital Assets,' safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3B and DOE Order 420.1B, 'Facility Safety,' and the expectations of DOE-STD-1189-2008, 'Integration of Safety into the Design Process,' provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Advanced Test Reactor Reliability Sustainment Project. While this project does not introduce new hazards to the ATR, it has the potential for significant impacts to safety-related systems, structures, and components that are credited in the ATR safety basis and are being replaced. Thus the project has been determined to meet the definition of a major modification and is being managed accordingly.

  4. Safety Design Strategy for the Advanced Test Reactor Emergency Firewater Injection System Replacement Project

    International Nuclear Information System (INIS)

    Duckwitz, Noel

    2011-01-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3B, 'Program and Project Management for the Acquisition of Capital Assets,' safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3B and DOE Order 420.1B, 'Facility Safety,' and the expectations of DOE-STD-1189-2008, 'Integration of Safety into the Design Process,' provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Advanced Test Reactor Reliability Sustainment Project. While this project does not introduce new hazards to the ATR, it has the potential for significant impacts to safety-related systems, structures, and components that are credited in the ATR safety basis and are being replaced. Thus the project has been determined to meet the definition of a major modification and is being managed accordingly.

  5. National Institute for Occupational Safety and Health, 1991 projects

    Energy Technology Data Exchange (ETDEWEB)

    1991-08-01

    The report presents information on projects conducted by NIOSH in 1991 aimed at improving working conditions and worker health. The planning format for 1991 was depicted using a flow chart. Each division of NIOSH was listed along with phone numbers and brief descriptions of the projects conducted by the division. Summaries were included of national prevention strategies for occupational lung diseases, musculoskeletal injuries, occupational cancers, severe occupational traumatic injuries, occupational cardiovascular diseases, disorders of reproduction, neurotoxic disorders, noise induced hearing loss, dermatological conditions, and psychological disorders. The purpose of each NIOSH project was described, and projects were categorized by program areas. These programs areas included the subjects of the national prevention strategies, agriculture related projects, construction related projects, assistance requests, and administration.

  6. The modification of main steam safety valves in Qinshan phase Ⅱ expansion project

    International Nuclear Information System (INIS)

    Chen Haiqiao

    2012-01-01

    The main steam safety valves of NPP steam system are second- class nuclear safety component. It used to limit the pressure of SG secondary side and main steam system via emitting steam into the environment. At present, the main steam safety valves have mechanical valves and assisted power valves. According to the experience of power plants at home and abroad, including Qinshan Phase Ⅱ unit 1/2 experience feedback, Qinshan Phase Ⅱ expansion project made modification on valve type, setting value and valve body. This paper introduce the characteristics of different safety valve types, the modification of main steam safety valves and the modification analysis on safety issues.security and impact on the other systems in Qinshan Phase Ⅱ expansion project. (author)

  7. Application of project management methodology in design management of nuclear safety related structure

    International Nuclear Information System (INIS)

    Chen Mao

    2004-01-01

    This paper focuses on the application of project management methodology in the design management of Nuclear Safety Related Structure (NSRS), considering the design management features of its civil construction. Based on the experiences from the management of several projects, the project management triangle is proposed to be used in the management, to well treat the position of design interface in the project management. Some other management methods are also proposed

  8. Global optimization of maintenance and surveillance testing based on reliability and probabilistic safety assessment. Research project

    International Nuclear Information System (INIS)

    Martorell, S.; Serradell, V.; Munoz, A.; Sanchez, A.

    1997-01-01

    Background, objective, scope, detailed working plan and follow-up and final product of the project ''Global optimization of maintenance and surveillance testing based on reliability and probabilistic safety assessment'' are described

  9. West Virginia peer exchange : streamlining highway safety improvement program project delivery.

    Science.gov (United States)

    2015-01-01

    The West Virginia Division of Highways (WV DOH) hosted a Peer Exchange to share information and experiences : for streamlining Highway Safety Improvement Program (HSIP) project delivery. The event was held September : 22 to 23, 2014 in Charleston, We...

  10. A Program Applying Professional Safety Basics in Construction Projects

    Directory of Open Access Journals (Sweden)

    Entisar Kadhim Rasheed

    2016-04-01

    Full Text Available When industrial and constructional renaissance started in the world, the great interest was going on towards the equipment’s, which was the first mean for production. After industry was settled the interest was going on towards the men ship which manpower on which the production depends. It was approved that it represents the basic part in all of the processes and the protection of those individuals against dangers of these equipment’s, industry and its accidents was the basic things which was studied in many researches until it crystallized in general principles for all industries and other take care in each industry. The professional safety is concerned as restrict which aims to take care of humanitarian and material principles also to raise the production of these principles, in the aspect of safety, health and providing the suitable healthy condition to the worker so he can feel safety, confidence and sociological settle, this will increase the production. So In order to maintain the manpower of business risks and to enable them to fulfill their role better to increase production and improve the quality and maintain the machine and supporting the national economy and keep pace with industrial developments and technological came the idea of research to focus on the importance of studying the subject of occupational safety by conducting a field survey to see the reality of professional safety in the relevant departments and work sites and through a questionnaire on the subject and conduct personal interviews with those concerned in this area and to prepare a program for the application of professional safety for each resource (labor, machines, materials, money in construction sites and departments concerned.

  11. Legacy data sharing to improve drug safety assessment: the eTOX project

    DEFF Research Database (Denmark)

    Sanz, Ferran; Pognan, François; Steger-Hartmann, Thomas

    2017-01-01

    The sharing of legacy preclinical safety data among pharmaceutical companies and its integration with other information sources offers unprecedented opportunities to improve the early assessment of drug safety. Here, we discuss the experience of the eTOX project, which was established through the...

  12. Legacy data sharing to improve drug safety assessment : the eTOX project

    NARCIS (Netherlands)

    Sanz, Ferran; Pognan, François; Steger-Hartmann, Thomas; Díaz, Carlos; Cases, Montserrat; Pastor, Manuel; Marc, Philippe; Wichard, Joerg; Briggs, Katharine; Watson, David K; Kleinöder, Thomas; Yang, Chihae; Amberg, Alexander; Beaumont, Maria; Brookes, Anthony J; Brunak, Søren; Cronin, Mark T D; Ecker, Gerhard F; Escher, Sylvia; Greene, Nigel; Guzmán, Antonio; Hersey, Anne; Jacques, Pascale; Lammens, Lieve; Mestres, Jordi; Muster, Wolfgang; Northeved, Helle; Pinches, Marc; Saiz, Javier; Sajot, Nicolas; Valencia, Alfonso; van der Lei, Johan; Vermeulen, Nico P E; Vock, Esther; Wolber, Gerhard; Zamora, Ismael

    2017-01-01

    The sharing of legacy preclinical safety data among pharmaceutical companies and its integration with other information sources offers unprecedented opportunities to improve the early assessment of drug safety. Here, we discuss the experience of the eTOX project, which was established through the

  13. 77 FR 25080 - Safety Zones; TriMet Bridge Project, Willamette River, Portland, OR

    Science.gov (United States)

    2012-04-27

    ... bridge construction cranes. (b) Regulation. In accordance with the general regulations in 33 CFR Part 165... SECURITY Coast Guard 33 CFR Part 165 RIN 1625-AA00 Safety Zones; TriMet Bridge Project, Willamette River... establishing safety zones encompassing the work trestles and construction cranes involved in the construction...

  14. Implementing an interprofessional patient safety learning initiative: insights from participants, project leads and steering committee members.

    Science.gov (United States)

    Jeffs, Lianne; Abramovich, Ilona Alex; Hayes, Chris; Smith, Orla; Tregunno, Deborah; Chan, Wai-Hin; Reeves, Scott

    2013-11-01

    Effective teamwork and interprofessional collaboration are vital for healthcare quality and safety; however, challenges persist in creating interprofessional teamwork and resilient professional teams. A study was undertaken to delineate perceptions of individuals involved with the implementation of an interprofessional patient safety competency-based intervention and intervention participants. The study employed a qualitative study design that triangulated data from interviews with six steering committee members and five members of the project team who developed and monitored the intervention and six focus groups with clinical team members who participated in the intervention and implemented local patient safety projects within a large teaching hospital in Canada. Our study findings reveal that healthcare professionals and support staff acquired patient safety competencies in an interprofessional context that can result in improved patient and work flow processes. However, key challenges exist including managing projects amidst competing priorities, lacking physician engagement and sustaining projects. Our findings point to leaders to provide opportunities for healthcare teams to engage in interprofessional teamwork and patient safety projects to improve quality of patient care. Further research efforts should examine the sustainability of interprofessional safety projects and how leaders can more fully engage the participation of all professions, specifically physicians.

  15. European community light water reactor safety research projects. Experimental issue

    International Nuclear Information System (INIS)

    1975-01-01

    Research programs on light water reactor safety currently carried out in the European Community are presented. They cover: accident conditions (LOCA, ECCS, core meltdown, external influences, etc...), fault and accident prevention and means of mitigation, normal operation conditions, on and off site implications and equipment under severe accident conditions, and miscellaneous subjects

  16. Nuclear emergency preparedness. Final report of the Nordic Nuclear Safety Research Project BOK-1

    DEFF Research Database (Denmark)

    Lauritzen, B.

    2002-01-01

    Final report of the Nordic Nuclear Safety Research project BOK-1. The BOK-1 project, “Nuclear Emergency Preparedness”, was carried out in 1998-2001 with participants from the Nordic and Baltic Sea regions. The project consists of six sub-projects:Laboratory measurements and quality assurance (BOK-1.......1); Mobile measurements and measurement strategies (BOK-1.2); Field measurements and data assimilation (BOK-1.3); Countermeasures in agriculture and forestry (BOK-1.4); Emergency monitoring in theNordic and Baltic Sea countries (BOK-1.5); and Nuclear exercises (BOK-1.6). For each sub-project, the project...

  17. EDF Contribution to the Mochovce completion and safety upgrading project

    International Nuclear Information System (INIS)

    Norvez, G.

    1997-01-01

    The challenge that SE a.s. took up in April 1996 to start Mochovce units 1 and 2 within a very demanding time frame and in satisfactory conditions is on the way to being wined. EMO managed to put in place an organisation able to ensure the continuity of the design and construction works and to integrate the requirements of modern safety. EDF is proud and happy to contribute to this effort by making available its expertise and experience in building and operating nuclear power plants. The success of Mochovce will not only contribute to the Slovak electricity needs coverage, but will be the first demonstration of a soviet design nuclear power plant brought to international safety standards. (author)

  18. Project of a binary breeder reactor and its inherent safety

    International Nuclear Information System (INIS)

    Nascimento, J.A. do; Dias, A.F.; Ishiguro, Y.

    1983-01-01

    A core layout for the binary breeder reactor (BBR) is developed based on the results of preliminary burnup calculations. The apparent breeding ratio, in the U 233 /Th fueled inner core, is low due to the accumulation of Pa-233 in the first few months of operation. The loss of reactivity during this time is around 3%. The BBR requires more reactivity control than Pu/U-fueled LMFBRs and the core layout developed has 19 control rod assemblies in the inner core. Three aspects related to the inherent safety of the Binary Breeder Reactor have been studied: the radial distribution of the sodium-void reactivity zone-wise Doppler reactivity and the fractions of delayed neutrons. The results show excellent characteristics for the BRB safety. (Author) [pt

  19. Project of a binary breeder reactor and its inherent safety

    International Nuclear Information System (INIS)

    Nascimento, J.A. do; Dias, A.F.; Ishiguro, Y.

    1983-01-01

    A core layout for the binary breeder reactor (BBR) is developed based on the results of preliminary burnup calculations. In the U 233 /TH fueled inner core, the apparent breeding ratio is low due to the accumulation of Pa-233 in the first few months of operation. The loss of reactivity during this time is approximatelly 3%. The BBR requires more reactivity control than Pu/U-fueled LMFBRs and the core layout developed has 19 control rod assemblies in the inner core. Three aspects related to the inherent safety of the BBR have been studied: radial distribution of the sodium-void reactivity, zone-wise Doppler reactivity, and the delayed neutron fractions. Results show excellent safety characteristics of the BBR. (Author) [pt

  20. Research project safety studies on waste management (PSE) concluded

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

    The closing statement illustrates a suggestion for the proceeding in the analysis of off-normal events in facilities for the disposal of nuclear waste and in reprocessing plants. Safety analyses with the specifically developed instruments refer to both overground facilities such as reprocessing plants and waste conditioning facilities and to ultimate storage of radioactive substances in domes aspects of transportation of radioactive materials on rail and road are also discussed. (DG) [de

  1. No 2943. Project of law relative to nuclear transparency and safety

    International Nuclear Information System (INIS)

    2006-03-01

    This project of law comprises 5 titles dealing with: 1 - general dispositions: definition and scope of nuclear safety, security, radiation protection, operators liability, facilities in concern; 2 - the high nuclear safety authority: role and duties; 3 - public information in the domain of nuclear safety and radiation protection: information right of the public, local information commissions, high committee for nuclear safety transparency and information; 4 - basic nuclear facilities and transport of radioactive materials: applicable rules, police controls and measures, penal dispositions (investigations, sanctions); 5 - miscellaneous dispositions: changes made with respect to previous legislative texts. (J.S.)

  2. 77 FR 3784 - Recreational Boating Safety Projects, Programs and Activities Funded Under Provisions of the...

    Science.gov (United States)

    2012-01-25

    ... detailed accounting of the projects, programs, and activities funded under the national recreational... Safety Projects, Programs and Activities Funded Under Provisions of the Transportation Equity Act for the 21st Century; Accounting of ACTION: Notice. SUMMARY: In 1999, the Transportation Equity Act for the...

  3. 75 FR 78725 - Recreational Boating Safety Projects, Programs and Activities Funded Under Provisions of the...

    Science.gov (United States)

    2010-12-16

    ... detailed accounting of the projects, programs, and activities funded under the national recreational... Safety Projects, Programs and Activities Funded Under Provisions of the Transportation Equity Act for the 21st Century; Accounting of ACTION: Notice. SUMMARY: In 1999, the Transportation Equity Act for the...

  4. The National Program for Occupational Safety and Health in Agriculture. 1992 Project Facts.

    Science.gov (United States)

    National Inst. for Occupational Safety and Health (DHHS/PHS), Cincinnati, OH.

    This book contains information about a project instituted in 1990 by the National Institute for Occupational Safety and Health (NIOSH) to prevent work-related diseases and injuries among agricultural workers. Included are facts about 25 projects within NIOSH and 42 cooperative agreements between NIOSH and institutions in 25 states. These…

  5. Study of Evaluation OSH Management System Policy Based On Safety Culture Dimensions in Construction Project

    Science.gov (United States)

    Latief, Yusuf; Armyn Machfudiyanto, Rossy; Arifuddin, Rosmariani; Mahendra Fira Setiawan, R.; Yogiswara, Yoko

    2017-07-01

    Safety Culture in the construction industry is very influential on the socio economic conditions that resulted in the country’s competitiveness. Based on the data, the accident rate of construction projects in Indonesia is very high. In the era of the Asian Economic Community (AEC) Indonesian contractor is required to improve competitiveness, one of which is the implementation of the project without zero accident. Research using primary and secondary data validated the results of the literature experts and questionnaire respondents were analyzed using methods SmartPLS, obtained pattern of relationships between dimensions of safety culture to improve the performance of Safety. The results showed that the behaviors and Cost of Safety into dimensions that significantly affect the performance of safety. an increase in visible policy-based on Regulation of Public Work and Housing No 5/PRT/M/2014 to improve to lower the accident rate.

  6. Safety assessment and regulatory strategy for NPP I and C modernization projects

    International Nuclear Information System (INIS)

    Manners, S.; Blocquel, Ch.

    1999-10-01

    IPSN is the technical support for the French nuclear safety authority (DSIN), but also acts independently. Through our participation at this IAEA meeting we wish to further our appreciation of the industry position for I and C modernization projects. We will present some of the concerns of the safety assessor and safety authority for such projects. We hope to share our experiences and views concerning current strategies for I and C modernization and licensing from. In our experience with NPP I and C programmes, the need for modification is most often not directly linked to safety. For our safety assessment we have to identify clearly and, as far as possible, categorize the safety relevance of the specified modifications and all safety impact in its implementation. Modernization can be simply for reasons of replacement of obsolete existing equipment or it can be linked to functional evolutions; safety functions may be directly or indirectly affected. The state of the art I and C solutions proposed by today's modernization programs have many benefits, but also pose a certain number of difficulties for the safety demonstration. On the implementation side, the safety assessment for a modernization project has to take into consideration specific issues compared with that for new plant. These include interface and compatibility with the existing installation, issues relating to 'on line' installation and commissioning, as well as operational issues concerning the changeover and trail periods. A further subject for discussion concerns how our regulatory requirements apply to modernization. We must as a minima comply with the requirements of the period. To what measure must we apply current or future (under development or for future reactor designs) standards? How can we tie in with requirements and legislation for new projects? Do we make a special case for back-fits? (authors)

  7. Procedures for initiation, cost-sharing and management of OECD projects in nuclear safety

    International Nuclear Information System (INIS)

    2002-01-01

    The OECD (CSNI) projects aim to produce results relevant for the safe operation of nuclear power plants through international collaborative projects. In general, the projects consist of advanced experimental programmes that are conducted at specialized facilities. At present, the following OECD (CSNI) projects are in operation: - The Halden Project, covering fuel/materials and I and C/Human Factors issues; - The Cabri Project, addressing reactivity transients on high burnup fuels; - The MASCA Project, which deals with in-vessel corium phenomena; - The OLHF Project, dealing with lower head failure mechanisms; - The SETH Project addressing thermal-hydraulics issues, started in 2001; - The MCCI Project on ex-vessel coolability and melt-concrete interaction. There are significant differences among these projects in terms of their motivation, size and scope. The Halden Project and the Cabri Water Loop Project are large undertakings where the host organisations assume full and direct responsibility for the project establishment and administration - as well as for the negotiation with relevant parties on the terms of participation. In the other cases, instead, the NEA secretariat has a more direct responsibility, conferred by the CSNI, in establishing the project technical and financial basis, as well as for its implementation and administration. The objective of this procedure is to provide a common basis for the establishment and management of the OECD projects in the area of nuclear safety. It is a follow-up of a recommendation expressed by the CSNI Bureau during its meeting in October 2001, where the procedures for the establishment and management of the OECD (CSNI) projects in nuclear safety were addressed. While this procedure attempts at defining general guidelines for project initiation, financing and management, one should bear in mind that each project has its own motivation, background and framework. Thus, some degree of flexibility in project structure

  8. Incorporation of occupational health and safety in cleaner production projects in South Africa

    DEFF Research Database (Denmark)

    Hedlund, Frank Huess

    2002-01-01

    The purpose of this research is to reveal ways in which occupational health and safety can be integrated in environmental cleaner production projects. Of particular interest are those cleaner production projects that are run by the Danish government's environmental assistance agency, Danced......, in South Africa.The study explores two main avenues of integration. First, integrating through better planning, focussing at the tools and procedures in use by Danced for project management -- integrating occupational health and safety into the project specification, so to speak.Second, integrating...... occupational health and safety into the environmental activities that take place at company level. Two ways of doing so are explored, the main distinction being company size. For large companies, integration of management systems may be attractive. For small companies, integration into a less formal network...

  9. Safety analysis for the 233-S decontamination and decommissioning project

    International Nuclear Information System (INIS)

    Thoren, S.

    1996-08-01

    Decommissioning of the 233-S Plutonium Concentration Facility (REDOX) is a proposed expedited response action that is regulated by the Comprehensive Environmental Response Compensation and Liability Act of 1980 and the Hanford Federal Facility Agreement and Consent Order. Due to progressive physical deterioration of this facility, a decontamination and decommissioning plan is being considered for the immediate future. This safety analysis describes the proposed actions involved in this D ampersand D effort; identifies the radioactive material inventories involved; reviews site specific environmental characteristics and postulates an accident scenario that is evaluated to identify resultant effects

  10. Ferrocyanide Safety Project: Subtask 3.4, Aging Studies

    International Nuclear Information System (INIS)

    Lilga, M.A.; Lumetta, M.R.; Riemath, W.F.; Romine, R.A.; Schiefelbein, G.F.

    1992-11-01

    The Hanford Ferrocyanide Task Team is addressing issues involving ferrocyanide precipitates in single-shell waste storage tanks (SSTs), in particular the storage of waste in a safe manner. This Task Team, composed of researchers from Westinghouse Hanford Company (WHC), Pacific Northwest Laboratory (PNL), and outside consultants, was formed in response to the need for an updated analysis of safety questions about the Hanford ferrocyanide tanks. This annual report gives the results of the work conducted by PNL in FY 1992 on Subtask 3.4, Aging Studies, which is part of Task 3, Chemical Nature of Feffocyanide in Wastes. Subtask 3.4 deals with the aging behavior and solubilization of ferrocyanide tank waste sludges in a basic aqueous environment. Investigated were the effects of pH variation, ionic strength, salts present in SSTS, and gamma radiation on solubilization of vendor-prepared Na 2 NiFe(CN) 6

  11. Ferrocyanide Safety Project: Subtask 3. 4, Aging Studies

    Energy Technology Data Exchange (ETDEWEB)

    Lilga, M.A.; Lumetta, M.R.; Riemath, W.F.; Romine, R.A.; Schiefelbein, G.F.

    1992-11-01

    The Hanford Ferrocyanide Task Team is addressing issues involving ferrocyanide precipitates in single-shell waste storage tanks (SSTs), in particular the storage of waste in a safe manner. This Task Team, composed of researchers from Westinghouse Hanford Company (WHC), Pacific Northwest Laboratory (PNL), and outside consultants, was formed in response to the need for an updated analysis of safety questions about the Hanford ferrocyanide tanks. This annual report gives the results of the work conducted by PNL in FY 1992 on Subtask 3.4, Aging Studies, which is part of Task 3, Chemical Nature of Feffocyanide in Wastes. Subtask 3.4 deals with the aging behavior and solubilization of ferrocyanide tank waste sludges in a basic aqueous environment. Investigated were the effects of pH variation, ionic strength, salts present in SSTS, and gamma radiation on solubilization of vendor-prepared Na[sub 2]NiFe(CN)[sub 6].

  12. Concluding colloquium of the Nuclear Safety Project (PNS)

    International Nuclear Information System (INIS)

    1986-08-01

    The main points of the report are: environmental loads due to nuclear power stations and fuel reprocessing plants, behaviour of the system during reactor faults, extent of damage for the largest hypothetical reactor accidents and its dependence on time, assessment of the consequences of large hypothetical accidents and safety-related assessment of nuclear plants. The contributions relate particularly to the dynamic stresses on reactor components, behaviour of fuel elements in accidents, core melt-down accidents in LWR's and retention, behaviour and effects of released radionuclides from nuclear plants. Up-dating contributions concern the course, the effects and the analysis of the Chernobyl reactor accident. One contribution each is concerned with the development of waste air filters, the soil/plant transfer of actinides and the description of an FDWR. (DG) [de

  13. 75 FR 5511 - Safety Zone; AICW Closure Safety Zone for Ben Sawyer Bridge Replacement Project, Sullivan's...

    Science.gov (United States)

    2010-02-03

    ..., including potential falling debris and the use of heavy equipment and machinery in the waterway, could lead... operation presents a potential hazard to mariners from falling debris and the use of heavy equipment and machinery. To provide for the safety of the public, the Coast Guard will temporarily restrict access to this...

  14. Preliminary safety evaluation for 241-C-106 waste retrieval, project W-320

    Energy Technology Data Exchange (ETDEWEB)

    Conner, J.C.

    1994-10-18

    This document presents the Preliminary Safety Evaluation for Project W-320, Tank 241-C-106 Waste Retrieval Sluicing System (WRSS). The US DOE has been mandated to develop plans for response to safety issues associated with the waste storage tanks at the Hanford Site, and to report the progress of implementing those plans to Congress. The objectives of Project W-230 are to design, fabricate, develop, test, and operate a new retrieval system capable of removing a minimum of about 75% of the high-heat waste contained in C-106. It is anticipated that sluicing operations can remove enough waste to reduce the remaining radiogenic heat load to levels low enough to resolve the high-heat safety issue as well as allow closure of the tank safety issue.

  15. The FORO Project on Safety Culture in Organizations, Facilities and Activities With Sources of Ionizing Radiation

    International Nuclear Information System (INIS)

    Bomben, A. M.; Ferro Fernández, R.; Arciniega Torres, J.; Ordoñez Gutiérrez, E.; Blanes Tabernero, A.; Cruz Suárez, R.; Da Silva Silveira, C.; Perera Meas, J.; Ramírez Quijada, R.; Videla Valdebenito, R.

    2016-01-01

    The aim of this paper is to present the Ibero-American Forum of Nuclear and Radiological Regulatory Authorities’ (FORO) Project on Safety Culture in organizations, facilities and activities with sources of ionizing radiation developed by experts from the Regulatory Authorities of Argentina, Brazil, Chile, Cuba, Spain, Mexico, Peru and Uruguay, under the scientific coordination of the International Atomic Energy Agency (IAEA). Taking into account that Safety Culture problems have been widely recognised as one of the major contributors to many radiological events, several international and regional initiatives are being carried out to foster and develop a strong Safety Culture. One of these initiatives is the two-year project sponsored by the FORO with the purpose to prepare a document to allow its member states understanding, promoting and achieving a higher level of Safety Culture.

  16. Dissemination material template, Deliverable 2.2 of the H2020 project SafetyCube (Safety CaUsation, Benefits and Efficiency).

    NARCIS (Netherlands)

    Tros, M. & Houtenbos, M.

    2016-01-01

    Safety CaUsation, Benefits and Efficiency (SafetyCube) is a European Commission supported Horizon 2020 project with the objective of developing an innovative road safety Decision Support System (DSS) that will enable policy-makers and stakeholders to select and implement the most appropriate

  17. Definition of user needs and “hot topics”, Deliverable 2.1 of the H2020 project SafetyCube (Safety CaUsation, Benefits and Efficiency).

    NARCIS (Netherlands)

    Hagström, L. Thomson, R. Skogsmo, I. Houtenbos, M. Durso, C. Thomas, P. Elvik, R. & Wismans, J.

    2016-01-01

    Safety CaUsation, Benefits and Efficiency (SafetyCube) is a European Commission supported Horizon 2020 project with the objective of developing an innovative road safety Decision Support System (DSS) that will enable policymakers and stakeholders to select and implement the most appropriate

  18. Cloud/Fog Computing System Architecture and Key Technologies for South-North Water Transfer Project Safety

    Directory of Open Access Journals (Sweden)

    Yaoling Fan

    2018-01-01

    Full Text Available In view of the real-time and distributed features of Internet of Things (IoT safety system in water conservancy engineering, this study proposed a new safety system architecture for water conservancy engineering based on cloud/fog computing and put forward a method of data reliability detection for the false alarm caused by false abnormal data from the bottom sensors. Designed for the South-North Water Transfer Project (SNWTP, the architecture integrated project safety, water quality safety, and human safety. Using IoT devices, fog computing layer was constructed between cloud server and safety detection devices in water conservancy projects. Technologies such as real-time sensing, intelligent processing, and information interconnection were developed. Therefore, accurate forecasting, accurate positioning, and efficient management were implemented as required by safety prevention of the SNWTP, and safety protection of water conservancy projects was effectively improved, and intelligential water conservancy engineering was developed.

  19. Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project

    Energy Technology Data Exchange (ETDEWEB)

    Gary Mecham

    2009-10-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

  20. Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project

    Energy Technology Data Exchange (ETDEWEB)

    Boyd D. Chirstensen

    2015-03-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1C, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

  1. Integration of Occupational Safety to Contractors` or Subcontractors` Performance Evaluation in Construction Projects

    Science.gov (United States)

    Kozlovská, Mária; Struková, Zuzana

    2013-06-01

    Several factors should be considered by the owner and general contractor in the process of contractors` and subcontractors` selection and evaluation. The paper reviews the recent models addressed to guide general contractors in subcontractors' selection process and in evaluation of different contractors during the execution of the project. Moreover the paper suggests the impact of different contractors' performance to the overall level of occupational health and safety culture at the sites. It deals with the factors influencing the safety performance of contractors during construction and analyses the methods for assessing the safety performance of construction contractors. The results of contractors' safety performance evaluation could be a useful tool in motivating contractors to achieve better safety outcomes or could have effect on owners` or general contractors' decision making about contractors suitability for future contracting works.

  2. The Development of Low Threshold Laser Arrays and Their Applications in Parallel Optical Datalinks

    Science.gov (United States)

    Zhao, Hanmin

    We present the analytical and experimental study for the development of ultra-low threshold InGaAs/GaAs/AlGaAs quantum well semiconductor lasers and laser arrays grown on non planar substrates by MOCVD. This study has resulted in the demonstration of some of the lowest threshold currents and current densities yet reported as well as the demonstration of multichannel optical datalinks working at 1Gbit/sec/channel. The gain properties of the InGaAs/GaAs strained quantum wells and the lasing properties of InGaAs/GaAs lasers were theoretically analysed. Using MOCVD growth technique, the growth condition for InGaAs/GaAs quantum wells and InGaAs/GaAs broad area lasers were optimized. InGaAs/GaAs broad area laser threshold current density as low as 56 A/cm^{-2} were obtained. The growth and doping properties of InGaAs/GaAs quantum wells and AlGaAs bulk layer on non planar substrates were studied and the unique properties we learned from the above study were used to design and fabricate a new buried heterostructure InGaAs/GaAs laser for low threshold and high efficiency operation. Record low threshold current of 0.5 mA and 0.6 mA were obtained for as cleaved DQW lasers and SQW lasers respectively. HR coated SQW laser threshold currents as low as 0.15 mA were obtained which is the lowest reported threshold current in a diode laser. This new technique produces high yield and high laser uniformity because of the simple growth and processing procedures involved. Highly uniform InGaAs/GaAs SQW and DQW laser arrays with sub-milliampere threshold currents were obtained. Using the above low threshold lasers, a unique three terminal laser structure that is suitable for high speed, high efficiency, large signal, digital modulation was investigated. Three terminal laser arrays were used in a wide bandwidth parallel optical datalink system. High data transfer rate (1GBit/sec/channel) and low bit error rate (BER) ({<}10^{-13}) with large phase margin were obtained. This parallel

  3. Upgrade Uranium Recovery Project No. 34110: final safety analysis report

    International Nuclear Information System (INIS)

    1981-09-01

    The accident analysis of the upgrade uranium recovery system indicated three potential hazards: (1) criticality, (2) toxic fumes from nitric acid solutions, and (3) release of toxic uranyl nitrate solutions. Any of these are capable of causing the death of one or more employees; therefore, they form the basis for the residual risks identified below. The analysis found no hazardous energies or substances capable of causing irreversible injury to, or the death of, any members of the public. The following residual risks will be controlled administratively by procedural constraints: An operator or maintenance error will cause 235 U to be transferred into an unsafe container and cause a criticality. An operator or maintenance error will cause containers of 235 U bearing material to be improperly spaced and cause a criticality. Extensive corrosion will cause a hole to form in a calciner tube, the corrosion will go undetected, and a criticality will result, and a loss of system and/or building solution containment will occur concurrent with a drain being open resulting in a criticality and/or release of toxic material. Additional residual risks that have a small probability are that an earthquake or tornado will affect the building, alter the system geometry, and initiate a criticality; that the compressed-gas (nitrogen) cylinder valve will be sheared off, become airborne, and alter the system geometry; and that loss of system and/or building solution containment may occur concurrently with fire sprinkler system actuation causing a criticality and/or release of toxic material. The following residual risks will be addressed in the Safety Study of the existing X-705 Building: that a spill of raffinate highly contaminated with 99 Tc will occur due to operator error or incorrect lab analysis and that a gaseous or liquid effluent release of small amounts of transuranic elements will occur

  4. Report of the 52. meeting of the Superior Council of the Nuclear Safety and Information (project)

    International Nuclear Information System (INIS)

    2000-01-01

    Since june 2000, the CSSIN (Superior Council on Nuclear Safety and Information) decided to present the meeting of its sessions, on the Internet site of the Nuclear Safety Authority. This document is the meeting project concerning the session of the 27 june 2000. The following subjects have been treated: the Blayais accident and its consequences; the Euratom Directive transposition on the workers and people protection; methodology and organization of the CSSIN concerning the civil nuclear installations and the radiation protection; actualization of the CSSIN heading in the Internet site of the Nuclear Safety Authority. (A.L.B.)

  5. Nordic nuclear safety research 1994-1997. Project on disposal of radioactive waste

    International Nuclear Information System (INIS)

    Broden, Karin

    1999-01-01

    This presentation describes the Nordic Nuclear Safety Research (NKS) programme, which is a scientific co-operation programme in nuclear safety, radiation protection and emergence preparedness. The purpose of the programme is to carry out cost-effective Nordic projects, thus producing research results, exercises, information, manuals, recommendations, and other types of background material. This material is to serve decision-makers and other concerned staff members at authorities, research establishments and enterprises in the nuclear field. Three waste disposal projects under NKS are briefly described: (1) Waste characterisation, (2) Performance analysis of the engineered barrier system of the repositories for low- and intermediate-level waste, (3) Environmental impact assessment

  6. Uranium Mill Tailings Remedial Action Project Safety Advancement Field Effort (SAFE) Program

    Energy Technology Data Exchange (ETDEWEB)

    1994-02-01

    In 1992, the Uranium Mill Tailings Remedial Action (UMTRA) Project experienced several health and safety related incidents at active remediation project sites. As a result, the U.S. Department of Energy (DOE) directed the Technical Assistance Contractor (TAC) to establish a program increasing the DOE`s overall presence at operational remediation sites to identify and minimize risks in operations to the fullest extent possible (Attachments A and B). In response, the TAC, in cooperation with the DOE and the Remedial Action Contractor (RAC), developed the Safety Advancement Field Effort (SAFE) Program.

  7. Uranium Mill Tailings Remedial Action Project Safety Advancement Field Effort (SAFE) Program

    International Nuclear Information System (INIS)

    1994-02-01

    In 1992, the Uranium Mill Tailings Remedial Action (UMTRA) Project experienced several health and safety related incidents at active remediation project sites. As a result, the U.S. Department of Energy (DOE) directed the Technical Assistance Contractor (TAC) to establish a program increasing the DOE's overall presence at operational remediation sites to identify and minimize risks in operations to the fullest extent possible (Attachments A and B). In response, the TAC, in cooperation with the DOE and the Remedial Action Contractor (RAC), developed the Safety Advancement Field Effort (SAFE) Program

  8. INTEGRAL BENCHMARKS AVAILABLE THROUGH THE INTERNATIONAL REACTOR PHYSICS EXPERIMENT EVALUATION PROJECT AND THE INTERNATIONAL CRITICALITY SAFETY BENCHMARK EVALUATION PROJECT

    Energy Technology Data Exchange (ETDEWEB)

    J. Blair Briggs; Lori Scott; Enrico Sartori; Yolanda Rugama

    2008-09-01

    Interest in high-quality integral benchmark data is increasing as efforts to quantify and reduce calculational uncertainties accelerate to meet the demands of next generation reactor and advanced fuel cycle concepts. The International Reactor Physics Experiment Evaluation Project (IRPhEP) and the International Criticality Safety Benchmark Evaluation Project (ICSBEP) continue to expand their efforts and broaden their scope to identify, evaluate, and provide integral benchmark data for method and data validation. Benchmark model specifications provided by these two projects are used heavily by the international reactor physics, nuclear data, and criticality safety communities. Thus far, 14 countries have contributed to the IRPhEP, and 20 have contributed to the ICSBEP. The status of the IRPhEP and ICSBEP is discussed in this paper, and the future of the two projects is outlined and discussed. Selected benchmarks that have been added to the IRPhEP and ICSBEP handbooks since PHYSOR’06 are highlighted, and the future of the two projects is discussed.

  9. INTEGRAL BENCHMARKS AVAILABLE THROUGH THE INTERNATIONAL REACTOR PHYSICS EXPERIMENT EVALUATION PROJECT AND THE INTERNATIONAL CRITICALITY SAFETY BENCHMARK EVALUATION PROJECT

    International Nuclear Information System (INIS)

    J. Blair Briggs; Lori Scott; Enrico Sartori; Yolanda Rugama

    2008-01-01

    Interest in high-quality integral benchmark data is increasing as efforts to quantify and reduce calculational uncertainties accelerate to meet the demands of next generation reactor and advanced fuel cycle concepts. The International Reactor Physics Experiment Evaluation Project (IRPhEP) and the International Criticality Safety Benchmark Evaluation Project (ICSBEP) continue to expand their efforts and broaden their scope to identify, evaluate, and provide integral benchmark data for method and data validation. Benchmark model specifications provided by these two projects are used heavily by the international reactor physics, nuclear data, and criticality safety communities. Thus far, 14 countries have contributed to the IRPhEP, and 20 have contributed to the ICSBEP. The status of the IRPhEP and ICSBEP is discussed in this paper, and the future of the two projects is outlined and discussed. Selected benchmarks that have been added to the IRPhEP and ICSBEP handbooks since PHYSOR-06 are highlighted, and the future of the two projects is discussed

  10. Developing an action-based health and safety training project in southern China.

    Science.gov (United States)

    Szudy, Betty; O'Rourke, Dara; Brown, Garrett D

    2003-01-01

    A project brought together international footwear manufacturers, labor rights groups, local contract factories, and occupational health professionals to strengthen factory health and safety programs in southern China. Steps involved in the two-year project, including needs assessment, interviews and focus groups with workers and supervisors; design and development of a participatory workshop; development of plant-wide health and safety committees in three footwear factories; and evaluation project impact, are discussed. The project significantly increased occupational safety and health knowledge, and hazards in the factories were identified and corrected. Successes and challenges faced by three functioning worker-management health and safety committees are discussed. Key elements to create effective programs with meaningful participation by workers include: 1) developing clear guidelines that enable multi-stakeholder groups to collaborate; 2) obtaining top-level management support; 3) building workers' knowledge and capacity to fully participate; 4) involving local labor rights groups and occupational professionals in support and technical assistance; and 5) connecting project goals to larger issues within a country and the global economy.

  11. Accident consequence calculations for project W-058 safety analysis

    International Nuclear Information System (INIS)

    Van Keuren, J.C.

    1997-01-01

    Accident consequence analyses have been performed for Project W-058, the Replacement Cross Site Transfer System. using the assumption and analysis techniques developed for the Tank Remediation Waste system Basis for Interim Operation. most potential accident involving the FISTS are bounded by the TWRS BIO analysis. However, the spray leak and pool leak scenarios require revised analyses since the RCSTS design utilizes larger diameter pipe and higher pressures than those analyzed in the TWRS BIO. Also the volume of diversion box and vent station are larger than that assumed for the valve pits in the TWRS BIO, which effects results of sprays or spills into the pits. the revised analysis for the spray leak is presented in Section 2, for the above ground spill in Section 3, for the presented in Section 2, for the above ground spill in Section 3, for the subsurface spill forming a pool in Section 4, and for the subsurface pool remaining subsurface in Section 5. The conclusion from these sections are summarized below

  12. JRC/IE support activities to PHARE nuclear safety programmes. Dissemination of PHARE project results

    International Nuclear Information System (INIS)

    Ranguelova, V.; Pla, P.; Rieg, C.; Bieth, M.

    2005-01-01

    Nuclear safety in Europe is one of European Union's primary concerns, therefore the European Union decided to take a prominent role to help the New Independent States and countries of Central and Eastern Europe to ensure the safety of their nuclear reactors. The European Union TACIS and PHARE programmes in nuclear safety have been undertaken since 1990. The European Commission's Directorate General External Relations (EC DG RELEX) and, Directorate General Europe Aid Co-operation Office (EC DG AIDCO), are responsible for programming and management of implementation of TACIS projects. Directorate General Enlargement (EC DG ELARG) is responsible for programming PHARE programmes, but implementation of most projects has been decentralised since 1999 budget year to the Beneficiary countries. DG ELARG acts as backstopping for the relevant EC Delegations. In these activities, the TSSTP Unit at the JRC/IE in Petten, The Netherlands, is a technical and scientific adviser of DG RELEX and DG AIDCO and provides support to DG ELARG for very specific technical issues. Several PHARE projects aiming at improving nuclear safety have been successfully implemented for a number of plants from Central and Eastern Europe. In some cases major safety issues have been addressed by means of multi-country projects and results have been disseminated to the rest of the nuclear community. Although a lot of information has been exchanged at a bilateral level, further effort is needed to collect the project results in a systematic way and make them available by means of the internet. At present the TSSTP Unit is implementing two projects for dissemination of PHARE project results. This activity will take a better advantage of today's communication technologies and ensure the management of the acquired knowledge through preservation and user-friendly access and retrieval of the project results. The paper provides an outline of the TSSTP Unit relevant knowledge preservation initiative, a description

  13. Annual report on reactor safety research projects. Reporting period 2013. Progress report

    International Nuclear Information System (INIS)

    2013-01-01

    Within its competence for energy research the Federal Ministry of Economics and Technology (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS)mbH, by order of the BMWi, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRSF- Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Project Management Agency/Authority Support Division of GRS. The reports as of the year 2000 are available in the Internet-based information system on results and data of reactor safety research (http://www.grs-fbw.de). The compilation of the reports is classified according to the classification system ''Joint Safety Research Index (JSRI)''. The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.)

  14. Overview of the NKS/RAK-1 project 'Strategies for reactor safety' and linkages to piping reliability studies

    International Nuclear Information System (INIS)

    Andersson, Kjell

    1997-01-01

    The NKS/RAK-1 project forms part of a four-year research program (1994-97) in the Nordic countries. The general objective of NKS/RAK-1 project is to explore strategies for reactor safety: to investigate and evaluate the safety work, to increase realism and reliability of safety analysis; and to increase the safety of nuclear installations in selected areas. The project has done extensive interview work at utilities and authorities, and analysed a number of case studies. Brief highlights and overviews of the sub-projects are presented in this paper

  15. Physical and data-link security techniques for future communication systems

    CERN Document Server

    Tomasin, Stefano

    2016-01-01

     This book focuses on techniques that can be applied at the physical and data-link layers of communication systems in order to secure transmissions against eavesdroppers. Topics ranging from information theory-based security to coding for security and cryptography are discussed, with presentation of cutting-edge research and innovative results from leading researchers. The characteristic feature of all the contributions is their relevance for practical embodiments: detailed consideration is given to applications of security principles to a variety of widely used communication techniques such as multiantenna systems, ultra-wide band communication systems, power line communications, and quantum key distribution techniques. A further distinctive aspect is the attention paid to both unconditional and computational security techniques, providing a bridge between two usually distinct worlds. The book comprises extended versions of contributions delivered at the Workshop on Communication Security, held in Ancona, I...

  16. Prevalence, incidence, indication, and choice of antidepressants in patients with and without chronic kidney disease: a matched cohort study in UK Clinical Practice Research Datalink.

    Science.gov (United States)

    Iwagami, Masao; Tomlinson, Laurie A; Mansfield, Kathryn E; McDonald, Helen I; Smeeth, Liam; Nitsch, Dorothea

    2017-07-01

    People with chronic kidney disease (CKD) have an increased prevalence of depression, anxiety, and neuropathic pain. We examined prevalence, incidence, indication for, and choice of antidepressants among patients with and without CKD. Using the UK Clinical Practice Research Datalink, we identified patients with CKD (two measurements of estimated glomerular filtration rate antidepressant prescribing in the six months prior to index date (prevalence), the first prescription after index date among non-prevalent users (incidence), and recorded diagnoses (indication). We compared antidepressant choice between patients with and without CKD among patients with a diagnosis of depression. There were 242 349 matched patients (median age 76 [interquartile range 70-82], male 39.3%) with and without CKD. Prevalence of antidepressant prescribing was 16.3 and 11.9%, and incidence was 57.2 and 42.4/1000 person-years, in patients with and without CKD, respectively. After adjusting for confounders, CKD remained associated with higher prevalence and incidence of antidepressant prescription. Regardless of CKD status, selective serotonin reuptake inhibitors were predominantly prescribed for depression or anxiety, while tricyclic antidepressants were prescribed for neuropathic pain or other reasons. Antidepressant choice was similar in depressed patients with and without CKD. The rate of antidepressant prescribing was nearly one and a half times higher among people with CKD than in the general population. © 2017 The Authors. Pharmacoepidemiology & Drug Safety Published by John Wiley & Sons Ltd. © 2017 The Authors. Pharmacoepidemiology & Drug Safety Published by John Wiley & Sons Ltd.

  17. Nuclear emergency preparedness. Final report of the Nordic nuclear safety research project BOK-1

    Energy Technology Data Exchange (ETDEWEB)

    Lauritzen, Bent [Risoe National Lab., Roskilde (Denmark)

    2002-02-01

    Final report of the Nordic Nuclear Safety Research project BOK-1. The BOK-1 project, 'Nuclear Emergency Preparedness', was carried out in 1998-2001 with participants from the Nordic and Baltic Sea regions. The project consists of six sub-projects: Laboratory measurements and quality assurance (BOK-1.1); Mobile measurements and measurement strategies (BOK-1.2); Field measurement and data assimilation (BOK-1.3); Countermeasures in agriculture and forestry (BOK-1.4); Emergency monitoring in the Nordic and Baltic Sea countries (BOK-1.5); and Nuclear exercises (BOK-1.6). For each sub-project, the project outline, objectives and organization are described and main results presented. (au)

  18. Nuclear emergency preparedness. Final report of the Nordic nuclear safety research project BOK-1

    International Nuclear Information System (INIS)

    Lauritzen, Bent

    2002-02-01

    Final report of the Nordic Nuclear Safety Research project BOK-1. The BOK-1 project, 'Nuclear Emergency Preparedness', was carried out in 1998-2001 with participants from the Nordic and Baltic Sea regions. The project consists of six sub-projects: Laboratory measurements and quality assurance (BOK-1.1); Mobile measurements and measurement strategies (BOK-1.2); Field measurement and data assimilation (BOK-1.3); Countermeasures in agriculture and forestry (BOK-1.4); Emergency monitoring in the Nordic and Baltic Sea countries (BOK-1.5); and Nuclear exercises (BOK-1.6). For each sub-project, the project outline, objectives and organization are described and main results presented. (au)

  19. Substantiation of the safety in the technical project of Belene NPP

    International Nuclear Information System (INIS)

    Boyadzhiev, A.

    1990-01-01

    The chapter contains an evaluation of the safety of Belene NPP project, based on an experts study of the corresponding volume of the Technical Project documentation of the main contractor and also on other related documents. The authors state that most of the remarks are constitutive, part of them requiring additional information or research. The general explicit conclusion is that the materials on the safety substantiation provided in the project are insufficient for making final statements on the safety of the NPP and there is a need for a detailed analysis and expertise. There are 12 topical conclusion paragraphs and each of them comprises a number of remarks. Among the remarks there are some related to the reactivity coefficient values in certain modes of operation, the problem of the mechanical safety and control system efficiency, the unacceptable operation at nominal power in case of stringent safety rules enforcement, the insufficiency of the PSA, the automatic control systems and the software codes not standing up to the contemporary requirements. (R.Ts.)

  20. Spent nuclear fuel project - criteria document spent nuclear fuel final safety analysis report

    International Nuclear Information System (INIS)

    MORGAN, R.G.

    1999-01-01

    The criteria document provides the criteria and planning guidance for developing the Spent Nuclear Fuel (SNF) Final Safety Analysis Report (FSAR). This FSAR will support the US Department of Energy, Richland Operations Office decision to authorize the procurement, installation, installation acceptance testing, startup, and operation of the SNF Project facilities (K Basins, Cold Vacuum Drying Facility, and Canister Storage Building)

  1. 77 FR 59749 - Safety Zone; Submarine Cable Installation Project; Chicago River, Chicago, IL

    Science.gov (United States)

    2012-10-01

    ...-AA00 Safety Zone; Submarine Cable Installation Project; Chicago River, Chicago, IL AGENCY: Coast Guard... the Chicago River due to the installation of submarine cables in the vicinity of both the West Adams... surrounding public and vessels from the hazards associated with the installation of submarine cables in the...

  2. 76 FR 78159 - Safety Zone; Submarine Cable Installation Project; Chicago River South Branch, Chicago, IL

    Science.gov (United States)

    2011-12-16

    ...-AA00 Safety Zone; Submarine Cable Installation Project; Chicago River South Branch, Chicago, IL AGENCY... vessels from a portion of the Chicago River South Branch due to the installation of submarine cables in... surrounding public and vessels from the hazards associated with the installation of submarine cables in the...

  3. 78 FR 18617 - Recreational Boating Safety Projects, Programs and Activities Funded Under Provisions of the...

