Safety review of experiments at Albuquerque Operations Office

International Nuclear Information System (INIS)

Elliott, K.

1984-01-01

The Department of Energy (DOE) Albuquerque Operations Office is responsible for the safety overview of nuclear reactor and critical assembly facilities at Sandia National Laboratories, Los Alamos National Laboratory, and the Rocky Flats Plant. The important safety concerns with these facilities involve the complex experiments that are performed, and that is the area emphasized. A determination is made by the Albuquerque Office (AL) with assistance from DOE/OMA whether or not a proposed experiment is an unreviewed safety question. Meetings are held with the contractor to resolve and clarify questions that are generated during the review of the proposed experiment. The AL safety evaluation report is completed and any recommendations are discussed. Prior to the experiment a preoperational appraisal is performed to assure that personnel, procedures, and equipment are in readiness for operations. During the experiment, any abnormal condition is reviewed in detail to determine any safety concerns

Guidance for implementing an environmental, safety, and health assurance program. Volume 10. Model guidlines for line organization environmental, safety and health audits and appraisals

International Nuclear Information System (INIS)

Ellingson, A.C.

1981-10-01

This is 1 of 15 documents designed to illustrate how an Environmental, Safety and Health (ES and H) Assurance Program may be implemented. The generic definition of ES and H Assurance Programs is given in a companion document entitled An Environmental, Safety and Health Assurance Program Standard. The Standard specifies that the operational level of an institution must have an internal assurance function, and this document provides guidance for the audit/appraisal portion of the operational level's ES and H program. The appendixes include an ES and H audit checklist, a sample element rating guide, and a sample audit plan for working level line organization internal audits

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)

Occupational Safety. Hand Tools. Pre-Apprenticeship Phase 1 Training.

Science.gov (United States)

Lane Community Coll., Eugene, OR.

This self-paced student training module on safety when using hand tools is one of a number of modules developed for Pre-apprenticeship Phase 1 Training. Purpose of the module is to teach students the correct safety techniques for operating common hand- and arm-powered tools, including selection, maintenance, technique, and uses. The module may…

Appraisal for Japan of the safety of transport of radioactive material. Provision for the application of the IAEA safety standards

International Nuclear Information System (INIS)

2006-01-01

The IAEA's Statute authorizes it to provide for the application of its standards at the request of any State. The objective of a TranSAS appraisal is to assist any requesting State to achieve a high level of safety in the transport of radioactive material by reviewing its implementation of the Transport Regulations and by making recommendations for improvement where appropriate.The IAEA discharges this statutory function through a number of mechanisms, including rendering independent peer review appraisal services to determine the status of compliance with its standards. The appraisal for Japan in December 2005 on the safety of the transport of radioactive material is the seventh TranSAS mission since the inception of the service. This report presents its findings. The TranSAS appraisal team completed a comprehensive appraisal of the implementation of the Transport Regulations in Japan. The cooperation of the authorities in Japan, and of all those who participated in the discussions, was excellent and contributed to the success of the appraisal. The comprehensive legal framework, with responsibilities identified in considerable detail and with clear lines of authority to minimize overlap of responsibilities, provides a sound basis for the implementation of the Transport Regulations. Generally, the Transport Regulations are implemented in accordance with IAEA requirements. Some areas for possible improvement have been identified. These areas relate mainly to reduction of regulations, quality management systems, training, compliance assurance and lessening the administrative burden for incorporating amendments to the IMDG Code. The findings include a considerable number of good practices, in particular in the area of maritime transport

Pre-Operational Seismic Walk-Through of NPPs in India

International Nuclear Information System (INIS)

Soni, R.S.; Mishra, R.K.; Agrawal, M.K.; Reddy, G.R.; Kushwaha, H.S.; Venkat Raj, V.; Badrinarayan, G.; Hawaldar, R.V.; Ingole, S.M.

2002-01-01

In nuclear power plants, it