    Science.gov (United States)

    2013-03-27

    .... Specific Accounting of Funds Factory Visit Program/Boat Testing Program: Funding was provided to continue... Safety Projects, Programs and Activities Funded Under Provisions of the Transportation Equity Act for the 21st Century; Accounting of ACTION: Notice. SUMMARY: In 1999, the Transportation Equity Act for the...

  4. 76 FR 63988 - Pilot Project on NAFTA Trucking Provisions; Pre-Authorization Safety Audits

    Science.gov (United States)

    2011-10-14

    ...-0097] Pilot Project on NAFTA Trucking Provisions; Pre-Authorization Safety Audits AGENCY: Federal Motor... demonstrate the ability of Mexico- domiciled motor carriers to operate safely in the United States beyond the commercial zones on the United States-Mexico border. This action is required by the ``U.S. Troop Readiness...

  5. Safety criteria for the future LMFBR's in France and main safety issues for the rapide 1500 project

    International Nuclear Information System (INIS)

    Justin, F.; Natta, M.; Orzoni, G.

    1985-04-01

    The main safety criteria for future LMFBR in France and the related issues for the RAPIDE 1500 project are presented and discussed. The evolutions with respect to SUPERPHENIX options and requirements are emphasized, in particular for the concerns of the prevention of core melt accidents, fuel damage limits and related required performances of the protection system, since one main option is not to consider whole core melt accidents in the containment design. One shall also point out the advantages of some mitigating features which were nevertheless added in the containment design, although without any explicit consideration for core melt accidents

  6. Occupational Safety and Health Program at the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    L. M. Calderon

    1999-01-01

    The West Valley Nuclear Services Co. LLC (WVNS) is committed to provide a safe, clean, working environment for employees, and to implement U.S. Department of Energy (DOE) requirements affecting worker safety. The West Valley Demonstration Project (WVDP) Occupational Safety and Health Program is designed to protect the safety, health, and well-being of WVDP employees by identifying, evaluating, and controlling biological, chemical, and physical hazards in the work place. Hazards are controlled within the requirements set forth in the reference section at the end of this report. It is the intent of the WVDP Occupational Safety and Health Program to assure that each employee is provided with a safe and healthy work environment. This report shows the logical path toward ensuring employee safety in planning work at the WVDP. In general, planning work to be performed safely includes: combining requirements from specific programs such as occupational safety, industrial hygiene, radiological control, nuclear safety, fire safety, environmental protection, etc.; including WVDP employees in the safety decision-making processes; pre-planning using safety support re-sources; and integrating the safety processes into the work instructions. Safety management principles help to define the path forward for the WVDP Occupational Safety and Health Program. Roles, responsibilities, and authority of personnel stem from these ideals. WVNS and its subcontractors are guided by the following fundamental safety management principles: ''Protection of the environment, workers, and the public is the highest priority. The safety and well-being of our employees, the public, and the environment must never be compromised in the aggressive pursuit of results and accomplishment of work product. A graded approach to environment, safety, and health in design, construction, operation, maintenance, and deactivation is incorporated to ensure the protection of the workers, the public, and the environment

  7. Severe accident assessment. Results of the reactor safety research project VAHTI

    International Nuclear Information System (INIS)

    Sairanen, R.

    1997-10-01

    The report provides a summary of the publicly funded nuclear reactor safety research project Severe Accident Management (VAHTI). The project has been conducted at the Technical Research Centre of Finland (VTT) during the years 1994-96. The main objective was to assist the severe accident management programmes of the Finnish nuclear power plants. The project was divided into five work packages: (1) thermal hydraulic validation of the APROS code, (2) core melt progression within a BWR pressure vessel, (3) failure mode of the BWR pressure vessel, (4) Aerosol behaviour experiments, and (5) development of a computerized severe accident training tool

  8. I and C safety research at the OECD Halden reactor project

    International Nuclear Information System (INIS)

    Gran, B.A.

    2007-01-01

    The overall objective of the Halden Reactor Project research on software systems dependability is to contribute to the successful introduction of digital I and C systems into NPPs. When celebrating the 50 years of the Halden Project in 2008, about 100 written reports have been delivered within this research. This research covers a number of topics covering safety, reliability, validation and verification, quality assurance, risk assessment, requirement engineering, error propagation, qualitative and quantitative assessment. In the paper some activities are described, pinpointing the importance of good joint projects with organisations in the member countries

  9. The International Science and Technology Center (ISTC) and ISTC projects related to nuclear safety. Information review

    International Nuclear Information System (INIS)

    Tocheny, Lev V.

    2003-01-01

    The ISTC is an intergovernmental organization created ten years ago by Russia, USA, EU and Japan in Moscow. The Center supports numerous science and technology projects in different areas, from biotechnologies and environmental problems to all aspects of nuclear studies, including those focused on the development of effective innovative concepts and technologies in the nuclear field, in general, and for improvement of nuclear safety, in particular. The presentation addresses some technical results of the ISTC projects as well as methods and approaches employed by the ISTC to foster close international collaboration and manage projects towards fruitful results. (author)

  10. Main benefits from 30 years of joint projects in nuclear safety

    International Nuclear Information System (INIS)

    Thadani, Ashok; Teschendorff, Victor; Vitanza, Carlo; Hrehor, Miroslav

    2012-01-01

    One of the major achievements of the OECD Nuclear Energy Agency (NEA) is the knowledge it has helped to generate through the organisation of joint international research projects. Such projects, primarily in the areas of nuclear safety and radioactive waste management, enable interested countries, on a cost-sharing basis, to pursue research or the sharing of data with respect to particular areas or issues. Over the years, more than 30 joint projects have been conducted with wide participation of member countries. The purpose of this report is to describe the achievements of the OECD/NEA joint projects on nuclear safety research that have been carried out over the past three decades, with a particular focus on thermal-hydraulics, fuel behaviour and severe accidents. It shows that the resolution of specific safety issues in these areas has greatly benefited from the joint projects' activities and results. It also highlights the added value of international co-operation for maintaining unique experimental infrastructure, preserving skills and generating new knowledge

  11. UMTRA project office federal employee occupational safety and health program plan

    International Nuclear Information System (INIS)

    1994-06-01

    This document establishes the Federal Employee Occupational Safety and Health (FEOSH) Program for the US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project Office. This program will ensure compliance with applicable requirements of DOE Order 3790.1B and DOE Albuquerque Operations Office (AL) Order 3790.lA. FEOSH Program responsibilities delegated by the DOE-AL to the UMTRA Project Office by AL Order 3790.1A also are assigned. The UMTRA Project Office has developed the UMTRA Project Environmental, Safety, and Health (ES ampersand H) Plan (DOE, 1992), which establishes the basic programmatic ES ampersand H requirements for all participants on the UMTRA Project. The ES ampersand H plan is designed primarily to cover remedial action activities at UMTRA sites and defines the ES ampersand H responsibilities of both the UMTRA Project Office and its contractors. The UMTRA FEOSH Program described herein is a subset of the overall UMTRA ES ampersand H program and covers only federal employees working on the UMTRA Project

  12. Steam Pressure-Reducing Station Safety and Energy Efficiency Improvement Project

    Energy Technology Data Exchange (ETDEWEB)

    Lower, Mark D [ORNL; Christopher, Timothy W [ORNL; Oland, C Barry [ORNL

    2011-06-01

    The Facilities and Operations (F&O) Directorate is sponsoring a continuous process improvement (CPI) program. Its purpose is to stimulate, promote, and sustain a culture of improvement throughout all levels of the organization. The CPI program ensures that a scientific and repeatable process exists for improving the delivery of F&O products and services in support of Oak Ridge National Laboratory (ORNL) Management Systems. Strategic objectives of the CPI program include achieving excellence in laboratory operations in the areas of safety, health, and the environment. Identifying and promoting opportunities for achieving the following critical outcomes are important business goals of the CPI program: improved safety performance; process focused on consumer needs; modern and secure campus; flexibility to respond to changing laboratory needs; bench strength for the future; and elimination of legacy issues. The Steam Pressure-Reducing Station (SPRS) Safety and Energy Efficiency Improvement Project, which is under the CPI program, focuses on maintaining and upgrading SPRSs that are part of the ORNL steam distribution network. This steam pipe network transports steam produced at the ORNL steam plant to many buildings in the main campus site. The SPRS Safety and Energy Efficiency Improvement Project promotes excellence in laboratory operations by (1) improving personnel safety, (2) decreasing fuel consumption through improved steam system energy efficiency, and (3) achieving compliance with applicable worker health and safety requirements. The SPRS Safety and Energy Efficiency Improvement Project being performed by F&O is helping ORNL improve both energy efficiency and worker safety by modifying, maintaining, and repairing SPRSs. Since work began in 2006, numerous energy-wasting steam leaks have been eliminated, heat losses from uninsulated steam pipe surfaces have been reduced, and deficient pressure retaining components have been replaced. These improvements helped ORNL

  13. Analysis of Aviation Safety Reporting System Incident Data Associated with the Technical Challenges of the Atmospheric Environment Safety Technology Project

    Science.gov (United States)

    Withrow, Colleen A.; Reveley, Mary S.

    2014-01-01

    This study analyzed aircraft incidents in the NASA Aviation Safety Reporting System (ASRS) that apply to two of the three technical challenges (TCs) in NASA's Aviation Safety Program's Atmospheric Environment Safety Technology Project. The aircraft incidents are related to airframe icing and atmospheric hazards TCs. The study reviewed incidents that listed their primary problem as weather or environment-nonweather between 1994 and 2011 for aircraft defined by Federal Aviation Regulations (FAR) Parts 121, 135, and 91. The study investigated the phases of flight, a variety of anomalies, flight conditions, and incidents by FAR part, along with other categories. The first part of the analysis focused on airframe-icing-related incidents and found 275 incidents out of 3526 weather-related incidents over the 18-yr period. The second portion of the study focused on atmospheric hazards and found 4647 incidents over the same time period. Atmospheric hazards-related incidents included a range of conditions from clear air turbulence and wake vortex, to controlled flight toward terrain, ground encounters, and incursions.

  14. SPATIAL ANALYSIS BASED HEALTH AND SAFETY RISK ASSESSMENT FOR LINEAR CONSTRUCTION PROJECTS

    Directory of Open Access Journals (Sweden)

    H. Atay

    2012-07-01

    Full Text Available This paper describes an on-going study that aims to develop a web-based spatial decision support system model for proactive health and safety management in linear construction projects. Currently, health and safety management is usually performed reactively instead of proactive management since hazard identification and risk assessment is mostly performed on paper based documents that are not effectively used at site. This leads to accidents and fatalities at construction sites. The proposed system automatically identifies the spatial risks according to the topographic and layout map of the site, project specification and health and safety regulations by means of spatial analysis. It enables the workers and management personnel to access the possible hazards and thematic risk map of any portion of the construction site for linear projects. Finally, the described approach provides the proposed mitigation measures for the identified hazards. The developed system is expected to raise awareness in H&S among workers and engineers, and increase participation of workers to health and safety management.

  15. Use of OECD/NEA Data Project Products in Probabilistic Safety Assessment

    International Nuclear Information System (INIS)

    Cherkas, G.; Raducu, Gheorghe; Riznic, J.; Yalaoui, S.; Huang, Hui-Wen; Holy, Jaroslav; Holmberg, Jan-Erik; Sandberg, Jorma; Balmain, Michel; Bonnevialle, Anne-Marie; Curnier, Florence; Georgescu, Gabriel; Lanore, Jeanne-Marie; Lindner, Arndt; Fujimoto, Haruo; Ahn, Kwang-Il; Hwang, Taesuk; Jang, Seung-Cheol; Husarcek, Jan; Kovacs, Zoltan; Vazquez, Teresa; Johanson, Gunnar; Liwaang, Bo; Nyman, Ralph; Dang, Vinh; Schoen, Gerhard; Brook, Kevin; Hamblen, David; Siu, Nathan; Sturzebecher, Karl; Tobin, Margaret; Wood, Jeff; Amri, Abdallah; Breest, Axel

    2014-01-01

    The Nuclear Energy Agency (NEA)/Committee for the Safety of Nuclear Installations' (CSNI) Working Group on Risk Assessment (WGRISK) is tasked with supporting the improved use of Probabilistic Safety Assessment (PSA) in risk informed regulation and safety management through the analysis of results and the development of perspectives regarding potentially important risk contributors and associated risk reduction strategies. The task consists of the following major activities: Development, distribution, and completion of survey questionnaires; Analysis of survey questionnaire results at a task workshop; Preparation of the final task report. The main objectives of this task, as proposed by WGRISK and approved by CSNI, are the following: - Identification and characterization of the current uses of OECD data project products and data in support of PSA. In this context, the term 'products' refers to data analysis results, technical reports, and other project outputs. - Identification and characterization of technical and programmatic characteristics that either support or impede use of data project products in PSA. This includes an assessment of which PSA parameters could be potentially estimated from the various data project products and gaps between available product information and PSA data needs. - Identification of recommendations for enhancing the usefulness of data project products and the coordination between WGRISK and the data projects. This task report consists of the following sections: - Chapter 1 Provides a general overview of motivation and approach used for this task. - Chapter 2 Describes scope and objectives of the task. - Chapter 3 Provides an overview of the ICDE, FIRE, OPDE/CODAP, and COMPSIS data projects. For each project, the project objectives, project history, data collection methodology and quality assurance, project status, example PSA Applications, and information related to project participation is provided. - Chapter 4 Describes the

  16. Project Guarantee 1985. Final repository for high-level radioactive wastes: The system of safety barriers

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

    Final disposal of radioactive waste involves preventing the waste from returning from the repository location into the biosphere by means of successively arranged containment measures known as safety barriers. In the present volume NGB 85-04 of the series of reports for Project 'Guarantee' 1985, the safety barrier system for the type C repository for high-level waste is described. The barrier parameters which are relevant for safety analysis are quantified and associated error limits and data scatter are given. The aim of the report is to give a summary documentation of the safety analysis input data and their scientific background. For secure containment of radioactive waste safety barriers are used which effectively limit the release of radioactive material from the repository (release barriers) and effectively retard the entry of the original radioactive material into the biosphere (time barriers). Safety barriers take the form of both technically constructed containment measures and the siting of the repository in suitable geological formations. The technical safety barrier system in the case of high-level waste comprises: the waste solidification matrix (borosilicate glass), massive steel canisters, encasement of the waste canisters, encasement of the waste canisters in highly compacted bentonite, sealing of vacant storage space and access routes on repository closure. The natural geological safety barriers - the host rock and overlying formations provide sufficiently long deep groundwater flow times from the repository location to the earth's surface and for additional lengthening of radionuclide migration times by means of various chemical and physical retardation mechanisms. The stability of the geological formations is so great that hydrogeological system is protected for a sufficient length of time from deterioration caused, in particular, by erosion. Observations in the final section of the report indicate that input data for the type C repository safety

  17. Safety Assessment Methodologies and Their Application in Development of Near Surface Waste Disposal Facilities--ASAM Project

    International Nuclear Information System (INIS)

    Batandjieva, B.; Metcalf, P.

    2003-01-01

    Safety of near surface disposal facilities is a primary focus and objective of stakeholders involved in radioactive waste management of low and intermediate level waste and safety assessment is an important tool contributing to the evaluation and demonstration of the overall safety of these facilities. It plays significant role in different stages of development of these facilities (site characterization, design, operation, closure) and especially for those facilities for which safety assessment has not been performed or safety has not been demonstrated yet and the future has not been decided. Safety assessments also create the basis for the safety arguments presented to nuclear regulators, public and other interested parties in respect of the safety of existing facilities, the measures to upgrade existing facilities and development of new facilities. The International Atomic Energy Agency (IAEA) has initiated a number of research coordinated projects in the field of development and improvement of approaches to safety assessment and methodologies for safety assessment of near surface disposal facilities, such as NSARS (Near Surface Radioactive Waste Disposal Safety Assessment Reliability Study) and ISAM (Improvement of Safety Assessment Methodologies for Near Surface Disposal Facilities) projects. These projects were very successful and showed that there is a need to promote the consistent application of the safety assessment methodologies and to explore approaches to regulatory review of safety assessments and safety cases in order to make safety related decisions. These objectives have been the basis of the IAEA follow up coordinated research project--ASAM (Application of Safety Assessment Methodologies for Near Surface Disposal Facilities), which will commence in November 2002 and continue for a period of three years

  18. Breckinridge Project, initial effort. Report VII, Volume 4. Safety and health plan

    Energy Technology Data Exchange (ETDEWEB)

    None

    1982-01-01

    The Safety and Health Plan recognizes the potential hazards associated with the Project and has been developed specifically to respond to these risks in a positive manner. Prevention, the primary objective of the Plan, starts with building safety controls into the process design and continues through engineering, construction, start-up, and operation of the Project facilities and equipment. Compliance with applicable federal, state, and local health and safety laws, regulations, and codes throughout all Project phases is required and assured. The Plan requires that each major Project phase be thoroughly reviewed and analyzed to determine that those provisions required to assure the safety and health of all employees and the public, and to prevent property and equipment losses, have been provided. The Plan requires followup on those items or situations where corrective action needs were identified to assure that the action was taken and is effective. Emphasis is placed on loss prevention. Exhibit 1 provides a breakdown of Ashland Synthetic Fuels, Inc.'s (ASFI's) Loss Prevention Program. The Plan recognizes that the varied nature of the work is such as to require the services of skilled, trained, and responsible personnel who are aware of the hazards and know that the work can be done safely, if done correctly. Good operating practice is likewise safe operating practice. Training is provided to familiarize personnel with good operational practice, the general sequence of activities, reporting requirements, and above all, the concept that each step in the operating procedures must be successfully concluded before the following step can be safely initiated. The Plan provides for periodic review and evaluation of all safety and loss prevention activities at the plant and departmental levels.

  19. The IAEA research project on improvement of safety assessment methodologies for near surface disposal facilities

    International Nuclear Information System (INIS)

    Torres-Vidal, C.; Graham, D.; Batandjieva, B.

    2002-01-01

    The International Atomic Energy Agency (IAEA) Research Coordinated Project on Improvement of Safety Assessment Methodologies for Near Surface Disposal Facilities (ISAM) was launched in November 1997 and it has been underway for three years. The ISAM project was developed to provide a critical evaluation of the approaches and tools used in long-term safety assessment of near surface repositories. It resulted in the development of a harmonised approach and illustrated its application by way of three test cases - vault, borehole and Radon (a particular range of repository designs developed within the former Soviet Union) type repositories. As a consequence, the ISAM project had over 70 active participants and attracted considerable interest involving around 700 experts from 72 Member States. The methodology developed, the test cases, the main lessons learnt and the conclusions have been documented and will be published in the form of an IAEA TECDOC. This paper presents the work of the IAEA on improvement of safety assessment methodologies for near surface waste disposal facilities and the application of these methodologies for different purposes in the individual stages of the repository development. The paper introduces the main objectives, activities and outcome of the ISAM project and summarizes the work performed by the six working groups within the ISAM programme, i.e. Scenario Generation and Justification, Modelling, Confidence Building, Vault, Radon Type Facility and Borehole test cases. (author)

  20. Performance assessment and the safety case: Lessons from recent international projects and areas for further development

    International Nuclear Information System (INIS)

    Galson, Daniel A.; Bailey, Lucy

    2014-01-01

    The European Commission (EC) PAMINA project - Performance Assessment Methodologies in Application to Guide the Development of the Safety Case - was conducted over the period 2006-2009 and brought together 27 organisations from 10 countries. PAMINA had the aim of improving and developing a common understanding of performance assessment (PA) methodologies for disposal concepts for spent fuel and other long-lived radioactive wastes in a range of geological environments. This was followed by a Nuclear Energy Agency (NEA) sponsored project on Methods for Safety Assessment of Geological Disposal Facilities for Radioactive Waste (MeSA), which was completed in 2012. This paper presents a selection of conclusions from these projects, in the context of general understanding developed on what would constitute an acceptable safety case for a geological disposal facility, and outlines areas for further development. The paper also introduces a new project on PA that is under consideration within the context of the EC Implementing Geological Disposal of Radioactive Waste Technology Platform (IGD-TP). (authors)

  1. Project SAFE. Update of the SFR-1 safety assessment. Phase 1

    International Nuclear Information System (INIS)

    Andersson, Johan; Riggare, P.; Skagius, K.

    1998-10-01

    SFR-1 is a facility for disposal of low-level radioactive operational waste from the nuclear power plants in Sweden. Low-level radioactive waste from industry, medicine, and research is also disposed in SFR-1. The facility is situated in bedrock beneath the Baltic Sea, 1 km off the coast near the Forsmark nuclear power plant. SFR-1 was built between the years 1983 and 1988. An assessment of the long-term performance of the facility was included in the vast documentation that was a part of the application for an operational license. The assessment was presented in the form of a final safety report. In the operational licence for SFR-1 it is stated that renewed safety assessments should be carried out at least each ten years. In order to meet this demand SKB has launched a special project, SAFE (Safety Assessment of Final Disposal of Operational Radioactive Waste). The aim of the project is to update the safety analysis and to prepare a safety report that will be presented to the Swedish authorities not later than year 2000. Project SAFE is divided into three phases. The first phase is a prestudy, and the results of the prestudy are given in this report. The aim of the prestudy is to identify issues where additional studies would improve the basis for the updated safety analysis as well as to suggest how these studies should be carried out. The work has been divided into six different topics, namely the inventory, the near field, the far field, the biosphere, radionuclide transport calculations and scenarios. For each topic the former safety reports and regulatory reviews are scrutinised and needs for additional work is identified. The evaluations are given in appendices covering the respective topics. The main report is a summary of the appendices with a more stringent description of the repository system and the processes that are of interest and therefore should be addressed in an updated safety assessment. However, it should be pointed out that one of the

  2. Representativeness and optimal use of body mass index (BMI) in the UK Clinical Practice Research Datalink (CPRD)

    OpenAIRE

    Bhaskaran, Krishnan; Forbes, Harriet J; Douglas, Ian; Leon, David A; Smeeth, Liam

    2013-01-01

    Objectives: To assess the completeness and representativeness of body mass index (BMI) data in the Clinical Practice Research Datalink (CPRD), and determine an optimal strategy for their use. Design: Descriptive study. Setting: Electronic healthcare records from primary care. Participants: A million patient random sample from the UK CPRD primary care database, aged ≥16 years. Primary and secondary outcome measures: BMI completeness in CPRD was evaluated by age, sex and calendar period. CPR...

  3. The arrangement of deformation monitoring project and analysis of monitoring data of a hydropower engineering safety monitoring system

    Science.gov (United States)

    Wang, Wanshun; Chen, Zhuo; Li, Xiuwen

    2018-03-01

    The safety monitoring is very important in the operation and management of water resources and hydropower projects. It is the important means to understand the dam running status, to ensure the dam safety, to safeguard people’s life and property security, and to make full use of engineering benefits. This paper introduces the arrangement of engineering safety monitoring system based on the example of a water resource control project. The monitoring results of each monitoring project are analyzed intensively to show the operating status of the monitoring system and to provide useful reference for similar projects.

  4. RADON-type disposal facility safety case for the co-ordinated research project on improvement of safety assessment methodologies for near surface radioactive waste disposal facilities (ISAM)

    International Nuclear Information System (INIS)

    Guskov, A.; Batanjieva, B.; Kozak, M.W.; Torres-Vidal, C.

    2002-01-01

    The ISAM safety assessment methodology was applied to RADON-type facilities. The assessments conducted through the ISAM project were among the first conducted for these kinds of facilities. These assessments are anticipated to lead to significantly improved levels of safety in countries with such facilities. Experience gained though this RADON-type Safety Case was already used in Russia while developing national regulatory documents. (author)

  5. Integrated Framework for Patient Safety and Energy Efficiency in Healthcare Facilities Retrofit Projects.

    Science.gov (United States)

    Mohammadpour, Atefeh; Anumba, Chimay J; Messner, John I

    2016-07-01

    There is a growing focus on enhancing energy efficiency in healthcare facilities, many of which are decades old. Since replacement of all aging healthcare facilities is not economically feasible, the retrofitting of these facilities is an appropriate path, which also provides an opportunity to incorporate energy efficiency measures. In undertaking energy efficiency retrofits, it is vital that the safety of the patients in these facilities is maintained or enhanced. However, the interactions between patient safety and energy efficiency have not been adequately addressed to realize the full benefits of retrofitting healthcare facilities. To address this, an innovative integrated framework, the Patient Safety and Energy Efficiency (PATSiE) framework, was developed to simultaneously enhance patient safety and energy efficiency. The framework includes a step -: by -: step procedure for enhancing both patient safety and energy efficiency. It provides a structured overview of the different stages involved in retrofitting healthcare facilities and improves understanding of the intricacies associated with integrating patient safety improvements with energy efficiency enhancements. Evaluation of the PATSiE framework was conducted through focus groups with the key stakeholders in two case study healthcare facilities. The feedback from these stakeholders was generally positive, as they considered the framework useful and applicable to retrofit projects in the healthcare industry. © The Author(s) 2016.

  6. RISMC Advanced Safety Analysis Project Plan – FY 2015 - FY 2019

    Energy Technology Data Exchange (ETDEWEB)

    Szilard, Ronaldo H. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Smith, Curtis L. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Youngblood, Robert [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-09-01

    In this report, a project plan is developed, focused on industry applications, using Risk-Informed Safety Margin Characterization (RISMC) tools and methods applied to realistic, relevant, and current interest issues to the operating nuclear fleet. RISMC focuses on modernization of nuclear power safety analysis (tools, methods and data); implementing state-of-the-art modeling techniques (which include, for example, enabling incorporation of more detailed physics as they become available); taking advantage of modern computing hardware; and combining probabilistic and mechanistic analyses to enable a risk informed safety analysis process. The modernized tools will maintain the current high level of safety in our nuclear power plant fleet, while providing an improved understanding of safety margins and the critical parameters that affect them. Thus, the set of tools will provide information to inform decisions on plant modifications, refurbishments, and surveillance programs, while improving economics. This set of tools will also benefit the design of new reactors, enhancing safety per unit cost of a nuclear plant. The proposed plan will focus on application of the RISMC toolkit, in particular, solving realistic problems of important current issues to the nuclear industry, in collaboration with plant owners and operators to demonstrate the usefulness of these tools in decision making.

  7. Description of data-sources used in SafetyCube, Deliverable 3.1 of the H2020 project SafetyCube (Safety CaUsation, Benefits and Efficiency).

    NARCIS (Netherlands)

    Hagström, L. Thomson, R. Hermitte, T. Weijermars, W. Bos, N. Talbot, R. Thomas, P. Dupont, E. Martensen, H. Bauer, R. Hours, M. Høye, E. Jänsch, M. Murkovic, A. Niewöhner, W. Papadimitriou, E. Pérez, C. Phan, V. Usami, D. & Vázquez-de-Prada, J.

    2017-01-01

    Safety CaUsation, Benefits and Efficiency (SafetyCube) is a European Commission supported Horizon 2020 project with the objective of developing an innovative road safety Decision Support System (DSS) that will enable policy-makers and stakeholders to select and implement the most appropriate

  8. Road safety in Poland : a contribution to the improvement of road safety in Poland in the framework of the GAMBIT project.

    NARCIS (Netherlands)

    Brouwer, M. Koornstra, M.J. Mulder, J.A.G. & Wegman, F.C.M.

    1995-01-01

    This report describes a SWOV Institute for Road Safety Research study. The study was commissioned: (1) to give a general opinion on the "GAMBIT" project contents; and (2) to express an expectation about the future traffic safety development in Poland. The SWOV contribution has been realized within

  9. Seismic safety margins research program. Project VIII load combination project: work plan

    International Nuclear Information System (INIS)

    Chou, C.K.; Vepa, K.; George, L.; Smith, P.D.

    1979-01-01

    The proposed load combination project has the following overall objectives: develop a methodology for appropriate combination of dynamic loads for nuclear power plants under normal plant operation, transients, accidents, and natural hazards; establish design criteria, load factors, and component service levels for appropriate combinations of dynamic loads or responses to be used in nuclear power plant design; determine the reliability of typical piping systems, both inside and outside the containment structure, and provide the NRC with a sound technical basis for defining the criteria for postulating pipe breaks; and determine the probabilities of a large LOCA induced directly and indirectly by a range of earthquakes

  10. Radiological and environmental consequences. Final report of the Nordic Nuclear Safety Research project BOK-2

    Energy Technology Data Exchange (ETDEWEB)

    Palsson, S.E. [Icelandic Radiation Protection Institute (Iceland)

    2002-11-01

    Final report of the Nordic Nuclear Safety Research project BOK-2, Radiological and Environmental Consequences. The project was carried out 1998-2001 with participants from all the Nordic countries. Representatives from the Baltic States were also invited to some of the meetings and seminars. The project consisted of work on terrestrial and marine radioecology and had a broad scope in order to enable participation of research groups with various fields of interest. This report focuses on the project itself and gives a general summary of the studies undertaken. A separate technical report summarises the work done by each research group and gives references to papers published in scientific journals. The topics in BOK-2 included improving assessment of old and recent fallout, use of radionuclides as tracers in Nordic marine areas, improving assessment of internal doses and use of mass spectrometry in radioecology. (au)

  11. International intercomparison and harmonization projects for demonstrating the safety of radioactive waste management, decommissioning and radioactive waste disposal

    International Nuclear Information System (INIS)

    Metcalf, Phil; O'Donnell, Patricio; Jova Sed, Luis; Batandjieva, Borislava; Rowat, John; Kinker, Monica

    2008-01-01

    Full text: The Joint Convention on the safety of spent fuel management and the safety of radioactive waste management and the international safety standards on radioactive waste management, decommissioning and radioactive waste disposal call for assessment and demonstration of the safety of facilities and activities; during siting, design and construction prior to operation, periodically during operation and at the end of lifetime or upon closure of a waste disposal facility. In addition, more recent revisions of the international safety standards require the development of a safety case for such facilities and activities, documentation presenting all the arguments supporting the safety of the facilities and activities covering site and engineering features, quantitative safety assessment and management systems. Guidance on meeting these safety requirements also indicates the need for a graded approach to safety assessment, with the extent and complexity of the assessment being proportional to the complexity of the activity or facility, and its propensity for radiation hazard. Safety assessment approaches and methodologies have evolved over several decades and international interest in these developments has been considerable as they can be complex and often subjective, which has led to international projects being established aimed at harmonization. The IAEA has sponsored a number of such initiatives, particularly in the area of disposal facility safety, but more recently in the areas of pre disposal waste management and decommissioning, including projects known as ISAM, ASAM, SADRWMS and DeSa. The projects have a number of common aspects including development of standardized methodological approaches, application on test cases and assessment review; they also have activity and facility specific elements. The paper presents an overview of the projects, the outcomes from the projects to date and their future direction aimed very much at practical application of

  12. The water reactor safety research project index: a description of the computerized system for its databank

    International Nuclear Information System (INIS)

    Della Loggia, E.; Primavera, R.

    1993-01-01

    The water reactor nuclear safety research project index has been published by the CEC for many years as a compilation of information on research projects relating to LWR nuclear safety. Since 1981, it has been published, alternatively with NEA (OECD), every second year. The number of contributions from research organizations in Community member countries has steadily increased and reached the level of 1 700 pages, in which more than 600 project descriptions have been collected. In 1988, for the first time, the document was produced using a computerized system developed with the assistance of the ISEI (Institute for Systems Engineering and Informatics) of JRC Ispra. The data have been stored in a computer based in Ispra. The system allows searching a preselected set of subjects through the information stored in the computer: it makes the updating of the projects description much easier and makes the retrieval of the data possible. This report presents a short description of the computerized system developed for the databank of the index. The computerized system presented in this report is structured in a quite general way and for that reason can be adapted very easily to every field where a databank needs to be constituted in order to collect extended information on several projects. (authors). 6 figs., 5 tabs., 5 refs

  13. General-purpose heat source project and space nuclear safety and fuels program. Progress report

    International Nuclear Information System (INIS)

    Maraman, W.J.

    1979-12-01

    This formal monthly report covers the studies related to the use of 238 PuO 2 in radioisotopic power systems carried out for the Advanced Nuclear Systems and Projects Division of the Los Alamos Scientific Laboratory. The two programs involved are general-purpose heat source development and space nuclear safety and fuels. Most of the studies discussed hear are of a continuing nature. Results and conclusions described may change as the work continues

  14. Final hazard classification and auditable safety analysis for the 105-C Reactor Interim Safe Storage Project

    International Nuclear Information System (INIS)

    Rodovsky, T.J.; Larson, A.R.; Dexheimer, D.

    1996-12-01

    This document summarizes the inventories of radioactive and hazardous materials present in the 105-C Reactor Facility and the operations associated with the Interim Safe Storage Project which includes decontamination and demolition and interim safe storage of the remaining facility. This document also establishes a final hazard classification and verifies that appropriate and adequate safety functions and controls are in place to reduce or mitigate the risk associated with those operations

  15. Construction safety monitoring based on the project's characteristic with fuzzy logic approach

    Science.gov (United States)

    Winanda, Lila Ayu Ratna; Adi, Trijoko Wahyu; Anwar, Nadjadji; Wahyuni, Febriana Santi

    2017-11-01

    Construction workers accident is the highest number compared with other industries and falls are the main cause of fatal and serious injuries in high rise projects. Generally, construction workers accidents are caused by unsafe act and unsafe condition that can occur separately or together, thus a safety monitoring system based on influencing factors is needed to achieve zero accident in construction industry. The dynamic characteristic in construction causes high mobility for workers while doing the task, so it requires a continuously monitoring system to detect unsafe condition and to protect workers from potential hazards. In accordance with the unique nature of project, fuzzy logic approach is one of the appropriate methods for workers safety monitoring on site. In this study, the focus of discussion is based on the characteristic of construction projects in analyzing "potential hazard" and the "protection planning" to be used in accident prevention. The data have been collected from literature review, expert opinion and institution of safety and health. This data used to determine hazard identification. Then, an application model is created using Delphi programming. The process in fuzzy is divided into fuzzification, inference and defuzzification, according to the data collection. Then, the input and final output data are given back to the expert for assessment as a validation of application model. The result of the study showed that the potential hazard of construction workers accident could be analysed based on characteristic of project and protection system on site and fuzzy logic approach can be used for construction workers accident analysis. Based on case study and the feedback assessment from expert, it showed that the application model can be used as one of the safety monitoring tools.

  16. Ferrocyanide Safety Project Task 3 Ferrocyanide Aging Studies FY 1993 annual report

    International Nuclear Information System (INIS)

    Lilga, M.A.; Lumetta, M.R.; Schiefelbein, G.F.

    1993-10-01

    The Hanford Ferrocyanide Task Team is addressing issues involving ferrocyanide precipitates in single-shell waste storage tanks (SSTs), in particular the storage of waste in a safe manner. This Task Team, composed of researchers from Westinghouse Hanford Company (WHC), Pacific Northwest Laboratory (PNL), and outside consultants, was formed in response to the need for an updated analysis of safety questions about the Hanford ferrocyanide tanks. The Ferrocyanides Safety Project at PNL is part of the Waste Tank Safety Program led by WHC. The overall purpose of the WHC program, sponsored by the US Department of Energy's Tank Farm Project Office, is to (1) maintain the ferrocyanide tanks with minimal risk of an accident, (2) select one or more strategies to assure safe storage, and (3) close out the unreviewed safety question (USQ). This annual report gives the results of the work conducted by PNL in FY 1993 on Task 3, Ferrocyanides Aging Studies, which deals with the aging behavior of simulated ferrocyanide wastes. Aging processes include the dissolution and hydrolysis of nickel ferrocyanides in high pH aqueous solutions. Investigated were the effects of pH variation; ionic strength and sodium ion concentration; the presence of anions such as phosphate, carbonate, and nitrate; temperature; and gamma radiation on solubility of ferrocyanide materials including In-Farm-lA, Rev. 4 flowsheet-prepared Na 2 NiFe(CN) 6

  17. Aviation Trends Related to Atmospheric Environment Safety Technologies Project Technical Challenges

    Science.gov (United States)

    Reveley, Mary S.; Withrow, Colleen A.; Barr, Lawrence C.; Evans, Joni K.; Leone, Karen M.; Jones, Sharon M.

    2014-01-01

    Current and future aviation safety trends related to the National Aeronautics and Space Administration's Atmospheric Environment Safety Technologies Project's three technical challenges (engine icing characterization and simulation capability; airframe icing simulation and engineering tool capability; and atmospheric hazard sensing and mitigation technology capability) were assessed by examining the National Transportation Safety Board (NTSB) accident database (1989 to 2008), incidents from the Federal Aviation Administration (FAA) accident/incident database (1989 to 2006), and literature from various industry and government sources. The accident and incident data were examined for events involving fixed-wing airplanes operating under Federal Aviation Regulation (FAR) Parts 121, 135, and 91 for atmospheric conditions related to airframe icing, ice-crystal engine icing, turbulence, clear air turbulence, wake vortex, lightning, and low visibility (fog, low ceiling, clouds, precipitation, and low lighting). Five future aviation safety risk areas associated with the three AEST technical challenges were identified after an exhaustive survey of a variety of sources and include: approach and landing accident reduction, icing/ice detection, loss of control in flight, super density operations, and runway safety.

  18. The use of living PSA in safety management, a procedure developed in the nordic project ''safety evaluation, NKS/SIK-1''

    International Nuclear Information System (INIS)

    Johanson, G.; Holmberg, J.

    1994-01-01

    The essential objective with the development of a living PSA concept is to bring the use of the plant specific PSA model out to the daily safety work to allow operational risk experience feedback and to increase the risk awareness of the intended users. This paper will present results of the Nordic project ''Safety Evaluation, NKS/SIK-1''. The SIK-1 project has defined and demonstrated the practical use of living PSA for safety evaluation and for identification of possible improvements in operational safety. Subjects discussed in this paper are dealing with the practical implementation and use of PSA to make proper safety related decisions and evaluation. (author). 24 refs, 1 fig., 1 tab

  19. Final report of the 'Nordic thermal-hydraulic and safety network (NOTNET)' - Project

    International Nuclear Information System (INIS)

    Tuunanen, J.; Tuomainen, M.

    2005-04-01

    A Nordic network for thermal-hydraulics and nuclear safety research was started. The idea of the network is to combine the resources of different research teams in order to carry out more ambitious and extensive research programs than would be possible for the individual teams. From the very beginning, the end users of the research results have been integrated to the network. Aim of the network is to benefit the partners involved in nuclear energy in the Nordic Countries (power companies, reactor vendors, safety regulators, research units). First task within the project was to describe the resources (personnel, know-how, simulation tools, test facilities) of the various teams. Next step was to discuss with the end users about their research needs. Based on these steps, few most important research topics with defined goals were selected, and coarse road maps were prepared for reaching the targets. These road maps will be used as a starting point for planning the actual research projects in the future. The organisation and work plan for the network were established. National coordinators were appointed, as well as contact persons in each participating organisation, whether research unit or end user. This organisation scheme is valid for the short-term operation of NOTNET when only Nordic organisations take part in the work. Later on, it is possible to enlarge the network e.g. within EC framework programme. The network can now start preparing project proposals and searching funding for the first common research projects. (au)

  20. Hydrogen Safety Project chemical analysis support task: Window ``C`` volatile organic analysis

    Energy Technology Data Exchange (ETDEWEB)

    Gillespie, B.M.; Stromatt, R.W.; Ross, G.A.; Hoope, E.A.

    1992-01-01

    This data package contains the results obtained by Pacific Northwest Laboratory (PNL) staff in the characterization of samples for the 101-SY Hydrogen Safety Project. The samples were submitted for analysis by Westinghouse Hanford Company (WHC) under the Technical Project Plan (TPP) 17667 and the Quality Assurance Plan MCS-027. They came from a core taken during Window ``C`` after the May 1991 gas release event. The analytical procedures required for analysis were defined in the Test Instructions (TI) prepared by the PNL 101-SY Analytical Chemistry Laboratory (ACL) Project Management Office in accordance with the TPP and the QA Plan. The requested analysis for these samples was volatile organic analysis. The quality control (QC) requirements for each sample are defined in the Test Instructions for each sample. The QC requirements outlined in the procedures and requested in the WHC statement of work were followed.

  1. Hydrogen Safety Project chemical analysis support task: Window C'' volatile organic analysis

    Energy Technology Data Exchange (ETDEWEB)

    Gillespie, B.M.; Stromatt, R.W.; Ross, G.A.; Hoope, E.A.

    1992-01-01

    This data package contains the results obtained by Pacific Northwest Laboratory (PNL) staff in the characterization of samples for the 101-SY Hydrogen Safety Project. The samples were submitted for analysis by Westinghouse Hanford Company (WHC) under the Technical Project Plan (TPP) 17667 and the Quality Assurance Plan MCS-027. They came from a core taken during Window C'' after the May 1991 gas release event. The analytical procedures required for analysis were defined in the Test Instructions (TI) prepared by the PNL 101-SY Analytical Chemistry Laboratory (ACL) Project Management Office in accordance with the TPP and the QA Plan. The requested analysis for these samples was volatile organic analysis. The quality control (QC) requirements for each sample are defined in the Test Instructions for each sample. The QC requirements outlined in the procedures and requested in the WHC statement of work were followed.

  2. Safety

    International Nuclear Information System (INIS)

    1998-01-01

    A brief account of activities carried out by the Nuclear power plants Jaslovske Bohunice in 1997 is presented. These activities are reported under the headings: (1) Nuclear safety; (2) Industrial and health safety; (3) Radiation safety; and Fire protection

  3. GROWTH OF THE INTERNATIONAL CRITICALITY SAFETY AND REACTOR PHYSICS EXPERIMENT EVALUATION PROJECTS

    Energy Technology Data Exchange (ETDEWEB)

    J. Blair Briggs; John D. Bess; Jim Gulliford

    2011-09-01

    Since the International Conference on Nuclear Criticality Safety (ICNC) 2007, the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and the International Reactor Physics Experiment Evaluation Project (IRPhEP) have continued to expand their efforts and broaden their scope. Eighteen countries participated on the ICSBEP in 2007. Now, there are 20, with recent contributions from Sweden and Argentina. The IRPhEP has also expanded from eight contributing countries in 2007 to 16 in 2011. Since ICNC 2007, the contents of the 'International Handbook of Evaluated Criticality Safety Benchmark Experiments1' have increased from 442 evaluations (38000 pages), containing benchmark specifications for 3955 critical or subcritical configurations to 516 evaluations (nearly 55000 pages), containing benchmark specifications for 4405 critical or subcritical configurations in the 2010 Edition of the ICSBEP Handbook. The contents of the Handbook have also increased from 21 to 24 criticality-alarm-placement/shielding configurations with multiple dose points for each, and from 20 to 200 configurations categorized as fundamental physics measurements relevant to criticality safety applications. Approximately 25 new evaluations and 150 additional configurations are expected to be added to the 2011 edition of the Handbook. Since ICNC 2007, the contents of the 'International Handbook of Evaluated Reactor Physics Benchmark Experiments2' have increased from 16 different experimental series that were performed at 12 different reactor facilities to 53 experimental series that were performed at 30 different reactor facilities in the 2011 edition of the Handbook. Considerable effort has also been made to improve the functionality of the searchable database, DICE (Database for the International Criticality Benchmark Evaluation Project) and verify the accuracy of the data contained therein. DICE will be discussed in separate papers at ICNC 2011. The status of the

  4. Project Guarantee 1985. Final repository for low- and intermediate level radioactive wastes: Safety report

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

    Storage of radioactive waste must delay the return of radionuclides to the biosphere for a long period of time and must maintain the release rates at a sufficiently low level for all time. This is achieved with the aid of a series of safety barriers which consist, on the one hand, of technical barriers in the repository and, on the other hand , of natural geological barriers as they occur at the repository location. In order to assess the efficiency of the barriers, the working methods of the technical barriers and the host rock must be understood. This understanding is transferred into quantitative models in order to calculate the safety of the repository. The individual barriers and the methods used to modelling their functions were described in volume NGB 85-07 of the Project Guarantee 1985 report series and the data necessary for modelling were given. The models and data are used in the safety analysis, the results of which are contained in the present report. Safety considerations show that models are available in Switzerland which allow, in principle, an assessment of the long-term behaviour of a repository for low- and intermediate-level waste. The evaluation of earlier studies and experimental work, suitable laboratory measurements and results from field research enable compilation of a representative data-set so that the requirements for quantitative statements on safety of final disposal are met from this side also. The safety calculations show that the radiation doses calculated for a base case scenario with realistic/conservative parameter values are negligibly low. Also, radiation doses which are clearly under the protection standard of 10 mrem per year result for conservative values and the cumulation of several conservative assumptions. Even assuming exposure of the repository by erosion, a radiotoxicity of the soil formed results which is under natural values

  5. On integration and innovation of sino-foreign safety culture in Haiyang AP1000 Project

    International Nuclear Information System (INIS)

    Li Ruipu; Song Fengwei

    2010-01-01

    The undergoing Haiyang Nuclear Power Plant is not only introducing the top-advanced AP1000 nuclear technology, but also the mature HSE management system from U.S.A. It's very important for both sides to communicate, comprehend and acculturation of both different culture. After over 1 year discussion and practice, the experts of Westinghouse Consortium and Chinese HSE engineers have established an distinctive safety culture of AP1000 Project initially, demonstrating the followings: Exemplary actions of the expat experts and the SNPTC leaders, the high level standard HSE procedures, HSE audit, various training, HSE inspection all-around, the safety performance assessment for prospective index, JHA/JSA , emergency system, humanism rewards and punishment etc.. Haiyang SPMO has made Three-Step master plan for AP1000 project HSE Routine by analysis the site problems and the difference between Chinese and American, that is, from 2008 to 2020, when nuclear power achieve to independent, safety culture of Haiyang AP1000 will change from 'dependent' to 'independent', until the last 'interdependent'. (authors)

  6. YUCCA MOUNTAIN SITE CHARACTERIZATIONS PROJECT TUNNEL BORING MACHINE (TBM) SYSTEM SAFETY ANALYSIS

    Energy Technology Data Exchange (ETDEWEB)

    N/A

    1997-02-19

    The purpose of this analysis is to systematically identify and evaluate hazards related to the tunnel boring machine (TBM) used in the Exploratory Studies Facility (ESF) at the Yucca Mountain Site Characterization Project. This process is an integral part of the systems engineering process; whereby safety is considered during planning, design, testing, and construction. Since the TBM is an ''as built'' system, the M&O is conducting the System Safety Analysis during the construction or assembly phase of the TBM. A largely qualitative approach was used since a radiological System Safety Analysis is not required. The risk assessment in this analysis characterizes the accident scenarios associated with the TBM in terms of relative risk and includes recommendations for mitigating all identified risks. The priority for recommending and implementing mitigation control features is: (1) Incorporate measures to reduce risks and hazards into the system/subsystem/component design, (2) add safety features and capabilities to existing designs, and (3) develop procedures and conduct training to increase worker awareness of potential hazards, on methods to reduce exposure to hazards, and on the actions required to avoid accidents or correct hazardous conditions. The scope of this analysis is limited to the TBM during normal operations, excluding hazards occurring during assembly and test of the TBM or maintenance of the TBM equipment.

  7. Nuclear knowledge management experience of the International Criticality Safety Benchmark Evaluation Project

    International Nuclear Information System (INIS)

    Briggs, J.B.; Nouri, A.; Dean, V.A.F.

    2004-01-01

    The International Criticality Safety Benchmark Evaluation Project (ICSBEP) was initiated in 1992 by the United States Department of Energy. The ICSBEP became an official activity of the Organization for Economic Cooperation and Development (OECD) -- Nuclear Energy Agency (NEA) in 1995. Representatives from the United States, United Kingdom, France, Japan, the Russian Federation, Hungary, Republic of Korea, Slovenia, Serbia and Montenegro (formerly Yugoslavia), Kazakhstan, Spain, Israel, Brazil, Poland, and the Czech Republic are now participating. South Africa, India, China, and Germany are considering participation. The purpose of the ICSBEP is to identify, evaluate, verify, and formally document a comprehensive and internationally peer-reviewed set of criticality safety benchmark data. The work of the ICSBEP is published as an OECD handbook entitled 'International Handbook of Evaluated Criticality Safety Benchmark Experiments'. The 2004 Edition of the Handbook contains benchmark specifications for 3331 critical or subcritical configurations that are intended for use in validation efforts and for testing basic nuclear data. The Handbook is being used extensively for validation of criticality safety methodologies and nuclear data testing and is expected to be a valuable resource for code and data validation and improvement efforts for decades to come. (author)

  8. YUCCA MOUNTAIN SITE CHARACTERIZATIONS PROJECT TUNNEL BORING MACHINE (TBM) SYSTEM SAFETY ANALYSIS

    International Nuclear Information System (INIS)

    1997-01-01

    The purpose of this analysis is to systematically identify and evaluate hazards related to the tunnel boring machine (TBM) used in the Exploratory Studies Facility (ESF) at the Yucca Mountain Site Characterization Project. This process is an integral part of the systems engineering process; whereby safety is considered during planning, design, testing, and construction. Since the TBM is an ''as built'' system, the MandO is conducting the System Safety Analysis during the construction or assembly phase of the TBM. A largely qualitative approach was used since a radiological System Safety Analysis is not required. The risk assessment in this analysis characterizes the accident scenarios associated with the TBM in terms of relative risk and includes recommendations for mitigating all identified risks. The priority for recommending and implementing mitigation control features is: (1) Incorporate measures to reduce risks and hazards into the system/subsystem/component design, (2) add safety features and capabilities to existing designs, and (3) develop procedures and conduct training to increase worker awareness of potential hazards, on methods to reduce exposure to hazards, and on the actions required to avoid accidents or correct hazardous conditions. The scope of this analysis is limited to the TBM during normal operations, excluding hazards occurring during assembly and test of the TBM or maintenance of the TBM equipment

  9. Cooperative project on methods and techniques for assessment of ageing and safety of nuclear objects

    International Nuclear Information System (INIS)

    Bundara, B.; Udovc, M.; Cvelbar, R.; Vojvodic Tuma, J.; Celin, R.; Cizelj, L.; Simonovski, I.; Pirs, B.; Zabric, I.

    2007-01-01

    Nuclear Power Plants are so far the most demanding electric power plants concerning the extent and complexity of knowledge that is needed for design, construction, installation, safe operation and proper maintenance. For safe operation of the NPP it is important to have reliable inspection procedures and methods to detect the relevant defects in the components. It is also important to have effective techniques and efficient methodology that enable precise estimation of the material degradation and reliable prediction of the remaining period of the safe service of structures and components. During the operation of NPP its materials, structures and components are exposed to various impacts that have for the result changes in the material. Changes usually manifest as deviation from the origin (generally considered as defects) and can be observed at level of microstructure and/or at structural level. Defects are consequence of ageing and ageing is a consequence of mechanical, thermal, chemical, radiation induced and other processes. Complexity of the NPP and continuous operation at high level of safety demands extensive cooperation of researchers and engineers with different scientific and educational background. In the paper is discussed the importance of sufficient support to the NPP related research projects and the need for cooperation between institutes. As an example is presented the cooperative project that bands the research groups with different scientific background into complementary team working on multidisciplinary project focused on assessment of ageing and safety of nuclear objects. (author)

  10. Contribution of the ARCAL XX/IAEA project to improvement of radiation safety in medical practices

    International Nuclear Information System (INIS)

    Medina Gironzini, E.

    2001-01-01

    The objectives of the ARCAL XX Project: 'Guidelines on Control of Radiation Sources' (1997-2000) are to promote an effective control of the radiation sources used in medicine, industrial and research applications, harmonising and updating existing procedures within Latin American, adopting the International Basic Safety Standards, in order to avoid unnecessary expositions limiting the probability of accidents occurrence. Nine countries participate with experts in the development of guidelines based in the regional experience. The guidelines contain Radiological Safety Requirements, Guide for Authorisation Application and Inspections Procedures. At this moment, there are guidelines for Radiotherapy, Nuclear Medicine and Diagnostic Radiology. The implementation of these guidelines will improve the effectiveness of regulatory control of radiation sources in Latin American and the radiological protection in aspects of occupational, medical, public and potential exposure. This document presents the experience in the development of these guidelines and their contribution for elaborating national regulations in medical practices. (author) [es

  11. River Protection Project Integrated safety management system phase II verification review plan - 7/29/99

    International Nuclear Information System (INIS)

    SHOOP, D.S.

    1999-01-01

    The purpose of this review is to verify the implementation status of the Integrated Safety Management System (ISMS) for the River Protection Project (RPP) facilities managed by Fluor Daniel Hanford, Inc. (FDH) and operated by Lockheed Martin Hanford Company (LMHC). This review will also ascertain whether within RPP facilities and operations the work planning and execution processes are in place and functioning to effectively protect the health and safety of the workers, public, environment, and federal property over the RPP life cycle. The RPP ISMS should support the Hanford Strategic Plan (DOERL-96-92) to safely clean up and manage the site's legacy waste and deploy science and technology while incorporating the ISMS central theme to ''Do work safely'' and protect human health and the environment

  12. Blood alcohol test results of motor vehicle deaths as an evaluation method for the Fairfax Alcohol Safety Action Project.

    Science.gov (United States)

    1973-01-01

    The Fairfax Alcohol Safety Action Project (ASAP) was started following the June 1971 approval of the proposal and working plan submitted to the Department of Transportation by the Highway Safety Division of Virginia. A total of $2,123,000 was allocat...

  13. 78 FR 56944 - Strata Energy, Inc. (Ross In Situ Recovery Uranium Project); Notice of Atomic Safety and...

    Science.gov (United States)

    2013-09-16

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 40-9091-MLA; ASLBP No. 12-915-01-MLA-BD01] Strata Energy, Inc. (Ross In Situ Recovery Uranium Project); Notice of Atomic Safety and Licensing Board Reconstitution Pursuant to 10 CFR 2.313(c) and 2.321(b), the Atomic Safety and Licensing Board (Board) in the...

  14. Waste Tank Organic Safety Project organic concentration mechanisms task. FY 1994 progress report

    International Nuclear Information System (INIS)

    Gerber, M.A.

    1994-09-01

    The Pacific Northwest Laboratory (PNL), Waste Tank Organic Safety Project is conducting research to support Westinghouse Hanford Company's (WHC) Waste Tank Safety Program, sponsored by the U.S. Department of Energy's Tank Farm Project Office. The goal of PNL's program is to provide a scientific basis for analyzing organics in Hanford's underground storage tanks (USTs) and for determining whether they are at concentrations that pose a potentially unsafe condition. Part of this research is directed toward determining what organic concentrations are safe by conducting research on organic aging mechanisms and waste energetics to assess the conditions necessary to produce an uncontrolled energy release in tanks due to reactions between the organics and the nitrate and nitrate salts in the tank wastes. The objective of the Organic Concentration Mechanisms Task is to assess the degree of localized enrichment of organics to be expected in the USTs due to concentration mechanisms. This report describes the progress of research conducted in FY 1994 on two concentration mechanisms of interest to the tank safety project: (1) permeation of a separate organic liquid phase into the interstitial spaces of the tank solids during the draining of free liquid from the tanks; and (2) concentration of organics on the surfaces of the solids due to adsorption. Three experiments were conducted to investigate permeation of air and solvent into a sludge simulant that is representative of single-shell tank sludge. The permeation behavior of air and solvent into the sludge simulant can be explained by the properties of the fluid pairs (air/supernate and solvent supernate) and the sludge. One important fluid property is the interfacial tension between the supernate and either the solvent or air. In general, the greater the interfacial tension between two fluids, the more difficult it will be for the air or solvent to displace the supernate during dewatering of the sludge

  15. Chernobyl 30 years on. Key remediation and safety projects are 'on track'

    Energy Technology Data Exchange (ETDEWEB)

    Dalton, David [NucNet, Brussels (Belgium)

    2016-06-15

    Thirty years after the accident at Chernobyl, key remediation and safety projects are on track and construction of the vital Euro 1.5 bn (US Dollars 1.6 bn) New Safe Confinement (NSC) is almost finished with commissioning scheduled for November 2017, the company in charge of construction and the European Bank for Reconstruction and Development (EBRD) told NucNet. The NSC is the most high profile and expensive element of the US Dollars 2.15 bn Shelter Implementation Plan (SIP), a framework developed to overcome the consequences of the accident.

  16. Engaging Agribusinesses: Feasibility and Cost of an ATV Safety Poster Project.

    Science.gov (United States)

    Jennissen, Charles A; Sweat, Shane; Wetjen, Kristel; Hoogerwerf, Pam; Denning, Gerene M

    2017-01-01

    All-terrain vehicle (ATV)-related deaths and injuries continue to be a significant problem. Influential change agents such as agribusinesses could be important partners for improving safety behaviors among rural ATV users. Our objective was to determine how effectively an injury prevention project could engage agribusinesses through the postal service and to assess their willingness to display a safety poster. One thousand two hundred forty-four agribusinesses received an ATV safety poster and a postcard survey by mail. A randomized sampling of these businesses was surveyed by telephone 4-7 weeks later. Telephone survey questions included whether they recalled receiving the poster, and if so, whether, where and how long the poster was displayed. One hundred six postcards were returned. Of the 192 eligible business persons contacted by telephone, 89% agreed to participate. Approximately one-third of telephone survey participants recalled receiving the poster. Among these, 81% with walk-in customers posted it, and 74% still had it displayed 1 month later. Of participants who did not recall receiving the poster, 83% stated they would have displayed the poster. The cost of displaying each poster in a business was 16.6 cents/day during the first month. Final costs/day would be much less because of continued display. A high percentage of agribusinesses displayed or would have displayed an ATV safety poster, and most displayed it beyond 1 month. Unfortunately, participant recruitment via postal delivery alone was challenging. Nevertheless, mass mailing of injury prevention materials to be displayed in the retail setting may be a low cost method for raising safety awareness.

  17. Technical and administrative approach for the West Valley Demonstration Project Safety Program

    International Nuclear Information System (INIS)

    Newsom, P.C.; Roberts, C.J.; Yuchien Yuan; Marchetti, S.

    1987-06-01

    The principal objective of the West Valley Demonstration Project (WVDP) is to vitrify the 2.2 million liters of high-level radioactive waste (HLW) stored at the Western New York Nuclear Service Center (WNYNSC). This simple statement of purpose, however, does not convey a sense of the complexity of the undertaking. The vitrification task is not only complex in and of itself, but requires a myriad of other activities to be accomplished on an intricate and fast paced schedule in order to support it. The West Valley Demonstration Project Act (P.L 96-368), U.S. Department of Energy Order DOE-5481.1A, Idaho Operations Office Order ID-5481.1 and standard nuclear industry practice all require that proposed systems and operations involving hazards not routinely encountered by the general public be analyzed to identify potential hazards and consequences, and to assure that reasonable measures are taken to eliminate, control, or mitigate these potential consequences. Virtually every substantive aspect of the WVDP involves hazards beyond those routinely encountered and accepted by the general public. In order to assure the safety of the public and the workers at the WVDP, a system of hazard identification, categorization, analysis and review has been established. In parallel with this system, a procedure for developing the minimum design specifications and quality assurance requirements has been developed for Project systems, components, and structures which play a role in the safety of a specific major facility or the overall Project. 29 refs., 3 figs., 6 tabs

  18. Selection of indicators for continuous monitoring of patient safety: recommendations of the project 'safety improvement for patients in Europe'

    DEFF Research Database (Denmark)

    Kristensen, Solvejg; Mainz, Jan; Bartels, Paul

    2009-01-01

    , proving that safety of care has improved with their usage, is questionable. The exact incidence and prevalence of patient safety quality problems are unknown. Therefore, there is a need for firm, evidence-based methods to survey and develop patient safety and derived activities. OBJECTIVE: The objective......BACKGROUND: Initiatives to improve patient safety have high priority among health professionals and politicians in most developed countries. Currently, however, assessment of patient safety problems relies mainly on case-based methodologies. The evidence for their efficiency and reproducibility...... for systematic monitoring is that it will be possible to continuously estimate the prevalence and incidence of patient safety quality problems. The lesson learnt from quality improvement is that it will pay off in terms of improving patient safety....

  19. State partnership in environmental health and safety phase of Plowshare projects

    International Nuclear Information System (INIS)

    Kinsman, S.

    1969-01-01

    When experiments on projects involving Plowshare devices are conceived, the state chosen for the project should be invited to participate in planning the health and safety aspects and be prepared to actively participate in the D-Day phase as well as the post-detonation activity. In California nuclear science technology and competence have preceded the social acceptance and use of nuclear devices for large scale Plowshare projects. However, the environmental surveillance program of the Bureau of Radiological Health in the State Department of Public Health has established an operative program which will be ready and able to function as an active participant or in a support role in environmental health phases of nuclear projects scheduled in the State. A description of our present program will be included in this paper. This will enable the attendees and readers to realize capabilities which will be activated for participation and/or support roles during Plowshare activities in the State or in a neighboring state if the need arises. (author)

  20. Reports on the projects in the field of reactor safety sponsored by the Federal Ministry for Research and Technology

    International Nuclear Information System (INIS)

    1977-11-01

    Investigations on the safety of Light Water Reactors (LWR) being performed in the framework of the Research Program Reactor Safety (RS-projects) are sponsored by the BMFT (Federal Minister for Research and Technology), Bundesminister fuer Forschung und Technologie. Objective of this program is to investigate in greater detail the safety margins of nuclear energy plants and their systems and the further development of safety technology. The GRS (Reactor Safety Association), Gesellschaft fuer Reaktorsicherheit mbH, by order of BMFT, informs continuously of the status of these investigations within the series 'GRS-F-Fortschrittsberichte' (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the different projects of the search program. The individual reports are prepared by the contractors themselves as a documentation of their progress in work and published by the GRS-FB (Research Coordination Department), Forschungsbetreuung at the GRS, within the framework of general information of the progress in reactor safety research. Each report describes the work performed, the results and the next steps of the work. The individual reports are attached to the classification system established by the CEC (Commission of the European Communities). The GRS-F-Progress Reports also include a list of the current investigations arranged according to the projects of the BMFT-Research Program Reactor Safety. This compilation, in addition to the LWR-investigations, also contains first contributions on the safety of advanced reactors. (orig.) [de

  1. Specific issues, exact locations: case study of a community mapping project to improve safety in a disadvantaged community.

    Science.gov (United States)

    Qummouh, Rana; Rose, Vanessa; Hall, Pat

    2012-12-01

    Safety is a health issue and a significant concern in disadvantaged communities. This paper describes an example of community-initiated action to address perceptions of fear and safety in a suburb in south-west Sydney which led to the development of a local, community-driven research project. As a first step in developing community capacity to take action on issues of safety, a joint resident-agency group implemented a community safety mapping project to identify the extent of safety issues in the community and their exact geographical location. Two aerial maps of the suburb, measuring one metre by two metres, were placed on display at different locations for four months. Residents used coloured stickers to identify specific issues and exact locations where crime and safety were a concern. Residents identified 294 specific safety issues in the suburb, 41.9% (n=123) associated with public infrastructure, such as poor lighting and pathways, and 31.9% (n=94) associated with drug-related issues such as drug activity and discarded syringes. Good health promotion practice reflects community need. In a very practical sense, this project responded to community calls for action by mapping resident knowledge on specific safety issues and exact locations and presenting these maps to local decision makers for further action.

  2. Reports on the projects in the field of reactor safety sponsored by the Federal Ministry for Research and Technology

    International Nuclear Information System (INIS)

    1977-06-01

    Investigations on the safety of Light Water Reactors (LWR) being performed in the framework of the Research Program Reactor Safety (RS-projects) are sponsored by the BMFT (Federal Minister for Research and Technology), Bundesminister fuer Forschung und Technologie. Objective of this program is to investigate in greater detail the safety margins of nuclear energy plants and their systems and the further development of safety technology. The GRS (Reactor Safety Association), Gesellschaft fuer Reaktorsicherheit mbH, by order of the BMFT, informs continuously of the status of these investigations within the series 'GRS-F-Forschrittsberichte' (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the different projects of the search program. The individual reports are prepared by the contractors themselves as a documentation of their progress in work and published by the GRS-FB (Research Coordination Department), Forschungsbetreuung at the GRS, within the framework of general information of the progress in reactor safety research. Each report describes the work performed, the results and the next steps of the work. The individual reports are attached to the classification system established by the CEC (Commission of the European Communities). The GRS-F-Progress Reports also include a list of the current investigations arranged according to the projects of the BMFT-Research Program Reactor Safety. This compilation, in addition to the LWR-investigations, also contains first contributions on the safety of advanced reactors. (orig.) [de

  3. Global alignment of immunization safety assessment in pregnancy - The GAIA project.

    Science.gov (United States)

    Bonhoeffer, Jan; Kochhar, Sonali; Hirschfeld, Steven; Heath, Paul T; Jones, Christine E; Bauwens, Jorgen; Honrado, Ángel; Heininger, Ulrich; Muñoz, Flor M; Eckert, Linda; Steinhoff, Mark; Black, Steven; Padula, Michael; Sturkenboom, Miriam; Buttery, Jim; Pless, Robert; Zuber, Patrick

    2016-12-01

    Immunization in pregnancy provides a promising contribution to globally reducing neonatal and under-five childhood mortality and morbidity. Thorough assessment of benefits and risks for the primarily healthy pregnant women and their unborn babies is required. The GAIA project was formed in response to the call of the World Health Organization for a globally concerted approach to actively monitor the safety of vaccines and immunization in pregnancy programs. GAIA aims to improve the quality of outcome data from clinical vaccine trials in pregnant women with a specific focus on the needs and requirements for safety monitoring in LMIC. In the first year of the project, a large and functional network of experts was created. The first outputs include a guidance document for clinical trials of immunization in pregnancy, a basic data collection guide, ten case definitions of key obstetric and neonatal health outcomes, an ontology of key terms and a map of pertinent disease codes. The GAIA Network is designed as an open and growing forum for professionals sharing the GAIA vision and aim. Based on the initial achievements, tools and services are developed to support investigators and strengthen immunization in pregnancy programs with specific focus on LMIC. Copyright © 2016. Published by Elsevier Ltd.

  4. The influence of organisational and management factors on safety performance in NNPPS. Rand D project

    International Nuclear Information System (INIS)

    Cal, C. de la; Gil, B.; Sola, R.; Vaquero, C.; Garces, M. I.

    2002-01-01

    The direct influence of organisational and managerial factors on safety performance in nuclear power plants has been widely proved by two findings, the analysis of their operating experience and the differences in safety levels reached by similar installations. Specially, the study of majors accidents such as TMI-2 and Chernobyl have demonstrated that the technical deficiencies are not the only root causes, but there are a whole set of human, organisational, managerial and social factors which are the origin from most of these deficiencies. In recent years, this fact is emphasised with the nuclear industry involved a process of change. The deregulation of the electricity market, which has increased the economic pressures to the companies and has driven in many cases to restructures in ownership (mergers, acquisitions), downsizing processes and outsourcing parts of the work, jointly with the development of information technologies and computer networks and with a change in the regulatory and social climates are some of the nre factors affecting the performance of nuclear power plants that have addressed, even more, to the need of re-viewing and assessing the impact of organisational aspects on their safe performance. There have been international efforts to analyse the influence of organisational factors in the safety of nuclear power plants following different approaches. Research institutions, utilities and regulatory bodies. individually or in co-operation, have tried to develop practical tools for taking into account the organisation. According to these international efforts the Association of Spanish Utilities, UNESA, and the Spanish Nuclear Regulatory Body, CSN, have included in 1998, for the first time in their Co-ordinated Plan for Research, an innovative five years R and D project entitled Development of methods to evaluate and model the impact of organisation on nuclear poer plants safety whose main objectives are to analyse the impact of organisation and

  5. Surveys of research projects concerning nuclear facility safety, financed by the Federal Ministry for the Environment, Nature Protection and Reactor Safety, 1987

    International Nuclear Information System (INIS)

    1988-06-01

    Each progress report is a collection of individual reports, categorized by subject matter. They are a documentation of the contractor's progress, rendered by themselves on standardized forms, published, for the sake of general information on progress made in investigations concerning reactor safety, by the project attendance department of the GRS. The individual reports have serial numbers. Each report includes particulars of the objective, work carried out, results obtained and plans for project continuation. (orig.) [de

  6. Quality assurance program plan for 324 Building B-Cell safety cleanout project (BCCP)

    International Nuclear Information System (INIS)

    Tanke, J.M.

    1997-01-01

    This Quality Assurance Program Plan (QAPP) provides information on how the Quality Assurance Program is implemented for the 324 Building B-Cell Safety Cleanout Project (BCCP). This QAPP is responsive to the Westinghouse Hanford Company Quality Assurance Program and Implementation Plan, WHC-SP-1131, for 10 CFR 830.120, Nuclear Safety Management, Quality Assurance Requirements; and DOE Order 5700.6C, Quality Assurance. This QAPP supersedes PNNL PNL-MA-70 QAP Quality Assurance Plan No. WTC-050 Rev. 2, issue date May 3, 1996. This QAPP has been developed specifically for the BCCP. It applies to those items and tasks which affect the completion of activities identified in the work breakdown structure of the Project Management Plan (PMP). These activities include all aspects of decontaminating B-Cell and project related operations within the 324 Building as it relates to the specific activities of this project. General facility activities (i.e. 324 Building Operations) are covered in the Building 324 QAPP. In addition, this QAPP supports the related quality assurance activities addressed in CM-2-14, Hazardous Material Packaging and Shipping, and HSRCM-1, Hanford Site Radiological Control Manual, The 324 Building is currently transitioning from being a Pacific Northwest National Laboratory (PNNL) managed facility to a B and W Hanford Company (BWHC) managed facility. During this transition process existing, PNNL procedures and documents will be utilized until replaced by BWHC procedures and documents. These documents conform to the requirements found in PNL-MA-70, Quality Assurance Manual and PNL-MA-8 1, Hazardous Materials Shipping Manual. The Quality Assurance Program Index (QAPI) contained in Table 1 provides a matrix which shows how project activities relate to 10 CFR 83 0.120 and 5700.6C criteria. Quality Assurance program requirements will be addressed separate from the requirements specified in this document. Other Hanford Site organizations/companies may be

  7. The Environmental Health/Home Safety Education Project: a successful and practical U.S.-Mexico border initiative.

    Science.gov (United States)

    Forster-Cox, Susan C; Mangadu, Thenral; Jacquez, Benjamín; Fullerton, Lynne

    2010-05-01

    The Environmental Health/Home Safety Education Project (Proyecto de Salud Ambiental y Seguridad en el Hogar) has been developed in response to a wide array of severe and often preventable environmental health issues occurring in and around homes on the U.S.-Mexico border. Utilizing well-trained community members, called promotoras , homes are visited and assessed for potential environmental hazards, including home fire and food safety issues. Data analyzed from project years 2002 to 2005 shows a significant impact in knowledge levels and initial behavior change among targeted participants as it relates to fire and food safety issues. Since the initiation of the project in 1999, hundreds of participants have improved their quality of life by making their homes safer. The project has proven to be sustainable, replicable, flexible, and attractive to funders.

  8. Safety cases for radioactive waste disposal facilities: guidance on confidence building and regulatory review IAEA-ASAM co-ordinated research project

    International Nuclear Information System (INIS)

    Ben Belfadhel, M.; Bennett, D.G.; Metcalf, P.; Nys, V.; Goldammer, W.

    2008-01-01

    The IAEA has been conducting two co-ordinated research programmes (CRPs) projects to develop and apply improved safety assessment methodologies for near-surface radioactive waste disposal facilities. The more recent of these projects, ASAM (application of safety assessment methodologies), included a Regulatory Review Working Group (RRWG) which has been working to develop guidance on how to gain confidence in safety assessments and safety cases, and on how to conduct regulatory reviews of safety assessments. This paper provides an overview of the ASAM project, focusing on the safety case and regulatory review. (authors)

  9. SAFETY

    CERN Document Server

    Niels Dupont

    2013-01-01

    CERN Safety rules and Radiation Protection at CMS The CERN Safety rules are defined by the Occupational Health & Safety and Environmental Protection Unit (HSE Unit), CERN’s institutional authority and central Safety organ attached to the Director General. In particular the Radiation Protection group (DGS-RP1) ensures that personnel on the CERN sites and the public are protected from potentially harmful effects of ionising radiation linked to CERN activities. The RP Group fulfils its mandate in collaboration with the CERN departments owning or operating sources of ionising radiation and having the responsibility for Radiation Safety of these sources. The specific responsibilities concerning "Radiation Safety" and "Radiation Protection" are delegated as follows: Radiation Safety is the responsibility of every CERN Department owning radiation sources or using radiation sources put at its disposition. These Departments are in charge of implementing the requi...

  10. Redox processes in the safety case of deep geological repositories of radioactive wastes. Contribution of the European RECOSY Collaborative Project

    International Nuclear Information System (INIS)

    Duro, L.; Bruno, J.; Grivé, M.; Montoya, V.; Kienzler, B.; Altmaier, M.; Buckau, G.

    2014-01-01

    Highlights: • The RECOSY project produced results relevant for the Safety Case of nuclear disposal. • We classify the safety related features where RECOSY has contributed. • Redox processes effect the retention of radionuclides in all repository subsystems. - Abstract: Redox processes influence key geochemical characteristics controlling radionuclide behaviour in the near and far field of a nuclear waste repository. A sound understanding of redox related processes is therefore of high importance for developing a Safety Case, the collection of scientific, technical, administrative and managerial arguments and evidence in support of the safety of a disposal facility. This manuscript presents the contribution of the specific research on redox processes achieved within the EURATOM Collaborative Project RECOSY (REdox phenomena COntrolling SYstems) to the Safety Case of nuclear waste disposal facilities. Main objectives of RECOSY were related to the improved understanding of redox phenomena controlling the long-term release or retention of radionuclides in nuclear waste disposal and providing tools to apply the results to Performance Assessment and the Safety Case. The research developed during the project covered aspects of the near-field and the far-field aspects of the repository, including studies relevant for the rock formations considered in Europe as suitable for hosting an underground repository for radioactive wastes. It is the intention of this paper to highlight in which way the results obtained from RECOSY can feed the scientific process understanding needed for the stepwise development of the Safety Case associated with deep geological disposal of radioactive wastes

  11. Validation of asthma recording in the Clinical Practice Research Datalink (CPRD).

    Science.gov (United States)

    Nissen, Francis; Morales, Daniel R; Mullerova, Hana; Smeeth, Liam; Douglas, Ian J; Quint, Jennifer K

    2017-08-11

    The optimal method of identifying people with asthma from electronic health records in primary care is not known. The aim of this study is to determine the positive predictive value (PPV) of different algorithms using clinical codes and prescription data to identify people with asthma in the United Kingdom Clinical Practice Research Datalink (CPRD). 684 participants registered with a general practitioner (GP) practice contributing to CPRD between 1 December 2013 and 30 November 2015 were selected according to one of eight predefined potential asthma identification algorithms. A questionnaire was sent to the GPs to confirm asthma status and provide additional information to support an asthma diagnosis. Two study physicians independently reviewed and adjudicated the questionnaires and additional information to form a gold standard for asthma diagnosis. The PPV was calculated for each algorithm. 684 questionnaires were sent, of which 494 (72%) were returned and 475 (69%) were complete and analysed. All five algorithms including a specific Read code indicating asthma or non-specific Read code accompanied by additional conditions performed well. The PPV for asthma diagnosis using only a specific asthma code was 86.4% (95% CI 77.4% to 95.4%). Extra information on asthma medication prescription (PPV 83.3%), evidence of reversibility testing (PPV 86.0%) or a combination of all three selection criteria (PPV 86.4%) did not result in a higher PPV. The algorithm using non-specific asthma codes, information on reversibility testing and respiratory medication use scored highest (PPV 90.7%, 95% CI (82.8% to 98.7%), but had a much lower identifiable population. Algorithms based on asthma symptom codes had low PPVs (43.1% to 57.8%)%). People with asthma can be accurately identified from UK primary care records using specific Read codes. The inclusion of spirometry or asthma medications in the algorithm did not clearly improve accuracy. The protocol for this research was approved

  12. Pilotprojekt "Patientensicherheit" in der medizinischen Lehre [Pilot project "Patient-Safety" in Medical Education

    Directory of Open Access Journals (Sweden)

    Rosentreter, Michael

    2011-02-01

    Full Text Available [english] Since the summer term 2009 the study project „Patientensicherheit – Der klinische Umgang mit Patienten- und Eingriffsverwechslungen sowie Medikationsfehlern“ (Patient Safety – the clinical handling of patients – and mistaking of procedures as well as medication errors is offered within the Modellstudiengang Medizin. Seminars on patient safety in Germany so far mainly address trained doctors and health economists. In contrast, this study project on patient safety should at an early stage contribute to a “culture of discussing and preventing mistakes” – an aspect that is little established in clinical medicine, but also in medical training. For this purpose, a broad variety of courses was developed, which – relying on problem-oriented learning – enables the students to analyse so-called adverse events (AE and develop adequate prevention measures on the basis of the insights gained by this analysis. Therefore, theoretical lessons are complemented by discussing prototypical clinical cases. These discussions are moderated by experienced clinicians. After completing the seminar, students showed a significant increase (comparison of means in the self-assessed qualifications „Wissen zu Patientensicherheit“ (Knowledge of Patient Safety and „Wahrnehmung von Risikosituationen“ (Appreciation of Risk Situations. All in all, the students rated their training success with a grade of 1.5 (good.[german] Seit dem Sommersemester 2009 wird im Rahmen des Modellstudiengangs Medizin der RWTH Aachen das Lehrprojekt „Patientensicherheit – Der klinische Umgang mit Patienten- und Eingriffsverwechslungen sowie Medikationsfehlern“ angeboten Seminare zur Patientensicherheit in Deutschland zielen bislang vor allem auf ausgebildete Ärzte und Gesundheitsökonomen ab. Demgegenüber soll das Lehrprojekt Patientensicherheit einen frühzeitigen Beitrag zu einer „Kultur der Fehlerdiskussion und -vermeidung“ leisten – ein Aspekt, der

  13. Understanding the relationship between safety culture dimensions and safety performance of construction projects through partial least square method

    Science.gov (United States)

    Latief, Yusuf; Machfudiyanto, Rossy A.; Arifuddin, Rosmariani; Yogiswara, Yoko

    2017-03-01

    Based on the data, 32% of accidental cases in Indonesia occurs on constructional sectors. It is supported by the data from Public Work and Housing Department that 27.43% of the implementation level of Safety Management System policy at construction companies in Indonesia remains unsafe categories. Moreover, there are dimensions of occupational safety culture formed including leadership, behavior, strategy, policy, process, people, safety cost, value and contract system. The aim of this study is to determine the model of an effective safety culture and know the relationship between dimensions in construction industry. The method used in this research was questionnaire survey which was distributed to the sample of construction companies either in a national private one in Indonesia. The result of this research is supposed to be able to illustrate the development of the relationship among occupational safety culture dimensions which have influences to the performances of constructional companies in Indonesia.

  14. Analysis of Aviation Safety Reporting System Incident Data Associated with the Technical Challenges of the System-Wide Safety and Assurance Technologies Project

    Science.gov (United States)

    Withrow, Colleen A.; Reveley, Mary S.

    2015-01-01

    The Aviation Safety Program (AvSP) System-Wide Safety and Assurance Technologies (SSAT) Project asked the AvSP Systems and Portfolio Analysis Team to identify SSAT-related trends. SSAT had four technical challenges: advance safety assurance to enable deployment of NextGen systems; automated discovery of precursors to aviation safety incidents; increasing safety of human-automation interaction by incorporating human performance, and prognostic algorithm design for safety assurance. This report reviews incident data from the NASA Aviation Safety Reporting System (ASRS) for system-component-failure- or-malfunction- (SCFM-) related and human-factor-related incidents for commercial or cargo air carriers (Part 121), commuter airlines (Part 135), and general aviation (Part 91). The data was analyzed by Federal Aviation Regulations (FAR) part, phase of flight, SCFM category, human factor category, and a variety of anomalies and results. There were 38 894 SCFM-related incidents and 83 478 human-factorrelated incidents analyzed between January 1993 and April 2011.

  15. Reports on research projects in the field of reactor safety sponsored by the Federal Minister for Research and Technology

    International Nuclear Information System (INIS)

    1978-09-01

    Investigations on the safety of Light Water Reactors (LWR) being performed in the framework of the Research Program Reactor Safety (RS - Projects) are sponsored by the BMFT (Federal Minister for Research and Technology), der Bundesminister fuer Forschung und Technologie. Objective of this program is to investigate in greater detail the safety margins of nuclear power plants and their systems and the further development of safety technology. Besides the investigations of LWR tasks first projects on the safety of FBR type reactors are sponsored by the BMFT. The GRS (Reactor Safety Association), Gesellschaft fuer Reaktorsicherheit mbH, by order of the BMFT, informs continuously of the status of such investigations by means of quarterly and annually publication of progress reports within the series GRS - F Fortschrittsberichte (GRS - F - Progress Reports). Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work. The individual reports are arranged according to the amended LWR Safety Research Program of the BMFT. Another table contents uses the same classification system as applied in the Nuclear Safety Index of the CEC Communities and the OECD. (orig./HP) 891 HP [de

  16. Environment, safety and health progress assessment of the Fernald Environmental Management Project (FEMP)

    Energy Technology Data Exchange (ETDEWEB)

    1991-11-01

    This report documents the results of the Environment, Safety, and Health (ES&H) Progress Assessment of the Fernald Environmental Management Project (FEMP), Fernald, Ohio, conducted from October 15 through October 25, 1991. The Secretary of Energy directed that small, focused, ES&H Progress Assessments be performed as part of the continuing effort to institutionalize line management accountability and the self-assessment process in the areas of ES&H. The FEMP assessment is the pilot assessment for this new program. The objectives for the FEMP ES&H Progress Assessment were to assess: (1) how the FEMP has progressed since the 1989 Tiger Assessment; (2) how effectively the FEMP has corrected specific deficiencies and associated root causes identified by that team; and (3) whether the current organization, resources, and systems are sufficient to proactively manage ES&H issues.

  17. Environment, safety and health progress assessment of the Fernald Environmental Management Project (FEMP)

    International Nuclear Information System (INIS)

    1991-11-01

    This report documents the results of the Environment, Safety, and Health (ES ampersand H) Progress Assessment of the Fernald Environmental Management Project (FEMP), Fernald, Ohio, conducted from October 15 through October 25, 1991. The Secretary of Energy directed that small, focused, ES ampersand H Progress Assessments be performed as part of the continuing effort to institutionalize line management accountability and the self-assessment process in the areas of ES ampersand H. The FEMP assessment is the pilot assessment for this new program. The objectives for the FEMP ES ampersand H Progress Assessment were to assess: (1) how the FEMP has progressed since the 1989 Tiger Assessment; (2) how effectively the FEMP has corrected specific deficiencies and associated root causes identified by that team; and (3) whether the current organization, resources, and systems are sufficient to proactively manage ES ampersand H issues

  18. Safety manual governing the authorization procedure for nuclear power plant/project

    International Nuclear Information System (INIS)

    1989-01-01

    The manual specifies the procedures to be followed by Nuclear Power Corporation and other nuclear installations in India for securing authorization of different phases of any nuclear power plant/project (except decommissioning). Section I of the manual sets down the specific objectives of review and assessment of the applications for authorization. Section II describes the modalities of the authorization process which include general aspects, functions of authorization, requirements on the applicant, stages of the authorization process and schedule of submission for authorization. Section III deals with typical information to be submitted in support of application for authorization. Appendix I gives in detail guidelines for organisation and contents of safety analysis reports for power reactors. Appendix II indicates the typical documentary submissions in support of applications for commissioning and operating authorization. (M.G.B.)

  19. Safety

    International Nuclear Information System (INIS)

    2001-01-01

    This annual report of the Senior Inspector for the Nuclear Safety, analyses the nuclear safety at EDF for the year 1999 and proposes twelve subjects of consideration to progress. Five technical documents are also provided and discussed concerning the nuclear power plants maintenance and safety (thermal fatigue, vibration fatigue, assisted control and instrumentation of the N4 bearing, 1300 MW reactors containment and time of life of power plants). (A.L.B.)

  20. Safety

    CERN Multimedia

    2003-01-01

    Please note that the safety codes A9, A10 AND A11 (ex annexes of SAPOCO/42) entitled respectively "Safety responsibilities in the divisions" "The safety policy committee (SAPOCO) and safety officers' committees" and "Administrative procedure following a serious accident or incident" are available on the web at the following URLs: Code A9: http://edms.cern.ch/document/337016/LAST_RELEASED Code A10: http://edms.cern.ch/document/337019/LAST_RELEASED Code A11: http://edms.cern.ch/document/337026/LAST_RELEASED Paper copies can also be obtained from the TIS divisional secretariat, e-mail: tis.secretariat@cern.ch. TIS Secretariat

  1. Development of Occupational Safety and Health Requirement Management System (OSHREMS) Software Using Adobe Dreamweaver CS5 for Building Construction Project

    OpenAIRE

    Abas Nor Haslinda; Adman Nurjeha; Deraman Rafikullah

    2017-01-01

    The construction industry sector is considered as being risky with frequent and high accident rate. According to Social Security Organization (SOCSO), the construction accidents has arisen from time to time. Construction Industry Development Board (CIDB) has developed the Safety and Health Assessment System in Construction (SHASSIC) for evaluating the performance of a contractor in construction project by setting out the safety and health management and practices, however the requirement chec...

  2. YUCCA MOUNTAIN SITE CHARACTERIZATION PROJECT EAST-WEST DRIFT SYSTEM SAFETY ANALYSIS

    Energy Technology Data Exchange (ETDEWEB)

    NA

    1999-06-08

    The purpose of this analysis is to systematically identify and evaluate hazards related to the design of the Yucca Mountain Project Exploratory Studies Facility (ESF) East-West Cross Drift. This analysis builds upon prior ESF System Safety Analyses and incorporates TS Main Drift scenarios, where applicable, into the East-West Drift scenarios. This System Safety Analysis (SSA) focuses on the personnel safety and health hazards associated with the engineered design of the East-West Drift. The analysis also evaluates other aspects of the East-West Drift, including purchased equipment (e.g., scientific mapping platform) or Systems/Structures/Components (SSCs) and out-of-tolerance conditions. In addition to recommending design mitigation features, the analysis identifies the potential need for procedures, training, or Job Safety Analyses (JSAs). The inclusion of this information in the SSA is intended to assist the organization(s) (e.g., constructor, Safety and Health, design) responsible for these aspects of the East-West Drift in evaluating personnel hazards and augment the information developed by these organizations. The SSA is an integral part of the systems engineering process, whereby safety is considered during planning, design, testing, and construction. A largely qualitative approach is used which incorporates operating experiences and recommendations from vendors, the constructor and the operating contractor. The risk assessment in this analysis characterizes the scenarios associated with East-West Drift SSCs in terms of relative risk and includes recommendations for mitigating all identified hazards. The priority for recommending and implementing mitigation control features is: (1) Incorporate measures to reduce risks and hazards into SSC designs. (2) Add safety features and capabilities to existing designs. (3) Develop procedures and conduct training to increase worker awareness of potential hazards, reduce exposure to hazards, and inform personnel of the

  3. Inventory of Federal energy-related environment and safety research for FY 1978. Volume II. Project listings and indexes

    Energy Technology Data Exchange (ETDEWEB)

    None

    1979-12-01

    This volume contains summaries of FY-1978 government-sponsored environment and safety research related to energy. Project summaries were collected by Aerospace Corporation under contract with the Department of Energy, Office of Program Coordination, under the Assistant Secretary for Environment. Summaries are arranged by log number, which groups the projects by reporting agency. The log number is a unique number assigned to each project from a block of numbers set aside for each agency. Information about the projects is included in the summary listings. This includes the project title, principal investigators, research organization, project number, contract number, supporting organization, funding level if known, related energy sources with numbers indicating percentages of effort devoted to each, and R and D categories. A brief description of each project is given, and this is followed by subject index terms that were assigned for computer searching and for generating the printed subject index in Volume IV.

  4. Inventory of Federal energy-related environment and safety research for FY 1978. Volume II. Project listings and indexes

    International Nuclear Information System (INIS)

    1979-12-01

    This volume contains summaries of FY-1978 government-sponsored environment and safety research related to energy. Project summaries were collected by Aerospace Corporation under contract with the Department of Energy, Office of Program Coordination, under the Assistant Secretary for Environment. Summaries are arranged by log number, which groups the projects by reporting agency. The log number is a unique number assigned to each project from a block of numbers set aside for each agency. Information about the projects is included in the summary listings. This includes the project title, principal investigators, research organization, project number, contract number, supporting organization, funding level if known, related energy sources with numbers indicating percentages of effort devoted to each, and R and D categories. A brief description of each project is given, and this is followed by subject index terms that were assigned for computer searching and for generating the printed subject index in Volume IV

  5. Reports covering research projects in the field of reactor safety supported by the German Federal Ministry for Research and Technology

    International Nuclear Information System (INIS)

    1976-03-01

    Investigations on the safety of Light Water Reactors (LWR) being performed in the framework of the safety program 'Reactor Safety' are sponsored by the Bundesminister fuer Forschung und Technologie (BMFT - Secretary of State for Research and Technology). Objective of this program is to continue improving the safety of LWR, in order to minimize the risk for the environment. With grant assistance from the Bundesminister des Innern. (BMI - Secretary of State for Home Affairs) research cont racts in the field of reactor safety are being performed. Results of these projects should contribute to resolve questions arising nuclear licensing procedures. The Forschungsbetreuung (FB - research supervision department) at the Institute for Reactor Safety (IRS), as consultants to BMFT and BMI, provides information about the progress of investigations. Individual reports will be prepared and put into standard forms by the research contractors. Each report gives information on: 1) the work accomplished, 2) the results obtained, 3) the work planned to be continued. Initial reports of research projects describe in addition the purpose of the work. A BMFT-research program on the safety of Fast Breeders (Schneller Brutreaktor - SBR) is presently under discussion. In order to define several problems, investigations included in the present compilation (RS 139, 140, 143, 162) will be previously performed. (orig.) [de

  6. Reports on the research projects in the field of reactor safety sponsored by the Federal Ministry for Science and Technology

    International Nuclear Information System (INIS)

    1977-03-01

    Investigations on the safety of Light Water Reactors (LWR) being performed in the framework of the safety program 'Reactor Safety' are sponsored by the Bundesminister fuer Forschung und Technologie (BMFT - Secretary of State for Research and Technology). Objective of this program is to continue improving the safety of LWRs, in order to minimize the risk for the environment. With grant assistance from the Bundesminister des Innern (BMI - Secretary of State for Home Affairs) research contracts in the field of reactor safety are being performed. Results of these projects should contribute to resolving questions arising from nuclear licensing procedures. The Forschungsbetreuung (FB - research supervision department) at the Institute for Reactor Safety (IRS), as consultants to BMFT and BMI, provides information about the progress of investigations. Individual reports will be prepared and put into standard forms by the research contractors. Each report gives information on: 1) the work accomplished, 2) the results obtained, 3) the work planned to be continued. Initial reports of research projects describe in addition the purpose of the work. A BMFT-research program on the safety of Fast Breeders (Schneller Brutreaktor - SBR) is presently under discussion. In order to define several problems, investigations included in the present compilation (RS 139, 140, 143, 162) will be previously performed. (orig.) [de

  7. DECOVALEX III PROJECT. Thermal-Hydro-Mechanical Coupled Processes in Safety Assessments. Report of Task 4

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Johan [JA Streamflow AB, Aelvsjoe (Sweden)

    2005-02-15

    A part (Task 4) of the International DECOVALEX III project on coupled thermo-hydro-mechanical (T-H-M) processes focuses on T-H-M modelling applications in safety and performance assessment of deep geological nuclear waste repositories. A previous phase, DECOVALEX II, saw a need to improve such modelling. In order to address this need Task 4 of DECOVALEX III has: Analysed two major T-H-M experiments (Task 1 and Task 2) and three different Bench Mark Tests (Task 3) set-up to explore the significance of T-H-M in some potentially important safety assessment applications. Compiled and evaluated the use of T-H-M modelling in safety assessments at the time of the year 2000. Organised a forum a forum of interchange between PA-analysts and THM modelers at each DECOVALEX III workshop. Based on this information the current report discusses the findings and strives for reaching recommendations as regards good practices in addressing coupled T-H-M issues in safety assessments. The full development of T-H-M modelling is still at an early stage and it is not evident whether current codes provide the information that is required. However, although the geosphere is a system of fully coupled processes, this does not directly imply that all existing coupled mechanisms must be represented numerically. Modelling is conducted for specific purposes and the required confidence level should be considered. It is necessary to match the confidence level with the modelling objective. Coupled THM modelling has to incorporate uncertainties. These uncertainties mainly concern uncertainties in the conceptual model and uncertainty in data. Assessing data uncertainty is important when judging the need to model coupled processes. Often data uncertainty is more significant than the coupled effects. The emphasis on the need for THM modelling differs among disciplines. For geological radioactive waste disposal in crystalline and other similar hard rock formations DECOVALEX III shows it is essential to

  8. Fall prevention and safety communication training for foremen: report of a pilot project designed to improve residential construction safety.

    Science.gov (United States)

    Kaskutas, Vicki; Dale, Ann Marie; Lipscomb, Hester; Evanoff, Brad

    2013-02-01

    Falls from heights account for 64% of residential construction worker fatalities and 20% of missed work days. We hypothesized that worker safety would improve with foremen training in fall prevention and safety communication. Training priorities identified through foreman and apprentice focus groups and surveys were integrated into an 8-hour training. We piloted the training with ten foremen employed by a residential builder. Carpenter trainers contrasted proper methods to protect workers from falls with methods observed at the foremen's worksites. Trainers presented methods to deliver toolbox talks and safety messages. Results from worksite observational audits (n=29) and foremen/crewmember surveys (n=97) administered before and after training were compared. We found that inexperienced workers are exposed to many fall hazards that they are often not prepared to negotiate. Fall protection is used inconsistently and worksite mentorship is often inadequate. Foremen feel pressured to meet productivity demands and some are unsure of the fall protection requirements. After the training, the frequency of daily mentoring and toolbox talks increased, and these talks became more interactive and focused on hazardous daily work tasks. Foremen observed their worksites for fall hazards more often. We observed increased compliance with fall protection and decreased unsafe behaviors during worksite audits. Designing the training to meet both foremen's and crewmembers' needs ensured the training was learner-centered and contextually-relevant. This pilot suggests that training residential foremen can increase use of fall protection, improve safety behaviors, and enhance on-the-job training and safety communication at their worksites. Construction workers' training should target safety communication and mentoring skills with workers who will lead work crews. Interventions at multiple levels are necessary to increase safety compliance in residential construction and decrease falls

  9. ASN guide project. Safety policy and management in INBs (base nuclear installations)

    International Nuclear Information System (INIS)

    2010-01-01

    This guide presents the recommendations of the French Nuclear Safety Authority (ASN) in the field of safety policy and management (PMS) for base nuclear installations (INBs). It gives an overview and comments of some prescriptions of the so-called INB order and PMS decision. These regulatory texts define a framework for provisions any INB operator must implement to establish his safety policy, to define and implement a system which allows the safety to be maintained, the improvement of his INB safety to be permanently looked for. The following issues are addressed: operator's safety policy, identification of elements important for safety, of activities pertaining to safety, and of associated requirements, safety management organization and system, management of activities pertaining to safety, documentation and archiving

  10. Research projects into the safety of nuclear power plants. Period cover 01. January - 30. June 2017. Progress report

    International Nuclear Information System (INIS)

    2017-01-01

    Within its competence for energy research the Federal Ministry for Economic Affairs and Energy (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fur Anlagen- und Reaktorsicherheit (GRS) gGmbH, by order of the BMWi, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Project Management Agency/ Authority Support Division of GRS. The reports as of the year 2000 are available in the internet-based information system on results and data of reactor safety research (https://www.grs-fbw.de). The compilation of the reports is classified according to the topic areas of reactor safety research. The reports are arranged in sequence of their project numbers. Ilt has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties.

  11. Feedback from uncertainties propagation research projects conducted in different hydraulic fields: outcomes for engineering projects and nuclear safety assessment.

    Science.gov (United States)

    Bacchi, Vito; Duluc, Claire-Marie; Bertrand, Nathalie; Bardet, Lise

    2017-04-01

    In recent years, in the context of hydraulic risk assessment, much effort has been put into the development of sophisticated numerical model systems able reproducing surface flow field. These numerical models are based on a deterministic approach and the results are presented in terms of measurable quantities (water depths, flow velocities, etc…). However, the modelling of surface flows involves numerous uncertainties associated both to the numerical structure of the model, to the knowledge of the physical parameters which force the system and to the randomness inherent to natural phenomena. As a consequence, dealing with uncertainties can be a difficult task for both modelers and decision-makers [Ioss, 2011]. In the context of nuclear safety, IRSN assesses studies conducted by operators for different reference flood situations (local rain, small or large watershed flooding, sea levels, etc…), that are defined in the guide ASN N°13 [ASN, 2013]. The guide provides some recommendations to deal with uncertainties, by proposing a specific conservative approach to cover hydraulic modelling uncertainties. Depending of the situation, the influencing parameter might be the Strickler coefficient, levee behavior, simplified topographic assumptions, etc. Obviously, identifying the most influencing parameter and giving it a penalizing value is challenging and usually questionable. In this context, IRSN conducted cooperative (Compagnie Nationale du Rhone, I-CiTy laboratory of Polytech'Nice, Atomic Energy Commission, Bureau de Recherches Géologiques et Minières) research activities since 2011 in order to investigate feasibility and benefits of Uncertainties Analysis (UA) and Global Sensitivity Analysis (GSA) when applied to hydraulic modelling. A specific methodology was tested by using the computational environment Promethee, developed by IRSN, which allows carrying out uncertainties propagation study. This methodology was applied with various numerical models and in

  12. Are automatic systems the future of motorcycle safety? A novel methodology to prioritize potential safety solutions based on their projected effectiveness.

    Science.gov (United States)

    Gil, Gustavo; Savino, Giovanni; Piantini, Simone; Baldanzini, Niccolò; Happee, Riender; Pierini, Marco

    2017-11-17

    Motorcycle riders are involved in significantly more crashes per kilometer driven than passenger car drivers. Nonetheless, the development and implementation of motorcycle safety systems lags far behind that of passenger cars. This research addresses the identification of the most effective motorcycle safety solutions in the context of different countries. A knowledge-based system of motorcycle safety (KBMS) was developed to assess the potential for various safety solutions to mitigate or avoid motorcycle crashes. First, a set of 26 common crash scenarios was identified from the analysis of multiple crash databases. Second, the relative effectiveness of 10 safety solutions was assessed for the 26 crash scenarios by a panel of experts. Third, relevant information about crashes was used to weigh the importance of each crash scenario in the region studied. The KBMS method was applied with an Italian database, with a total of more than 1 million motorcycle crashes in the period 2000-2012. When applied to the Italian context, the KBMS suggested that automatic systems designed to compensate for riders' or drivers' errors of commission or omission are the potentially most effective safety solution. The KBMS method showed an effective way to compare the potential of various safety solutions, through a scored list with the expected effectiveness of each safety solution for the region to which the crash data belong. A comparison of our results with a previous study that attempted a systematic prioritization of safety systems for motorcycles (PISa project) showed an encouraging agreement. Current results revealed that automatic systems have the greatest potential to improve motorcycle safety. Accumulating and encoding expertise in crash analysis from a range of disciplines into a scalable and reusable analytical tool, as proposed with the use of KBMS, has the potential to guide research and development of effective safety systems. As the expert assessment of the crash

  13. Advanced Crash Avoidance Technologies (ACAT) Program - Final Report of the Volvo-Ford-UMTRI Project: Safety Impact Methodology for Lane Departure Warning - Method Development and Estimation of Benefits

    Science.gov (United States)

    2010-10-01

    The Volvo-Ford-UMTRI project: Safety Impact Methodology (SIM) for Lane Departure Warning is part of the U.S. Department of Transportation's Advanced Crash Avoidance Technologies (ACAT) program. The project developed a basic analytical framework for e...

  14. Safety assessment methodologies and their application in development of near surface waste disposal facilities - the ASAM project

    International Nuclear Information System (INIS)

    Metcalf, P.

    2003-01-01

    The scope of ASAM project covers near surface disposal facilities for all types of low and intermediate level wastes with emphasis of the post-closure safety assessment.The objectives are to explore practical application to a range of disposal facilities for a number of purposes e.g. development of design concepts, safety re-assessment, upgrading safety and to develop practical approaches to assist regulators, operators and other experts in review of safety assessment. The task of the Co-ordination Group are: reassessment of existing facilities - use of safety assessment in decision making on selection of options (volunteer site Hungary); disused sealed sources - evaluation of disposability of disused sealed sources in near surface facilities (volunteer site Saratov, Russia); mining and minerals processing waste - evaluation of long-term safety (volunteer site pmc S. Africa). An agreement on the scope and objectives of the project are reached and the further consideration, such as human intrusion/institutional control/security; waste from oil/gas industry; very low level waste; categorization of sealed sources coordinated with other IAEA activities are outlined

  15. Indigenous Healing and Seeking Safety: A Blended Implementation Project for Intergenerational Trauma and Substance Use Disorders

    Directory of Open Access Journals (Sweden)

    Teresa Naseba Marsh

    2016-06-01

    Full Text Available Background: As with many Indigenous groups around the world, Aboriginal communities in Canada face significant challenges with trauma and substance use disorders (SUD. Treatment for intergenerational trauma (IGT and SUD is challenging due to the complexity of both disorders. There is strong evidence that strengthening cultural identity, incorporating traditional healing practices, encouraging community integration, and inviting political empowerment can enhance and improve mental health and substance use disorders in Aboriginal populations. Methods: The purpose of this study was to explore whether the blending of Indigenous traditional healing practices and the Western treatment model Seeking Safety, which is used to treat post-traumatic stress disorder (PTSD and SUD, resulted in a reduction of IGT symptoms and SUD. Twelve Aboriginal men and 12 Aboriginal women were recruited into this study—all of whom resided in Northern Ontario and self-identified as having experienced IGT and SUD. The Indigenous Healing and Seeking Safety (IHSS group (conducted as sharing circles were offered twice a week over 13 weeks. Data was collected via semi-structured interviews as well as an end-of-treatment focus group. A qualitative thematic analysis was performed to depict themes. Results: Out of the 24 Aboriginal people who entered the program, nine women and eight men completed the program. Analysis from the qualitative thematic data identified four core themes. Furthermore, the sharing circles and the presence of Elders and Aboriginal helpers increased the benefits of the blended approach. Conclusion: Evidence from this qualitative study suggests that it could be beneficial to incorporate Indigenous traditional healing practices into Seeking Safety to enhance the health and well-being of Aboriginal people with IGT and SUD. This implementation project, if replicated, has the potential to enhance the health and well-being of Aboriginal peoples. The use of

  16. Project Gel a Randomized Rectal Microbicide Safety and Acceptability Study in Young Men and Transgender Women.

    Directory of Open Access Journals (Sweden)

    Ian McGowan

    Full Text Available The purpose of Project Gel was to determine the safety and acceptability of rectal microbicides in young men who have sex with men (MSM and transgender women (TGW at risk of HIV infection.MSM and TGW aged 18-30 years were enrolled at three sites; Pittsburgh, PA; Boston, MA; and San Juan, PR. Stage 1A was a cross-sectional assessment of sexual health and behavior in MSM and TGW. A subset of participants from Stage 1A were then enrolled in Stage 1B, a 12-week evaluation of the safety and acceptability of a placebo rectal gel. This was followed by the final phase of the study (Stage 2 in which a subset of participants from Stage 1B were enrolled into a Phase 1 rectal safety and acceptability evaluation of tenofovir (TFV 1% gel.248 participants were enrolled into Stage 1A. Participants' average age was 23.3 years. The most common sexually transmitted infection (STIs at baseline were Herpes simplex (HSV-2 (16.1% by serology and rectal Chlamydia trachomatis (CT (10.1% by NAAT. 134 participants were enrolled into Stage 1B. During the 12 week period of follow-up 2 HIV, 5 rectal CT, and 5 rectal Neisseria gonorrhea infections were detected. The majority of adverse events (AEs were infections (N = 56 or gastrointestinal (N = 46 and were mild (69.6% or moderate (28.0%. Of the participants who completed Stage 1B, 24 were enrolled into Stage 2 and randomized (1:1 to receive TFV or placebo gel. All participants completed Stage 2. The majority of AEs were gastrointestinal (N = 10 and of mild (87.2% or moderate (10.3% severity.In this study we were able to enroll a sexually active population of young MSM and TGW who were willing to use rectal microbicides. TFV gel was safe and acceptable and should be further developed as an alternative HIV prevention intervention for this population.ClinicalTrials.gov NCT01283360.

  17. 75 FR 53701 - Clinical Studies of Safety and Effectiveness of Orphan Products Research Project Grant (R01...

    Science.gov (United States)

    2010-09-01

    ... [Federal Register Volume 75, Number 169 (Wednesday, September 1, 2010)] [Notices] [Page 53701] [FR Doc No: 2010-21795] DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket No. FDA-2010-N-0394] Clinical Studies of Safety and Effectiveness of Orphan Products Research Project...

  18. Spent Nuclear Fuel (SNF) project Integrated Safety Management System phase I and II Verification Review Plan

    International Nuclear Information System (INIS)

    CARTER, R.P.

    1999-01-01

    The U.S. Department of Energy (DOE) commits to accomplishing its mission safely. To ensure this objective is met, DOE issued DOE P 450.4, Safety Management System Policy, and incorporated safety management into the DOE Acquisition Regulations ([DEAR] 48 CFR 970.5204-2 and 90.5204-78). Integrated Safety Management (ISM) requires contractors to integrate safety into management and work practices at all levels so that missions are achieved while protecting the public, the worker, and the environment. The contractor is required to describe the Integrated Safety Management System (ISMS) to be used to implement the safety performance objective

  19. Spent Nuclear Fuel (SNF) project Integrated Safety Management System phase I and II Verification Review Plan

    Energy Technology Data Exchange (ETDEWEB)

    CARTER, R.P.

    1999-11-19

    The U.S. Department of Energy (DOE) commits to accomplishing its mission safely. To ensure this objective is met, DOE issued DOE P 450.4, Safety Management System Policy, and incorporated safety management into the DOE Acquisition Regulations ([DEAR] 48 CFR 970.5204-2 and 90.5204-78). Integrated Safety Management (ISM) requires contractors to integrate safety into management and work practices at all levels so that missions are achieved while protecting the public, the worker, and the environment. The contractor is required to describe the Integrated Safety Management System (ISMS) to be used to implement the safety performance objective.

  20. Project SAFE. Update of the SFR-1 safety assessment. Phase 1. Appendix A1: Inventory

    International Nuclear Information System (INIS)

    Riggare, P.

    1998-01-01

    One of the aims in the safety assessment of SFR-1 is to estimate the release to the environment. In order to make these calculations there is a need to describe the inventory in greater detail. The new computerised database of waste in SFR-1 gives a good possibility to achieve this. The aim for project SAFE is to make both conservative and realistic radionuclide transport calculations. To achieve this goal there must be two inventories. The conservative inventory is the inventory used in the design of the repository, which in most parts is identical with the limits in the licence for SFR-1. There is a great interest to have good estimates of the volumes of the different waste types. A thorough prognosis should be made in 1999, but until then the latest one from 1995 could be used in the calculations. The total (actual) inventory of nuclides is calculated from the measurements of the easy-to-measure nuclides since, in principle, all hard-to-measure nuclides are calculated by correlation factors to 60 Co and 137 Cs . These factors should be reviewed since there are quite large uncertainties involved. 14 C dominates the individual doses after a few hundred years and the collective dose in the inland-scenario. The amount of the nuclide is uncertain since the correlation factor is very uncertain. The chemical speciation of 14 C is also of interest due to different properties of organic and inorganic carbon. 36 Cl is very hard to measure. Although the authorities in their reviews of the safety reports say that there probably are small doses from chlorine, the inventory should be improved. 59 Ni is a long-lived nuclide that sets a limit to the close-to-the-core metal scrap that can be taken to SFR- 1. There is an ongoing research project to provide a better measuring method for 59 Ni. This should make it possible to improve the knowledge about 59 Ni inventory. The assumption that 90 % of the inventory is collected in the ion-exchange resins should be checked. Actinides

  1. Practical guidelines for the registration and monitoring of serious traffic injuries, Deliverable 7.1 of the H2020 project SafetyCube (Safety CaUsation, Benefits and Efficiency).

    NARCIS (Netherlands)

    Pérez, K. Weijermars, W.A.M. Amoros, E. Bauer, R. Bos, N. Dupont, E. Filtness, A. Houwing, S. Johannsen, H. Leskovsek, B. Machata, K. Martin, JL. Nuyttens, N. Olabarria, M. Pascal, L. & Van den Berghe, W.

    2017-01-01

    Safety CaUsation, Benefits and Efficiency (SafetyCube) is a European Commission supported Horizon 2020 project. The project’s main objective is the development of an innovative road safety Decision Support System (DSS) that will enable policy-makers and stakeholders to select and implement the most

  2. Development of a harmonized approach to safety assessment of decommissioning: Lessons learned from international experience (DeSa project)

    International Nuclear Information System (INIS)

    Percival, K.; Nokhamzon, J.-G.; Ferch, R.; Batandjieva, B.

    2006-01-01

    The number of nuclear facilities being or planned to be shutdown as they reach the end of their design life, due to accidents or other political and social factors has been increasing worldwide. This has led to an increase in the awareness of regulators and operators of the importance of development and implementation of adequate safety requirements and criteria for decommissioning of these facilities. A general requirement at international and national levels, even for new facilities to be commissioned, is the development of a decommissioning plan, which includes evaluation of potential radiological consequences to public and workers during planned and accidental decommissioning activities. Experience has been gained in the safety assessment of decommissioning at various sites with different complexities and hazard potentials. This experience shows that various approaches have been used in conducting safety assessments and that there is a need for harmonisation of these approaches and for transferring the good practice and lessons learned to other countries, in particular developing countries with limited financial and human resources. The IAEA launched an international project on Evaluation and Demonstration of Safety during Decommissioning (DeSa) in 2004 to provide a forum for exchange of lessons learned between site operators, regulators, safety assessors and other specialists in safety assessment of decommissioning of nuclear power plants, research reactors, laboratories, nuclear fuel cycle facilities, etc. This paper presents the lessons learned through the project up to date, i.e.; (i) a common approach to safety assessment is being applied worldwide with the following steps - establishment of assessment framework; description of the facility; definition of decommissioning activities; hazard identification and analysis; calculation of consequences; and analysis of results; (ii) a deterministic approach to safety assessment is most commonly applied; (iii) a

  3. Connected commercial vehicles -- retrofit safety device kit project : data acquisition system (DAS) documentation.

    Science.gov (United States)

    Connected vehicle wireless data communications can enable safety applications that may reduce injuries and fatalities. Cooperative vehicle-to-vehicle (V2V) safety applications will be effective only if a high fraction of vehicles are equipped. Deploy...

  4. Modernization and safety improvement project of the NPP V-2 Jaslovske Bohunice

    International Nuclear Information System (INIS)

    Michal, V.; Losonsky, B.; Magdolen, J.

    2000-01-01

    This contribution deals with the form, present state, and results of the Nuclear Power Plants Research Institute (the Slovak acronym is VUJE - Vyskumny Ustav Jadrovych Elektrarni) participation in the NPP V-2 Jaslovske Bohunice Modernization and Safety Improvement Project. A short description of VUJE history, activity, and results is also presented as well as NPPs Jaslovske Bohunice characterization. VUJE was established in 1977 and deals with scientific and research needs of nuclear power plants, such as design, construction, commissioning and operation. The next fields of VUJE activity are, NPP reconstruction, NPP personnel training, radioactive waste management technology, and NPP decommissioning. The nuclear power plant, Jaslovske Bohunice, is situated approximately 15 km from the district town of Trnava in the southwestern region of the Slovak Republic. The construction of the first Czechoslovak NPP A-1 began on this site in 1957 .The construction of the double-unit NPP V-1 with WWER-440 (type V-230) reactor began in 1972. The first unit of NPP V-1 began operation in 1978 and the second in 1980. NPPs construction on the Bohunice site continued with NPP V-2, which has two units with WWER-440 (type V-213) reactors. Unit 1 and Unit 2 of NPP V-2 were commissioned in 1984 and 1985, respectively. Slovak electric utility Slovenske elektrarne (SE) is the owner/commissioner of NPP V-2. This NPP is responsible for more than 20% of the total electrical energy production of SE, making it an essential supporter of the Slovak economy. (authors)

  5. Selection of maximum design earthquake parameters for a dam safety project in British Columbia

    International Nuclear Information System (INIS)

    Smith, H.R.; Wightman, A.; Naumann, C.M.

    1991-01-01

    A study was carried out for the Greater Vancouver Water District to determine maximum design earthquake (MDE) parameters for dam safety projects. Three types of maximum credible earthquake (MCE) were investigated: a mega thrust earthquake (interplate event) of magnitude 9 on the Richter scale under the west coast of Vancouver Island; a magnitude 7.5 earthquake (intraplate event) under Georgia Straight at a depth of ca 60 km; and a local magnitude 6.5 shallow earthquake near the study site, on the north shore mountains near Vancouver. Conclusions of the study include the following. Strong motion records are recorded on three component accelerograms, and considering the individual components rather than the maximum ground motion can result in underestimation of seismic loading. It is recommended that the peak ground motions be defined by the envelope of the larger component, which would include peak ground acceleration, peak velocity and response spectra. The peak ground acceleration of the most critical earthquake, of magnitude 6.5 at 10 km, was estimated at 0.5 gravities. A variety of check methodologies yielded peak horizontal ground acceleration (PGA) ranging from 0.44 to 0.55 gravities. PGA values chosen for seismic analysis must consider duration and direction of peak as well as type of analysis, failure mode and material types. 9 refs., 10 figs., 2 tabs

  6. Project SAFE. Update of the SFR-1 safety assessment. Phase 1. Appendix A5: Radionuclide transport

    International Nuclear Information System (INIS)

    Moreno, L.

    1998-01-01

    A critical revision of the previous safety assessments made by SKB on the Final Repository for Radioactive Operational Waste, SFR is presented. The review of the Deepened Safety Assessment is also discussed. Based on this critical revision improvements are suggested. Hydrology, formation of complexes, and long-term behaviour of the barriers are some of the aspects where the safety assessment could be improved

  7. Inventory of Federal energy-related environment and safety research for FY 1979. Volume II. Project listings and indexes

    International Nuclear Information System (INIS)

    1980-12-01

    This volume contains summaries of FY 1979 government-sponsored environment and safety research related to energy arranged by log number, which groups the projects by reporting agency. The log number is a unique number assigned to each project from a block of numbers set aside for each contributing agency. Information elements included in the summary listings are project title, principal investigators, research organization, project number, contract number, supporting organization, funding level, related energy sources with numbers indicating percentages of effort devoted to each, and R and D categories. A brief description of each project is given, and this is followed by subject index terms that were assigned for computer searching and for generating the printed subject index in the back of this volume

  8. Inventory of Federal energy-related environment and safety research for FY 1979. Volume II. Project listings and indexes

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-12-01

    This volume contains summaries of FY 1979 government-sponsored environment and safety research related to energy arranged by log number, which groups the projects by reporting agency. The log number is a unique number assigned to each project from a block of numbers set aside for each contributing agency. Information elements included in the summary listings are project title, principal investigators, research organization, project number, contract number, supporting organization, funding level, related energy sources with numbers indicating percentages of effort devoted to each, and R and D categories. A brief description of each project is given, and this is followed by subject index terms that were assigned for computer searching and for generating the printed subject index in the back of this volume.

  9. Local police enforcement, public information and education strategies to foster more and proper use of child safety seats by toddlers : evaluation of a demonstration project

    Science.gov (United States)

    1994-03-01

    This project evaluated the effects of enforcing safety belt (SB)/child safety seat (CSS) laws and providing public information and education (PI&E) about the laws and use and proper use of CSSs--without external funding. Project goals focused on incr...

  10. Development of Occupational Safety and Health Requirement Management System (OSHREMS Software Using Adobe Dreamweaver CS5 for Building Construction Project

    Directory of Open Access Journals (Sweden)

    Abas Nor Haslinda

    2017-01-01

    Full Text Available The construction industry sector is considered as being risky with frequent and high accident rate. According to Social Security Organization (SOCSO, the construction accidents has arisen from time to time. Construction Industry Development Board (CIDB has developed the Safety and Health Assessment System in Construction (SHASSIC for evaluating the performance of a contractor in construction project by setting out the safety and health management and practices, however the requirement checklist provided is not comprehensive. Therefore, this study aims to develop a software system for facilitating OSH in building construction project, namely OSH requirements management system (OSHREMS, using Adobe Dreamweaver CS5 and Sublime Text as PHP editor. The results from a preliminary study which was conducted through interviews showed that, the respondents were only implementing the basic requirements that comply with legislations, with the absence of appropriate and specific guideline in ensuring occupational safety and health (OSH at the workplace. The tool will be benefits for contractors and other parties to effectively manage the OSH requirements for their projects based on project details.

  11. Marine radioecology. Final reports from sub-projects within the Nordic nuclear safety research project EKO-1

    International Nuclear Information System (INIS)

    Palsson, S.E.

    2001-04-01

    This report contains a collection of eight papers describing research done in the NKS/EKO-1 project. It also contains a preface giving a summary of the results. The EKO-1 project as a whole has been described in the report NKS(97)FR4. The aim of the project was to make a joint Nordic study on radionuclides in sediments and water and the interaction between these two phaseS. Relatively less emphasis had been put on this factor compared to others in previous Nordic studies on marine radioecology. For some of the participating countries this work was the first of its kind undertaken. The project involved field, laboratory and model studies. The work and results helped to highlight the important role of sediments when assessing the consequences of real or possible releases of radionuclides to the marine environment (au)

  12. Research projects into the safety of nuclear power plants. Period covered 01. July 2011 - 31. December 2011. Progress report

    International Nuclear Information System (INIS)

    2011-01-01

    The GRS research projects on the safety of nuclear power plants in the period 01. July 2011 - 31. December 2011 cover the following topics: (A) Joint safety research topics (European Commission): (1) Integrity and reliability: mechanical components, electrical and electronic components; (2) design basis accidents: reactor physics and fuel rod behavior, loss-of-coolant accidents; (3) severe accidents: core damage, hydrogen, steam explosion, corium behavior in the reactor pressure vessel (RPV) and the containment, fire; (4) fission products in the primary circuit and the containment, transport of aerosols and gases, fission product retention in the containment (spray systems, filters, etc.); (5) containment: concrete behavior in case of accidents; (6) risk analyses: probabilistic safety/risk analyses, human behavior, man-machine interaction, automation, computer application. (B) Reactor safety research topics: (1) component safety: component loads, materials load capacity, stress limits, non-destructive testing; (2) plant behavior and accident sequences: thermal hydraulics, efficiency of plant-internal emergency protection measures. New reactor concepts, reactor physics and fuel rod behavior, core damage processes in the RPV, corium in the containment, thermal hydraulics of the containment, hydrogen distribution in the containment atmosphere, combustion and counter measures, fission product behavior in the containment, probabilistic safety analyses, external impacts; (3) man-machine interaction, human behavior, man-machine interface, technical support systems, innovative reactor systems.

  13. Criticality Safety Lessons Learned in a Deactivation and Decommissioning Environment [A Guide for Facility and Project Managers

    Energy Technology Data Exchange (ETDEWEB)

    Nirider, L. Tom

    2003-08-06

    This document was designed as a reference and a primer for facility and project managers responsible for Deactivation and Decommissioning (D&D) processes in facilities containing significant inventories of fissionable materials. The document contains lessons learned and guidance for the development and management of criticality safety programs. It also contains information gleaned from occurrence reports, assessment reports, facility operations and management, NDA program reviews, criticality safety experts, and criticality safety evaluations. This information is designed to assist in the planning process and operational activities. Sufficient details are provided to allow the reader to understand the events, the lessons learned, and how to apply the information to present or planned D&D processes. Information is also provided on general lessons learned including criticality safety evaluations and criticality safety program requirements during D&D activities. The document also explores recent and past criticality accidents in operating facilities, and it extracts lessons learned pertinent to D&D activities. A reference section is included to provide additional information. This document does not address D&D lessons learned that are not pertinent to criticality safety.

  14. Seismic safety margins research program. Phase I final report - Major structure response (Project IV)

    International Nuclear Information System (INIS)

    Benda, B.J.; Johnson, J.J.; Lo, T.Y.

    1981-08-01

    The primary task of the Major Structure Response Project within the Seismic Safety Margins Research Program (SSMRP) was to develop detailed finite element models of the Zion Nuclear Power Plant's containment building and auxiliary-fuel-turbine (AFT) complex. The resulting models served as input to the seismic methodology analysis chain. The containment shell was modeled as a series of beam elements with the shear and bending characteristics of a circular cylindrical shell. Masses and rotary inertias were lumped at nodal points; thirteen modes were included in the analysis. The internal structure was modeled with three-dimensional finite elements, with masses again lumped at selected nodes; sixty modes were included in the analysis. The model of the AFT complex employed thin plate and shell elements to represent the concrete shear walls and floor diaphragms, and beam and truss elements to model the braced frames. Because of the size and complexity of the model, and the potentially large number of degrees of freedom, masses were lumped at a limited number of node points. These points were selected so as to minimize the effect of the discrete mass distribution on structural response. One hundred and thirteen modes were extracted. A second objective of Project IV was to investigate the effects of uncertainty and variability on structural response. To this end, four side studies were conducted. Three of them, briefly summarized in this volume, addressed themselves respectively to an investigation of sources of random variability in the dynamic response of nuclear power plant structures; formulation of a methodology for modeling and evaluating the effects of structural uncertainty on predicted modal characteristics of major nuclear power plant structures and substructures; and a preliminary evaluation of nonlinear responses in shear-wall structures. A fourth side study, reported in detail in this volume, quantified variations in dynamic characteristics and seismic

  15. Project JADE. Long-term function and safety. Comparison of repository systems

    International Nuclear Information System (INIS)

    Birgersson, Lars; Pers, K.; Wiborgh, M.

    2001-12-01

    A comparison of the KBS-3 V(ertical deposition), KBS-3 H(orizontal deposition) and MLH repository systems with regard to the long-term repository performance and the radionuclide migration is presented in the report. Several differences between the repository systems have been identified. The differences are mainly related to the: distance between canister and backfilled tunnels, excavated rock volumes, deposition hole direction. The overall conclusion is that the differences are in general quite small with regard to the repository function and safety. None of the differences are of such importance for the long-term repository performance and radionuclide migration that they discriminate any of the repository systems. The differences between the two KBS-3 systems are small. Based on this study, there is no reason to change from the reference system KBS-3 V to KBS-3 H. MLH has the potential to be a very robust system, especially in a long-term perspective. However, the MLH system will require extensive research, development, and analysis before it will be as confident as the reference repository system, KBS-3 V. Although the MLH and KBS-3 H systems are in some ways favourable compared to the reference system KBS-3 V, the overall conclusion is that the KBS-3 V system is still a very attractive system. A major advantage with KBS-3 V is that it is by far the most investigated and developed system. The JADE-project was initiated in 1996, and the main part of the study was carried out during 1997 and 1998. The JADE study is consequently based on presumptions that were valid a few years ago. Some of these presumptions have been modified since then. The new presumptions are however not judged to change the overall conclusions

  16. Project JADE. Long-term function and safety. Comparison of repository systems

    Energy Technology Data Exchange (ETDEWEB)

    Birgersson, Lars; Pers, K.; Wiborgh, M. [Kemakta Konsult AB, Stockholm (Sweden)

    2001-12-01

    A comparison of the KBS-3 V(ertical deposition), KBS-3 H(orizontal deposition) and MLH repository systems with regard to the long-term repository performance and the radionuclide migration is presented in the report. Several differences between the repository systems have been identified. The differences are mainly related to the: distance between canister and backfilled tunnels, excavated rock volumes, deposition hole direction. The overall conclusion is that the differences are in general quite small with regard to the repository function and safety. None of the differences are of such importance for the long-term repository performance and radionuclide migration that they discriminate any of the repository systems. The differences between the two KBS-3 systems are small. Based on this study, there is no reason to change from the reference system KBS-3 V to KBS-3 H. MLH has the potential to be a very robust system, especially in a long-term perspective. However, the MLH system will require extensive research, development, and analysis before it will be as confident as the reference repository system, KBS-3 V. Although the MLH and KBS-3 H systems are in some ways favourable compared to the reference system KBS-3 V, the overall conclusion is that the KBS-3 V system is still a very attractive system. A major advantage with KBS-3 V is that it is by far the most investigated and developed system. The JADE-project was initiated in 1996, and the main part of the study was carried out during 1997 and 1998. The JADE study is consequently based on presumptions that were valid a few years ago. Some of these presumptions have been modified since then. The new presumptions are however not judged to change the overall conclusions.

  17. Spent Nuclear Fuel Project path forward: nuclear safety equivalency to comparable NRC-licensed facilities

    Energy Technology Data Exchange (ETDEWEB)

    Garvin, L.J.

    1995-11-01

    This document includes the Technical requirements which meet the nuclear safety objectives of the NRC regulations for fuel treatment and storage facilities. These include requirements regarding radiation exposure limits, safety analysis, design and construction. This document also includes administrative requirements which meet the objectives of the major elements of the NRC licensing process. These include formally documented design and safety analysis, independent technical review, and oppportunity for public involvement.

  18. Spent Nuclear Fuel Project path forward: nuclear safety equivalency to comparable NRC-licensed facilities

    International Nuclear Information System (INIS)

    Garvin, L.J.

    1995-11-01

    This document includes the Technical requirements which meet the nuclear safety objectives of the NRC regulations for fuel treatment and storage facilities. These include requirements regarding radiation exposure limits, safety analysis, design and construction. This document also includes administrative requirements which meet the objectives of the major elements of the NRC licensing process. These include formally documented design and safety analysis, independent technical review, and oppportunity for public involvement

  19. Integrated Design and Analysis Environment for Safety Critical Human-Automation Systems Project

    Data.gov (United States)

    National Aeronautics and Space Administration — Flight deck systems, like many safety critical systems, often involve complex interactions between multiple human operators, automated subsystems, and physical...

  20. Development of a Web-based child safety education program for Busan Safe City WHO Certification Project.

    Science.gov (United States)

    Bae, Jeongyee; Panuncio, Rosel L; Sohn, Haesook

    2009-12-01

    As a nation that is tremendously affected by disaster- and injury-related deaths, Korea's second largest city, Busan, earnestly heeds World Health Organization's call for an international network of safe communities. As citizens of Busan dream of a safe city, officials are dedicating efforts in planning, developing and implementing sustainable programs aiming to reduce risk and promote safety awareness. The present article outlines the Busan Safe City Project and describes the development process of one of its programs, a Web-based safety education for children. Child safety remains a nationwide issue because in 2007, Korea ranked third in numbers of accident-related child deaths among the Organization for Economic Cooperation and Development countries. Future stages will involve program evaluation, revision and public release. This development process will guide other programs specific for other target populations. With everyone's help, the city continues to strive to be a healthy, safe, and dynamic Busan.

  1. Proposal of a risk-factor-based analytical approach for integrating occupational health and safety into project risk evaluation.

    Science.gov (United States)

    Badri, Adel; Nadeau, Sylvie; Gbodossou, André

    2012-09-01

    Excluding occupational health and safety (OHS) from project management is no longer acceptable. Numerous industrial accidents have exposed the ineffectiveness of conventional risk evaluation methods as well as negligence of risk factors having major impact on the health and safety of workers and nearby residents. Lack of reliable and complete evaluations from the beginning of a project generates bad decisions that could end up threatening the very existence of an organization. This article supports a systematic approach to the evaluation of OHS risks and proposes a new procedure based on the number of risk factors identified and their relative significance. A new concept called risk factor concentration along with weighting of risk factor categories as contributors to undesirable events are used in the analytical hierarchy process multi-criteria comparison model with Expert Choice(©) software. A case study is used to illustrate the various steps of the risk evaluation approach and the quick and simple integration of OHS at an early stage of a project. The approach allows continual reassessment of criteria over the course of the project or when new data are acquired. It was thus possible to differentiate the OHS risks from the risk of drop in quality in the case of the factory expansion project. Copyright © 2011 Elsevier Ltd. All rights reserved.

  2. Dynamite warehouse safety management system for the second stage project of Ling'ao nuclear power plant

    International Nuclear Information System (INIS)

    Tong Jiansheng

    2007-01-01

    A large amount of dynamite is stored for the second stage project of Ling'ao Nuclear Power Plant, which is applied to negative digging and provides broken stones by blasting in the project construction. The monitoring system is improved to obtain a higher safety level of the dynamite warehouse. The improved system is a combination of computer net, advanced communication, and modern control techniques, with electronic detection, current software, image processing and video display. The system integrates information, communication, control and command, with information and resources shared, therefore, unified command and dispatch can be carried out. Practice shows that the system is high-effective, intelligent, and multi-dimensional. (author)

  3. 13. status report of the project HDR safety program of Kernforschungszentrum Karlsruhe. Working report 05.46/89

    International Nuclear Information System (INIS)

    Katzenmeier, G.

    1989-01-01

    The programme phase III, which extends to the end of 1991, is divided into the part projects containment behaviour in extreme accidents, long-term damage and monitoring the components in operation, behaviour of damaged components in dynamic accidents and large fires of actual materials. The main aims, state of the HDR safety programme, main points of the programme for 1990 and 8 technical reports on phase II and III are documented. There is a survey of costs. (DG) [de

  4. 76 FR 37815 - Cooperative Agreement To Support Shellfish Safety Assistance Project

    Science.gov (United States)

    2011-06-28

    ... Nutrition (CFSAN), Office of Food Safety is announcing its intent to award a single source cooperative... Safety and Applied Nutrition (HFS-325), Food and Drug Administration, 5100 Paint Branch Pkwy., College.... vulnificus control plan; 11. In conjunction with FDA, conduct of retail and processing plant product sampling...

  5. MULTI-AGENT MODEL OF SAFETY MANAGEMENT IN PLANNING PROJECTS FOR THE CREATION OF OBJECTS WITH MASS STAY OF PEOPLE

    Directory of Open Access Journals (Sweden)

    Олег Богданович ЗАЧКО

    2017-03-01

    Full Text Available In today's conditions, with increasing of the scale of industrialization the Ukraine's major cities, also increases the threat of emergency situations (ES, disasters and accidents at the objects with the mass stay of people (OMSP. Inadequate level of paying attention to the exploitation of OMSP at all stages of the project lifecycle gives its tangible negative consequences. The analysis of statistics for the last 5-10 years has shown the significant growth of dynamics of mortality after emergencies on enterprises, which shows that in most cases the cause of these deaths is the lack of strict management consistency across all hierarchy management structure that is the project-oriented management, ignorance the rules of fire safety at the workplace, lack of automatic fire alarm systems and alarm systems and extinguishing, especially in the regional context. Therefore, the definition of the concept of objects with the mass stay of people using safety-oriented approach will allow them to identify and ultimately increase security at such objectsIn the article the literary analysis of the available scientific studies. Developed multi-agent safety management model in planning projects for the creation of objects with the mass stay of people.

  6. SAFETY

    CERN Multimedia

    C. Schaefer and N. Dupont

    2013-01-01

      “Safety is the highest priority”: this statement from CERN is endorsed by the CMS management. An interpretation of this statement may bring you to the conclusion that you should stop working in order to avoid risks. If the safety is the priority, work is not! This would be a misunderstanding and misinterpretation. One should understand that “working safely” or “operating safely” is the priority at CERN. CERN personnel are exposed to different hazards on many levels on a daily basis. However, risk analyses and assessments are done in order to limit the number and the gravity of accidents. For example, this process takes place each time you cross the road. The hazard is the moving vehicle, the stake is you and the risk might be the risk of collision between both. The same principle has to be applied during our daily work. In particular, keeping in mind the general principles of prevention defined in the late 1980s. These principles wer...

  7. SAFETY

    CERN Multimedia

    M. Plagge, C. Schaefer and N. Dupont

    2013-01-01

    Fire Safety – Essential for a particle detector The CMS detector is a marvel of high technology, one of the most precise particle measurement devices we have built until now. Of course it has to be protected from external and internal incidents like the ones that can occur from fires. Due to the fire load, the permanent availability of oxygen and the presence of various ignition sources mostly based on electricity this has to be addressed. Starting from the beam pipe towards the magnet coil, the detector is protected by flooding it with pure gaseous nitrogen during operation. The outer shell of CMS, namely the yoke and the muon chambers are then covered by an emergency inertion system also based on nitrogen. To ensure maximum fire safety, all materials used comply with the CERN regulations IS 23 and IS 41 with only a few exceptions. Every piece of the 30-tonne polyethylene shielding is high-density material, borated, boxed within steel and coated with intumescent (a paint that creates a thick co...

  8. CSNI collective statement on support facilities for existing and advanced reactors. The function of OECD/Nea joint projects Nea committee on the safety of nuclear installations (CSNI)

    International Nuclear Information System (INIS)

    2008-01-01

    The NEA Committee on the Safety of Nuclear Installations (CSNI) has recently completed a study on the availability and utilisation of facilities supporting safety studies for current and advanced nuclear power reactors. The study showed that significant steps had been undertaken in the past several years in support of safety test facilities, mainly by conducting multinational joint projects centered on the capability of unique test facilities worldwide. Given the positive experience of the safety research projects, it has been recommended that efforts be made to prioritize technical issues associated with advanced (Generation IV) reactor designs and to develop options on how to efficiently obtain the necessary data through internationally co-ordinated research, preparing a gradual extension of safety research beyond the needs set by currently operating reactors. This statement constitutes a reference for future CSNI activities and for safety authorities, R and D centres and industry for internationally co-ordinated research initiatives in the nuclear safety research area. (author)

  9. Operational safety of geological disposal: IRSN project 'EXREV' for developing a safety assessment strategy for the operation and reversibility of a geological repository

    International Nuclear Information System (INIS)

    Tichauer, M.; Pellegrini, D.; Serres, C.; Besnus, F.

    2014-01-01

    A high-level waste geological disposal facility is envisioned by the legislator in the French Planning Act no. 2006-739 of 28 June 2006. This act sets major milestones for the operator (Andra) in 2013 (public debate), 2015 (licensing) and 2025 (operation). In the framework of the regulatory review process, IRSN's mission is to conduct an assessment of the safety case provided by Andra at every stage of the process for the French regulator, namely the Nuclear Safety Authority (ASN). In 2005, IRSN gathered more than twenty years of research and expertise in order to provide a comprehensive appraisal of the 'Dossier 2005' prepared by Andra, related to the feasibility of a geological disposal in the Callovo-Oxfordian clay formation. At this time, the description of the operational phase was only at a preliminary stage, but this step paved the way for developing an assessment strategy of the operational phase. In this perspective, IRSN set up the EXREV project in 2008 in order to build up a doctrine and to identify key safety issues to be dealt with. (authors)

  10. Growth and Expansion of the International Criticality Safety Benchmark Evaluation Project and the Newly Organized International Reactor Physics Experiment Evaluation Project

    Energy Technology Data Exchange (ETDEWEB)

    J. Blair Briggs; Lori Scott; Yolanda Rugama; Enrico Satori

    2007-05-01

    Since ICNC 2003, the International Criticality Safety Benchmark Evaluation Project (ICSBEP) has continued to expand its efforts and broaden its scope. Criticality-alarm / shielding type benchmarks and fundamental physics measurements that are relevant to criticality safety applications are not only included in the scope of the project, but benchmark data are also included in the latest version of the handbook. A considerable number of improvements have been made to the searchable database, DICE and the criticality-alarm / shielding benchmarks and fundamental physics measurements have been included in the database. There were 12 countries participating on the ICSBEP in 2003. That number has increased to 18 with recent contributions of data and/or resources from Brazil, Czech Republic, Poland, India, Canada, and China. South Africa, Germany, Argentina, and Australia have been invited to participate. Since ICNC 2003, the contents of the “International Handbook of Evaluated Criticality Safety Benchmark Experiments” have increased from 350 evaluations (28,000 pages) containing benchmark specifications for 3070 critical or subcritical configurations to 442 evaluations (over 38,000 pages) containing benchmark specifications for 3957 critical or subcritical configurations, 23 criticality-alarm-placement / shielding configurations with multiple dose points for each, and 20 configurations that have been categorized as fundamental physics measurements that are relevant to criticality safety applications in the 2006 Edition of the ICSBEP Handbook. Approximately 30 new evaluations and 250 additional configurations are expected to be added to the 2007 Edition of the Handbook. Since ICNC 2003, a reactor physics counterpart to the ICSBEP, The International Reactor Physics Experiment Evaluation Project (IRPhEP) was initiated. Beginning in 1999, the IRPhEP was conducted as a pilot activity by the by the Organization of Economic Cooperation and Development (OECD) Nuclear Energy

  11. Growth and Expansion of the International Criticality Safety Benchmark Evaluation Project and the Newly Organized International Reactor Physics Experiment Evaluation Project

    International Nuclear Information System (INIS)

    J. Blair Briggs; Lori Scott; Yolanda Rugama; Enrico Satori

    2007-01-01

    Since ICNC 2003, the International Criticality Safety Benchmark Evaluation Project (ICSBEP) has continued to expand its efforts and broaden its scope. Criticality-alarm/shielding type benchmarks and fundamental physics measurements that are relevant to criticality safety applications are not only included in the scope of the project, but benchmark data are also included in the latest version of the handbook. A considerable number of improvements have been made to the searchable database, DICE and the criticality-alarm/shielding benchmarks and fundamental physics measurements have been included in the database. There were 12 countries participating on the ICSBEP in 2003. That number has increased to 18 with recent contributions of data and/or resources from Brazil, Czech Republic, Poland, India, Canada, and China. South Africa, Germany, Argentina, and Australia have been invited to participate. Since ICNC 2003, the contents of the ''International Handbook of Evaluated Criticality Safety Benchmark Experiments'' have increased from 350 evaluations (28,000 pages) containing benchmark specifications for 3070 critical or subcritical configurations to 442 evaluations (over 38,000 pages) containing benchmark specifications for 3957 critical or subcritical configurations, 23 criticality-alarm-placement/shielding configurations with multiple dose points for each, and 20 configurations that have been categorized as fundamental physics measurements that are relevant to criticality safety applications in the 2006 Edition of the ICSBEP Handbook. Approximately 30 new evaluations and 250 additional configurations are expected to be added to the 2007 Edition of the Handbook. Since ICNC 2003, a reactor physics counterpart to the ICSBEP, The International Reactor Physics Experiment Evaluation Project (IRPhEP) was initiated. Beginning in 1999, the IRPhEP was conducted as a pilot activity by the by the Organization of Economic Cooperation and Development (OECD) Nuclear Energy Agency

  12. Spent nuclear fuel project cold vacuum drying facility safety equipment list

    Energy Technology Data Exchange (ETDEWEB)

    IRWIN, J.J.

    1999-02-24

    This document provides the safety equipment list (SEL) for the Cold Vacuum Drying Facility (CVDF). The SEL was prepared in accordance with the procedure for safety structures, systems, and components (SSCs) in HNF-PRO-516, ''Safety Structures, Systems, and Components,'' Revision 0 and HNF-PRO-097, Engineering Design and Evaluation, Revision 0. The SEL was developed in conjunction with HNF-SO-SNF-SAR-O02, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998). The SEL identifies the SSCs and their safety functions, the design basis accidents for which they are required to perform, the design criteria, codes and standards, and quality assurance requirements that are required for establishing the safety design basis of the SSCs. This SEL has been developed for the CVDF Phase 2 Safety Analysis Report (SAR) and shall be updated, expanded, and revised in accordance with future phases of the CVDF SAR until the CVDF final SAR is approved.

  13. Spent nuclear fuel project cold vacuum drying facility safety equipment list

    International Nuclear Information System (INIS)

    IRWIN, J.J.

    1999-01-01

    This document provides the safety equipment list (SEL) for the Cold Vacuum Drying Facility (CVDF). The SEL was prepared in accordance with the procedure for safety structures, systems, and components (SSCs) in HNF-PRO-516, ''Safety Structures, Systems, and Components,'' Revision 0 and HNF-PRO-097, Engineering Design and Evaluation, Revision 0. The SEL was developed in conjunction with HNF-SO-SNF-SAR-O02, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998). The SEL identifies the SSCs and their safety functions, the design basis accidents for which they are required to perform, the design criteria, codes and standards, and quality assurance requirements that are required for establishing the safety design basis of the SSCs. This SEL has been developed for the CVDF Phase 2 Safety Analysis Report (SAR) and shall be updated, expanded, and revised in accordance with future phases of the CVDF SAR until the CVDF final SAR is approved

  14. The engineering project and reliability research of the safety interlock slow control system in BESIII

    International Nuclear Information System (INIS)

    Zhang Yinhong; Zhao Jingwei; Li Xiaonan; Xie Xiaoxi; Gao Cuishan; Bai Jingzhi; Chen Xihui; Min Jian; Nie Zhendong

    2008-01-01

    The new safety interlock slow control system of BESIII is designed to ensure that the BESIII interior equipments and the accelerator control center to work in coordination, and to guarantee the safety of the operating staff and all the important equipments at the same time. This paper introduces the hardware and software design of safety interlock system from the engineering requirements angle, including a detailed research on the software implementation technique of the state machine on PLC and the reliability of the system. (authors)

  15. Final report of the 'Nordic thermal-hydraulic and safety network (NOTNET)' - Project

    Energy Technology Data Exchange (ETDEWEB)

    Tuunanen, J.; Tuomainen, M. [VTT Processes (Finland)

    2005-04-01

    A Nordic network for thermal-hydraulics and nuclear safety research was started. The idea of the network is to combine the resources of different research teams in order to carry out more ambitious and extensive research programs than would be possible for the individual teams. From the very beginning, the end users of the research results have been integrated to the network. Aim of the network is to benefit the partners involved in nuclear energy in the Nordic Countries (power companies, reactor vendors, safety regulators, research units). First task within the project was to describe the resources (personnel, know-how, simulation tools, test facilities) of the various teams. Next step was to discuss with the end users about their research needs. Based on these steps, few most important research topics with defined goals were selected, and coarse road maps were prepared for reaching the targets. These road maps will be used as a starting point for planning the actual research projects in the future. The organisation and work plan for the network were established. National coordinators were appointed, as well as contact persons in each participating organisation, whether research unit or end user. This organisation scheme is valid for the short-term operation of NOTNET when only Nordic organisations take part in the work. Later on, it is possible to enlarge the network e.g. within EC framework programme. The network can now start preparing project proposals and searching funding for the first common research projects. (au)

  16. Prevalence of hypercalcemia of malignancy among cancer patients in the UK: analysis of the Clinical Practice Research Datalink database.

    Science.gov (United States)

    Jick, Susan; Li, Lin; Gastanaga, Victor M; Liede, Alexander

    2015-12-01

    The reported proportion of cancer patients who experience hypercalcemia of malignancy (HCM) ranges between 3% and 30%. HCM can be observed with any type of tumor and occurs most commonly in lung cancer, breast cancer and multiple myeloma. While HCM is a potentially fatal condition, the prevalence of HCM is not well defined. Using the United Kingdom Clinical Practice Research Datalink, we identified adult cancer patients with recorded corrected serum calcium (CSC). Hypercalcemic patients (CSC ≥ 10.8 mg/dL) were classified into 4 CSC levels. We estimated annual prevalence of HCM overall, stratified by cancer type, and in patients with stage IV cancer. Among 37,442 cancer patients in 2003-2012 the prevalence of grade 1 HCM increased from 0.13% to 0.45% and the prevalence of HCM overall (grade 1 or higher) increased from 0.20% to 0.67% over the study period. Prevalence estimates varied across cancer type and were highest for lung cancer, multiple myeloma and patients with stage IV cancer. We provide the first systematic analysis using a UK population-based data source to estimate number of cancer patients affected with HCM by grade. The increase in HCM prevalence over the 10-year study period is likely due to the increased recording of laboratory values, particularly comparing more recent data to 2003. Our findings suggest that HCM in general is not a common condition. Copyright © 2015 Elsevier Ltd. All rights reserved.

  17. Which Patients with Giant Cell Arteritis Will Develop Cardiovascular or Cerebrovascular Disease? A Clinical Practice Research Datalink Study.

    Science.gov (United States)

    Robson, Joanna C; Kiran, Amit; Maskell, Joe; Hutchings, Andrew; Arden, Nigel; Dasgupta, Bhaskar; Hamilton, William; Emin, Akan; Culliford, David; Luqmani, Raashid

    2016-06-01

    To evaluate the risk of cerebrovascular disease and cardiovascular disease (CVD) in patients with giant cell arteritis (GCA), and to identify predictors. The UK Clinical Practice Research Datalink 1991-2010 was used for a parallel cohort study of 5827 patients with GCA and 37,090 age-, sex-, and location-matched controls. A multivariable competing risk model (non-cerebrovascular/CV-related death as the competing risk) determined the relative risk [subhazard ratio (SHR)] between patients with GCA compared with background controls for cerebrovascular disease, CVD, or either. Each cohort (GCA and controls) was then analyzed individually using the same multivariable model, with age and sex now present, to identify predictors of CVD or cerebrovascular disease. Patients with GCA, compared with controls, had an increased risk SHR (95% CI) of cerebrovascular disease (1.45, 1.31-1.60), CVD (1.49, 1.37-1.62), or either (1.47, 1.37-1.57). In the GCA cohort, predictors of "cerebrovascular disease or CVD" included increasing age, > 80 years versus cerebrovascular disease or CVD than age-, sex-, and location-matched controls. In common with the non-GCA cohort, patients who are older, male, and from the most deprived compared with least deprived areas have a higher risk of cerebrovascular disease or CVD. Further work is needed to understand how this risk may be mediated by specific behavioral, social, and economic factors.

  18. Replacement cross-site transfer system project W-058 safety class upgrade summary report

    International Nuclear Information System (INIS)

    Schlosser, R.L.

    1998-01-01

    This report evaluates the design of the replacement cross-site transfer system structures, systems, and components for safety related applications as defined in the Tank Waste Remediation Systems Basis for Interim Operations

  19. Extended occupant safety through virtual testing: objectives of the European project VITES

    NARCIS (Netherlands)

    Hoof, J.F.A.M. van; Happee, R.; Baldauf, H.; Puppini, R.; Oakley, C.

    2001-01-01

    Increasingly stringent international passenger safety norms and the need to reduce vehicle body weight for environmental and protection requirements demand efficient and innovative design methods. Computer simulation, or virtual testing, allows an integrated evaluation of these aspects in the early

  20. Agent-Based Simulation and Assessment of NAS Security and Safety Project

    Data.gov (United States)

    National Aeronautics and Space Administration — The key innovation proposed here is the use of agent-based modeling and simulation to evaluate the safety of the National Airspace under crisis operations and...

  1. Project #10404 - Scoping Study for Implementation of the Highway Safety Manual in Alabama

    Science.gov (United States)

    2012-08-01

    This report outlines a cost-effective and thoughtful way to implement the Highway Safety Manual (HSM) in Alabama. The HSM was published by the American Association of State Highway and Transportation Officials, and it was prepared by the Transportati...

  2. RISMC advanced safety analysis project plan: FY2015 - FY2019. Light Water Reactor Sustainability Program

    International Nuclear Information System (INIS)

    Szilard, Ronaldo H; Smith, Curtis L; Youngblood, Robert

    2014-01-01

    In this report, the Advanced Safety Analysis Program (ASAP) objectives and value proposition is described. ASAP focuses on modernization of nuclear power safety analysis (tools, methods and data); implementing state-of-the-art modeling techniques (which include, for example, enabling incorporation of more detailed physics as they become available); taking advantage of modern computing hardware; and combining probabilistic and mechanistic analyses to enable a risk informed safety analysis process. The modernized tools will maintain the current high level of safety in our nuclear power plant fleet, while providing an improved understanding of safety margins and the critical parameters that affect them. Thus, the set of tools will provide information to inform decisions on plant modifications, refurbishments, and surveillance programs, while improving economics. The set of tools will also benefit the design of new reactors, enhancing safety per unit cost of a nuclear plant. As part of the discussion, we have identified three sets of stakeholders, the nuclear industry, the Department of Energy (DOE), and associated oversight organizations. These three groups would benefit from ASAP in different ways. For example, within the DOE complex, the possible applications that are seen include the safety of experimental reactors, facility life extension, safety-by-design in future generation advanced reactors, and managing security for the storage of nuclear material. This report provides information in five areas: (1) A value proposition (@@@why is this important?@@@) that will make the case for stakeholder's use of the ASAP research and development (R&D) products; (2) An identification of likely end users and pathway to adoption of enhanced tools by the end-users; (3) A proposed set of practical and achievable @@use case@@@ demonstrations; (4) A proposed plan to address ASAP verification and validation (V&V) needs; and (5) A proposed schedule for the multi-year ASAP.

  3. Karlsruhe Research Center, Nuclear Safety Research Project (PSF). Annual report 1994

    International Nuclear Information System (INIS)

    Hueper, R.

    1995-08-01

    The reactor safety R and D work of the Karlsruhe Research Centre (FZKA) has been part of the Nuclear Safety Research Projet (PSF) since 1990. The present annual report 1994 summarizes the R and D results. The research tasks are coordinated in agreement with internal and external working groups. The contributions to this report correspond to the status of early 1995. An abstract in English precedes each of them, whenever the respective article is written in German. (orig.) [de

  4. Environmental restoration contractor facility safety plan -- MO-561 100-D site remediation project

    International Nuclear Information System (INIS)

    Donahoe, R.L.

    1996-11-01

    This safety plan is applicable to Environmental Restoration Contractor personnel who are permanently assigned to MO-561 or regularly work in the facility. The MO-561 Facility is located in the 100-D Area at the Hanford Site in Richland, Washington. This plan will: (a) identify hazards potentially to be encountered by occupants of MO-561; (b) provide requirements and safeguards to ensure personnel safety and regulatory compliance; (c) provide information and actions necessary for proper emergency response

  5. Specific safety measures for emergency lanes and shoulders of motorways : a proposal for motorways' authorities in the framework of the European research project Safety Standards for Road Design and Redesign SAFESTAR, Workpackage 1.1.

    NARCIS (Netherlands)

    Braimaister, L.

    1999-01-01

    This workpackage is one of seven workpackages of the European SAFESTAR project, launched by DG VII. Directing on safety standards and recommendations for the Trans-European Roadway Network (TERN), the workpackage considered safety measures on emergency lanes (stopping strips), which are inherent

  6. Evaluating ambulatory practice safety: the PROMISES project administrators and practice staff surveys.

    Science.gov (United States)

    Singer, Sara J; Reyes Nieva, Harry; Brede, Namara; Ling, Judy; Leydon, Nicholas; Weissman, Joel S; Goldmann, Don; Griswold, Paula; Yoon, Catherine; Orav, E John; Bates, David W; Biondolillo, Madeleine; Schiff, Gordon D

    2015-02-01

    Ambulatory practices deliver most health care services and contribute to malpractice risk. Yet, policymakers and practitioners often lack information about safety and malpractice risk needed to guide improvement. To assess staff and administrator perceptions of safety and malpractice risk in ambulatory settings. We administered surveys in small-sized to medium-sized primary care practices in Massachusetts as part of a randomized controlled trial to reduce ambulatory malpractice risk. Twenty-five office practice managers/administrators and 482 staff, including [physicians, physician assistants, and nurse practitioners (MD/PA/NPs)], nurses, other clinicians, managers, and administrators. Surveys included structured questions about 3 high-risk clinical domains: referral, test result, and medication management, plus communication with patients and among staff. The 30-item administrator survey evaluated the presence of organizational safety structures and processes; the 63-item staff survey queried safety and communication concerns. Twenty-two administrators (88%) and 292 staff (61%) responded. Administrators frequently reported important safety systems and processes were absent. Suboptimal or incomplete implementation of referral and test result management systems related to staff perceptions of their quality (Pmanagement system safety, talking openly about safety problems, willingness to report mistakes, and feeling rushed. MD/PA/NPs viewed high-risk system reliability more negatively (P<0.0001) and teamwork more positively (P<0.03) than others. Results show opportunities for improvement in closing informational loops and establishing more reliable systems and environments where staff feels respected and safe speaking up. Initiatives to transform primary care should emphasize improving communication among facilities and practitioners.

  7. The funding of dangerous nuclear projects. Nuclear trade and safety: the role of French private banks. What are we talking about?

    International Nuclear Information System (INIS)

    Philippe, Isabelle

    2011-01-01

    Countries which export nuclear technologies, notably France, have developed mechanisms of financial support to incite private banks to finance the sale of reactors to foreign countries, notably EPRs in the case of France. After having briefly introduced this issue, and dealing with the French case, this publication indicates the concerned banks, and outlines that some of them finance nuclear projects which have been assessed by NGOs as dangerous in terms of nuclear safety. It notably presents the Angra 3 project in Brazil: its cost, its planning, its main safety problems (obsolete technology, building authorization awarded without any actual safety analysis, situation of conflict of interest for the Brazilian regulator). It also presents the Jaitapur project in India in which Areva is as well involved: costs, funding, planning, main risks (seismic risk area, safety level much lower than the one required in France, controversy on the impact study). The document finally explains why banks must not fund nuclear projects

  8. Ferrocyanide safety project: Task 3. 5 cyanide species analytical methods development

    Energy Technology Data Exchange (ETDEWEB)

    Bryan, S.A.; Pool, K.H.; Burger, L.L.; Carlson, C.D.; Hess, N.J.; Matheson, J.D.; Ryan, J.L.; Scheele, R.D.; Tingey, J.M.

    1993-01-01

    This report summarizes the results of studies conducted in FY 1992 to develop methods for the identification and quantification of cyanide species in ferrocyanide tank waste. Currently there are 24 high-level waste storage tanks at the Hanford Site that have been placed on a Ferrocyanide Tank Watchlist because they contain an estimated 1,000 g-moles or greater amount of precipitated ferrocyanide. This amount of ferrocyanide is of concern because the consequences of a potential explosion may exceed those reported previously in safety analyses. The threshold concentration of total cyanide within the tank waste matrix that is expected to be a safety concern is estimated at approximately 1 to 3 wt%. Methods for detection and speciation of ferrocyanide complexes in actual waste are needed to definitively measure and quantitate the amount of ferrocyanides present within actual waste tanks to a lower limit of at least 0.1 wt% in order to bound the safety concern.

  9. Ferrocyanide safety project: Task 3.5 cyanide species analytical methods development. FY 1992 annual report

    Energy Technology Data Exchange (ETDEWEB)

    Bryan, S.A.; Pool, K.H.; Burger, L.L.; Carlson, C.D.; Hess, N.J.; Matheson, J.D.; Ryan, J.L.; Scheele, R.D.; Tingey, J.M.

    1993-01-01

    This report summarizes the results of studies conducted in FY 1992 to develop methods for the identification and quantification of cyanide species in ferrocyanide tank waste. Currently there are 24 high-level waste storage tanks at the Hanford Site that have been placed on a Ferrocyanide Tank Watchlist because they contain an estimated 1,000 g-moles or greater amount of precipitated ferrocyanide. This amount of ferrocyanide is of concern because the consequences of a potential explosion may exceed those reported previously in safety analyses. The threshold concentration of total cyanide within the tank waste matrix that is expected to be a safety concern is estimated at approximately 1 to 3 wt%. Methods for detection and speciation of ferrocyanide complexes in actual waste are needed to definitively measure and quantitate the amount of ferrocyanides present within actual waste tanks to a lower limit of at least 0.1 wt% in order to bound the safety concern.

  10. Seismic Safety Margins Research Program Phase I final report: fragilities development (Project VI)

    International Nuclear Information System (INIS)

    Bohn, M.P.; Cover, L.E.; Dong, R.G.; Vagliente, V.N.; Campbell, R.D.; Wesley, D.A.

    1982-12-01

    The Seismic Safety Margins Research Program is an NRC-funded program directed towards estimating the conservatism in the NRC Standard Review Plan seismic safety requirements with the ultimate goal of developing improved requirements. As part of this program, calculations of the seismic risk from a typical commercial nuclear reactor are being made. These calculations require 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 have been developed to apply to generic categories of components

  11. Waste Tank Organic Safety Project: Analysis of liquid samples from Hanford waste tank 241-C-103

    International Nuclear Information System (INIS)

    Pool, K.H.; Bean, R.M.

    1994-03-01

    A suite of physical and chemical analyses has been performed in support of activities directed toward the resolution of an Unreviewed Safety Question concerning the potential for a floating organic layer in Hanford waste tank 241-C-103 to sustain a pool fire. The analysis program was the result of a Data Quality Objectives exercise conducted jointly with staff from Westinghouse Hanford Company and Pacific Northwest Laboratory (PNL). The organic layer has been analyzed for flash point, organic composition including volatile organics, inorganic anions and cations, radionuclides, and other physical and chemical parameters needed for a safety assessment leading to the resolution of the Unreviewed Safety Question. The aqueous layer underlying the floating organic material was also analyzed for inorganic, organic, and radionuclide composition, as well as other physical and chemical properties. This work was conducted to PNL Quality Assurance impact level III standards (Good Laboratory Practices)

  12. Projective goals - concepts and pragmatic aspects based on the terminology and methodology of safety science

    International Nuclear Information System (INIS)

    Compes, P.C.

    1991-01-01

    Protective goals set the line of orientation of tasks and activities in the field of accident prevention. They have to be based on safety-science methods in order to develop from the conceptual idea to the practically feasible solution, while using the scientific methods to take into account the facts and the capabilities of a situation and, proceeding from them, finding an efficient and rational, optimal pragmatic approach by way of various strategies or tactics. In this process, the activities of defining, informing, thinking and developing need the proper terminology. Safety is absence of danger, protection is limitation of danger and prevention of damage. So it is protection what is needed with danger being given, and risks have to be minimized. Riskology is a novel method of safety science, combining risk analysis and risk control into a systematic concept which is practice-oriented. Applying this to the field of nuclear engineering, the hitherto achieved should receive new impulses. (orig.) [de

  13. Ferrocyanide safety project: Task 3.5 cyanide species analytical methods development

    International Nuclear Information System (INIS)

    Bryan, S.A.; Pool, K.H.; Burger, L.L.; Carlson, C.D.; Hess, N.J.; Matheson, J.D.; Ryan, J.L.; Scheele, R.D.; Tingey, J.M.

    1993-01-01

    This report summarizes the results of studies conducted in FY 1992 to develop methods for the identification and quantification of cyanide species in ferrocyanide tank waste. Currently there are 24 high-level waste storage tanks at the Hanford Site that have been placed on a Ferrocyanide Tank Watchlist because they contain an estimated 1,000 g-moles or greater amount of precipitated ferrocyanide. This amount of ferrocyanide is of concern because the consequences of a potential explosion may exceed those reported previously in safety analyses. The threshold concentration of total cyanide within the tank waste matrix that is expected to be a safety concern is estimated at approximately 1 to 3 wt%. Methods for detection and speciation of ferrocyanide complexes in actual waste are needed to definitively measure and quantitate the amount of ferrocyanides present within actual waste tanks to a lower limit of at least 0.1 wt% in order to bound the safety concern

  14. Systems Engineering Management Plan for Tank Farm Restoration and Safety Operations, Project W-314

    International Nuclear Information System (INIS)

    MCGREW, D.L.

    2000-01-01

    The Systems Engineering Management Plan for Project W-314 has been prepared within the guidelines of HNF-SD-WM-SEMP-002, TWRS Systems Engineering Management Plan. The activities within this SEMP have been tailored, in accordance with the TWRS SEMP and DOE Order 430.1, Life Cycle Asset Management, to meet the needs of the project

  15. Seismic Safety Margins Research Program. Phase 1. Project V. Structural sub-system response: subsystem response review

    International Nuclear Information System (INIS)

    Fogelquist, J.; Kaul, M.K.; Koppe, R.; Tagart, S.W. Jr.; Thailer, H.; Uffer, R.

    1980-03-01

    This project is directed toward a portion of the Seismic Safety Margins Research Program which includes one link in the seismic methodology chain. The link addressed here is the structural subsystem dynamic response which consists of those components and systems whose behavior is often determined decoupled from the major structural response. Typically the mathematical model utilized for the major structural response will include only the mass effects of the subsystem and the main model is used to produce the support motion inputs for subsystem seismic qualification. The main questions addressed in this report have to do with the seismic response uncertainty of safety-related components or equipment whose seismic qualification is performed by (a) analysis, (b) tests, or (c) combinations of analysis and tests, and where the seismic input is assumed to have no uncertainty

  16. Environment, safety, health, and quality plan for the TRU- Contaminated Arid Soils Project of the Landfill Stabilization Focus Area Program

    International Nuclear Information System (INIS)

    Watson, L.R.

    1995-06-01

    The Landfill Stabilization Focus Area (LSFA) is a program funded by the US Department of Energy Office of Technology Development. LSFA supports the applied research, development, demonstration, testing, and evaluation of a suite of advanced technologies that together form a comprehensive remediation system for the effective and efficient remediation of buried waste. The TRU-Contaminated Arid Soils project is being conducted under the auspices of the LSFA Program. This document describes the Environment, Safety, Health, and Quality requirements for conducting LSFA/Arid Soils activities at the Idaho National Engineering Laboratory. Topics discussed in this report, as they apply to LSFA/Arid Soils operations, include Federal, State of Idaho, and Environmental Protection Agency regulations, Health and Safety Plans, Quality Program, Data Quality Objectives, and training and job hazard analysis. Finally, a discussion is given on CERCLA criteria and system and performance audits as they apply to the LSFA Program

  17. Interim safety equipment list for 241-C-106 waste retrieval, project W-320

    International Nuclear Information System (INIS)

    Conner, J.C.

    1996-01-01

    The purpose of this supporting document is to provide safety classifications for systems, structures, and components of the Tank 241-C-106 Waste Retrieval Sluicing System (WRSS) and to document the methodology used to develop these safety classifications. The WRSS requires two transfer lines, one to carry sluiced waste slurry to tank 241-AY-102 and the other to return supernatant to tank 241-C-106; pumps in each tank; sluicers to direct the supernatant stream inside tank 241-C-106; a slurry distributor in tank 241-AY-102; heating, ventilation, and air conditioning for tank 241-C-106; and instrumentation and control devices

  18. Specific safety aspects of the water-steam cycle important to nuclear power plant project

    International Nuclear Information System (INIS)

    Lobo, C.G.

    1986-01-01

    The water-steam cycle in a nuclear power plant is similar to that used in conventional power plants. Some systems and components are required for the safe nuclear power plant operation and therefore are designed according to the safety criteria, rules and regulations applied in nuclear installations. The aim of this report is to present the safety characteristics of the water-steam cycle of a nuclear power plant with pressurized water reactor, as applied for the design of the nuclear power plants Angra 2 and Angra 3. (Author) [pt

  19. Feasibility studies of safety assessment methods for programmable automation systems. Final report of the AVV project

    International Nuclear Information System (INIS)

    Haapanen, P.; Maskuniitty, M.; Pulkkinen, U.; Heikkinen, J.; Korhonen, J.; Tuulari, E.

    1995-10-01

    Feasibility studies of two different groups of methodologies for safety assessment of programmable automation systems has been executed at the Technical Research Centre of Finland (VTT). The studies concerned the dynamic testing methods and the fault tree (FT) and failure mode and effects analysis (FMEA) methods. In order to get real experience in the application of these methods, an experimental testing of two realistic pilot systems were executed and a FT/FMEA analysis of a programmable safety function accomplished. The purpose of the studies was not to assess the object systems, but to get experience in the application of methods and assess their potentials and development needs. (46 refs., 21 figs.)

  20. The comparative analysis of safety and economic competitiveness of the advanced high-power reactor projects of NPP

    International Nuclear Information System (INIS)

    Batyrbekov, G.A.; Makhanov, U.M.; Philimonova, R.A.; Kichutkina, E.G.

    2002-01-01

    The comparative analysis results of the safety and economic competitiveness of the seven advanced large sized reactors projects (900 MW and more) are submitted in that report: EPR, Frameatome France, Siemens Germany; EP-1000 Westinghouse, USA and Genesi Italy; Candu 9, Atomic Energy of Canada Ltd; System 80 +, ABB, USA; KNGR, group NSSS Engineering and Development, Korea Power Engineering Company, Inc; APWR, Electric Power company, Japan Atomic Power Company, Mitsubishi Heavy Industries, Westinghouse Electric; and WWER-1000 (V-392), Atomenergoproject/Gidropress Russian Federation. According to the economic competitiveness of listed compared power reactors the 14 criteria of safety have been accepted. These criteria: 1. Features of the barrier system of 'defence-in-depth'. 2. The self-security of a reactor under increase of power and reactivity of a reactor, decrease of the expense and phase transformations of the reactor core coolant (presence of negative feedbacks). 3. Presence of the reactor shutdown systems responding principles of a variety, independence and reservation. Presence of the passive means of initiation and operation of the emergency protection. 4. The emergency cooling of the core of reactor. A presence of the passive means of cooling. Presence of the water reservation for the water supply of the different safety systems. 5. The emergency electrical supply, its reliability and degree of reservation. 6. The prevention measures of the heavy accident with the melt core. The decrease of the heavy accident probability. 7. The account of the heavy accident under development of the levels of protection. 8. The protection levels of NPP, the technological criteria of efficiency of the each safety barriers and the limiting radiation criteria for the each level of protection , in particular for the design-basis and beyond-design-basis accidents. 9. The measures for reduction of the heavy accident consequences. The management by the beyond

  1. Studies and research relatives to the safety of the Super-Phenix project

    International Nuclear Information System (INIS)

    Anselin, F.; Penet, F.

    1978-01-01

    The analysis of safety reports concerning the Creys Malville power station (Superphenix) must be based on technical data supplied by the NERSA, responsible for the plant, and on results of research and development programme carried out in various establishments and at the CEA in particular. By virtue of the procedure laid down for the safety analysis, i.e. analysis by the barrier method, verification of reactor shut down rules at power, permanence of cooling, confinement of dangerous products in the event of hypothetical failure of the above two functions safety R and D programmes have a double aspect: accident prevention on the one hand and study of the development of accident, even the most hypothetical on the other. In the accident prevention field the studies deal with the resistance of barriers under normal and accidental working conditions, inspection systems and reactor safety functions allowing abnormal situations to be detected and the reactor shut down; whence the special emphasis placed on emergency shut-down and cooling systems. In the accident field the R and D activities cover a wide range of studies on phenomena liable to arise, independently of their probability of occurence during the lifetime of the reactor; heating in the mass or boiling of sodium, fuel, meeting, movements of fused materials, fuel-sodium thermal interaction, core deformation, resistance of confinement recovery of molten fuel, post-accident cooling, transfer of radioactivity and contamination outside the reactor, radiological consequences and means of confinement of dangerous products [fr

  2. 76 FR 25278 - Safety Zone; TriMet Bridge Project, Willamette River; Portland, OR

    Science.gov (United States)

    2011-05-04

    ... enforcement period, all vessels will be required to transit through the area at a no wake speed and at a safe... submit comments by mail and would like to know that they reached the Facility, please enclose a stamped... crane barges that can be affected by vessel wakes. To ensure the safety of construction crews on the...

  3. Potential Crash Reduction Benefits of Safety Improvement Projects - Part A : Shoulder Rumble Strips

    Science.gov (United States)

    2012-06-01

    This research provides a comprehensive evaluation of the safety benefits of shoulder rumble strips in rural highways in Idaho. The effectiveness of shoulder rumble strips in reducing the number and severity of run-off-the-road (ROR) crashes was exami...

  4. Project Guarantee 1985. Final repository for high-level radioactive wastes: Safety report

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

    Disposal of radioactive was involves preventing releases to the biosphere for a long period of time and subsequently limiting the magnitude of releases by means of a series of safety barriers: the waste solidification matrix (borosilicate glass), massive steel canisters in highly compacted bentonite, sealing of void spacer and access routes on repository closure. The geological barriers are formed by the crystalline bed-rock and the overlying sedimentary layers. In order to perform a safety assessment the behaviour of these technical barriers and of the host rock must be understood and this understanding must be translated into quantitative models which allow calculation of repository performance. For the particular case of a Swiss repository, the main criterion is the individual dose limit of 10 mrem/year, which is given in the safety guidelines of the Swiss authorities. The procedure for the safety analysis involves examination of all scenarios which could give rise to radionuclide release from the repository. Qualitative considerations of both the magnitude of their consequences and their likelihood are used in order to identify a restricted number of scenarios for quantitative analysis

  5. K Basins Spent Nuclear Fuel (SNF) Project Safety Analysis Report for Packaging (SARP) approval plan

    International Nuclear Information System (INIS)

    1995-01-01

    This document delineates the plan for preparation, review, and approval of the K Basins Spent Nuclear Fuel (SNF) Packaging Design Criteria (PDC) document and the on-site Safety Analysis Report for Packaging (SARP). The packaging addressed in these documents is used to transport SNF in a Multi- canister Overpack (MCO) configuration

  6. United States Postal Service Alaska Hovercraft Demonstration Project Technology and Safety Assessment

    Science.gov (United States)

    2000-02-01

    This report presents the results of the technology and safety assessment of the Bethel/Kuskokwim River hovercraft service,operated by the Alaska Hovercraft Joint Venture (AHJV). The primary purpose of the service was a two-year demonstration of bypas...

  7. Safety Research Experiment Facility Project. Conceptual design report. Volume II. Building and facilities

    International Nuclear Information System (INIS)

    1975-12-01

    The conceptual design of Safety Research Experiment Facility (SAREF) site system includes a review and evaluation of previous geotechnical reports for the area where SAREF will be constructed and the conceptual design of access and in-plant roads, parking, experiment-transport-vehicle maneuvering areas, security fencing, drainage, borrow area development and restoration, and landscaping

  8. The in-depth safety assessment (ISA) pilot projects in Ukraine

    International Nuclear Information System (INIS)

    Kot, C. A.

    1998-01-01

    Ukraine operates pressurized water reactors of the Soviet-designed type, VVER. All Ukrainian plants are currently operating with annually renewable permits until they update their safety analysis reports (SARs). After approval of the SARS by the Ukrainian Nuclear Regulatory Authority, the plants will be granted longer-term operating licenses. In September 1995, the Nuclear Regulatory Authority and the Government Nuclear Power Coordinating Committee of Ukraine issued a new contents requirement for the safety analysis reports of VVERs in Ukraine. It contains requirements in three major areas: design basis accident (DBA) analysis, probabilistic risk assessment (PRA), and beyond design-basis accident (BDBA) analysis. The DBA requirements are an expanded version of the older SAR requirements. The last two requirements, on PRA and BDBA, are new. The US Department of Energy (USDOE), through the International Nuclear Safety Program (INSP), has initiated an assistance and technology transfer program to Ukraine to assist their nuclear power stations in developing a Western-type technical basis for the new SARS. USDOE sponsored In-Depth Safety Assessments (ISAs) have been initiated at three pilot nuclear reactor units in Ukraine, South Ukraine Unit 1, Zaporizhzhya Unit 5, and Rivne Unit 1. USDOE/INSP have structured the ISA program in such a way as to provide maximum assistance and technology transfer to Ukraine while encouraging and supporting the Ukrainian plants to take the responsibility and initiative and to perform the required assessments

  9. Responsible Management for Health, Safety and Environment (HSE) in Uranium Mining & Mineral Processing Projects

    International Nuclear Information System (INIS)

    Saint-Pierre, Sylvain

    2014-01-01

    If management is adequate for conventional HSE risk, the bulk of the job should be taken care of Good practices are already well known for the remaining risk, including radiation safety Radiation should be addressed in a proportionate manner as part of overall HSE management. However, public expectations are probably the highest for radiation, wastes, discharges, etc.

  10. General-purpose heat source project and space nuclear safety and fuels program. Progress reportt, January 1980

    International Nuclear Information System (INIS)

    Maraman, W.J.

    1980-04-01

    This formal monthly report covers the studies related to the use of 238 PuO 2 in radioisotopic power systems carried out for the Advanced Nuclear Systems and Projects Division of the Los Alamos Scientific Laboratory. The two programs involved are the general-purpose heat source development and space nuclear safety and fuels. Most of the studies discussed here are of a continuing nature. Results and conclusions described may change as the work continues. Published reference to the results cited in this report should not be made without the explicit permission of the person in charge of the work

  11. Safety evaluation of the loss of fluid test facility project No. 394

    International Nuclear Information System (INIS)

    1975-05-01

    Assessment of the safety of the LOFT facility and subsequent recommendations have been based on a comparison of the LOFT facility to requirements for commercial power reactors. In this comparison, the many unique features of the LOFT facility were considered including the low power level, the limited operational use as a test reactor, and the remoteness of the site. Based on this assessment, it is concluded, that while the likelihood of an accidental release of fission products may be greater than for a commercial power reactor, the consequences of such a release are reduced by the lower fission product inventory, the remoteness of the site and the capability of evacuating the Idaho National Engineering Laboratory (INEL) and adjacent areas. There is reasonable assurance that the public health and safety will not be endangered due to operation of this facility, specifically: The INEL site is acceptable with respect to location, land use, population distribution, controlled access, hydrology, meteorology, geology and seismology. Sufficient engineered safety features have been included to assure that the potential offsite doses are well within 10 CFR Part 100 guidelines. The LOFT facility has been designed in general accordance with standards, guides and codes which are comparable to those applied to commercial power reactors and any exceptions to these have been based on the unique features of the LOFT facility. Certain matters including the final safety analyses based on detailed component designs, Technical Specifications, LOCE controls and detailed program plan have not been reviewed but we assume will properly be resolved by ERDA, which has the ultimate responsibility for the safety of this facility. Changes to the facility design or program plan such as removal of the fueled Mobile Test Assembly or blowdowns to the containment vessel also will require additional analyses and review. (U.S.)

  12. Microbiological Quality and Food Safety of Plants Grown on ISS Project

    Data.gov (United States)

    National Aeronautics and Space Administration — This project aligns with current plans for deployment of a vegetable production unit on the International Space Station (Veggie) and the procurement and evaluation...

  13. 77 FR 14970 - Safety Zones; Sellwood Bridge Project, Willamette River; Portland, OR

    Science.gov (United States)

    2012-03-14

    ... and seismic requirements, upgrade the interchange at Oregon Route 43, and provide substantially improved bicycle and pedestrian facilities. The project includes the construction of two temporary..., design, or operation; test methods; sampling procedures; and related management systems practices) that...

  14. Representativeness and optimal use of body mass index (BMI) in the UK Clinical Practice Research Datalink (CPRD)

    Science.gov (United States)

    Bhaskaran, Krishnan; Forbes, Harriet J; Douglas, Ian; Leon, David A; Smeeth, Liam

    2013-01-01

    Objectives To assess the completeness and representativeness of body mass index (BMI) data in the Clinical Practice Research Datalink (CPRD), and determine an optimal strategy for their use. Design Descriptive study. Setting Electronic healthcare records from primary care. Participants A million patient random sample from the UK CPRD primary care database, aged ≥16 years. Primary and secondary outcome measures BMI completeness in CPRD was evaluated by age, sex and calendar period. CPRD-based summary BMI statistics for each calendar year (2003–2010) were age-standardised and sex-standardised and compared with equivalent statistics from the Health Survey for England (HSE). Results BMI completeness increased over calendar time from 37% in 1990–1994 to 77% in 2005–2011, was higher among females and increased with age. When BMI at specific time points was assigned based on the most recent record, calendar–year-specific mean BMI statistics underestimated equivalent HSE statistics by 0.75–1.1 kg/m2. Restriction to those with a recent (≤3 years) BMI resulted in mean BMI estimates closer to HSE (≤0.28 kg/m2 underestimation), but excluded up to 47% of patients. An alternative strategy of imputing up-to-date BMI based on modelled changes in BMI over time since the last available record also led to mean BMI estimates that were close to HSE (≤0.37 kg/m2 underestimation). Conclusions Completeness of BMI in CPRD increased over time and varied by age and sex. At a given point in time, a large proportion of the most recent BMIs are unlikely to reflect current BMI; consequent BMI misclassification might be reduced by employing model-based imputation of current BMI. PMID:24038008

  15. Lansoprazole use and tuberculosis incidence in the United Kingdom Clinical Practice Research Datalink: A population based cohort.

    Directory of Open Access Journals (Sweden)

    Tom A Yates

    2017-11-01

    Full Text Available Recent in vitro and animal studies have found the proton pump inhibitor (PPI lansoprazole to be highly active against Mycobacterium tuberculosis. Omeprazole and pantoprazole have no activity. There is no evidence that, in clinical practice, lansoprazole can treat or prevent incident tuberculosis (TB disease.We studied a cohort of new users of lansoprazole, omeprazole, or pantoprazole from the United Kingdom Clinical Practice Research Datalink to determine whether lansoprazole users have a lower incidence of TB disease than omeprazole or pantoprazole users. Negative control outcomes of myocardial infarction (MI and herpes zoster were also studied. Multivariable Cox proportional hazards regression was used to adjust for potential confounding by a wide range of factors. We identified 527,364 lansoprazole initiators and 923,500 omeprazole or pantoprazole initiators. Lansoprazole users had a lower rate of TB disease (n = 86; 10.0 cases per 100,000 person years; 95% confidence interval 8.1-12.4 than omeprazole or pantoprazole users (n = 193; 15.3 cases per 100,000 person years; 95% confidence interval 13.3-17.7, with an adjusted hazard ratio (HR of 0.68 (0.52-0.89. No association was found with MI (adjusted HR 1.04; 95% confidence interval 1.00-1.08 or herpes zoster (adjusted HR 1.03; 95% confidence interval 1.00-1.06. Limitations of this study are that we could not determine whether TB disease was due to reactivation of latent infection or a result of recent transmission, nor could we determine whether lansoprazole would have a beneficial effect if given to people presenting with TB disease.In this study, use of the commonly prescribed and cheaply available PPI lansoprazole was associated with reduced incidence of TB disease. Given the serious problem of drug resistance and the adverse side effect profiles of many TB drugs, further investigation of lansoprazole as a potential antituberculosis agent is warranted.

  16. Representativeness and optimal use of body mass index (BMI) in the UK Clinical Practice Research Datalink (CPRD).

    Science.gov (United States)

    Bhaskaran, Krishnan; Forbes, Harriet J; Douglas, Ian; Leon, David A; Smeeth, Liam

    2013-09-13

    To assess the completeness and representativeness of body mass index (BMI) data in the Clinical Practice Research Datalink (CPRD), and determine an optimal strategy for their use. Descriptive study. Electronic healthcare records from primary care. A million patient random sample from the UK CPRD primary care database, aged ≥16 years. BMI completeness in CPRD was evaluated by age, sex and calendar period. CPRD-based summary BMI statistics for each calendar year (2003-2010) were age-standardised and sex-standardised and compared with equivalent statistics from the Health Survey for England (HSE). BMI completeness increased over calendar time from 37% in 1990-1994 to 77% in 2005-2011, was higher among females and increased with age. When BMI at specific time points was assigned based on the most recent record, calendar-year-specific mean BMI statistics underestimated equivalent HSE statistics by 0.75-1.1 kg/m(2). Restriction to those with a recent (≤3 years) BMI resulted in mean BMI estimates closer to HSE (≤0.28 kg/m(2) underestimation), but excluded up to 47% of patients. An alternative strategy of imputing up-to-date BMI based on modelled changes in BMI over time since the last available record also led to mean BMI estimates that were close to HSE (≤0.37 kg/m(2) underestimation). Completeness of BMI in CPRD increased over time and varied by age and sex. At a given point in time, a large proportion of the most recent BMIs are unlikely to reflect current BMI; consequent BMI misclassification might be reduced by employing model-based imputation of current BMI.

  17. Lansoprazole use and tuberculosis incidence in the United Kingdom Clinical Practice Research Datalink: A population based cohort.

    Science.gov (United States)

    Yates, Tom A; Tomlinson, Laurie A; Bhaskaran, Krishnan; Langan, Sinead; Thomas, Sara; Smeeth, Liam; Douglas, Ian J

    2017-11-01

    Recent in vitro and animal studies have found the proton pump inhibitor (PPI) lansoprazole to be highly active against Mycobacterium tuberculosis. Omeprazole and pantoprazole have no activity. There is no evidence that, in clinical practice, lansoprazole can treat or prevent incident tuberculosis (TB) disease. We studied a cohort of new users of lansoprazole, omeprazole, or pantoprazole from the United Kingdom Clinical Practice Research Datalink to determine whether lansoprazole users have a lower incidence of TB disease than omeprazole or pantoprazole users. Negative control outcomes of myocardial infarction (MI) and herpes zoster were also studied. Multivariable Cox proportional hazards regression was used to adjust for potential confounding by a wide range of factors. We identified 527,364 lansoprazole initiators and 923,500 omeprazole or pantoprazole initiators. Lansoprazole users had a lower rate of TB disease (n = 86; 10.0 cases per 100,000 person years; 95% confidence interval 8.1-12.4) than omeprazole or pantoprazole users (n = 193; 15.3 cases per 100,000 person years; 95% confidence interval 13.3-17.7), with an adjusted hazard ratio (HR) of 0.68 (0.52-0.89). No association was found with MI (adjusted HR 1.04; 95% confidence interval 1.00-1.08) or herpes zoster (adjusted HR 1.03; 95% confidence interval 1.00-1.06). Limitations of this study are that we could not determine whether TB disease was due to reactivation of latent infection or a result of recent transmission, nor could we determine whether lansoprazole would have a beneficial effect if given to people presenting with TB disease. In this study, use of the commonly prescribed and cheaply available PPI lansoprazole was associated with reduced incidence of TB disease. Given the serious problem of drug resistance and the adverse side effect profiles of many TB drugs, further investigation of lansoprazole as a potential antituberculosis agent is warranted.

  18. Understanding flucloxacillin prescribing trends and treatment non-response in UK primary care: a Clinical Practice Research Datalink (CPRD) study.

    Science.gov (United States)

    Francis, Nick A; Hood, Kerenza; Lyons, Ronan; Butler, Christopher C

    2016-07-01

    The volume of prescribed antibiotics is associated with antimicrobial resistance and, unlike most other antibiotic classes, flucloxacillin prescribing has increased. We aimed to describe UK primary care flucloxacillin prescribing and factors associated with subsequent antibiotic prescribing as a proxy for non-response. Clinical Practice Research Datalink patients with acute prescriptions for oral flucloxacillin between January 2004 and December 2013, prescription details, associated Read codes and patient demographics were identified. Monthly prescribing rates were plotted and logistic regression identified factors associated with having a subsequent antibiotic prescription within 28 days. 3 031 179 acute prescriptions for 1 667 431 patients were included. Average monthly prescription rates increased from 4.74 prescriptions per 1000 patient-months in 2004 to 5.74 (increase of 21.1%) in 2013. The highest prescribing rates and the largest increases in rates were seen in older adults (70+ years), but the overall increase in prescribing was not accounted for by an ageing population. Prescribing 500 mg tablets/capsules rather than 250 mg became more common. Children were frequently prescribed low doses and small volumes (5 day course) and prescribing declined for children, including for impetigo. Only 4.2% of new prescriptions involved co-prescription of another antibiotic. Age (antibiotic prescription, which occurred after 17.6% of first prescriptions. There is a need to understand better the reasons for increased prescribing of flucloxacillin in primary care, optimal dosing (and the need to co-prescribe other antibiotics) and the reasons why one in five patients are prescribed a further antibiotic within 4 weeks. © The Author 2016. Published by Oxford University Press on behalf of the British Society for Antimicrobial Chemotherapy.

  19. Validation of Stevens-Johnson syndrome or toxic epidermal necrolysis diagnoses in the Clinical Practice Research Datalink.

    Science.gov (United States)

    Frey, Noel; Bircher, Andreas; Bodmer, Michael; Jick, Susan S; Meier, Christoph R; Spoendlin, Julia

    2017-04-01

    To evaluate the validity of recorded diagnoses of Stevens-Johnson syndrome (SJS) and toxic epidermal necrolysis (TEN) in the Clinical Practice Research Datalink (CPRD). We identified patients with a diagnosis of SJS or TEN between 1995 and 2013 in the CPRD. We reviewed information from patient records, free text, and hospital episode statistics (HES) data, and excluded patients with no indication of a secondary care referral. Remaining patients were classified as probable, possible, or unlikely cases of SJS/TEN by two specialised clinicians or based on pre-defined classification criteria. We quantified positive predictive values (PPV) for all SJS/TEN patients and for patients categorised as 'probable/possible' cases of SJS/TEN, based on a representative subsample of 118 patients for whom we had unequivocal information (original discharge letters or HES data). We identified 1324 patients with a diagnosis of SJS/TEN, among whom 638 had a secondary care referral recorded. Of those, 565 were classified as probable or possible cases after expert review. We calculated a PPV of 0.79 (95% CI, 0.71-0.86) for all SJS/TEN patients with a recorded secondary care referral, and a PPV of 0.87 (95% CI, 0.81-0.93) for probable/possible cases. After excluding 14 false positive patients, our study population consisted of 551 SJS/TEN patients. Diagnoses of SJS/TEN are recorded with moderate diagnostic accuracy in the CPRD, which was substantially improved by additional expert review of all available information. We established a large population-based SJS/TEN study population of high diagnostic validity from the CPRD. Copyright © 2016 John Wiley & Sons, Ltd. Copyright © 2016 John Wiley & Sons, Ltd.

  20. Safety engineering aspects of radioactive waste disposal, and evaluation of the Konrad and Gorleben radioactive waste disposal projects

    International Nuclear Information System (INIS)

    Roethemeyer, H.

    1992-01-01

    Safety engineering aspects of radioactive waste disposal, and evaluation of the Konrad and Gorleben radioactive waste disposal projects. Final disposal is defined as the safe, sufficiently long and maintenance-free isolation of unavoidable hazardous materials in deep geological formations of the earth's crust. A holistic view of the world around us is prerequisite for implementation of this nature-conserving scheme. However, the complexity of the relevant processes, man-made ones inclusive, and their interactions defies exact calculations and forces us to resort to forecasts. Aspects related to the scientificio-technical fundamentals of such forecasts are dealt with, and the Konrad and Gorleben radioactive waste disposal projects are evaluated on the basis of these aspects. (orig./HSCH) [de

  1. Overview of PHARE projects implemented in Romania between 1997 and 2008 for enhancing the nuclear safety level

    Energy Technology Data Exchange (ETDEWEB)

    Sanda, Radian; Zerger, Benoit; Manna, Giustino; Farrar, Brian [European Commission, Petten (Netherlands). Joint Research Centre (JRC)

    2015-01-15

    Through the Poland Hungary Aid for Reconstruction of the Economy (PHARE) programme, the European Commission (EC) supported the transition of the Eastern European states to the European market economy. PHARE was a pre-accession financial assistance programme which involved countries from Central and Eastern Europe that applied to become members of the European Union. The paper presents a synthesis of the projects carried out in Romania for enhancing nuclear safety by consolidating key areas such as Regulatory Activities, Radioactive Waste Management and On-Site assistance, in order to fulfil the requirements for accession to the European Union. Statistical considerations on the impact of the projects are also proposed and an analysis of the methodology of intervention is made.

  2. Impact of accelerator based technologies on nuclear fission safety - Share cost project of the European Community

    International Nuclear Information System (INIS)

    1997-01-01

    As a result of the growing interest in Accelerator-Driven Systems (ADS), some European institutes have established a shared cost project in the framework of the European Community. The overall objective of the project is to make an assessment of the possibilities of accelerator-driven hybrid reactor systems from the point of view of safe energy production, minimum waste production and transmutation capabilities

  3. Metholology for the selection of LWR safety R and D projects. Phase I, status report

    International Nuclear Information System (INIS)

    El-Sheikh, K.A.

    1980-03-01

    The objective of the LWR R and D Selection Methodology Program is to develop and demonstrate an R and D selection methodology appropriate for LWR safety technology. This report documents the development work from the program beginning in April, 1979 to the end of Fiscal Year 1979. The scope of work for this period included three tasks; methodology review (Task 1), measures development (Task 2), and methodology development for the first phase of application (Task 3). The accomplishments of these tasks are presented

  4. From Here to There: Lessons from an Integrative Patient Safety Project in Rural Health Care Settings

    Science.gov (United States)

    2005-05-01

    by the Agency for Healthcare Research and Quality. Interdisciplinary teams of health care providers from 30 rural hospitals and Indian Health...tertiary care settings. Thus, little is known about the status of patient safety initiatives in rural areas or the extent to which urban interventions...Hoas H, Guttmannova K. A description of bioethics activities in rural hospitals. Cambridge Quarterly of Healthcare Ethics 2000;9(2):230–8. 3. Cook AF

  5. European project SARGEN IV: safety approach and assessment of GEN IV reactors

    International Nuclear Information System (INIS)

    Ammirabile, L.

    2013-01-01

    • SARGEN I V has elaborated a proposal for the harmonization of safety assessment practices for GEN IV NPP. • An overall reinforcement of DiD is expected for GEN I V NPP, including improved independence between all levels of DiD. • An inherent approach should reinforce the fulfillment of fundamental safety functions e.g. the consequences for some situations should be reduced and the grace periods should be extended. For the same reason, the use of passive systems can be envisaged. • The need of complementary and integrated deterministic and probabilistic approaches is reiterated. • Methodologies: Some of them are not yet applied. • Assessment of hazards would be a challenging aspect of next generation of NPP safety assessment and should be improved, which is confirmed by the first insights of Fukushima Daiichi TEPCO reactors accidents. • Provisions to cope with extreme events notably to improve the grace period before cliff-edge effects and thus allowing back-up measures to be implemented have to be defined and should be considered as hardened equipments

  6. River Protection Project Integrated safety management system phase II verification report, volumes I and II - 8/19/99

    Energy Technology Data Exchange (ETDEWEB)

    SHOOP, D.S.

    1999-09-10

    The Department of Energy policy (DOE P 450.4) is that safety is integrated into all aspects of the management and operations of its facilities. In simple and straightforward terms, the Department will ''Do work safely.'' The purpose of this River Protection Project (RPP) Integrated Safety Management System (ISMS) Phase II Verification was to determine whether ISMS programs and processes are implemented within RFP to accomplish the goal of ''Do work safely.'' The goal of an implemented ISMS is to have a single integrated system that includes Environment, Safety, and Health (ES&H) requirements in the work planning and execution processes to ensure the protection of the worker, public, environment, and federal property over the RPP life cycle. The ISMS is comprised of the (1) described functions, components, processes, and interfaces (system map or blueprint) and (2) personnel who are executing those assigned roles and responsibilities to manage and control the ISMS. Therefore, this review evaluated both the ''paper'' and ''people'' aspects of the ISMS to ensure that the system is implemented within RPP. Richland Operations Office (RL) conducted an ISMS Phase I Verification of the TWRS from September 28-October 9, 1998. The resulting verification report recommended that TWRS-RL and the contractor proceed with Phase II of ISMS verification given that the concerns identified from the Phase I verification review are incorporated into the Phase II implementation plan.

  7. Safety control system and its interface to EPICS for the off-line front end of the SPES project

    International Nuclear Information System (INIS)

    Vasquez, J.; Andrighetto, A.; Bassato, G.; Costa, L.; Giacchini, M.; Bertocco, M.

    2012-01-01

    The SPES (Selective Production of Exotic Species) project is based on a facility for the production of neutron-rich radioactive ion beams using the isotope separation on-line technique. The SPES off-line front-end apparatus involves a number of subsystems and procedures that are potentially dangerous both for human operators and for the equipment. The high voltage power supply, the ion source complex power supplies, the target chamber handling systems and the laser source are some example of these subsystems. For that reason, a safety control system has been developed. It is based on Schneider Electrics Preventa family safety modules that control the power supply of critical subsystems in combination with safety detectors that monitor critical variables. A Programmable Logic Controller (PLC), model BMXP342020 from the Schneider Electrics Modicon M340 family, is used for monitoring the status of the system as well as controlling the sequence of some operations in automatic way. A touch screen, model XBTGT5330 from the Schneider Electrics Magelis family, is used as Human Machine Interface (HMI) and communicates with the PLC using MODBUS-TCP. Additionally, an interface to the EPICS control network was developed using a home-made MODBUS-TCP EPICS driver in order to integrate it to the control system of the Front End as well as present the status of the system to the users on the main control panel. (authors)

  8. No 2943. Project of law relative to nuclear transparency and safety; N. 2943. Projet de loi relatif a la transparence et a la securite en matiere nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-03-15

    This project of law comprises 5 titles dealing with: 1 - general dispositions: definition and scope of nuclear safety, security, radiation protection, operators liability, facilities in concern; 2 - the high nuclear safety authority: role and duties; 3 - public information in the domain of nuclear safety and radiation protection: information right of the public, local information commissions, high committee for nuclear safety transparency and information; 4 - basic nuclear facilities and transport of radioactive materials: applicable rules, police controls and measures, penal dispositions (investigations, sanctions); 5 - miscellaneous dispositions: changes made with respect to previous legislative texts. (J.S.)

  9. Passive ALWR safety: the ALPHA project at Switzerland's PSI - a progress report

    International Nuclear Information System (INIS)

    Yadigaroglu, G.; Varadi, G.; Dreier, J.

    1995-01-01

    The Paul Scherrer Institute (PSI) initiated the ALPHA project in 1991 for the experimental and analytical investigation of the long-term decay heat removal from the containment of the next generation of 'passive' advanced light water reactors (ALWRs). The dynamic containment response to such systems, as well as containment phenomena, are investigated. The ALPHA project includes integral system tests in the large-scale (1:25 in volume) PANDA facility; the smaller-scale separate effects LINX series of tests related to various passive containment mixing, stratification, and condensation phenomena in the presence of non-condensable gases; the AIDA tests on the behavior of aerosols in passive containment cooling systems (PCCS); and supporting analytical work. The project has been, so far, directed mainly to the investigation of the General Electric simplified boiling water reactor (SBWR) PCCS and related phenomena. (author) 2 figs., 4 refs

  10. Methodology for Safety Assessment Applied to Predisposal Waste Management. Report of the Results of the International Project on Safety Assessment Driving Radioactive Waste Management Solutions (SADRWMS) 2004–2010)

    International Nuclear Information System (INIS)

    2015-12-01

    Report of the Results of the International Project on Safety Assessment Driving Radioactive Waste Management Solutions (SADRWMS) (2004–2010) The IAEA’s progamme on Safety Assessment Driving Radioactive Waste Management Solutions (SADRWMS) focused on approaches and mechanisms for application of safety assessment methodologies for the predisposal management of radioactive waste. The initial outcome of the SADRWMS Project was achieved through the development of flowcharts, which have since been incorporated into IAEA Safety Standards Series No. GSG-3, Safety Case and Safety Assessment for Predisposal Management of Radioactive Waste. In 2005, an initial specification was developed for the Safety Assessment Framework (SAFRAN) software tool to apply the SADRWMS flowcharts. In 2008, an in-depth application of the SAFRAN tool and the SADRWMS methodology was carried out on the predisposal management facilities of the Thailand Institute of Nuclear Technology Radioactive Waste Management Centre (TINT Facility). This publication summarizes the content and outcomes of the SADRWMS programme. The Chairman’s Report of the SADRWMS Project and the Report of the TINT test case are provided on the CD-ROM which accompanies this report

  11. Methodology for Safety Assessment Applied to Predisposal Waste Management. Report of the Results of the International Project on Safety Assessment Driving Radioactive Waste Management Solutions (SADRWMS) 2004–2010). Companion CD-ROM

    International Nuclear Information System (INIS)

    2015-12-01

    Report of the Results of the International Project on Safety Assessment Driving Radioactive Waste Management Solutions (SADRWMS) (2004–2010) The IAEA’s progamme on Safety Assessment Driving Radioactive Waste Management Solutions (SADRWMS) focused on approaches and mechanisms for application of safety assessment methodologies for the predisposal management of radioactive waste. The initial outcome of the SADRWMS Project was achieved through the development of flowcharts, which have since been incorporated into IAEA Safety Standards Series No. GSG-3, Safety Case and Safety Assessment for Predisposal Management of Radioactive Waste. In 2005, an initial specification was developed for the Safety Assessment Framework (SAFRAN) software tool to apply the SADRWMS flowcharts. In 2008, an in-depth application of the SAFRAN tool and the SADRWMS methodology was carried out on the predisposal management facilities of the Thailand Institute of Nuclear Technology Radioactive Waste Management Centre (TINT Facility). This publication summarizes the content and outcomes of the SADRWMS programme. The Chairman’s Report of the SADRWMS Project and the Report of the TINT test case are provided on this CD-ROM which accompanies the report

  12. Project EXCEL: Holiday Inn at Union Square, Housekeeping Department. Safety and Security, Module 2.

    Science.gov (United States)

    Career Resources Development Center, Inc., San Francisco, CA.

    Project EXCEL is a federally-funded workplace literacy program involving hotel enterprises in the San Francisco (California) Bay area. Its focus is on identification and instruction of literacy skills essential to job success for limited-English-proficient (LEP) workers. Training is intended to enable employees to understand written work orders,…

  13. 77 FR 35466 - Pilot Project Grants in Support of Railroad Safety Risk Reduction Programs

    Science.gov (United States)

    2012-06-13

    ... contributions must be allowable, reasonable, allocable, and in accordance with applicable Office of Management... required for Grants.gov registration. The Office of Management and Budget requires that all businesses and... demonstrate that an applicant has a definite understanding of the scope and cost of the project. If FRA...

  14. Seismic Safety Margins Research Program (Phase I). Project IV. Structural building response; Structural Building Response Review

    International Nuclear Information System (INIS)

    Healey, J.J.; Wu, S.T.; Murga, M.

    1980-02-01

    As part of the Phase I effort of the Seismic Safety Margins Research Program (SSMRP) being performed by the University of California Lawrence Livermore Laboratory for the US Nuclear Regulatory Commission, the basic objective of Subtask IV.1 (Structural Building Response Review) is to review and summarize current methods and data pertaining to seismic response calculations particularly as they relate to the objectives of the SSMRP. This material forms one component in the development of the overall computational methodology involving state of the art computations including explicit consideration of uncertainty and aimed at ultimately deriving estimates of the probability of radioactive releases due to seismic effects on nuclear power plant facilities

  15. Seismic Safety Margins Research Program (Phase I). Project VII. Systems analysis specification of computational approach

    International Nuclear Information System (INIS)

    Wall, I.B.; Kaul, M.K.; Post, R.I.; Tagart, S.W. Jr.; Vinson, T.J.

    1979-02-01

    An initial specification is presented of a computation approach for a probabilistic risk assessment model for use in the Seismic Safety Margin Research Program. This model encompasses the whole seismic calculational chain from seismic input through soil-structure interaction, transfer functions to the probability of component failure, integration of these failures into a system model and thereby estimate the probability of a release of radioactive material to the environment. It is intended that the primary use of this model will be in sensitivity studies to assess the potential conservatism of different modeling elements in the chain and to provide guidance on priorities for research in seismic design of nuclear power plants

  16. Hanford Site organic waste tanks: History, waste properties, and scientific issues. Hanford Tank Safety Project

    Energy Technology Data Exchange (ETDEWEB)

    Strachan, D.M.; Schulz, W.W.; Reynolds, D.A.

    1993-01-01

    Eight Hanford single-shell waste tanks are included on a safety watch list because they are thought to contain significant concentrations of various organic chemical. Potential dangers associated with the waste in these tanks include exothermic reaction, combustion, and release of hazardous vapors. In all eight tanks the measured waste temperatures are in the range 16 to 46{degree}C, far below the 250 to 380{degree}C temperatures necessary for onset of rapid exothermic reactions and initiation of deflagration. Investigation of the possibility of vapor release from Tank C-103 has been elevated to a top safety priority. There is a need to obtain an adequate number of truly representative vapor samples and for highly sensitive and capable methods and instruments to analyze these samples. Remaining scientific issues include: an understanding of the behavior and reaction of organic compounds in existing underground tank environments knowledge of the types and amounts of organic compounds in the tanks knowledge of selected physical and chemical properties of organic compounds source, composition, quality, and properties of the presently unidentified volatile organic compound(s) apparently evolving from Tank C-103.

  17. Technology relevance of the 'uncertainty analysis in modelling' project for nuclear reactor safety

    International Nuclear Information System (INIS)

    D'Auria, F.; Langenbuch, S.; Royer, E.; Del Nevo, A.; Parisi, C.; Petruzzi, A.

    2007-01-01

    The OECD/NEA Nuclear Science Committee (NSC) endorsed the setting up of an Expert Group on Uncertainty Analysis in Modelling (UAM) in June 2006. This Expert Group reports to the Working Party on Scientific issues in Reactor Systems (WPRS) and because it addresses multi-scale / multi-physics aspects of uncertainty analysis, it will work in close co-ordination with the benchmark groups on coupled neutronics-thermal-hydraulics and on coupled core-plant problems, and the CSNI Group on Analysis and Management of Accidents (GAMA). The NEA/NSC has endorsed that this activity be undertaken with Prof. K. Ivanov from the Pennsylvania State University (PSU) as the main coordinator and host with the assistance of the Scientific Board. The objective of the proposed work is to define, coordinate, conduct, and report an international benchmark for uncertainty analysis in best-estimate coupled code calculations for design, operation, and safety analysis of LWRs entitled 'OECD UAM LWR Benchmark'. At the First Benchmark Workshop (UAM-1) held from 10 to 11 May 2007 at the OECD/NEA, one action concerned the forming of a sub-group, led by F. D'Auria, member of CSNI, responsible for defining the objectives, the impact and benefit of the UAM for safety and licensing. This report is the result of this action by the subgroup. (authors)

  18. Safety equipment list for 241-C-106 waste retrieval, Project W-320: Revision 1

    International Nuclear Information System (INIS)

    Conner, J.C.

    1994-01-01

    The goals of the C-106 sluicing operation are: (1) to stabilize the tank by reducing the heat load in the tank to less than 42 MJ/hr (40,000 Btu/hour), and (2) to initiate demonstration of single-shell tank (SST) retrieval technology. The purpose of this supporting document (SD) is as follows: (1) to provide safety classifications for items (systems, structures, equipment, components, or parts) for the waste retrieval sluicing system (WRSS), and (2) to document and methodology used to develop safety classifications. Appropriate references are made with regard to use of existing systems, structures, equipments, components, and parts for C-106 single-shell transfer tank located in the C Tank Farm, and 241-AY-102 (AY-102) double shell receiver tanks (DST) located in the Aging Waste Facility (AWF). The Waste Retrieval Sluicing System consists of two transfer lines that would connect the two tanks, one to carry the sluiced waste slurry to AY-102, and the other to return the supernatant liquid to C-106. The supernatant, or alternate fluid, will be used to mobilize waste in C-106 for the sluicing process. The equipment necessary for the WRSS include pumps in each tank, sluicers to direct the supernatant stream in C-106, a slurry distributor in AY-102, HVAC for C-106, instrumentation and control devices, and other existing components as required

  19. Randomized Trial of Reducing Ambulatory Malpractice and Safety Risk: Results of the Massachusetts PROMISES Project.

    Science.gov (United States)

    Schiff, Gordon D; Reyes Nieva, Harry; Griswold, Paula; Leydon, Nicholas; Ling, Judy; Federico, Frank; Keohane, Carol; Ellis, Bonnie R; Foskett, Cathy; Orav, E John; Yoon, Catherine; Goldmann, Don; Weissman, Joel S; Bates, David W; Biondolillo, Madeleine; Singer, Sara J

    2017-08-01

    Evaluate application of quality improvement approaches to key ambulatory malpractice risk and safety areas. In total, 25 small-to-medium-sized primary care practices (16 intervention; 9 control) in Massachusetts. Controlled trial of a 15-month intervention including exposure to a learning network, webinars, face-to-face meetings, and coaching by improvement advisors targeting "3+1" high-risk domains: test result, referral, and medication management plus culture/communication issues evaluated by survey and chart review tools. Chart reviews conducted at baseline and postintervention for intervention sites. Staff and patient survey data collected at baseline and postintervention for intervention and control sites. Chart reviews demonstrated significant improvements in documentation of abnormal results, patient notification, documentation of an action or treatment plan, and evidence of a completed plan (all Pplan decreased by 19.4 days (P<0.001). Staff surveys showed modest but nonsignificant improvement for intervention practices relative to controls overall and for the 3 high-risk domains that were the focus of PROMISES. A consortium of stakeholders, quality improvement tools, coaches, and learning network decreased selected ambulatory safety risks often seen in malpractice claims.

  20. The OECD Halden Reactor Project - international research on safety and reliability of nuclear power generation

    International Nuclear Information System (INIS)

    Broy, Y.; Wiesenack, W.; Moen, L.A.

    2001-01-01

    The Halden Reactor was one of the first experimental reactors in the world, built into a mountain cave in the middle of the town of Halden (120 km south of Oslo). The reactor went critical for the first time in June 1959. The experimental programme is run under the auspices of the OECD Halden Reactor Project (HRP). This was established in 1958 as a joint undertaking of the OECD Nuclear Energy Agency. The Project is an international collaboration and today 21 participating countries are sponsoring the experimental programme. This paper gives an overview of the Halden Reactor and its associated experimental facilities; the current research program on fuels and materials testing, including some selected results; and finally an outline of the planned research activities in the period 2000 - 2002. (authors)

  1. Safety against releases in severe accidents. Annual report 1996. Project plan 1997

    International Nuclear Information System (INIS)

    1997-01-01

    The work scope of the RAK-2 project is divided into three sub-projects: RAK-2.1 Severe Accident Phenomenology; RAK-2.2 Computerised Accident Management; RAK-2.3 Reactors In Nordic Surroundings. The work in subproject 1 progresses roughly according to budget and time schedule. Some adjustments in the technical work scope were made during 1996. Main tasks of RAK-2.1 in 1996: Complete recriticality studies for Nordic BWRs; Investigate phenomena related to late phase melt progression; Issue and NKS Final Technical Report on KTH experiments. Main tasks of RAK-2.2 in 1996: CAMS would be further developed with signal validation, tracking simulation, state identification and PSA and risk monitoring applications; Carry out a feasibility study for development of a PWR version of CAMS in collaboration with EdF, France; Use CAMS in the Halden Man-Machine laboratory to perform human factor studies. Main tasks of RAK-2.3 in 1996: Collect and report data from the British reactor types AGR, MAGNOX and PWR; Make a report on accidents in nuclear ships; Put the collected data together in a common data base covering neighbour reactors treated in SIK-3 and RAK-2.3; Update the data in the former SIK-3 report if needed. The work in project 2 progresses according to plans. The data collection of British reactors with in sub-project 3 has been delayed significantly due to difficulty of obtaining information from some of the British utilities, but the problems are expected to be solved by the end of 1997. (EG)

  2. Microbiological Quality and Food Safety of Plants Grown on ISS Project

    Science.gov (United States)

    Wheeler, Raymond M. (Compiler)

    2014-01-01

    The goal of this project is to select and advance methods to enable real-time sampling, microbiological analysis, and sanitation of crops grown on the International Space Station (ISS). These methods would validate the microbiological quality of crops grown for consumption to ensure safe and palatable fresh foods. This would be achieved through the development / advancement of microbiological sample collection, rapid pathogen detection and effective sanitation methods that are compatible with a microgravity environment.

  3. Irradiation to ensure the safety and quality of prepared meals. Results of the coordinated research project (2002-2006)

    International Nuclear Information System (INIS)

    2009-02-01

    The consumption of prepared meals has increased enormously during the last decade, not only in developed countries but also in developing countries where many types of ethnic foods are now also prepared as convenience foods. Consumer studies carried out on the consumption of these types of foods have shown that perceived time pressures contribute positively to the purchase of both prepared meals and takeaway meals. Other reasons are also mentioned in the literature, among them are the increasing proportion of working women outside of the home, not enjoying cooking for oneself and the need of family members to eat at different times. Traditionally, prepared meals are retort processed, or, more recently, stored frozen, whereas an increasing demand exists for chilled commodities, partly due to their fresh appearance. However, the chilled prepared meals are non-sterile and potential survival of some pathogenic microorganisms and/or post-processing contamination before packaging creates microbiological risks and a considerable limitation of shelf life. This is particularly important for countries where the microbiological safety of many ethnic prepared meals is questionable and their shelf life limited due to the conditions under which they are produced, stored and distributed. Food irradiation used on its own, or in combination with other technologies, could significantly enhance the microbial safety of such products as well as extend their shelf life. Although extensive research has been carried out on the microbiological, chemical, nutritional and sensorial effects of irradiating individual uncooked food items, little work has been reported on the irradiation of complex food systems such as prepared meals. In 2002, the Joint FAO/IAEA Division of Nuclear Techniques in Food and Agriculture initiated in a Coordinated Research Project on Irradiation to Ensure the Safety and Quality of Prepared Meals. This project included the studies of participants from different

  4. Riting" cultural safety within the postcolonial and postnational feminist project: toward new epistemologies of healing.

    Science.gov (United States)

    Anderson, Joan; Perry, JoAnn; Blue, Connie; Browne, Annette; Henderson, Angela; Khan, Koushambhi Basu; Reimer Kirkham, Sheryl; Lynam, Judith; Semeniuk, Pat; Smye, Vicki

    2003-01-01

    The concept of cultural safety, developed by indigenous nurses in the postcolonial climate of New Zealand, has not been widely examined in North America. In this article we explicate the theoretical and methodological issues that came to the forefront in our attempts to use this concept in our research with different populations in Canada. We argue that this concept prompts us to "think critically" about ourselves and our patients, and to be mindful of our own sociocultural, economic, and historical location. This critical reflection has implications for how we live, relate to one another, and practice in our various professional disciplines. On the basis of our findings, we discuss how the concept might be rewritten within a critical postcolonial and postnational feminist discourse.

  5. Ferrocyanide Safety Project: Subtask 3.4, Aging Studies. FY 1992, annual report

    Energy Technology Data Exchange (ETDEWEB)

    Lilga, M.A.; Lumetta, M.R.; Riemath, W.F.; Romine, R.A.; Schiefelbein, G.F.

    1992-11-01

    The Hanford Ferrocyanide Task Team is addressing issues involving ferrocyanide precipitates in single-shell waste storage tanks (SSTs), in particular the storage of waste in a safe manner. This Task Team, composed of researchers from Westinghouse Hanford Company (WHC), Pacific Northwest Laboratory (PNL), and outside consultants, was formed in response to the need for an updated analysis of safety questions about the Hanford ferrocyanide tanks. This annual report gives the results of the work conducted by PNL in FY 1992 on Subtask 3.4, Aging Studies, which is part of Task 3, Chemical Nature of Feffocyanide in Wastes. Subtask 3.4 deals with the aging behavior and solubilization of ferrocyanide tank waste sludges in a basic aqueous environment. Investigated were the effects of pH variation, ionic strength, salts present in SSTS, and gamma radiation on solubilization of vendor-prepared Na{sub 2}NiFe(CN){sub 6}.

  6. Safety assessment methodologies for near surface disposal facilities. Results of a co-ordinated research project (ISAM). Volume 1: Review and enhancement of safety assessment approaches and tools. Volume 2: Test cases

    International Nuclear Information System (INIS)

    2004-07-01

    For several decades, countries have made use of near surface facilities for the disposal of low and intermediate level radioactive waste. In line with the internationally agreed principles of radioactive waste management, the safety of these facilities needs to be ensured during all stages of their lifetimes, including the post-closure period. By the mid 1990s, formal methodologies for evaluating the long term safety of such facilities had been developed, but intercomparison of these methodologies had revealed a number of discrepancies between them. Consequently, in 1997, the International Atomic Energy Agency launched a Co-ordinated Research Project (CRP) on Improvement of Safety Assessment Methodologies for Near Surface Disposal Facilities (ISAM). The particular objectives of the CRP were to provide a critical evaluation of the approaches and tools used in post-closure safety assessment for proposed and existing near-surface radioactive waste disposal facilities, enhance the approaches and tools used and build confidence in the approaches and tools used. The CRP ran until 2000 and resulted in the development of a harmonized assessment methodology (the ISAM project methodology), which was applied to a number of test cases. Over seventy participants from twenty-two Member States played an active role in the project and it attracted interest from around seven hundred persons involved with safety assessment in seventy-two Member States. The results of the CRP have contributed to the Action Plan on the Safety of Radioactive Waste Management which was approved by the Board of Governors and endorsed by the General Conference in September 2001. Specifically, they contribute to Action 5, which requests the IAEA Secretariat to 'develop a structured and systematic programme to ensure adequate application of the Agency's waste safety standards', by elaborating on the Safety Requirements on 'Near Surface Disposal of Radioactive Waste' (Safety Standards Series No. WS-R-1) and

  7. Seismic safety-margins research program. Phase I final report - development of seismic input (Project II)

    International Nuclear Information System (INIS)

    Bernreuter, D.L.; Chung, D.H.; Mortgat, C.P.

    1982-06-01

    Project II was charged with developing a probabilistic statement of the seismic hazard at the zion site. The definition of the seismic hazard included both the time histories upon which the SMACS computation was based and the hazard curve necessary for the calculation of unconditional release probabilities by SEISIM. In this volume, the application of the probabilistic approach is discussed using expert opinion to obtain estimates of the seismic hazard at the Zion site. The ground motion models used to develop the seismic hazard at the Zion site and the extensive sensitivity studies which were performed to determine the important parameters and the significance of uncertainty in them are described

  8. Providing the Basis for Innovative Improvements in Advanced LWR Reactor Passive Safety Systems Design: An Educational R and D Project

    International Nuclear Information System (INIS)

    Brian G. Williams; Jim C. P. Liou; Hiral Kadakia; Bill Phoenix; Richard R. Schultz

    2007-01-01

    This project characterizes typical two-phase stratified flow conditions in advanced water reactor horizontal pipe sections, following activation of passive cooling systems. It provides (1) a means to educate nuclear engineering students regarding the importance of two-phase stratified flow in passive cooling systems to the safety of advanced reactor systems and (2) describes the experimental apparatus and process to measure key parameters essential to consider when designing passive emergency core cooling flow paths that may encounter this flow regime. Based on data collected, the state of analysis capabilities can be determined regarding stratified flow in advanced reactor systems and the best paths forward can be identified to ensure that the nuclear industry can properly characterize two-phase stratified flow in passive emergency core cooling systems

  9. The importance of Probabilistic Safety Assessment in the careful study of risks involved to new nuclear power plant projects

    International Nuclear Information System (INIS)

    Mata, Jônatas F.C. da; Mesquita, Amir Z.

    2017-01-01

    The Fukushima Daiichi nuclear accident in Japan in 2011 has raised public fears about the actual safety of nuclear power plants in several countries. The response to this concern by government agencies and private companies has been objective and pragmatic in order to guarantee best practices in the design, construction, operation and decommissioning phases of nuclear reactors. In countries where the nucleo-electric matrix is consolidated, such as the United States, France and the United Kingdom, the safety assessment is carried out considering deterministic and probabilistic criteria. In the licensing stages of new projects, it is necessary to analyze and simulate the behavior of the nuclear power plant, when subjected to conditions that can lead to sequences of accidents. Each initiator event is studied and simulated through computational models, which allow the description and estimation of possible physical phenomena occurring in nuclear reactors. Probabilistic Safety Assessment (PSA) is fundamental in this process, as it studies in depth the sequences of events that can lead to the fusion of the nucleus of the nuclear reactor. Such sequences should be quantified in terms of probability of occurrence and your possible consequences, and organized through techniques such as Fault Tree Analysis and Event Tree Analysis. For these simulations, specialized computer codes for each type of phenomenon should be used, as well as databases based on experience gained in the operation of similar nuclear reactors. The present work will describe, in an objective way, the procedures for the realization of PSA and its applicability to the assurance of the operational reliability of the nuclear reactors, as well as a brief comparative between the approaches used in some countries traditionally users of thermonuclear energy and Brazil. By means of this analysis, it can be concluded that nuclear power is increasingly reliable and safe, being able to provide the necessary

  10. The importance of Probabilistic Safety Assessment in the careful study of risks involved to new nuclear power plant projects

    Energy Technology Data Exchange (ETDEWEB)

    Mata, Jônatas F.C. da, E-mail: jonatasfmata@yahoo.com.br [Universidade do Estado de Minas Gerais (UEMG), João Monlevade, MG (Brazil); Mesquita, Amir Z., E-mail: amir@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2017-07-01

    The Fukushima Daiichi nuclear accident in Japan in 2011 has raised public fears about the actual safety of nuclear power plants in several countries. The response to this concern by government agencies and private companies has been objective and pragmatic in order to guarantee best practices in the design, construction, operation and decommissioning phases of nuclear reactors. In countries where the nucleo-electric matrix is consolidated, such as the United States, France and the United Kingdom, the safety assessment is carried out considering deterministic and probabilistic criteria. In the licensing stages of new projects, it is necessary to analyze and simulate the behavior of the nuclear power plant, when subjected to conditions that can lead to sequences of accidents. Each initiator event is studied and simulated through computational models, which allow the description and estimation of possible physical phenomena occurring in nuclear reactors. Probabilistic Safety Assessment (PSA) is fundamental in this process, as it studies in depth the sequences of events that can lead to the fusion of the nucleus of the nuclear reactor. Such sequences should be quantified in terms of probability of occurrence and your possible consequences, and organized through techniques such as Fault Tree Analysis and Event Tree Analysis. For these simulations, specialized computer codes for each type of phenomenon should be used, as well as databases based on experience gained in the operation of similar nuclear reactors. The present work will describe, in an objective way, the procedures for the realization of PSA and its applicability to the assurance of the operational reliability of the nuclear reactors, as well as a brief comparative between the approaches used in some countries traditionally users of thermonuclear energy and Brazil. By means of this analysis, it can be concluded that nuclear power is increasingly reliable and safe, being able to provide the necessary

  11. The evolution of multiagency partnerships for safety over the course of research engagement: experiences from the NoGAPS project

    Science.gov (United States)

    Donaldson, Alex; Gabbe, Belinda J; Muhammad, Akram; Shee, Anna Wong; Lloyd, David G; Cook, Jill

    2016-01-01

    Objective Implementation of effective population-level injury prevention interventions requires broad multiagency partnerships. Different stakeholders address this from varying perspectives, and potential conflicts in priorities need to be addressed for such partnerships to be effective. The researcher-led National Guidance for Australian football Partnerships and Safety (NoGAPS) project involved the engagement and participation of seven non-academic partners, including government health promotion and safety agencies; peak sports professional and advocacy bodies and health insurance organisations. Design The partnership's ongoing development was assessed by each partner completing the Victorian Health Promotion Foundation Partnership Analysis Tool (VPAT) annually over 2011–2015. Changes in VPAT scores were compared through repeated measures analysis of variance. Results Overall, mean total VPAT scores increased significantly over the 5-year period (125.1–141.2; F5,30=4.61, p=0.003), showing a significant improvement in how the partnership was functioning over time. This was largely driven by significant increases in several VPAT domains: ‘determining the need for a partnership’ (F5,30=4.15, p=0.006), ‘making sure the partnership works’ (F5,30=2.59, p=0.046), ‘planning collaborative action’ (F5,30=5.13, p=0.002) and ‘minimising the barriers to the partnership’ (F5,30=6.66, ppartnership to address sport injury prevention implementation. For NoGAPS, the engagement of stakeholders from the outset facilitated the development of new and/or stronger links between non-academic partners. Partners shared the common goal of ensuring the real-world uptake of interventions and research evidence-informed recommendations. Effective multiagency partnerships have the potential to influence the implementation of policies and practices beyond the life of a research project. PMID:27016461

  12. Conceptual aspects of the safety evaluation of a project of complementary spent nuclear fuel dry storage unit

    International Nuclear Information System (INIS)

    Freitas, Rafaela da S. A.; Fontes, Gladson S.; Saldanha, Pedro L. C.

    2017-01-01

    Based on the number of cycles and the amount of new fuel elements exchanged in the reactor cores at each cycle, the forecast for the exhaustion of the spent nuclear fuel pools of the Brazil plants has provision until 2021. As are still in the studies the availability of a long-term storage facility for spent fuel, the short-term solution will be the construction of the Complementary Storage Spent Nuclear Fuel Unit, it will build inside the site in Angra Plants. The dry cask is a method of storage in which the fuel elements of high-level radioactive waste are stored, such as spent nuclear fuel, which already cooled in the fuel pool for at least one year and up to ten years. The purpose of the present paper is to discuss a conceptual study of the safety analysis of a project of licensing of a Dry Storage Unit (DSU) with the objective of verifying the application of national and international criteria, requirements and standards. The safety analysis will make on the principles adopted by the US Nuclear USNRC and the standards adopted at CNEN for dry storage. The concept of installation, seismic, geological and other analysis will be approached for approval of the site to be installed at DSU, the approved permit for the construction and finally the external and internal events that may occur being incidents and / or accidents and which are The necessary mitigations if something occurs within a period of time. (author)

  13. Safety evaluation report related to the operation of WPPSS Nuclear Project No. 2, (Docket No. 50-397). Supplement No. 4

    International Nuclear Information System (INIS)

    1983-12-01

    Supplement No. 4 to the Safety Evaluation Report on the application filed by Washington Public Power Supply System for a license to operate the WPPSS Nuclear Project No. 2, located in Richland, Washington, has been prepared by the Division of Licensing, Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report and Supplement Nos. 1, 2 and 3

  14. Safety measures for the main control board replacement project at Ikata units 1 and 2

    International Nuclear Information System (INIS)

    Hashimoto, Nozomu; Tada, Kenji

    2013-01-01

    When Units 1 and 2 of the Ikata Power Station underwent replacement of their main control boards, control cabinets, and associated equipment, it was necessary to remove all the control boards, cabinets, and cables from the control building including from the main control room. This meant the loss of operation and monitoring functions in the main control room and functions of control cabinets. To maintain the operation and monitoring functions required under plant shutdown conditions, temporary operation and monitoring equipment (i.e., temporary main control board) was installed in the temporary main control room. The advance preparations included a trial switching from the permanent to the temporary main control board to identify and address potential problems in advance. When the replacement work was underway, a work schedule sheet posted in the temporary and the permanent control rooms was used to prevent human errors caused by operators’ recognition errors. Monitoring and control signals were switched from the old boards to the temporary boards and from the temporary boards to the new boards at appropriate timings to ensure plant safety during the replacement operation. (author)

  15. Management of Innovative Projects for Ensuring the Economic Safety in the Conditions of Integration of Economies into the World Economy

    Directory of Open Access Journals (Sweden)

    T. K. Usmanova

    2017-01-01

    Full Text Available Purpose: the aim of the article is to reveal problems and prospects, formulate economic security within the framework of innovation projects management, plan technologies in the context of integrating economies into the world economy, identify opportunities for forming, organizing, financing, managing priority economic directions. The subject is the management of innovative projects to ensure the economic security of Russian regions. The relevance of the chosen topic is due to the study of the features of the current state and the problems of the formation of economic security, the development of innovative design solutions in the context of integrating economies into the world economy. Ensuring the economic security of the regions of Russia directly depends on the introduction of innovative technologies and project management in the sectors of the national economy of Russia. Methods: the methodology of the solution of objectives is based on usage of a method of dialectic research, methods of the economic analysis, forecasting, the situational and systemic analysis, expert evaluations and the analysis of empirical data. Hypothesis. Ensuring an economic safety requires formation of innovative solutions, change of the current legislation within the Strategy of social and economic development in the conditions of integration of economies into the world economy. Results: the practical significance of the work is to identify the interrelationship between the development processes of innovative projects that ensure the economic security of the regions of Russia within the framework of regulating the current legislation, forecasting effective economic activity within the framework of the New Industrialization Strategy, selecting optimal project planning models to ensure the country's economic security and competitiveness in the conditions of integration Economies into the world economy. Conclusions and Relevance: in the conditions of integration of

  16. Climate change projections of West Nile virus infections in Europe: implications for blood safety practices.

    Science.gov (United States)

    Semenza, Jan C; Tran, Annelise; Espinosa, Laura; Sudre, Bertrand; Domanovic, Dragoslav; Paz, Shlomit

    2016-03-08

    West Nile virus (WNV) is transmitted by mosquitoes in both urban as well as in rural environments and can be pathogenic in birds, horses and humans. Extrinsic factors such as temperature and land use are determinants of WNV outbreaks in Europe, along with intrinsic factors of the vector and virus. With a multivariate model for WNV transmission we computed the probability of WNV infection in 2014, with July 2014 temperature anomalies. We applied the July temperature anomalies under the balanced A1B climate change scenario (mix of all energy sources, fossil and non-fossil) for 2025 and 2050 to model and project the risk of WNV infection in the future. Since asymptomatic infections are common in humans (which can result in the contamination of the donated blood) we estimated the predictive prevalence of WNV infections in the blood donor population. External validation of the probability model with 2014 cases indicated good prediction, based on an Area Under Curve (AUC) of 0.871 (SD = 0.032), on the Receiver Operating Characteristic Curve (ROC). The climate change projections for 2025 reveal a higher probability of WNV infection particularly at the edges of the current transmission areas (for example in Eastern Croatia, Northeastern and Northwestern Turkey) and an even further expansion in 2050. The prevalence of infection in (blood donor) populations in the outbreak-affected districts is expected to expand in the future. Predictive modelling of environmental and climatic drivers of WNV can be a valuable tool for public health practice. It can help delineate districts at risk for future transmission. These areas can be subjected to integrated disease and vector surveillance, outreach to the public and health care providers, implementation of personal protective measures, screening of blood donors, and vector abatement activities.

  17. Seismic Safety Margins Research Program. Phase I final report - Subsystem response (Project V)

    International Nuclear Information System (INIS)

    Shieh, L.C.; Chuang, T.Y.; O'Connell, W.J.

    1981-10-01

    This document reports on (1) the computation of the responses of subsystems, given the input subsystem support motion for components and systems whose failure can lead to an accident sequence (radioactive release), and (2) the results of a sensitivity study undertaken to determine the contributions of the several links in the seismic methodology chain (SMC) - seismic input (SI), soil-structure interaction (SSI), structure response (STR), and subsystem response (SUB) - to the uncertainty in subsystem response. For the singly supported subsystems (e.g., pumps, turbines, electrical control panels, etc.), we used the spectral acceleration response of the structure at the point where the subsystem components were mounted. For the multiple supported subsystems, we developed 13 piping models of five safety-related systems, and then used the pseudostatic-mode method with multisupport input motion to compute the response parameters in terms of the parameters used in the fragility descriptions (i.e., peak resultant accelerations for valves and peak resultant moments for piping). Damping and frequency were varied to represent the sources of modeling and random uncertainty. Two codes were developed: a modified version of SAPIV which assembles the piping supports into groups depending on the support's location relative to the attached structure, and SAPPAC a stand-alone modular program from which the time-history analysis module is extracted. On the basis of our sensitivity study, we determined that the variability in the combined soil-structure interaction, structural response, and subsystem response areas contribute more to uncertainty in subsystem response than does the variability in the seismic input area, assuming an earthquake within the limited peak ground acceleration range, i.e., 0.15 to 0.30g. The seismic input variations were in terms of different earthquake time histories. (author)

  18. Annual report on reactor safety research projects sponsored by the Minister for Research and Technology of the Federal Republic of Germany 1989

    International Nuclear Information System (INIS)

    1990-08-01

    Investigations on the safety of light water reactors (LWR) being performed in the framework of his research program on reactor safety are sponsored by the Bundesminister fuer Forschung und Technologie (BMFT) (Federal Minister for Research and Technology). Objective of this program is to investigate in greater detail the safety margins of nuclear power plants and their systems and the further development of safety technology. Besides the investigations of LWR tasks also projects on the safety of advanced reactors are sponsored by the BMFT. The Gesellschaft fuer Reaktorsicherheit (GRS), (Society for Reactor Safety), by order of the BMFT, informs continuously of the status of such investigations by means of semi-annual and annual publication of progress reports within the series GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by the Forschungsbetreuung at the GRS, (FB) (Research Coordination Department), within the framework of general informations of progress in reactor safety research. The individual reports are classified according to the same classification system as applied in the nuclear index of the CEC (Commission of the European Communities) and the OECD (Organization for Economic Cooperation and Development). The reports are arranged in sequence of their project numbers. (orig./HP)

  19. Analysis of Correlations between the Level of Partnering Relations and their Influence on the Time, Cost, Quality and Safety of Implementation of Construction Projects

    Directory of Open Access Journals (Sweden)

    Radziszewska-Zielina Elżbieta

    2014-11-01

    Full Text Available The present paper uses the developed model of the influence of partnering relations on the time, cost, quality and safety of implementation of construction projects. On its basis, a questionnaire has been created and a preliminary survey has been conducted. The paper presents an analysis of correlations between the level of partnering relations in the context of the partnering measures indicated in the model and their influence on the time, cost, quality and safety of implementation of construction projects. The analysis was conducted based on the data collected in 52 construction projects. The values of the Spearman rank correlation coefficient and the Pearson product-moment correlation coefficient have been calculated for the examined relations. The analysis allowed for indicating the measures of partnering whose improvement most often brings benefits with regard to the time, cost, quality and safety of implementation of construction projects. Among the 80 analysed correlations, the ones identified as strong were: 15 relations connected with the time, 8 with the cost, 5 with the quality and 1 with the safety of implementation of construction projects.

  20. Identification of road user related risk factors, Deliverable 5.1 of the H2020 project SafetyCube (Safety CaUsation, Benefits and Efficiency).

    NARCIS (Netherlands)

    Filtness, A. & Papadimitriou, E. (Eds.) Leskovšek, B. Focant, N. Martensen, H. Sgarra, V. Usami, D.S. Soteropoulos, A. Stadlbauer, S. Theofilatos, A. Yannis, G. Ziakopoulos, A. Diamandouros, K. Durso, C. Goldenbeld, C. Loenis, B. Schermers, G. Petegem, J.-H. van Elvik, R. Hesjevoll, I.S. Quigley, C. & Papazikou, E.

    2017-01-01

    The present Deliverable (D5.1) describes the identification and evaluation of infrastructure related risk factors. It outlines the results of Task 5.1 of WP5 of SafetyCube, which aimed to identify and evaluate infrastructure related risk factors and related road safety problems by (i) presenting a

  1. Physical and psychological consequences of serious road traffic injuries, Deliverable 7.2 of the H2020 project SafetyCube (Safety CaUsation, Benefits and Efficiency).

    NARCIS (Netherlands)

    Weijermars, W.A.M. Meunier, J.-C. Bos, N. Perez, C. Hours, M. Johannsen, H. Barnes, J. Brown, L. Quigley, C. Filtness, A. Perez, C. Olabarria, M. Duran, X. Hours, M. Martin, J. Bauer, R. & Johannsen, H.

    2017-01-01

    SafetyCube aims to develop an innovative road safety Decision Support System (DSS) that will enable policy-makers and stakeholders to select the most appropriate strategies, measures and cost-effective approaches to reduce casualties of all road user types and all severities. Work Package 7 of

  2. Technical safety requirements for the South Tank Farm remediation project, Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Platfoot, J.H.

    1999-01-01

    The South Tank Farm (STF) is a series of six, 170,000-gal underground, domed storage tanks that were placed into service in 1943. The tanks were constructed of a concrete mixture known as gunite. They were used as a portion of the Liquid LOW-LEVEL WASTE (LLW) System for the collection, neutralization, storage, and transfer of the aqueous portion of the radioactive and/or hazardous chemical wastes produced as part of normal facility operations at Oak Ridge National Laboratory (ORNL). Although the last of the tanks was taken out of service in 1986, they have been shown by structural analysis to continue to be structurally sound. An attempt was made in 1983 to empty the tanks; however, removal of all the sludge from the tanks was not possible with the equipment and schedule available. Since removal of the liquid waste in 1983, liquid continues to accumulate within the tanks. The in-leakage is believed to be the result of groundwater dripping into the tanks around penetrations in the domes. The tanks are currently being maintained under a Surveillance and Maintenance Program, which includes activities such as level monitoring, vegetation control, High Efficiency Particulate Air filter leakage requirement testing/replacement, sign erection/repair, pump-out of excess liquids, and instrument calibration/maintenance. A technique known as confined sluicing, which uses a high-pressure, low-volume water jet integrated with a jet pump, will be used to remove the sludge. The Technical Safety Requirements (TSRs) are those operational requirements that specify the operating limits and surveillance requirements, the basis thereof, safety boundaries, and the management of administrative controls necessary to ensure the safe operation of the STF remediation project. Effective implementation of TSRs will limit to acceptable levels the risks to the public and workers from uncontrolled releases of radioactive or other hazardous material

  3. HAZWOPER work plan and site safety and health plan for the Alpha characterization project at the solid waste storage area 4 bathtubbing trench at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    1994-07-01

    This work plan/site safety and health plan is for the alpha sampling project at the Solid Waste Storage Area 4 bathtubbing trench. The work will be conducted by the Oak Ridge National Laboratory (ORNL) Environmental Sciences Division and associated ORNL environmental, safety, and health support groups. This activity will fall under the scope of 29 CFR 1910.120, Hazardous Waste Operations and Emergency Response (HAZWOPER). The purpose of this document is to establish health and safety guidelines to be followed by all personnel involved in conducting work for this project. Work will be conducted in accordance with requirements as stipulated in the ORNL HAZWOPER Program Manual and applicable ORNL; Martin Marietta Energy Systems, Inc.; and U.S. Department of Energy policies and procedures. The levels of protection and the procedures specified in this plan are based on the best information available from historical data and preliminary evaluations of the area. Therefore, these recommendations represent the minimum health and safety requirements to be observed by all personnel engaged in this project. Unforeseeable site conditions or changes in scope of work may warrant a reassessment of the stated protection levels and controls. All adjustments to the plan must have prior approval by the safety and health disciplines signing the original plan

  4. HAZWOPER work plan and site safety and health plan for the Alpha characterization project at the solid waste storage area 4 bathtubbing trench at Oak Ridge National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    1994-07-01

    This work plan/site safety and health plan is for the alpha sampling project at the Solid Waste Storage Area 4 bathtubbing trench. The work will be conducted by the Oak Ridge National Laboratory (ORNL) Environmental Sciences Division and associated ORNL environmental, safety, and health support groups. This activity will fall under the scope of 29 CFR 1910.120, Hazardous Waste Operations and Emergency Response (HAZWOPER). The purpose of this document is to establish health and safety guidelines to be followed by all personnel involved in conducting work for this project. Work will be conducted in accordance with requirements as stipulated in the ORNL HAZWOPER Program Manual and applicable ORNL; Martin Marietta Energy Systems, Inc.; and U.S. Department of Energy policies and procedures. The levels of protection and the procedures specified in this plan are based on the best information available from historical data and preliminary evaluations of the area. Therefore, these recommendations represent the minimum health and safety requirements to be observed by all personnel engaged in this project. Unforeseeable site conditions or changes in scope of work may warrant a reassessment of the stated protection levels and controls. All adjustments to the plan must have prior approval by the safety and health disciplines signing the original plan.

  5. The challenge of defining risk-based metrics to improve food safety: inputs from the BASELINE project.

    Science.gov (United States)

    Manfreda, Gerardo; De Cesare, Alessandra

    2014-08-01

    In 2002, the Regulation (EC) 178 of the European Parliament and of the Council states that, in order to achieve the general objective of a high level of protection of human health and life, food law shall be based on risk analysis. However, the Commission Regulation No 2073/2005 on microbiological criteria for foodstuffs requires that food business operators ensure that foodstuffs comply with the relevant microbiological criteria. Such criteria define the acceptability of a product, a batch of foodstuffs or a process, based on the absence, presence or number of micro-organisms, and/or on the quantity of their toxins/metabolites, per unit(s) of mass, volume, area or batch. The same Regulation describes a food safety criterion as a mean to define the acceptability of a product or a batch of foodstuff applicable to products placed on the market; moreover, it states a process hygiene criterion as a mean indicating the acceptable functioning of the production process. Both food safety criteria and process hygiene criteria are not based on risk analysis. On the contrary, the metrics formulated by the Codex Alimentarius Commission in 2004, named Food Safety Objective (FSO) and Performance Objective (PO), are risk-based and fit the indications of Regulation 178/2002. The main aims of this review are to illustrate the key differences between microbiological criteria and the risk-based metrics defined by the Codex Alimentarius Commission and to explore the opportunity and also the possibility to implement future European Regulations including PO and FSO as supporting parameters to microbiological criteria. This review clarifies also the implications of defining an appropriate level of human protection, how to establish FSO and PO and how to implement them in practice linked to each other through quantitative risk assessment models. The contents of this review should clarify the context for application of the results collected during the EU funded project named BASELINE (www

  6. A method to assess road safety of planned infrastructure : case study of Maastricht in the framework of the European research project DUMAS, Workpackage 9.

    NARCIS (Netherlands)

    Sluis, J. van der & Janssen, S.T.M.C.

    2001-01-01

    This case study of Maastricht was part of Workpackage 9 ‘Town studies’ of the research project Developing Urban Management And Safety (DUMAS), commissioned by the European Commission. One of the main objectives of DUMAS was to develop an assessment framework to encourage the use of objective

  7. Safety evaluation of geological disposal concepts for low and medium-level wastes in rock-salt (Pacoma project)

    International Nuclear Information System (INIS)

    Prij, J.; Van Dalen, A.; Roodbergen, H.A.; Slagter, W.; Van Weers, A.W.; Zanstra, D.A.; Glasbergen, P.; Koester, H.W.; Lembrechts, J.F.; Nijhof-Pan, I.; Slot, A.F.M.

    1991-01-01

    In the framework of the Performance Assessment of Confinements for MLW and Alpha Waste (PACOMA) the disposal options dealing with rock-salt are studied by GSF and ECN (with subcontract to RIVM). The overall objectives of these studies are to develop and demonstrate procedures for the radiological safety assessment of a deep repository in salt formations. An essential objective is to show how far appropriate choices of the repository design parameters can improve the performances of the whole system. The research covers two waste inventories (the Dutch OPLA and the PACOMA reference inventory), two disposal techniques (conventional and solution mining) and three types of formations (salt dome, pillow and bedded salt). An important part of the research has been carried out in the socalled VEOS project within the framework of the Dutch OPLA study. The methodology used in the consequence analysis is a deterministic one. The models and calculation tools used to perform the consequence analysis are the codes: EMOS, METROPOL and BIOS. The results are expressed in terms of dose rates and doses to individuals as well as to groups. Detailed information with respect to the input data and the results obtained with the three codes is given in three annexes to this final report

  8. Status of the design and safety project for the sodium-cooled fast reactor as a generation IV nuclear energy system

    International Nuclear Information System (INIS)

    Niwa, Hajime; Fiorini, Gian-Luigi; Sim, Yoon-Sub; Lennox, Tom; Cahalan, James E.

    2005-01-01

    The Design and Safety Project Management Board (DSPMB) was established under the Sodium Cooled Fast Reactor (SFR) System Steering Committee (SSC) in the Generation IV international Forum. The DSPMB will promote collaborative R and D activities on reactor core design, and safety assessment for candidate systems, and also integrate these results together with those from other PMBs such as advanced fuel and component to a whole fast reactor system in order to develop high performance systems that will satisfy the goals of Generation IV nuclear energy systems. The DSPMB has formulated the present R and D schedules for this purpose. Two SFR concepts were proposed: a loop-type system with primarily a MOX fuel core and a pool-type system with a metal fuel core. Study of innovative systems and their evaluation will also be included. The safety project will cover both the safety assessment of the design and the preparation of the methods/tools to be used for the assessment. After a rather short viability phase, the project will move to the performance phase for development of performance data and design optimization of conceptual designs. This paper describes the schedules, work packages and tasks for the collaborative studies of the member countries. (author)

  9. Nordic nuclear safety research program 1994-1997. Project coordination incl. SAM-4 general information issues. Report 1996. Plans for 1997

    International Nuclear Information System (INIS)

    1997-04-01

    NKS (Nordic Nuclear Safety Research) is a cooperative body in nuclear safety, radiation protection and emergency preparedness. Its purpose is to carry out cost-effective Nordic projects, thus producing research results, exercises, information, recommendations, manuals etc., to be used by decision makers and other concerned staff members at authorities and within the nuclear industry. This is the annual report for 1996, the third year of the fifth four-year NKS program (1994-1997). The report also contains plans for the rest of the program period, including budget proposals. The following major fields of research have been identified: reactor safety; radioactive waste; radioecology; emergency preparedness; and information issues. A total of nine projects are now under way within that framework. One project (RAK-1) is dedicated to reactor safety strategies: how to avoid serious accidents. A parallel project (RAK-2) deals with minimizing releases in case of an accident. When can an overheated reactor core still be water-cooled? What might be the consequences of the cooling? All Nordic countries have long-lived low and medium level radioactive waste that requires final disposal. One project (AFA-1) addresses that issue. Environmental impact of radioactive releases is studied in two radioecology projects. The project on marine radioecology, including sediment research (EKO-1), encompasses sampling, analysis and modeling. These are also key issues in the project on long ecological half-lives in semi-natural systems (EKO-2). The transfer of radioactive cesium and strontium in the chains soil - vegetation - sheep and mushroom - roe deer is studied, along with freshwater systems. Long-term doses to main is the ultimate output from the obtained models. Another aspect of environmental impact is emergency preparedness. A recently started project, EKO-5, addresses the issue of early planning for cleanup operations following a fallout. 'Early' in this context means within the

  10. Project SAFE. Update of the SFR-1 safety assessment. Phase 1. Appendix A4: Far-field

    International Nuclear Information System (INIS)

    Follin, S.; Andersson, Johan; Holmen, J.; Axelsson, C.L.

    1998-01-01

    This appendix has identified potential needs for updated hydrogeological modelling of the SFR in connection to the planned update of the performance assessment of the SFR within the framework of the SAFE-project. The objectives of such updated modelling should be to present a credible representation of the hydrogeological system, to explore effects of seals and repository extensions and to provide input to the release and transport calculations of the assessment. The last objective has led to the conclusion that an important focus of the modelling should be to determine the flow through the vaults under different conditions as this flow appear to be a very important quantity in the radionuclide release calculations. The suggested modelling should use relevant data and apply modern modelling tools and techniques, but should be geared towards the objectives. For this reasons it is suggested to apply a set of complementary and sometimes nested approaches, where each model approach is set up in order to address a specific set of questions. Answering these questions would motivate simplifications made in subsequent steps of the modelling. To the extent possible the models should be compared with existing data on flow and Baltic water breakthrough. However, in making such comparisons the accuracy of the measurements and the precision of the models need to be considered. A one-to-one match cannot be expected. It appears that careful geochemical evaluation of the site would only be necessary if more credit is placed on migration in the geosphere. If such an evaluation is considered it should be co-ordinated with the regional groundwater modelling. The issue of gas production should be reconsidered in a scenario and process analysis of SFR. However, given the strong conclusions already made it appears that gas migration in the rock will still remain as a minor issue. The major assumptions going into the analysis of the near-field in the final safety report and the deepened

  11. Regulatory review and confidence building in post-closure safety assessments and safety cases for near surface disposal facilities, IAEA ASAM coordinated research project

    International Nuclear Information System (INIS)

    Belfadhel, M.B.; Bennett, D.G.; Gonzales, A.; Metcalf, P.; Nys, V.; Simeonov, G.; Zeleznik, N.

    2006-01-01

    The IAEA successfully concluded a Coordinated Research Program (CRP) called ISAM, which focused on the development of an Improved Safety Assessment Methodology for near-surface radioactive waste disposal facilities (1997-2002). In November 2002, and as an extension of ISAM, the IAEA launched a new CRP called ASAM, designed to test the Application of the Safety Assessment Methodology by considering a range of near surface disposal facilities. The ASAM work programme is being implemented by three application working groups and two cross-cutting working groups. The application working groups are testing the applicability of the ISAM methodology by assessing an existing disposal facility in Hungary, a copper mine in South Africa, and a hypothetical facility containing heterogenous wastes, such as disused sealed sources. The first cross-cutting working group is addressing a number of technical issues that are common to all near-surface disposal facilities, while the second group, the Regulatory Review Working Group (RRWG) is developing guidance on how to gain confidence in safety assessments and safety cases, and on how to conduct regulatory reviews of safety assessments. This paper provides a brief overview of the work being conducted by the Regulatory Review Working Group. (author)

  12. A major safety overhaul

    CERN Multimedia

    2003-01-01

    A redefined policy, a revamped safety course, an environmental project... the TIS (Technical Inspection and Safety) Division has begun a major safety overhaul. Its new head, Wolfgang Weingarten, explains to the Bulletin why and how this is happening.

  13. Highway safety design workshops.

    Science.gov (United States)

    2010-11-01

    Highway safety is an ongoing concern for the Texas Department of Transportation (TxDOT). As part of its : proactive commitment to improving highway safety, TxDOT is moving toward including quantitative safety : analyses earlier in the project develop...

  14. Roadway safety design workbook.

    Science.gov (United States)

    2009-07-01

    Highway safety is an ongoing concern to the Texas Department of Transportation (TxDOT). As part of its : proactive commitment to improving highway safety, TxDOT is moving toward including quantitative safety : analyses earlier in the project developm...

  15. Safety Evaluation Report related to the operation of South Texas Project, Units 1 and 2 (Docket Nos. 50-498 and 50-499). Supplement No. 1

    International Nuclear Information System (INIS)

    1986-09-01

    In April 1986 the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-0781) regarding the application of Houston Lighting and Power Company (applicant and agent for the owners) for a license to operate South Texas Project, Units 1 and 2 (Docket Nos. 50-498 and 50-499). The facility is located in Matagorda County, Texas, west of the Colorado River, 8 miles north-northwest of the town of Matagorda and about 89 miles southwest of Houston. This first supplement to NUREG-0781 reports the status of certain items that remained unresolved at the time the Safety Evaluation Report was published

  16. Safety evaluation report related to the construction of Skagit/Hanford Nuclear Project, Units 1 and 2. Docket Nos. STN 50-522 and 50-523

    International Nuclear Information System (INIS)

    1982-12-01

    Supplement 3 to the Safety Evaluation Report for the application filed by Puget Sound Power and Light Company on behalf of itself, the Pacific Power and Light Company, The Washington Water Power Company, and the Portland General Electric Company for construction permits to build the Skagit/Hanford Nuclear Project has been issued by the Office of Nuclear Reactor Regulation of the United States Nuclear Regulatory Commission. This supplement is an evaluation of the site relocation amendment to the Preliminary Safety Analysis Report. The proposed site has been relocated from Skagit County, Washington, to the Department of Energy's Hanford Reservation

  17. ITER safety

    International Nuclear Information System (INIS)

    Raeder, J.; Piet, S.; Buende, R.

    1991-01-01

    As part of the series of publications by the IAEA that summarize the results of the Conceptual Design Activities for the ITER project, this document describes the ITER safety analyses. It contains an assessment of normal operation effluents, accident scenarios, plasma chamber safety, tritium system safety, magnet system safety, external loss of coolant and coolant flow problems, and a waste management assessment, while it describes the implementation of the safety approach for ITER. The document ends with a list of major conclusions, a set of topical remarks on technical safety issues, and recommendations for the Engineering Design Activities, safety considerations for siting ITER, and recommendations with regard to the safety issues for the R and D for ITER. Refs, figs and tabs

  18. 3D based integrated support concept for improving safety and cost-efficiency of nuclear decommissioning projects

    International Nuclear Information System (INIS)

    Szoeke, Istvan

    2016-01-01

    extensive rework during the decommissioning phase. 3D technologies have the potential for minimising knowledge loss during the transition to decommissioning, and support efficient reconstruction of design and other knowledge supporting more optimised decommissioning strategies. Application of advanced 3D visualisation technologies are applied for planning the manipulation of heavy large components in decommissioning projects. With the decreasing time and cost investment required for application of 3D simulation and AR technology, an increasing number of experts are exploring the possibilities in using such methods for supporting on-site logistics (categorisation, transportation, and temporary storage) of contaminated and activated components during decommissioning. 3D radiological simulation and visualisation technology provides a new more efficient way for explaining complex radiological conditions, work plans, and compliance with regulatory requirements. Advanced support systems based on 3D technologies have successfully been applied in the decommissioning of a number of nuclear installations (e.g. Fugen NPP, Chernobyl NPP, Leningrad NPP, Andreeva Bay branch of Northwest Center for Radioactive Waste Management in NW Russia) for increasing safety and optimising costs. For further details the reader is referred to the literature

  19. A Pharmacovigilance Study in First Episode of Psychosis: Psychopharmacological Interventions and Safety Profiles in the PEPs Project.

    Science.gov (United States)

    Bioque, Miquel; Llerena, Adrián; Cabrera, Bibiana; Mezquida, Gisela; Lobo, Antonio; González-Pinto, Ana; Díaz-Caneja, Covadonga M; Corripio, Iluminada; Aguilar, Eduardo J; Bulbena, Antoni; Castro-Fornieles, Josefina; Vieta, Eduard; Lafuente, Amàlia; Mas, Sergi; Parellada, Mara; Saiz-Ruiz, Jerónimo; Cuesta, Manuel J; Bernardo, Miguel

    2016-04-01

    The characterization of the first episode of psychosis and how it should be treated are principal issues in actual research. Realistic, naturalistic studies are necessary to represent the entire population of first episode of psychosis attended in daily practice. Sixteen participating centers from the PEPs project recruited 335 first episode of psychosis patients, aged 7 to 35 years. This article describes and discusses the psychopharmacological interventions and safety profiles at baseline and during a 60-day pharmacovigilance period. The majority of first episode of psychosis patients received a second-generation antipsychotic (96.3%), orally (95%), and in adjusted doses according to the product specifications (87.2%). A total of 24% were receiving an antipsychotic polytherapy pattern at baseline, frequently associated with lower or higher doses of antipsychotics than the recommended ones. Eight patients were taking clozapine, all in monotherapy. Males received higher doses of antipsychotic (P=.043). A total of 5.2% of the patients were being treated with long-acting injectable antipsychotics; 12.2% of the patients received anticholinergic drugs, 12.2% antidepressants, and 13.7% mood stabilizers, while almost 40% received benzodiazepines; and 35.52% reported at least one adverse drug reaction during the pharmacovigilance period, more frequently associated with higher antipsychotic doses and antipsychotic polytherapy (85.2% vs 45.5%, Psecurity issues, support future research of determinate pharmacological strategies for the treatment of early phases of psychosis, such as the role of clozapine, long-acting injectable antipsychotics, antipsychotic combination, and the use of benzodiazepines. © The Author 2015. Published by Oxford University Press on behalf of CINP.

  20. Report of investigation into allegations of retaliation for raising safety and quality of work issues regarding Argonne National Laboratory's Integral Fast Reactor project

    International Nuclear Information System (INIS)

    1991-12-01

    In August 1990 James A. Smith resigned his position as an experimenter at Argonne National Laboratory-West (ANL-W), located near Idaho Falls, Idaho. Smith who holds a Ph.D. in metallurgy, had worked at the Laboratory since 1988, primarily on its Integral Fast Reactor (IFR) project. He alleged that the quality of the Laboratory's work on that project had been undermined by fundamental errors in metallurgy and related sciences, at least some of which had nuclear safety implications; that the Laboratory had published false and misleading accounts of its work; that prevailing attitudes at the Laboratory were antithetical to quality scientific work; and that because he had expressed concerns about these matters his job was threatened by his managers. Evidence gathered during an investigation by the Department of Energy's Office of Nuclear Safety (NS) is presented and conclusions and recommendations are provided

  1. Probabilistic evaluation of scenarios in long-term safety analyses. Results of the project ISIBEL; Probabilistische Bewertung von Szenarien in Langzeitsicherheitsanalysen. Ergebnisse des Vorhabens ISIBEL

    Energy Technology Data Exchange (ETDEWEB)

    Buhmann, Dieter; Becker, Dirk-Alexander; Laggiard, Eduardo; Ruebel, Andre; Spiessl, Sabine; Wolf, Jens

    2016-07-15

    In the frame of the project ISIBEL deterministic analyses on the radiological consequences of several possible developments of the final repository were performed (VSG: preliminary safety analysis of the site Gorleben). The report describes the probabilistic evaluation of the VSG scenarios using uncertainty and sensitivity analyses. It was shown that probabilistic analyses are important to evaluate the influence of uncertainties. The transfer of the selected scenarios in computational cases and the used modeling parameters are discussed.

  2. Annual report on reactor safety research projects sponsored by the Ministry of Economics and Labour of the Federal Republic of Germany. Reporting period 2004. Progress report

    International Nuclear Information System (INIS)

    2004-01-01

    Within its competence for energy research, the Bundesministerium fuer Wirtschaft und Technology (BMWi) (Federal Ministry of Economics and Technology) sponsors investigations into the safety of nuclear power plants. The objective of these investigations is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order of the BMWi, continuously issues information on the status of such investigations by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work and are published by the Research Management Division of GRS within the framework of general information on the progress in reactor safety research. The compilation of the reports is classified according to general topics related to reactor safety research. Further, use is made of the classification system 'Joint Safety Research Index' of the CEC (Commission of the European Communities). The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.)

  3. Annual report on reactor safety research projects sponsored by the Ministry of Economics and Labour of the Federal Republic of Germany. Reporting period 2004. Progress report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    Within its competence for energy research, the Bundesministerium fuer Wirtschaft und Technology (BMWi) (Federal Ministry of Economics and Technology) sponsors investigations into the safety of nuclear power plants. The objective of these investigations is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order of the BMWi, continuously issues information on the status of such investigations by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work and are published by the Research Management Division of GRS within the framework of general information on the progress in reactor safety research. The compilation of the reports is classified according to general topics related to reactor safety research. Further, use is made of the classification system 'Joint Safety Research Index' of the CEC (Commission of the European Communities). The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.)

  4. Project Guarantee 1985. Final repository for low- and intermediate-level radioactive wastes: The system of safety barriers

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

    The safety barrier system for the type B repository for low- and intermediate-level waste is described. The barrier parameters which are relevant for safety analysis are quantified and associated error limits and data scatter are given. The aim of the report is to give a summary documentation of the safety analysis input data and their scientific background. For secure containment of radioactive waste safety barriers are used which effectively limit the release of radioactive material from the repository (release barriers) and effectively retard the entry of the original radioactive material into the biosphere (time barriers). In the case of low- and intermediate-level waste the technical safety barrier system comprises: waste solidification matrix (cement, bitumen and resin), immobilisation of the waste packages in containers using liquid cement, concrete repository containers, backfilling of remaining vacant storage space with special concrete, concrete lining of the repository caverns, sealing of access tunnels on final closure of the repository. Natural geological safety barriers - host rock and overlying formations - have the following important functions. Because of its stability, the host rock in the repository zone protects the technical safety barrier system from destruction caused by climatic effects and erosion for a sufficient length of time. It also provides for low water flow and favourable chemistry (reducing conditions)

  5. ICDE project report: collection and analysis of common-cause failure of safety valves and relief valves

    International Nuclear Information System (INIS)

    2002-01-01

    This report documents a study performed on the set of common cause failures (CCF) of safety and relief valves (SRV). The data studied here were derived from the International CCF Data Exchange (ICDE) database, to which several countries have submitted CCF event data. The purpose of the ICDE is to allow multiple countries to collaborate and exchange CCF data to enhance the quality of risk analyses that include CCF modeling. Because CCF events are typically rare events, most countries do not experience enough CCF events to perform meaningful analyses. Data combined from several countries, however, yields sufficient data for more rigorous analyses. This report is the result of an in-depth review of the SRV events and presents several insights about them. The objective of this document is to look beyond the CCF parameter estimates that can be obtained from the CCF data, to gain further understanding of why CCF events occur and what measures may be taken to prevent, or at least mitigate the effect of, SRV CCF events. The report presents details of the ICDE project, a quantitative presentation of the SRV events, and a discussion of some engineering aspects of the events. This study examined 149 events in the ICDE database by tabulating the data and observing trends. Once trends were identified individual events were reviewed for insights. The database contains information developed during the original entry of the events that was used in this study. The data span a period from 1977 through 1999. The data is not necessarily complete for each country through this period. This information includes root cause, coupling factor, common cause component group (CCCG) size, and corrective action. As part of this study, these events were reviewed again and additional categorizations of the data were included. Those categories included the degree of failure, affected subsystem, and detection method. This study begins with an overview of the entire data set (Section Five). Charts and

  6. Iterative performance assessments as a regulatory tool for evaluating repository safety: How experiences from SKI Project-90 were used in formulating the new performance assessment project SITE-94

    International Nuclear Information System (INIS)

    Andersson, J.

    1993-01-01

    The Swedish Nuclear Power Inspectorate, SKI, regulatory research program has to prepare for the process of licensing a repository for spent nuclear fuel, by building up the necessary knowledge and review capacity. SKIs main strategy for meeting this demand is to develop an independent performance assessment capability. SKIs first own performance assessment project, Project-90, was completed in 1991 and is now followed by a new project, SITE-94. SITE-94 is based on conclusions reached within Project-90. An independent review of Project-90, carried out by a NEA team of experts, has also contributed to the formation of the project. Another important reason for the project is that the implementing organization in Sweden, SKB, has proposed to submit an application to start detailed investigation of a repository candidate site around 1997. SITE-94 is a performance assessment of a hypothetical repository at a real site. The main objective of the project is to determine how site specific data should be assimilated into the performance assessment process, and to evaluate how uncertainties inherent in site characterization will influence performance assessment results. This will be addressed by exploring multiple interpretations, conceptual models, and parameters consistent with the site data. The site evaluation will strive for consistency between geological, hydrological, rock mechanical, and geochemical descriptions. Other important elements of SITE-94 are the development of a practical and defensible methodology for defining, constructing and analyzing scenarios, the development of approaches for treatment of uncertainties, evaluation of canister integrity, and the development and application of an appropriate quality assurance plan for performance assessments

  7. A validation study of the CirCom comorbidity score in an English cirrhosis population using the Clinical Practice Research Datalink.

    Science.gov (United States)

    Crooks, Colin J; West, Joe; Jepsen, Peter

    2018-01-01

    The CirCom score has been developed from Danish data as a specific measure of comorbidity for cirrhosis to predict all-cause mortality. We compared its performance with the Charlson Comorbidity Index (CCI) in an English cirrhosis population. We used comorbidity scores in a survival model to predict mortality in a cirrhosis cohort in the Clinical Practice Research Datalink. The discrimination of each score was compared by age, gender, socioeconomic status, cirrhosis etiology, cirrhosis stage, and year after cirrhosis diagnosis. We also measured their ability to predict liver-related versus non-liver-related death. There was a small improvement in the C statistic from the model using the CirCom score (C=0.63) compared to the CCI (C=0.62), and there was an overall improvement in the net reclassification index of 1.5%. The improvement was more notable in younger patients, those with an alcohol etiology, and those with compensated cirrhosis. Both scores performed better (C statistic >0.7) for non-liver-related deaths than liver-related deaths (C statistic cause and non-liver mortality, but not liver-related mortality. Therefore, it is important to include a measure of comorbidity in studies of cirrhosis survival, alongside a measure of cirrhosis severity.

  8. Progress in Methodologies for the Assessment of Passive Safety System Reliability in Advanced Reactors. Results from the Coordinated Research Project on Development of Advanced Methodologies for the Assessment of Passive Safety Systems Performance in Advanced Reactors

    International Nuclear Information System (INIS)

    2014-09-01

    Strong reliance on inherent and passive design features has become a hallmark of many advanced reactor designs, including several evolutionary designs and nearly all advanced small and medium sized reactor (SMR) designs. Advanced nuclear reactor designs incorporate several passive systems in addition to active ones — not only to enhance the operational safety of the reactors but also to eliminate the possibility of serious accidents. Accordingly, the assessment of the reliability of passive safety systems is a crucial issue to be resolved before their extensive use in future nuclear power plants. Several physical parameters affect the performance of a passive safety system, and their values at the time of operation are unknown a priori. The functions of passive systems are based on basic physical laws and thermodynamic principals, and they may not experience the same kind of failures as active systems. Hence, consistent efforts are required to qualify the reliability of passive systems. To support the development of advanced nuclear reactor designs with passive systems, investigations into their reliability using various methodologies are being conducted in several Member States with advanced reactor development programmes. These efforts include reliability methods for passive systems by the French Atomic Energy and Alternative Energies Commission, reliability evaluation of passive safety system by the University of Pisa, Italy, and assessment of passive system reliability by the Bhabha Atomic Research Centre, India. These different approaches seem to demonstrate a consensus on some aspects. However, the developers of the approaches have been unable to agree on the definition of reliability in a passive system. Based on these developments and in order to foster collaboration, the IAEA initiated the Coordinated Research Project (CRP) on Development of Advanced Methodologies for the Assessment of Passive Safety Systems Performance in Advanced Reactors in 2008. The

  9. Long-term safety for KBS-3 repositories at Forsmark and Laxemar - a first evaluation. Main Report of the SR-Can project

    Energy Technology Data Exchange (ETDEWEB)

    Hedin, Allan (ed.)

    2006-10-15

    This document is the main report from the safety assessment project SR-Can. The SR-Can project is a preparatory stage for the SR-Site assessment, the report that will be used in support of SKB's application for a final repository. The purposes of the safety assessment SR-Can are the following: 1. To make a first assessment of the safety of potential KBS-3 repositories at Forsmark and Laxemar to dispose of canisters as specified in the application for the encapsulation plant. 2. To provide feedback to design development, to SKB's RandD programme, to further site investigations and to future safety assessment projects. 3. To foster a dialogue with the authorities that oversee SKB's activities, i.e. the Swedish Nuclear Power Inspectorate, SKI, and the Swedish Radiation Protection Authority, SSI, regarding interpretation of applicable regulations, as a preparation for the SR-Site project. The assessment relates to the KBS-3 disposal concept in which copper canisters with a cast iron insert containing spent nuclear fuel are surrounded by bentonite clay and deposited at approximately 500 m depth in saturated, granitic rock. Preliminary data from the Forsmark and Laxemar sites, presently being investigated by SKB as candidates for a KBS-3 repository are used in the assessment. An important aim of this report is to demonstrate the proper handling of requirements placed on the safety assessment in applicable regulations. Therefore, regulations issued by the Swedish Nuclear Power Inspectorate and the Swedish Radiation Protection Institute are reproduced in an Appendix where references are given to sections in the main text where the handling of the different requirements is discussed. The principal acceptance criterion requires that 'the annual risk of harmful effects after closure does not exceed 10{sup -6} for a representative individual in the group exposed to the greatest risk'. 'Harmful effects' refer to cancer and hereditary effects

  10. Long-term safety for KBS-3 repositories at Forsmark and Laxemar - a first evaluation. Main Report of the SR-Can project

    International Nuclear Information System (INIS)

    Hedin, Allan

    2006-10-01

    This document is the main report from the safety assessment project SR-Can. The SR-Can project is a preparatory stage for the SR-Site assessment, the report that will be used in support of SKB's application for a final repository. The purposes of the safety assessment SR-Can are the following: 1. To make a first assessment of the safety of potential KBS-3 repositories at Forsmark and Laxemar to dispose of canisters as specified in the application for the encapsulation plant. 2. To provide feedback to design development, to SKB's RandD programme, to further site investigations and to future safety assessment projects. 3. To foster a dialogue with the authorities that oversee SKB's activities, i.e. the Swedish Nuclear Power Inspectorate, SKI, and the Swedish Radiation Protection Authority, SSI, regarding interpretation of applicable regulations, as a preparation for the SR-Site project. The assessment relates to the KBS-3 disposal concept in which copper canisters with a cast iron insert containing spent nuclear fuel are surrounded by bentonite clay and deposited at approximately 500 m depth in saturated, granitic rock. Preliminary data from the Forsmark and Laxemar sites, presently being investigated by SKB as candidates for a KBS-3 repository are used in the assessment. An important aim of this report is to demonstrate the proper handling of requirements placed on the safety assessment in applicable regulations. Therefore, regulations issued by the Swedish Nuclear Power Inspectorate and the Swedish Radiation Protection Institute are reproduced in an Appendix where references are given to sections in the main text where the handling of the different requirements is discussed. The principal acceptance criterion requires that 'the annual risk of harmful effects after closure does not exceed 10 -6 for a representative individual in the group exposed to the greatest risk'. 'Harmful effects' refer to cancer and hereditary effects. The risk limit corresponds to an

  11. Evaluation of research projects and studies on nuclear safety in the context of implementation of the German Atomic Energy Act (AtG). Vol. 9

    International Nuclear Information System (INIS)

    Casper, H.

    2000-01-01

    The content of this report is a collection of research projects and investigations in the field of nuclear safety evaluated in 1999 and 2000 with regard to the application of the Atomic Energy Act (Atomgesetz). In addition the report gives an overview on objectives and procedures used for the evaluation. The purpose of this project, being executed for the Federal Ministry for Environment, Nature Conservation and Nuclear Safety (BMU) of the Federal Republic of Germany is to inform all parties involved in the licensing procedure as well as the consulting councils on the latest nuclear safety research results and the status of their verification in a precise short manner. In addition experts' opinions are given with regard to the relevance of these research results to nuclear rules and guidelines as well as to the execution of the Atomic Energy Act. The information consists of precise and short evaluations of final research reports or technical reports. These evaluations are prepared by specialists who are acquainted with the technical aspects of the licensing procedure of nuclear plants in the Federal Republic of Germany. This volume is the ninth report of this series. (orig.) [de

  12. A web-based incident reporting system and multidisciplinary collaborative projects for patient safety in a Japanese hospital.

    Science.gov (United States)

    Nakajima, K; Kurata, Y; Takeda, H

    2005-04-01

    When patient safety programs were mandated for Japanese health care institutions, a safety culture, a tool for collecting incident reports, an organizational arrangement for multidisciplinary collaboration, and interventional methods for improvement had to be established. Observational study of effects of new patient safety programs. Osaka University Hospital, a large government-run teaching hospital. A voluntary and anonymous web-based incident reporting system was introduced. For the new organizational structure a clinical risk management committee, a department of clinical quality management, and area clinical risk managers were established with their respective roles clearly defined to advance the plan-do-study-act cycle and to integrate efforts. For preventive action, alert procedures, staff education, ward rounds by peers, a system oriented approach for reducing errors, and various feedback channels were introduced. Continuous incident reporting by all hospital staff has been observed since the introduction of the new system. Several error inducing situations have been improved: wrong choice of drug in computer prescribing, maladministration of drugs due to a look-alike appearance or confusion about the manipulation of a medical device, and poor after hours service of the blood transfusion unit. Staff participation in educational seminars has been dramatically improved. Ward rounds have detected problematic procedures which needed to be dealt with. Patient safety programs based on a web-based incident reporting system, responsible persons, staff education, and a variety of feedback procedures can help promote a safety culture, multidisciplinary collaboration, and strong managerial leadership resulting in system oriented improvement.

  13. Annual report on reactor safety research projects sponsored by the Ministry of Economics and Labour of the Federal Republic of Germany. Reporting period 2003. Progress report

    International Nuclear Information System (INIS)

    2003-01-01

    The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order of the BMWi, continuously issues information on the status of the investigations into the safety of nuclear power plants by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work and are published by the Research Management Division of GRS within the framework of general information on the progress in reactor safety research. The compilation of the reports is classified according to general topics related to reactor safety research. Further, use is made of the classification system ''Joint Safety Research Index'' of the CEC (commission of the european communities). The reports are arranged in sequence of their project numbers

  14. Annual report on reactor safety research projects sponsored by the Ministry of Economics and Labour of the Federal Republic of Germany. Reporting period 2002. 2. progress report

    International Nuclear Information System (INIS)

    The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order of the BMWi, continuously issues information on the status of the investigations into the safety of nuclear power plants by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work and are published by the Research Management Division of GRS within the framework of general information on the progress in reactor safety research. The compilation of the reports is classified according to general topics related to reactor safety research. Further, use is made of the classification system ''Joint Safety Research Index'' of the CEC (commission of the european communities). The reports are arranged in sequence of their project numbers. (orig.) [de

  15. Safety Evaluation Report related to the operation of South Texas Project, Units 1 and 2 (Docket Nos. 50-498 and 50-499)

    International Nuclear Information System (INIS)

    1986-04-01

    The Safety Evaluation Report for the application filed by Houston Lighting and Power Company, City Public Service Board of San Antonio, Central Power and Light Company, and the City of Austin, as applicants and owners, for licenses to operate the South Texas Project Units 1 and 2 (Docket Nos. 50-498 and 50-499) has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Matagorda County, Texas, west of the Colorado River, 8 miles north-northwest of the town of Matagorda and about 89 miles southwest of Houston. Subject to resolution of the items discussed in this report, the staff concludes that the applicant can operate the facility without endangering the health and safety of the public

  16. Safety evaluation report related to the operation of South Texas Project, Units 1 and 2 (Docket Nos. 50-498 and 50-499)

    International Nuclear Information System (INIS)

    1987-01-01

    In April 1986 staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-0781) regarding the application of Houston Lighting and Power Company (applicant and agent for the owners) for a license to operate South Texas Project, Units 1 and 2 (Docket Nos. 50-498 and 50-499). The facility is located in Matagorda County, Texas, west of the Colorado River, 8 miles north-northwest of the town of Matagorda and about 89 miles southwest of Houston. The first supplement to NUREG-0781 was issued in September 1986. This second supplement reports on the status of unresolved items in the Safety Evaluation Report and identifies certain additional items that have since been reviewed by the staff

  17. Safety Evaluation Report related to the operation of WPPSS Nuclear Project No. 2 (Docket No. 50-397)

    International Nuclear Information System (INIS)

    1984-04-01

    This report, Supplement No. 5 to the Safety Evaluation Report (SSER 5) on the Washington Public Power Supply System application for a license to operate WNP-2 (Docket No. 50-397), located in Benton County, Washington, approximately 12 miles north of Richland, Washington, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report and Supplements No. 1, 2, 3, and 4

  18. ePORT, NASA's Computer Database Program for System Safety Risk Management Oversight (Electronic Project Online Risk Tool)

    Science.gov (United States)

    Johnson, Paul W.

    2008-01-01

    ePORT (electronic Project Online Risk Tool) provides a systematic approach to using an electronic database program to manage a program/project risk management processes. This presentation will briefly cover the standard risk management procedures, then thoroughly cover NASA's Risk Management tool called ePORT. This electronic Project Online Risk Tool (ePORT) is a web-based risk management program that provides a common framework to capture and manage risks, independent of a programs/projects size and budget. It is used to thoroughly cover the risk management paradigm providing standardized evaluation criterion for common management reporting, ePORT improves Product Line, Center and Corporate Management insight, simplifies program/project manager reporting, and maintains an archive of data for historical reference.

  19. Environmental benefits and concerns on safety: communicating latest results on nanotechnology safety research-the project DaNa2.0.

    Science.gov (United States)

    Kühnel, D; Marquardt, C; Nau, K; Krug, H F; Paul, F; Steinbach, C

    2017-04-01

    The use of nanotechnology and advanced materials promises to revolutionise many areas of technology and improve our daily life. In that respect, many positive effects on the environment are expected, either directly, by developing new technologies for remediation, filtering techniques or energy generation, or indirectly, by e.g. saving resources due to lower consumption of raw materials, or lower energy and fuel consumption due to reduced weight of vehicles. However, such beneficial effects of new technologies are often confronted by concerns regarding the safety of novel substances or materials. During the past 10 years, great effort has been put into research on potential hazards of nanomaterials towards environmental organisms. As the methodology for reliable assessment of nanomaterials was immature, many studies reporting contradictory results have been published, hindering both risk assessment for nanomaterials, as well as the knowledge communication to all involved stakeholders. Thus, DaNa 2.0 serves as a platform to implement trusted knowledge on nanomaterials for an objective discussion.

  20. Reports on research projects in the field of reactor safety sponsored by the Federal Minister for Research and Technology

    International Nuclear Information System (INIS)

    1981-03-01

    The GRS (Reactor Safety Association), Gesellschaft fuer Reaktorsicherheit mbH, by order of the BMFT, informs continuously of the status of such investigations by means of quarterly and annually publication of progress reports within the series GRS-F-Fortschrittsbericht (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about objectives, the work performed, the results the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by the FB (Research Coordination Department), Forschungsbetreuung at the GRS, within the framework of general information of progress in reactor safety research. The individual reports are arranged according to the Research Program on the Safety of LWRs 1977-1980 of the BMFT. Another table of contents uses the same classification system as applied in the Nuclear Safety Index of the CEC (Commission of the European Communities) and the OECD (Organization for Economic Cooperation and Development). The reports are marked by current numbers in sequence of their arrangement in this compilation. (orig./HP) [de

  1. Reports on research projects in the field of reactor safety sponsored by the Federal Minister for Research and Technology

    International Nuclear Information System (INIS)

    1981-06-01

    The GRS (Reactor Safety Association), Gesellschaft fuer Reaktorsicherheit mbH, by order of the BMFT, informs continuously of the status of such investigations by means of quarterly and annually publication of progress reports within the series GRS-F-Fortschrittsbericht (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about objectives, the work performed, the results the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by the FB (Research Coordination Department), Forschungsbetreuung at the GRS, within the framework of general information of progress in reactor safety research. The individual reports are arranged according to the Research Program on the Safety of LWRs 1977-1980 of the BMFT. Another table of contents uses the same classification system as applied in the Nuclear Safety Index of the CEC (Commission of the European Communities) and the OECD (Organization for Economic Cooperation and Development). The reports are marked by current numbers in sequence of their arrangement in this compilation. (orig./HP) [de

  2. 77 FR 59551 - Safety Zone, Changes to Original Rule; Boston Harbor's Rock Removal Project, Boston Inner Harbor...

    Science.gov (United States)

    2012-09-28

    ... transiting to and from the work site with explosives onboard. The second safety zone will be a 100-yard... vessel ``MANTIS'' while transporting explosives to and from the work site. (iii) All navigable waters... hailed by a U.S. Coast Guard vessel by siren, radio, flashing light, or other means, the operator of a...

  3. Project health and safety plan for the Gunite and Associated Tanks at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Abston, J.P.

    1997-04-01

    The Lockheed Martin Energy Systems, Inc. (Energy Systems) policy is to provide a safe and healthful workplace for all employees and subcontractors. The accomplishment of this policy requires that operations at the Gunite and Associated Tanks (GAAT) in the North and South Tank Farms (NTF and STF) at the Department of Energy (DOE) Oak Ridge National Laboratory are guided by an overall plan and consistent proactive approach to health and safety (H and S) issues. The policy and procedures in this plan apply to all GAAT operations in the NTF and STF. The provisions of this plan are to be carried out whenever activities identifies s part of the GAAT are initiated that could be a threat to human health or the environment. This plan implements a policy and establishes criteria for the development of procedures for day-to-day operations to prevent or minimize any adverse impact to the environment and personnel safety and health and to meet standards that define acceptable management of hazardous and radioactive materials and wastes. The plan is written to utilize past experience and best management practices in order to minimize hazards to human health or the environment from events such as fires, explosions, falls, mechanical hazards, or any unplanned release of hazardous or radioactive materials to the air. This plan explains additional task-specific health and safety requirements such as the Site Safety and health Addendum and Activity Hazard Analysis, which should be used in concert with this plan and existing established procedures

  4. Project health and safety plan for the Gunite and Associated Tanks at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    Abston, J.P.

    1997-04-01

    The Lockheed Martin Energy Systems, Inc. (Energy Systems) policy is to provide a safe and healthful workplace for all employees and subcontractors. The accomplishment of this policy requires that operations at the Gunite and Associated Tanks (GAAT) in the North and South Tank Farms (NTF and STF) at the Department of Energy (DOE) Oak Ridge National Laboratory are guided by an overall plan and consistent proactive approach to health and safety (H and S) issues. The policy and procedures in this plan apply to all GAAT operations in the NTF and STF. The provisions of this plan are to be carried out whenever activities identifies s part of the GAAT are initiated that could be a threat to human health or the environment. This plan implements a policy and establishes criteria for the development of procedures for day-to-day operations to prevent or minimize any adverse impact to the environment and personnel safety and health and to meet standards that define acceptable management of hazardous and radioactive materials and wastes. The plan is written to utilize past experience and best management practices in order to minimize hazards to human health or the environment from events such as fires, explosions, falls, mechanical hazards, or any unplanned release of hazardous or radioactive materials to the air. This plan explains additional task-specific health and safety requirements such as the Site Safety and health Addendum and Activity Hazard Analysis, which should be used in concert with this plan and existing established procedures.

  5. Passive Safety Systems in Advanced Water Cooled Reactors (AWCRS). Case Studies. A Report of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

    International Nuclear Information System (INIS)

    2013-09-01

    This report presents the results from the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) collaborative project (CP) on Advanced Water Cooled Reactor Case Studies in Support of Passive Safety Systems (AWCR), undertaken under the INPRO Programme Area C. INPRO was launched in 2000 - on the basis of a resolution of the IAEA General Conference (GC(44)/RES/21) - to ensure that nuclear energy is available in the 21st century in a sustainable manner, and it seeks to bring together all interested Member States to consider actions to achieve innovation. An important objective of nuclear energy system assessments is to identify 'gaps' in the various technologies and corresponding research and development (R and D) needs. This programme area fosters collaboration among INPRO Member States on selected innovative nuclear technologies to bridge technology gaps. Public concern about nuclear reactor safety has increased after the Fukushima Daiichi nuclear power plant accident caused by the loss of power to pump water for removing residual heat in the core. As a consequence, there has been an increasing interest in designing safety systems for new and advanced reactors that are passive in nature. Compared to active systems, passive safety features do not require operator intervention, active controls, or an external energy source. Passive systems rely only on physical phenomena such as natural circulation, thermal convection, gravity and self-pressurization. Passive safety features, therefore, are increasingly recognized as an essential component of the next-generation advanced reactors. A high level of safety and improved competitiveness are common goals for designing advanced nuclear power plants. Many of these systems incorporate several passive design concepts aimed at improving safety and reliability. The advantages of passive safety systems include simplicity, and avoidance of human intervention, external power or signals. For these reasons, most

  6. National assembly constitution of the 4. of october 1958 eleventh legislature. Law project relative to the openness and safety in nuclear matter

    International Nuclear Information System (INIS)

    2001-07-01

    This law project is the first text submitted to the Parliament in order to given a general frame to nuclear activities. It refers to principles of other activities areas such precautionary principle, the polluter pays principle, and public information principle. It extends the information right of citizens by creating an access right to information held by the operators of nuclear activities. A transparency high committee about nuclear safety is created whom mission is to contribute to public information on nuclear activities and to guarantee its quality and reliability. (N.C.)

  7. Case studies in the application of probabilistic safety assessment techniques to radiation sources. Final report of a coordinated research project 2001-2003

    International Nuclear Information System (INIS)

    2006-04-01

    Radiation sources are used worldwide in many industrial and medical applications. In general, the safety record associated with their use has been very good. However, accidents involving these sources have occasionally resulted in unplanned exposures to individuals. When assessed prospectively, this type of exposure is termed a 'potential exposure'. The International Commission on Radiological Protection (ICRP) has recommended the assessment of potential exposures that may result from radiation sources and has suggested that probabilistic safety assessment (PSA) techniques may be used in this process. Also, Paragraph 2.13 of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (BSS) requires that the authorization process for radiation sources include an assessment of all exposures, including potential exposures, which may result from the use of a radiation source. In light of the ICRP's work described above, and the possibility that PSA techniques could be used in exposure assessments that are required by the BSS, the IAEA initiated a coordinated research project (CRP) to study the benefits and limitations of the application of PSA techniques to radiation sources. The results of this CRP are presented in this publication. It should be noted that these results are based solely on the work performed, and the conclusions drawn, by the research teams involved in this CRP. It is intended that international organizations involved in radiation protection will review the information in this report and will take account of it during the development of guidance and requirements related to the assessment of potential exposures from radiation sources. Also, it is anticipated that the risk insights obtained through the studies will be considered by medical practitioners, facility staff and management, equipment designers, and regulators in their safety management and risk evaluation activities. A draft

  8. Traceability and communication of requirements in digital and I and C systems development - Project report 2003[TACO. Reactor safety

    Energy Technology Data Exchange (ETDEWEB)

    Sivertsen, T.; Frederiksen, R.; Thunem, A.P.J. [Institute for Energy Technology (IFE), Kjeller (Norway); Holmberg, J.E.; Valkonen, J.; Ventae, O. [VTT, Espoo (Finland)

    2004-03-01

    The overall objective of the TACO project is to improve the knowledge on principles and best practices related to the issues concretised in the preproject. On basis of experiences in the Nordic countries, the project aims at identifying the best practices and most important criteria for ensuring effective communication in relation to requirements elicitation and analysis, understandability of requirements to all parties, and traceability of requirements through the different design phases. It is expected that the project will provide important input to the development of guidelines and establishment of recommended practices related to these activities. In the year 2003, the TACO-project concentrated on four central issues: 1) Representation of requirements origins. 2) Traceability techniques. 3) Configuration management and the traceability of requirements. 4) Identification and categorisation of system aspects and their models The work was presented at the first TACO Industrial Seminar, which took place in Stockholm on the 12th of December 2003. The seminar was hosted by SKI. (au)

  9. Safety impacts of the I-35W improvements done under Minnesota's urban partnership agreement (UPA) project : final report.

    Science.gov (United States)

    2017-06-01

    As part of an Urban Partnership Agreement project, the Minnesota Department of Transportation added lanes : and began operating a priced dynamic shoulder lane (PDSL) on parts of Interstate 35W. Following the opening of : these improvements, the frequ...

  10. Incidence rates of suicidal behaviors and treated depression in patients with and without psoriatic arthritis using the Clinical Practice Research Datalink.

    Science.gov (United States)

    Hagberg, Katrina Wilcox; Li, Lin; Peng, Michael; Shah, Kamal; Paris, Maria; Jick, Susan

    2016-09-01

    To estimate rates of suicidal behaviors and treated depression in patients with psoriatic arthritis (PsA) in comparison to non-PsA patients. Using the Clinical Practice Research Datalink, we conducted a cohort study of patients with PsA compared to non-PsA patients. Patients with codes for suicidal behaviors (ideation, attempts, and suicide) and treated depression (diagnosis plus anti-depressant prescription) recorded during follow-up were identified as cases. We estimated incidence rates (IRs) and incidence rate ratios (IRRs) with 95% confidence intervals (CIs) for each outcome and stratified results in the PsA cohort by receipt of systemic PsA drugs. The rates of suicide ideation, attempt, and suicide were similar for PsA and non-PsA patients [IRR = 0.99 (95%CI: 0.67-1.47), IRR = 1.07 (95%CI: 0.86-1.34), and 0.34 (95%CI: 0.05-2.48), respectively] and rates of suicidal behaviors were slightly higher among PsA patients who received PsA drugs compared to those who did not. PsA patients had slightly higher rate of treated depression compared to non-PsA patients [IRR = 1.38 (95%CI: 1.27-1.49)] and were significantly higher in PsA patients who received drugs [IRR = 1.59 (95%CI: 1.35-1.86)]. Rate of depression was higher in patients with PsA compared to non-PsA patients. The rate of suicidal behaviors was similar between the two cohorts.

  11. Interval between onset of psoriasis and psoriatic arthritis comparing the UK Clinical Practice Research Datalink with a hospital-based cohort.

    Science.gov (United States)

    Tillett, William; Charlton, Rachel; Nightingale, Alison; Snowball, Julia; Green, Amelia; Smith, Catherine; Shaddick, Gavin; McHugh, Neil

    2017-12-01

    To describe the time interval between the onset of psoriasis and PsA in the UK primary care setting and compare with a large, well-classified secondary care cohort. Patients with PsA and/or psoriasis were identified in the UK Clinical Practice Research Datalink (CPRD). The secondary care cohort comprised patients from the Bath PsA longitudinal observational cohort study. For incident PsA patients in the CPRD who also had a record of psoriasis, the time interval between PsA diagnosis and first psoriasis record was calculated. Comparisons were made with the time interval between diagnoses in the Bath cohort. There were 5272 eligible PsA patients in the CPRD and 815 in the Bath cohort. In both cohorts, the majority of patients (82.3 and 61.3%, respectively) had psoriasis before their PsA diagnosis or within the same calendar year (10.5 and 23.8%), with only a minority receiving their PsA diagnosis first (7.1 and 14.8%). Excluding those who presented with arthritis before psoriasis, the median time between diagnoses was 8 years [interquartile range (IQR) 2-15] in the CPRD and 7 years (IQR 0-20) in the Bath cohort. In the CPRD, 60.1 and 75.1% received their PsA diagnosis within 10 and 15 years of their psoriasis diagnosis, respectively; this was comparable with 57.2 and 67.7% in the Bath cohort. A similar distribution for the time interval between psoriasis and arthritis was observed in the CPRD and secondary care cohort. These data can inform screening strategies and support the validity of data from each cohort. © The Author 2017. Published by Oxford University Press on behalf of the British Society for Rheumatology. All rights reserved. For Permissions, please email: journals.permissions@oup.com

  12. Evaluation of methods to estimate missing days' supply within pharmacy data of the Clinical Practice Research Datalink (CPRD) and The Health Improvement Network (THIN).

    Science.gov (United States)

    Lum, Kirsten J; Newcomb, Craig W; Roy, Jason A; Carbonari, Dena M; Saine, M Elle; Cardillo, Serena; Bhullar, Harshvinder; Gallagher, Arlene M; Lo Re, Vincent

    2017-01-01

    The extent to which days' supply data are missing in pharmacoepidemiologic databases and effective methods for estimation is unknown. We determined the percentage of missing days' supply on prescription and patient levels for oral anti-diabetic drugs (OADs) and evaluated three methods for estimating days' supply within the Clinical Practice Research Datalink (CPRD) and The Health Improvement Network (THIN). We estimated the percentage of OAD prescriptions and patients with missing days' supply in each database from 2009 to 2013. Within a random sample of prescriptions with known days' supply, we measured the accuracy of three methods to estimate missing days' supply by imputing the following: (1) 28 days' supply, (2) mode number of tablets/day by drug strength and number of tablets/prescription, and (3) number of tablets/day via a machine learning algorithm. We determined incidence rates (IRs) of acute myocardial infarction (AMI) using each method to evaluate the impact on ascertainment of exposure time and outcomes. Days' supply was missing for 24 % of OAD prescriptions in CPRD and 33 % in THIN (affecting 48 and 57 % of patients, respectively). Methods 2 and 3 were very accurate in estimating days' supply for OADs prescribed at a consistent number of tablets/day. Method 3 was more accurate for OADs prescribed at varying number of tablets/day. IRs of AMI were similar across methods for most OADs. Missing days' supply is a substantial problem in both databases. Method 2 is easy and very accurate for most OADs and results in IRs comparable to those from method 3.

  13. Main technical options of the Jules Horowitz Reactor project to achieve high flux performances and high safety level

    International Nuclear Information System (INIS)

    Ballagny, A.; Bergamaschi, Y.; Bouilloux, Y.; Bravo, X.; Guigon, B.; Rommens, M.; Tremodeux, P.

    2003-01-01

    Since the shutdown of the SILOE reactor in 1997, the OSIRIS reactor has ensured the needs regarding technological irradiation at CEA including those of its industrial partners and customers. The Jules Horowitz Reactor will replace it and will offer a quite larger experimental field. It has the ambition to provide the necessary nuclear data and to maintain a fission research capability in Europe after 2010. The Jules Horowitz Reactor will represent a significant step in terms of performances and experimental capabilities. This paper will present the main design option resulting from the preliminary studies. The choice of the specific power around 600 KW/l for the reference core configuration is a key decision to ensure the required flux level. Consequently many choices have to be made regarding the materials used in the core and the fuel element design. These involve many specific qualifications including codes validation. The main safety options are based on: 1) A safety approach based upon the defence-in-depth principle. 2) A strategy of generic approaches to assess experimental risks in the facility. 3) Internal events analysis taking into account risks linked to reactor and experiments (eg., radioactive source-term). 4) Systematic consideration of external hazards (eg., earthquake, airplane crash) and internal hazards. 5) Design of containment to manage and mitigate a severe reactor accident (consideration of 'BORAX' accident, according to french safety practice for MTRs, beyond design basis reactivity insertion accident, involving core melting and core destruction phenomena). (author)

  14. Main technical options of the Jules Horowitz reactor project to achieve high flux performances and high safety level

    International Nuclear Information System (INIS)

    Ballagny, A.; Bergamaschi, Y.; Bouilloux, Y.; Bravo, X.; Guigon, B.; Rommens, M.; Tremodeux, P.

    2003-01-01

    Since the shutdown of the SILOE reactor in 1997, the OSIRIS reactor has ensured the needs regarding technological irradiation at CEA including those of its industrial partners and customers. The Jules Horowitz Reactor will replace it and will offer a quite larger experimental field. It has the ambition to provide the necessary nuclear data and to maintain a fission research capability in Europe after 2010. The Jules Horowitz Reactor will represent a significant step in terms of performances and experimental capabilities. This paper will present the main design option resulting from the preliminary studies. The choice of the specific power around 600 kW/I for the reference core configuration is a key decision to ensure the required flux level. Consequently many choices have to be made regarding the materials used in the core and the fuel element design. These involve many specific qualifications including codes validation. The main safety options are based on: - A safety approach based upon the defence-in-depth principle. - A strategy of generic approaches to assess experimental risks in the facility. - Internal events analysis taking into account risks linked to reactor and experiments (e.g., radioactive source-term). - Systematic consideration of external hazards (e.g., earthquake, airplane crash) and internal hazards. - Design of containment to manage and mitigate a severe reactor accident (consideration of 'BORAX' accident, according to french safety practice for MTRs, beyond design basis reactivity insertion accident, involving core melting and core destruction phenomena). (authors)

  15. Improving our PRODUCT: a quality and safety improvement project demonstrating the value of a preprocedural checklist for fluoroscopy.

    Science.gov (United States)

    Leschied, Jessica R; Glazer, Daniel I; Bailey, Janet E; Maturen, Katherine E

    2015-03-01

    To implement a preprocedural checklist in gastrointestinal (GI)/genitourinary (GU) fluoroscopy suites to assist radiology residents in performing studies with optimal fluoroscopic technique with a goal to lower radiation dose delivered to patients and operators. We introduced a preprocedural checklist in the form of a mnemonic to first-year resident fluoroscopy operators. The checklist was augmented by teaching sessions at the fluoroscopy tower. Fluoroscopy time (FT) was collected for GI/GU fluoroscopy studies performed by first-year residents who did not use the checklist (year 1) and compared with FT from first-year residents who used the checklist for one full academic year (year 2). Residents in both groups were surveyed to assess their knowledge of radiation safety at the end of their respective radiology 1 (R1) academic years. A total of 778 examinations were analyzed from year 1, and 941 total examinations from year 2. After implementation of the checklist, mean FT for all studies decreased by 41.1 seconds (P fluoroscopy tower operation increased slightly in year 2 (P = .144). A visual preprocedural radiation safety checklist in GI/GU fluoroscopy was associated with a reduction in mean FT and may contribute to a culture of radiation safety awareness. Copyright © 2015 AUR. Published by Elsevier Inc. All rights reserved.

  16. An Application Example Analysis of Quality Assurance Program for STELLA(Sodium Integral Effect Test Loop for Safety Simulation and Assessment) Project

    International Nuclear Information System (INIS)

    Jung, Minhwan; Gam, Dayoung; Eoh, Jae-Hyuk; Jeong, Ji-Young

    2015-01-01

    KAERI has been conducting various basic R and D activities in the field of nuclear technology. In addition, KAERI is now participating in the Generation IV International Forum (GIF), preparing for the development of key technologies for Generation IV nuclear energy system, including Sodium cooled Fast Reactor (SFR) development. All of the key technologies for SFR development need an appropriate level of QA activities to achieve the GIF safety and performance objectives. Therefore, QA activities have been conducted as an essential part of the national SFR project. As a result, QAM (Quality Assurance Manual) and QAP (Quality Assurance Procedures) have been developed for the SFR project, which are based on ASME NQA-1, KEPIC QAP and the GIF Quality Management System Guidelines. In this work, the introduction background and application examples of the QA program for the STELLA project were investigated. Application of the QA for the STELLA project has great significance because the QA has been mainly applied for the nuclear power plant area in operation, which helps ensure the reliability of the test data and completeness of the research performance. Nevertheless, developing more appropriate QA procedures remains a major task because some parts of them are not applicable to the Na-experiment

  17. An Application Example Analysis of Quality Assurance Program for STELLA(Sodium Integral Effect Test Loop for Safety Simulation and Assessment) Project

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Minhwan; Gam, Dayoung; Eoh, Jae-Hyuk; Jeong, Ji-Young [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    KAERI has been conducting various basic R and D activities in the field of nuclear technology. In addition, KAERI is now participating in the Generation IV International Forum (GIF), preparing for the development of key technologies for Generation IV nuclear energy system, including Sodium cooled Fast Reactor (SFR) development. All of the key technologies for SFR development need an appropriate level of QA activities to achieve the GIF safety and performance objectives. Therefore, QA activities have been conducted as an essential part of the national SFR project. As a result, QAM (Quality Assurance Manual) and QAP (Quality Assurance Procedures) have been developed for the SFR project, which are based on ASME NQA-1, KEPIC QAP and the GIF Quality Management System Guidelines. In this work, the introduction background and application examples of the QA program for the STELLA project were investigated. Application of the QA for the STELLA project has great significance because the QA has been mainly applied for the nuclear power plant area in operation, which helps ensure the reliability of the test data and completeness of the research performance. Nevertheless, developing more appropriate QA procedures remains a major task because some parts of them are not applicable to the Na-experiment.

  18. The fetal heart rate collaborative practice project: situational awareness in electronic fetal monitoring-a Kaiser Permanente Perinatal Patient Safety Program Initiative.

    Science.gov (United States)

    MacEachin, S Rachel; Lopez, Connie M; Powell, Kimberly J; Corbett, Nancy L

    2009-01-01

    Electronic fetal monitoring has historically been interpreted with wide variation between and within disciplines on the obstetric healthcare team. This leads to inconsistent decision making in response to tracing interpretation. To implement a multidisciplinary electronic fetal monitoring training program, utilizing the best evidence available, enabling standardization of fetal heart rate interpretation to promote patient safety. Local multidisciplinary expertise along with an outside consultant collaborated over a series of meetings to create a multimedia instructional electronic fetal monitoring training program. After production was complete, a series of conferences attended by nurses, certified nurse midwives, and physician champions, from each hospital, attended to learn how to facilitate training at their own perinatal units. All healthcare personnel across the Kaiser Permanente perinatal program were trained in NICHD nomenclature, emergency response, interpretation guidelines, and how to create local collaborative practice agreements. Metrics for program effectiveness were measured through program evaluations from attendees, the Safety Attitudes Questionnaire. Program evaluations rendered very positive scores from both physicians and clinicians. Comparing baseline to 4 years later, the perception of safety from the staff has increased over 10% in 5 out of the 6 factors analyzed. Active participation from all disciplines in this training series has highlighted the importance of teamwork and communication. The Fetal Heart Rate Collaborative Practice Project continues to evolve utilizing other educational modalities, such as online EFM education and unit-based interdisciplinary tracing reviews.

  19. Spacecraft Fire Safety Demonstration

    Data.gov (United States)

    National Aeronautics and Space Administration — The objective of the Spacecraft Fire Safety Demonstration project is to develop and conduct large-scale fire safety experiments on an International Space Station...

  20. Nuclear and non-nuclear safety aspects in nuclear facilities dismantling. The example of a PWR pilot decommissioning project

    International Nuclear Information System (INIS)

    Massaut, V.; Deboodt, P.; Dadoumont, J.; Valenduc, P.; Denissen, L.

    2002-01-01

    The dismantling of nuclear facilities, and in particular of nuclear power plants, involves new challenges for the nuclear industry. Although the dismantling of various activated and contaminated components is nowadays considered as almost industrial practice, the safety aspects of decommissioning bring some specific features which are not always taken into account in the operation of the plants. Moreover, most of the plants and facilities currently decommissioned are rather old and were never foreseen to be decommissioned. The operations involved in dismantling and decontamination, often imply new or unforeseen situations. On the nuclear, or radiological side, the radioprotection optimisation of the operations involved often requires to model the environment and to analyse different scenarios to tackle the operation. Recent 3-D software (like the Visiplan software) allowing representation of the actual environment and the influence of the various sources present, is really needed to be able to minimise the radiological impact on the operators. The risk of contamination spread, by opening loops and components or by the dismantling process itself, is also an important aspect of the radiological protection study. Nevertheless, the radiological aspects of the safety approach are not the only ones to be dealt with when decommissioning nuclear facilities. Indeed, classical industrial safety aspects are also important: the dismantling can bring handling and transporting risk (heavy loads, difficult ways, uneasy access, etc.) but also the handling of toxic or hazardous materials. For instance, the removal of asbestos in contaminated areas can lead to additional hazard; the presence of alkali metals (like Na or NaK), of toxic metals (like e.g. Beryllium) or of corrosive fluids (acid,...) have to be tackled often in unstructured environment, and sometimes with limited knowledge of the actual situation. This leads to approach the operations following the ASARA principle (As

  1. Efficacy and safety of anakinra for the treatment of rheumatoid arthritis: an update of the Oregon Drug Effectiveness Review Project

    Science.gov (United States)

    Thaler, Kylie; Chandiramani, Divya V; Hansen, Richard A; Gartlehner, Gerald

    2009-01-01

    Objective To systematically review the general and comparative efficacy and safety of anakinra for rheumatoid arthritis. Methods We searched MEDLINE®, Embase, The Cochrane Library, and the International Pharmaceutical Abstracts from 1980 to April 2009. We manually searched reference lists of pertinent review articles and explored the Center for Drug Evaluation and Research database. For efficacy we included randomized controlled trials (RCTs) comparing anakinra with placebo or other biologics. For safety both experimental and observational studies were eligible. Two persons independently reviewed abstracts and full text articles and extracted relevant data. Results We included data from 3 RCTs comparing anakinra with placebo for rheumatoid arthritis (RA). The pooled relative risk (RR) of an ACR50 (American College of Rheumatology) response for anakinra compared with placebo is 2.28 (95% CI 1.41 to 3.67). Adjusted indirect comparisons of ACR50 response rates of anakinra and anti-TNF agents showed a RR of 0.67 (95% CI 0.38 to 1.17) favoring the anti-TNF drugs. This result did not reach statistical significance. For safety, we included 9 experimental and observational studies of 24 weeks to 3 years duration. Up to 30% of patients withdrew from the studies due to adverse events. 67.2% (95% CI 38.7 to 95.7) of patients experienced an injection site reaction. Conclusions Anakinra is an effective drug for treating RA. Indirect comparisons with adalimumab, etanercept and infliximab, however, showed a trend towards greater efficacy for the anti-TNF drugs. Anakinra also seems to be associated with comparably high rates of injection site reactions. These results should be taken into account when considering biologic therapy for patients with RA. PMID:20054439

  2. 77 FR 46764 - Clinical Studies of Safety and Effectiveness of Orphan Products Research Project Grant (R01)

    Science.gov (United States)

    2012-08-06

    ... Products Research Project Grant (R01) AGENCY: Food and Drug Administration, HHS. ACTION: Notice. SUMMARY... people in the United States per year. B. Research Objectives The goal of FDA's OPD grant program is to...: Register With Electronic Research Administration (eRA) Commons Steps 1 through 5, in detail, can be found...

  3. 75 FR 47602 - Clinical Studies of Safety and Effectiveness of Orphan Products Research Project Grant (R01)

    Science.gov (United States)

    2010-08-06

    ... Products Research Project Grant (R01) AGENCY: Food and Drug Administration, HHS. ACTION: Notice. SUMMARY... per year. B. Research Objectives The goal of FDA's OPD grant program is to support the clinical...: Track AOR Status Step 6: Register With Electronic Research Administration (eRA) Commons Steps 1 through...

  4. Experimental studies of thermo-hydraulic processes during passive safety systems operation in new WWER NPP projects

    International Nuclear Information System (INIS)

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

    2014-01-01

    The results of experimental study of thermal-hydraulic processes during operation of the passive safety systems of WWER reactors of new generation are given. The interaction processes of counter flows of saturated steam and cold water in vertical steam-line of the auxiliary passive core reflood system from secondary hydraulic accumulator are studied. The peculiarities of undeveloped boiling on single horizontal tube heating by steam and steam-gas mixture, which is character for WWER steam generator condensing mode, are investigated [ru

  5. Seismic Safety Margins Research Program (Phase I). Project I. Plant/site selection, plant/site selection assessment report

    International Nuclear Information System (INIS)

    Reed, R.L.

    1979-01-01

    Lawrence Livermore Laboratory (LLL) is conducting research on the seismic risk of nuclear power plants through the Seismic Safety Margins Research Program (SSMRP). Phase I of the SSMRP will include a study of an existing plant and site. Results are presented of a study of existing and planned nuclear power plants in the United States. Selection criteria were developed and a recommendation for a specific plant for the SSMRP Phase I effort is given. Power plant characteristics including types of nuclear steam supply steam, containment structure, electric power capacity, geographic location, site seismicity, and foundation soil properties were evaluated

  6. Assessment of passive safety injection systems of ALWRs. Final report of the European Commission 4th framework programme. Project FI4I-CT95-004 (APSI)

    International Nuclear Information System (INIS)

    Tuunanen, J.; D'Auria, F.; Kimber, G.

    1999-01-01

    The European Commission 4th Framework Programme project 'Assessment of Passive Safety Injection Systems of Advanced Light Water Reactors (FI4I-CT95-0004)' involved experiments on the PACTEL test facility and computer simulations of selected experiments. The experiments focused on the performance of Passive Safety Injection Systems (PSIS) of Advanced Light Water Reactors (ALWRs) in Small Break Loss-Of-Coolant Accident (SBLOCA) conditions. The PSIS consisted of a Core Make-up Tank (CMT) and two pipelines. A pressure balancing line (PBL) connected the CMT to one cold leg. The injection line (IL) connected it to the downcomer. The project involved 15 experiments in three series. The experiments provided valuable information about condensation and heat transfer processes in the CMT, thermal stratification of water in the CMT, and natural circulation flow through the PSIS lines. The experiments showed the examined PSIS works efficiently in SBLOCAs although the flow through the PSIS may stop in very small SBLOCAs, when the hot water fills the CMT. The experiments also demonstrated the importance of flow distributor (sparger) in the CMT to limit rapid condensation. The project included validation of three thermal-hydraulic computer codes (APROS, CATHARE and RELAP5). The analyses showed the codes are capable of simulating the overall behaviour of the transients. The codes predicted accurately the core heatup, which occurred when the primary coolant inventory was reduced so much that the core top became free of water. The detailed analyses of the calculation results showed that some models in the codes still need improvements. Especially, further development of models for thermal stratification, condensation and natural circulation flow with small driving forces would be necessary for accurate simulation of phenomena in the PSIS. (orig.)

  7. Health and safety plan for the Molten Salt Reactor Experiment remediation project at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Burman, S.N.; Uziel, M.S.

    1995-12-01

    The Lockheed Martin Energy Systems, Inc., (Energy Systems) policy is to provide a safe and healthful workplace for all employees and subcontractors. The accomplishment of the policy requires that operations at the Molten Salt Reactor Experiment (MSRE) facility at the Department of Energy (DOE) Oak Ridge National Laboratory (ORNL) are guided by an overall plan and consistent proactive approach to safety and health (S and H) issues. The policy and procedures in this plan apply to all MSRE operations. The provisions of this plan are to be carried out whenever activities are initiated at the MSRE that could be a threat to human health or the environment. This plan implements a policy and establishes criteria for the development of procedures for day-to-day operations to prevent or minimize any adverse impact to the environment and personnel safety and health and to meet standards that define acceptable management of hazardous and radioactive materials and wastes. The plan is written to utilize past experience and the best management practices to minimize hazards to human health or the environment from events such as fires, explosions, falls, mechanical hazards, or any unplanned release of hazardous or radioactive materials to the air

  8. Health and safety plan for the Molten Salt Reactor Experiment remediation project at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    Burman, S.N.; Uziel, M.S.

    1995-12-01

    The Lockheed Martin Energy Systems, Inc., (Energy Systems) policy is to provide a safe and healthful workplace for all employees and subcontractors. The accomplishment of the policy requires that operations at the Molten Salt Reactor Experiment (MSRE) facility at the Department of Energy (DOE) Oak Ridge National Laboratory (ORNL) are guided by an overall plan and consistent proactive approach to safety and health (S and H) issues. The policy and procedures in this plan apply to all MSRE operations. The provisions of this plan are to be carried out whenever activities are initiated at the MSRE that could be a threat to human health or the environment. This plan implements a policy and establishes criteria for the development of procedures for day-to-day operations to prevent or minimize any adverse impact to the environment and personnel safety and health and to meet standards that define acceptable management of hazardous and radioactive materials and wastes. The plan is written to utilize past experience and the best management practices to minimize hazards to human health or the environment from events such as fires, explosions, falls, mechanical hazards, or any unplanned release of hazardous or radioactive materials to the air.

  9. Nuclear safety in perspective

    DEFF Research Database (Denmark)

    Andersson, K.; Sjöberg, B.M.D.; Lauridsen, Kurt

    2003-01-01

    The aim of the NKS/SOS-1 project has been to enhance common understanding about requirements for nuclear safety by finding improved means of communicat-ing on the subject in society. The project, which has been built around a number of seminars, wassupported by limited research in three sub......-projects: Risk assessment Safety analysis Strategies for safety management The report describes an industry in change due to societal factors. The concepts of risk and safety, safety management and systems forregulatory oversight are de-scribed in the nuclear area and also, to widen the perspective, for other...

  10. Considerations on safety against seismic excitations in the project of reactor auxiliary building and control building in nuclear power plants

    International Nuclear Information System (INIS)

    Santos, S.H.C.; Castro Monteiro, I. de

    1986-01-01

    The seismic requests to be considered in the project of main buildings of a nuclear power plant are discussed. The models for global seismic analysis of nuclear power plant structures, as well as models for global strength distribution are presented. The models for analysing reactor auxiliary building and control building, which together with the reactor building and turbine building form the main energy generation complex in a nuclear power plant, are described. (M.C.K.) [pt

  11. Accident and safety analyses for the HTR-modul. Partial project 1: Computer codes for system behaviour calculation. Final report. Pt. 2

    International Nuclear Information System (INIS)

    Lohnert, G.; Becker, D.; Dilcher, L.; Doerner, G.; Feltes, W.; Gysler, G.; Haque, H.; Kindt, T.; Kohtz, N.; Lange, L.; Ragoss, H.

    1993-08-01

    The project encompasses the following project tasks and problems: (1) Studies relating to complete failure of the main heat transfer system; (2) Pebble flow; (3) Development of computer codes for detailed calculation of hypothetical accidents; (a) the THERMIX/RZKRIT temperature buildup code (covering a.o. a variation to include exothermal heat sources); (b) the REACT/THERMIX corrosion code (variation taking into account extremely severe air ingress into the primary loop); (c) the GRECO corrosion code (variation for treating extremely severe water ingress into the primary loop); (d) the KIND transients code (for treating extremely fast transients during reactivity incidents. (4) Limiting devices for safety-relevant quantities. (5) Analyses relating to hypothetical accidents. (a) hypothetical air ingress; (b) effects on the fuel particles induced by fast transients. The problems of the various tasks are defined in detail and the main results obtained are explained. The contributions reporting the various project tasks and activities have been prepared for separate retrieval from the database. (orig./HP) [de

  12. Accident and safety analyses for the HTR-modul. Partial project 1: Computer codes for system behaviour calculation. Final report. Pt. 1

    International Nuclear Information System (INIS)

    Lohnert, G.; Becker, D.; Dilcher, L.; Doerner, G.; Feltes, W.; Gysler, G.; Haque, H.; Kindt, T.; Kohtz, N.; Lange, L.; Ragoss, H.

    1993-08-01

    The project encompasses the following project tasks and problems: (1) Studies relating to complete failure of the main heat transfer system; (2) Pebble flow; (3) Development of computer codes for detailed calculation of hypothetical accidents; (a) the THERMIX/RZKRIT temperature buildup code (covering a.o. a variation to include exothermal heat sources); (b) the REACT/THERMIX corrosion code (variation taking into account extremely severe air ingress into the primary loop); (c) the GRECO corrosion code (variation for treating extremely severe water ingress into the primary loop); (d) the KIND transients code (for treating extremely fast transients during reactivity incidents. (4) Limiting devices for safety-relevant quantities. (5) Analyses relating to hypothetical accidents. (a) hypothetical air ingress; (b) effects on the fuel particles induced by fast transients. The problems of the various tasks are defined in detail and the main results obtained are explained. The contributions reporting the various project tasks and activities have been prepared for separate retrieval from the database. (orig./HP) [de

  13. Nuclear threats in the vicinity of the Nordic countries. Final report of the Nordic Nuclear Safety Research project SBA-1

    International Nuclear Information System (INIS)

    Eikelmann, I.M.H.

    2002-11-01

    The acute phase of a nuclear accident and the possibility of high exposure of the populations are always the most important threats in the emergency preparedness work. Radioactive contamination from an accident can however also cause long term effects for land use and enhanced doses to special population groups and economic problems for agriculture, reindeer industry, hunting, tourism and recreation. For planning purposes it is always valuable to be aware of surrounding radiation hazards and other potential threats. Thus, mapping such threats in a Nordic context is an important factor in emergency preparedness in the area. This report presents a cross-disciplinary study from the NKS research program 1998-2001.The scope of the project was to prepare a 'base of knowledge' regarding possible nuclear threats in the vicinity of the Nordic countries. This base of knowledge will, by modere information technology as different websites, be made available to authorities, media and the population. The users of the websites can easily get information on different types of nuclear installations and threats. The users can get an overview of the situation and, if they so wish, make their own judgements. The project dealt with a geographical area including North-west Russia and the Baltic states. The results from the different activities in the project were generated in a web based database called the 'the base of knowledge'. Key words Nuclear threats, Nordic countries, nuclear power plants, nuclear ship, nuclear waste, literature database, base of knowledge, webaccessed information, atmospheric transport, decommissioning of submarines, nuclear installations, waste management, radioactive contamination in marine environment, radioactive sources, criticality analysis. (au)

  14. Nuclear threats in the vicinity of the Nordic countries. Final report of the Nordic Nuclear Safety Research project SBA-1

    Energy Technology Data Exchange (ETDEWEB)

    Eikelmann, I.M.H. [Norwegian Radiation Protection Authority (Norway)

    2002-11-01

    The acute phase of a nuclear accident and the possibility of high exposure of the populations are always the most important threats in the emergency preparedness work. Radioactive contamination from an accident can however also cause long term effects for land use and enhanced doses to special population groups and economic problems for agriculture, reindeer industry, hunting, tourism and recreation. For planning purposes it is always valuable to be aware of surrounding radiation hazards and other potential threats. Thus, mapping such threats in a Nordic context is an important factor in emergency preparedness in the area. This report presents a cross-disciplinary study from the NKS research program 1998-2001.The scope of the project was to prepare a 'base of knowledge' regarding possible nuclear threats in the vicinity of the Nordic countries. This base of knowledge will, by modere information technology as different websites, be made available to authorities, media and the population. The users of the websites can easily get information on different types of nuclear installations and threats. The users can get an overview of the situation and, if they so wish, make their own judgements. The project dealt with a geographical area including North-west Russia and the Baltic states. The results from the different activities in the project were generated in a web based database called the 'the base of knowledge'. Key words Nuclear threats, Nordic countries, nuclear power plants, nuclear ship, nuclear waste, literature database, base of knowledge, webaccessed information, atmospheric transport, decommissioning of submarines, nuclear installations, waste management, radioactive contamination in marine environment, radioactive sources, criticality analysis. (au)

  15. Trends in the incidence of chronic fatigue syndrome and fibromyalgia in the UK, 2001-2013: a Clinical Practice Research Datalink study.

    Science.gov (United States)

    Collin, Simon M; Bakken, Inger J; Nazareth, Irwin; Crawley, Esther; White, Peter D

    2017-06-01

    Objective Trends in recorded diagnoses of chronic fatigue syndrome (CFS, also known as 'myalgic encephalomyelitis' (ME)) and fibromyalgia (FM) in the UK were last reported more than ten years ago, for the period 1990-2001. Our aim was to analyse trends in incident diagnoses of CFS/ME and FM for the period 2001-2013, and to investigate whether incidence might vary by index of multiple deprivation (IMD) score. Design Electronic health records cohort study. Setting NHS primary care practices in the UK. Participants Participants: Patients registered with general practices linked to the Clinical Practice Research Datalink (CPRD) primary care database from January 2001 to December 2013. Main outcome measure Incidence of CFS/ME, FM, post-viral fatigue syndrome (PVFS), and asthenia/debility. Results The overall annual incidence of recorded cases of CFS/ME was 14.8 (95% CI 14.5, 15.1) per 100,000 people. Overall annual incidence per 100,000 people for FM was 33.3 (32.8-33.8), for PVFS 12.2 (11.9, 12.5), and for asthenia/debility 7.0 (6.8, 7.2). Annual incidence rates for CFS/ME diagnoses decreased from 17.5 (16.1, 18.9) in 2001 to 12.6 (11.5, 13.8) in 2013 (annual percent change -2.8% (-3.6%, -2.0%)). Annual incidence rates for FM diagnoses decreased from 32.3 (30.4, 34.3) to 27.1 (25.5, 28.6) in 2007, then increased to 38.2 (36.3, 40.1) per 100,000 people in 2013. Overall annual incidence of recorded fatigue symptoms was 2246 (2242, 2250) per 100,000 people. Compared with the least deprived IMD quintile, incidence of CFS/ME in the most deprived quintile was 39% lower (incidence rate ratio (IRR) 0.61 (0.50, 0.75)), whereas rates of FM were 40% higher (IRR 1.40 (0.95, 2.06)). Conclusion These analyses suggest a gradual decline in recorded diagnoses of CFS/ME since 2001, and an increase in diagnoses of fibromyalgia, with opposing socioeconomic patterns of lower rates of CFS/ME diagnoses in the poorest areas compared with higher rates of FM diagnoses.

  16. A validation study of the CirCom comorbidity score in an English cirrhosis population using the Clinical Practice Research Datalink

    Directory of Open Access Journals (Sweden)

    Crooks CJ

    2018-01-01

    Full Text Available Colin J Crooks,1,2 Joe West,1,2 Peter Jepsen3,4 1Division of Epidemiology and Public Health, University of Nottingham, Nottingham, UK; 2Nottingham Digestive Diseases Biomedical Research Centre, School of Medicine, University of Nottingham, Nottingham, UK; 3Department of Hepatology and Gastroenterology, Aarhus University Hospital, Aarhus, Denmark; 4Department of Clinical Epidemiology, Aarhus University Hospital, Aarhus, Denmark Purpose: The CirCom score has been developed from Danish data as a specific measure of comorbidity for cirrhosis to predict all-cause mortality. We compared its performance with the Charlson Comorbidity Index (CCI in an English cirrhosis population. Patients and methods: We used comorbidity scores in a survival model to predict mortality in a cirrhosis cohort in the Clinical Practice Research Datalink. The discrimination of each score was compared by age, gender, socioeconomic status, cirrhosis etiology, cirrhosis stage, and year after cirrhosis diagnosis. We also measured their ability to predict liver-related versus non-liver-related death.Results: There was a small improvement in the C statistic from the model using the CirCom score (C=0.63 compared to the CCI (C=0.62, and there was an overall improvement in the net reclassification index of 1.5%. The improvement was more notable in younger patients, those with an alcohol etiology, and those with compensated cirrhosis. Both scores performed better (C statistic >0.7 for non-liver-related deaths than liver-related deaths (C statistic <0.6, as comorbidity was only weakly predictive of liver-related death.Conclusion: The CirCom score provided a small improvement in performance over the CCI in the prediction of all-cause and non-liver mortality, but not liver-related mortality. Therefore, it is important to include a measure of comorbidity in studies of cirrhosis survival, alongside a measure of cirrhosis severity. Keywords: cirrhosis, mortality, comorbidity, prognosis

  17. Annual report on reactor safety research projects sponsored by the Ministry for Research and Technology of the Federal Republic of Germany. Reporting period 1993. Progress report

    International Nuclear Information System (INIS)

    1994-10-01

    The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, by order of the BMFT, informs continuously of the status of such investigations by means of semi-annual and annual publication of progress reports within the series GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by the Forschungsbetreuung at the GRS, (FB) (Research Coordination Department), within the framework of general information of progress in reactor safety research. The individual reports are classified according to the same classification system as applied in the nuclear index of the CEC (Commission of the European Communities) and the OECD (Organization for Economic Cooperation and Development). The reports are arranged in sequence of their project numbers. (orig./HP)

  18. National Dam Safety Program. Millbrook Watershed Project Site I (inventory Number NY 715) Susquehanna River Basin, Chenango County, New York. Phase 1 Inspection Report

    Science.gov (United States)

    1980-09-30

    Milibrook Watershed Project Site T fn~ %/ V National. Darm Safety Program Albny 1223 6. PJERMN ORG RAE04 NUBE Department of th Ar4 Neworek, No 128 9...4U CA > c~ 9%1 Ul NU.LUr -w Z CC 00 tn U.0D L ft SA. .4 ft 0WO ’ O ~02 cmi at 0 0 LA . 30S-U 30 0 ... J 00 z A ~0 3l zu 0 &u .ft~z ft 0 00 -. Q U. m...m m -4 4( -- jC 1- h .0 m -14 0. ~~Ia U% -4-4 tI L.4ET ID eu - - - - - N CU44-. -4..-4 - -L U SlU 20 uv0. 0. zcc f 0 LL U W LA N 0 - a U~ a. C.cr r L

  19. Annual report on reactor safety research projects sponsored by the Ministry for Research and Technology of the Federal Republic of Germany 1988

    International Nuclear Information System (INIS)

    1989-06-01

    The GRS (Society for Reactor Safety), Gesellschaft fuer Reaktorsicherheit mbH, by order of the BMFT, informs continuously of the status of such investigations by means of semi-annual and annual publication of progress reports within the series GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about objectives, the work performed, the results, the next steps of the work etc. The individual reports are prepared in a standard form by the contractors themselves as a documentation of their progress in work and published by the FB (Research Coordination Department) Forschungsbetreuung at the GRS, within the framework of general information of progress in the reactor safety research. The individual reports are classified according to the same classification system as applied in the nuclear index of the CEC (Commission of the European Communities) and the OECD (Organization for Economic Cooperation and Development). The reports are arranged in sequence of their project numbers. Besides the progress reports, lists of reports exchanged under international exchange agreements by the BMFT are published within this series. (orig./HP)

  20. FMCSA’s advanced system testing utilizing a data acquisition system on the highways (FAST DASH) safety technology evaluation project #3 : novel convex mirrors : technology brief.

    Science.gov (United States)

    2016-11-01

    The Federal Motor Carrier Safety Administration (FMCSA) established the FAST DASH program to perform efficient independent evaluations of promising safety technologies aimed at commercial vehicle operations. In this third FAST DASH safety technology ...

  1. Multimegawatt Space Reactor Safety

    International Nuclear Information System (INIS)

    Stanley, M.L.

    1989-01-01

    The Multimegawatt (MMW) Space Reactor Project supports the Strategic Defense Initiative Office requirement to provide reliable, safe, cost-effective, electrical power in the MMW range. Specifically, power may be used for neutral particle beams, free electron lasers, electromagnetic launchers, and orbital transfer vehicles. This power plant technology may also apply to the electrical power required for other uses such as deep-space probes and planetary exploration. The Multimegawatt Space Reactor Project, the Thermionic Fuel Element Verification Program, and Centaurus Program all support the Multimegawatt Space Nuclear Power Program and form an important part of the US Department of Energy's (DOE's) space and defense power systems activities. A major objective of the MMW project is the development of a reference flight system design that provides the desired levels of public safety, health protection, and special nuclear material (SNM) protection when used during its designated missions. The safety requirements for the MMW project are a hierarchy of requirements that consist of safety requirements/regulations, a safety policy, general safety criteria, safety technical specifications, safety design specifications, and the system design. This paper describes the strategy and philosophy behind the development of the safety requirements imposed upon the MMW concept developers. The safety organization, safety policy, generic safety issues, general safety criteria, and the safety technical specifications are discussed

  2. Geo scientific basis for making the safety case for a SF/HL W/IL W repository in Opalinus clay in ne Switzerland (project Entsorgungsnachweis) 1: overview and main conclusions

    International Nuclear Information System (INIS)

    Gautschi, A.; Lambert, A.; Zuidema, P.

    2004-01-01

    This paper provides an overview of the geo-scientific basis and the main conclusions concerning the safety case for Project Entsorgungsnachweis (Nagra, 2002a, see first paper). The key geo-scientific input for the safety case is summarised in the following three papers. The data and arguments are discussed in great detail in Nagra (2002b) and in numerous reference reports cited therein. (author)

  3. Analysis of scholar transport safety based upon accidentology and benchmarking database. Delivrable D1.1. SAFEWAY2SCHOOL report: seventh framework programme Sustainable surface transport (SST)-2008-RTD-1 Collaborative project 233967

    OpenAIRE

    PAUZIE, A; JANKOWSKA, D; EGGER, S; MUNKSTEDT, S; SPENCE, A; ANUND, A; MONTARINI, R; FERRARINI, C

    2010-01-01

    This report is based upon knowledge available, on one hand on road safety issues and context (A1.1, Del 1.4 : accident analysis database) and, on the other hand, on technologies on the market or under development developed in current research projects, including related measures and guidelines (A1.3, Benchmarking database). For each of these topics, a small paragraph overviews the current context and safety issues, functional concept and maturity of available technology, identified European p...

  4. Road safety audit tools, procedures, and experiences : a literature review and recommendations : research in the framework of the European research project Safety Standards for Road Design and Redesign SAFESTAR, Workpackage 8.

    NARCIS (Netherlands)

    Kooi, R.M. van der

    1999-01-01

    This report describes tools and procedures established in different countries which apply Road Safety Audits (RSA). These RSAs are utilized to identify potential safety problems and they concentrate on safety measures to overcome these problems. This technique is used to detect possible safety

  5. Review of interactions between climate policy and energy safety in Europe (ELIPSE project) - Final report, December 2012

    International Nuclear Information System (INIS)

    Guivarch, Celine; Rozenberg, Julie; Vogt-Schilb, Adrien; Monjon, Stephanie

    2013-01-01

    The ELIPSE project is a better understanding of the consequences of ambitious energy policies for a secure energy in Europe. It is based on a choice of indicators for a secure energy which are related to availability and diversification, energy dependence and efficiency, energy cost for the society, and acceptability. Four RCP (representative concentration pathways) scenarios are selected. Their results are discussed, notably in terms of evolution of emissions, of evolution of the carbon tax, of carbon-tax variability, of GDP growth according to scenarios with or without climate policy, of primary energy supply with or without climate policy, of oil supply in Europe and oil prices with or without climate policy. The authors discuss the perspectives of evolution of energy security in Europe on the short, medium or long term, and the influence of different factors. They discuss the development and spreading of low carbon technologies (renewable energies, carbon capture and storage, electric vehicles)

  6. Position adopted by the government about the safety options of the EPR reactor project; Prise de position du gouvernement concernant les options de surete du projet de reacteur EPR

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-10-01

    On September 28, 2004, on behalf of the French ministers in charge of nuclear safety, the general director of nuclear safety and radiation protection addressed to the president of Electricite de France (EdF) a letter presenting the government's position about the safety options of the EPR (European Pressurized Reactor) project. On the basis of the examination carried out by the nuclear safety authority (ASN) and by the permanent group of reactor experts, the government has considered these options as satisfactory with respect to the safety improvement objectives. Therefore, the government requested EdF to comply with these technical rules for any future reactor development. This dossier includes: the letter of the government, the technical directives for the design and construction of the next generation of PWR-type reactors, the technical rules relative to the design of the main primary and secondary coolant circuits of PWR-type reactors, and the technical file about the safety of the EPR project reprinted from the 2003 report of nuclear safety and radiation protection authority. (J.S.)

  7. Developing a Practical and Sustainable Faculty Development Program With a Focus on Teaching Quality Improvement and Patient Safety: An Alliance for Independent Academic Medical Centers National Initiative III Project.

    Science.gov (United States)

    Rodrigue, Christopher; Seoane, Leonardo; Gala, Rajiv B; Piazza, Janice; Amedee, Ronald G

    2012-01-01

    Teaching the next generation of physicians requires more than traditional teaching models. The Accreditation Council for Graduate Medical Education's Next Accreditation System places considerable emphasis on developing a learning environment that fosters resident education in quality improvement and patient safety. The goal of this project was to develop a comprehensive and sustainable faculty development program with a focus on teaching quality improvement and patient safety. A multidisciplinary team representing all stakeholders in graduate medical education developed a validated survey to assess faculty and house officer baseline perceptions of their experience with faculty development opportunities, quality improvement tools and training, and resident participation in quality improvement and patient safety programs at our institution. We then developed a curriculum to address these 3 areas. Our pilot survey revealed a need for a comprehensive program to teach faculty and residents the art of teaching. Two other areas of need are (1) regular resident participation in quality improvement and patient safety efforts and (2) effective tools for developing skills and habits to analyze practices using quality improvement methods. Resident and faculty pairs in 17 Ochsner training programs developed and began quality improvement projects while completing the first learning module. Resident and faculty teams also have been working on the patient safety modules and incorporating aspects of patient safety into their individual work environments. Our team's goal is to develop a sustainable and manageable faculty development program that includes modules addressing quality improvement and patient safety in accordance with Accreditation Council for Graduate Medical Education accreditation requirements.

  8. A EU simulation platform for nuclear reactor safety: multi-scale and multi-physics calculations, sensitivity and uncertainty analysis (NURESIM project)

    International Nuclear Information System (INIS)

    Chauliac, Christian; Bestion, Dominique; Crouzet, Nicolas; Aragones, Jose-Maria; Cacuci, Dan Gabriel; Weiss, Frank-Peter; Zimmermann, Martin A.

    2010-01-01

    The NURESIM project, the numerical simulation platform, is developed in the frame of the NURISP European Collaborative Project (FP7), which includes 22 organizations from 14 European countries. NURESIM intends to be a reference platform providing high quality software tools, physical models, generic functions and assessment results. The NURESIM platform provides an accurate representation of the physical phenomena by promoting and incorporating the latest advances in core physics, two-phase thermal-hydraulics and fuel modelling. It includes multi-scale and multi-physics features, especially for coupling core physics and thermal-hydraulics models for reactor safety. Easy coupling of the different codes and solvers is provided through the use of a common data structure and generic functions (e.g., for interpolation between non-conforming meshes). More generally, the platform includes generic pre-processing, post-processing and supervision functions through the open-source SALOME software, in order to make the codes more user-friendly. The platform also provides the informatics environment for testing and comparing different codes. The contribution summarizes the achievements and ongoing developments of the simulation platform in core physics, thermal-hydraulics, multi-physics, uncertainties and code integration

  9. The design, safety and project development status of the modular high temperature gas-cooled reactor in the United States

    International Nuclear Information System (INIS)

    Mears, L.D.; Dean, R.A.

    1987-01-01

    The cooperative government and industry Modular High Temperature Gas-Cooled Reactor (MHTGR) Program in the United States has advanced a 350 MW(t) plant design through the conceptual development stage. The system incorporates an annular core of prismatic fuel elements within a steel pressure vessel connected, in a side-by-side arrangement, by a concentric duct to a second steel vessel containing a steam generator and helium coolant circulator. The reference plant design consists of four reactor modules installed in separate below-grade silos, providing steam to two conventional turbine generators. The nominal net plant output is 540 MW(e). The small reactor system takes unique advantage of the high temperature capability of the refractory coated fuel and the large thermal inertia of the graphite moderator to provide a design capable of withstanding a complete loss of active core cooling without causing excessive core heatup and significant release of fission products from the fuel. Present program activities are concentrated on interactions with the Nuclear Regulatory Commission aimed at obtaining a Licensability Statement. A project initiative to build a prototype plant which would demonstrate the MHTGR-unique licensing process, plant performance, costs and schedule plus establish an industrial infrastructure to proceed with follow-on commercial MHTGR plants by the turn of the century, is being undertaken by the utility/vendor participants (author)

  10. Operational safety

    International Nuclear Information System (INIS)

    Anon.

    1977-01-01

    The PNL Safety, Standards and Compliance Program contributed to the development and issuance of safety policies, standards, and criteria; for projects in the nuclear and nonnuclear areas. During 1976 the major emphasis was on developing criteria, instruments and methods to assure that radiation exposure to occupational personnel and to people in the environs of nuclear-related facilities is maintained at the lowest level technically and economically practicable. Progress in 1976 is reported on the preparation of guidelines for radiation exposure; Pu dosimetry studies; the preparation of an environmental monitoring handbook; and emergency instrumentation preparedness

  11. Safety and security of energy infrastructures in Europe - the EC - DG JRC's energy risks monitor (ERMON) project

    International Nuclear Information System (INIS)

    Kirchsteiger, C.

    2005-01-01

    Full text: Technological progress is directed towards fulfilling human needs for development and progress. At the same time, the detriments or risks arising from specific technologies can not be avoided. The potential public health, environmental and economic risk impact of technologies is therefore a topic of considerable public and professional debate across all different industry sectors, - from energy production to transport and process industries. This demonstrates the need for all different types of risks to be systematically assessed and managed in order to protect public health and safety, and to limit the environmental and economic impacts of potential accidents. Risk-based methods provide various qualitative and quantitative measures that can significantly support consistent decision-making on managing accidental risks related to a specific technology across its entire life cycle, both for harmful effects inside the installation and off-site (for fixed installations). However, these methods rarely consider the requirements of individuals who suddenly find themselves in need of information on the 'risk dimension' of a certain technology compared to alternatives with similar benefits. Therefore, there is a necessity that risk assessment methods and modeling data are consistent within a specific technology sector or across technological divides so that they can produce results that are, at least in principle, dependable and comparable. The paper starts with mapping of current regulation on managing the risks related to the operation of fixed industrial installations for energy production and chemical process industry in different member states of the enlarged European Union (EU) with regard to consistency in the risk assessment approaches, methods and data as used by industry and as required or recommended by the regulators, and the specific requirements related to damage compensation. The review shows that technological risks are dealt with quite

  12. TWRS safety program plan

    Energy Technology Data Exchange (ETDEWEB)

    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

  13. Hydrogen Technologies Safety Guide

    Energy Technology Data Exchange (ETDEWEB)

    Rivkin, C. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Burgess, R. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Buttner, W. [National Renewable Energy Lab. (NREL), Golden, CO (United States)

    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.

  14. Improved processes for meeting the data requirements for implementing the Highway Safety Manual (HSM) and Safety Analyst in Florida.

    Science.gov (United States)

    2014-03-01

    Recent research in highway safety has focused on the more advanced and statistically proven techniques of highway : safety analysis. This project focuses on the two most recent safety analysis tools, the Highway Safety Manual (HSM) : and SafetyAnalys...

  15. Grimsel test site investigation Phase IV. The Nagra-JAEA in situ study of safety relevant radionuclide retardation in fractured crystalline rock. III: The RRP project final report

    International Nuclear Information System (INIS)

    Alexander, W. R.; Frieg, B.; Ota, K.

    2009-11-01

    To enhance the understanding of radionuclide transport/retardation in fractured rock, Nagra and JAEA worked together for nearly 15 years on a Radionuclide Migration Programme at Nagra's Grimsel Test Site (GTS). This started with the Migration Experiment (MI) project and moved on to Excavation Project (EP) and the Connected Porosity project. Traditionally, studies such as MI produce data for the overall flow system 'seen' by the radionuclides. These data are then modelled to produce a set of best fit bulk or average values for the transport/retardation parameters. However, the model values obtained may not be a unique solution and no detailed information is obtained about where the retardation actually takes place. The extrapolation from one flow system to another where properties are different can only be done if the underlying processes are well understood. This is a key issue as the geosphere around a radioactive waste repository will not be exhaustively explored due to the necessity to maintain favourable characteristics in as unperturbed a state as possible. Hence, it is essential that extrapolations from similar sites, where such restrictions do not apply, can be justified by a thorough understanding of the factors influencing in situ radionuclide transport and retardation. As part of this strategy, Nagra and JAEA proposed another experiment which took a step further than MI-EP. In the Nagra-JAEA EP radionuclide cocktails of strongly sorbing radionuclides with complex chemistries were injected into a water-conducting shear zone, followed by the excavation of the traced part of the shear zone (approximately two tonnes of rock). The development, improvement and testing of new methodologies and techniques was required owing to the complexity of the project and to the scale of the in situ experiment. The extensive efforts undertaken in order to guarantee a successful experiment required a series of laboratory and field tests at the GTS, the latter wherever

  16. Law project aiming to enforce the maritime transport safety and fight against the sea pollutions; Proposition de loi tendant a renforcer la securite du transport maritime et a lutter contre les pollutions marines

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-12-01

    Facing the increase of the maritime transport, the poor quality of the ships and the flag of convenience problem, this law project is proposed. It concerns the ships maintenance and safety standards, the delivery of a control certificate, the social rights of the sailors, the coasts and ports access control. (A.L.B.)

  17. Using Patient-Reported Outcome Measures (PROMs) to promote quality of care and safety in the management of patients with Advanced Chronic Kidney disease (PRO-trACK project): a mixed-methods project protocol.

    Science.gov (United States)

    Aiyegbusi, Olalekan Lee; Kyte, Derek; Cockwell, Paul; Marshall, Tom; Dutton, Mary; Slade, Anita; Marklew, Neil; Price, Gary; Verdi, Rav; Waters, Judi; Sharpe, Keeley; Calvert, Melanie

    2017-06-30

    Advanced chronic kidney disease (CKD) has a major effect on the quality of life and health status of patients and requires accurate and responsive management. The use of electronic patient-reported outcome measures (ePROMs) could assist patients with advanced pre-dialysis CKD, and the clinicians responsible for their care, by identifying important changes in symptom burden in real time. We report the protocol for 'Using Patient-Reported Outcome measures (PROMs) to promote quality of care and safety in the management of patients with Advanced Chronic Kidney Disease' (PRO-trACK) project, which will explore the feasibility and validity of an ePROM system for use in patients with advanced CKD. The project will use a mixed-methods approach in three studies: (1) usability testing of the ePROM system involving up to 30 patients and focusing on acceptability and technical performance/stability; (2) ascertaining the views of patient and clinician stakeholders on the optimal use and administration of the CKD ePROM system-this will involve qualitative face-to-face/telephone interviewing with up to 30 patients or until saturation is achieved, focus groups with up to 15 clinical staff, management and IT team members; (3) psychometric assessment of the system, within a cohort of at least 180 patients with advanced CKD, to establish the measurement properties of the ePROM. This project was approved by the West Midlands Edgbaston Research Ethics Committee (Reference 17/WM/0010) and received Health Research Authority (HRA) approval on 24 February 2017.The findings from this project will be provided to clinicians at the Department of Renal Medicine, Queen Elizabeth Hospitals, Birmingham (QEHB), NHS England, presented at conferences and to the Kidney Patients' Association, British Kidney Patient Association and the British Renal Society. Articles based on the findings will be written and submitted for publication in peer-reviewed journals. © Article author(s) (or their employer

  18. ITER-FEAT safety

    International Nuclear Information System (INIS)

    Gordon, C.W.; Bartels, H.-W.; Honda, T.; Raeder, J.; Topilski, L.; Iseli, M.; Moshonas, K.; Taylor, N.; Gulden, W.; Kolbasov, B.; Inabe, T.; Tada, E.

    2001-01-01

    Safety has been an integral part of the design process for ITER since the Conceptual Design Activities of the project. The safety approach adopted in the ITER-FEAT design and the complementary assessments underway, to be documented in the Generic Site Safety Report (GSSR), are expected to help demonstrate the attractiveness of fusion and thereby set a good precedent for future fusion power reactors. The assessments address ITER's radiological hazards taking into account fusion's favourable safety characteristics. The expectation that ITER will need regulatory approval has influenced the entire safety design and assessment approach. This paper summarises the ITER-FEAT safety approach and assessments underway. (author)

  19. CO2 geological storage into a lateral aquifer of an offshore gas field in the South China Sea: storage safety and project design

    Science.gov (United States)

    Zhang, Liang; Li, Dexiang; Ezekiel, Justin; Zhang, Weidong; Mi, Honggang; Ren, Shaoran

    2015-06-01

    The DF1-1 gas field, located in the western South China Sea, contains a high concentration of CO2, thus there is great concern about the need to reduce the CO2 emissions. Many options have been considered in recent years to dispose of the CO2 separated from the natural gas stream on the Hainan Island. In this study, the feasibility of CO2 storage in the lateral saline aquifer of the DF1-1 gas field is assessed, including aquifer selection and geological assessment, CO2 migration and storage safety, project design, and economic analysis. Six offshore aquifers have been investigated for CO2 geological storage. The lateral aquifer of the DF1-1 gas field has been selected as the best target for CO2 injection and storage because of its proven sealing ability, and the large storage capacity of the combined aquifer and hydrocarbon reservoir geological structure. The separated CO2 will be dehydrated on the Hainan Island and transported by a long-distance subsea pipeline in supercritical or liquid state to the central platform of the DF1-1 gas field for pressure adjustment. The CO2 will then be injected into the lateral aquifer via a subsea well-head through a horizontal well. Reservoir simulations suggest that the injected CO2 will migrate slowly upwards in the aquifer without disturbing the natural gas production. The scoping economic analysis shows that the unit storage cost of the project is approximately US26-31/ton CO2 with the subsea pipeline as the main contributor to capital expenditure (CAPEX), and the dehydration system as the main factor of operating expenditure (OPEX).

  20. RETROCK Project. Treatment of geosphere retention phenomena in safety assessments. Scientific basis of retention processes and their implementation in safety assessment models (WP2). Work Package 2 report of the RETROCK Concerted Action

    International Nuclear Information System (INIS)

    Nykyri, M.

    2004-10-01

    This report considers the present-day understanding and approaches to take into account retention and transport processes in the performance assessment (PA) models used in the evaluation of the long-term safety of deep geological repositories for radioactive waste. It is a product of Work Package 2 in the RETROCK Concerted Action, a part of EURATOM's research and training programme. The processes emphasised in RETROCK are the influences of the flow field, matrix diffusion, and sorption on radionuclide transport characteristics. These processes, and radioactive decay, provide the key terms to the transport equations of the PA models. The following processes are handled more cursorily: colloid-facilitated transport, microbial activity, gas-mediated transport, precipitation/coprecipitation, and off diagonal Onsager processes. The environment in question is saturated sparsely fractured rock in the repository far field. The fracture network offers flow paths for the groundwater transporting radionuclides away from a repository. The radionuclides in various chemical forms interact physically and chemically with other matter in groundwater, fracture surfaces, fracture infills and the rock matrix adjacent to the fractures. These interactions typically result in significant retardation, and decay, of radionuclides compared to the velocity of the groundwater. The PA models usually take into account retention phenomena using simplified concepts that are justified by their conservatism. They are complemented by a large variety of more detailed and realistic process-specific models that can be used to support the choice of data for PA models, as well as specific arguments made in safety cases. While the fundamental understanding, the conceptualisations of the phenomena, the models and the computing resources develop, the extensive data requirements often become a most restrictive factor to the use of a model. The difficulties in obtaining data tend to hinder the utilisation of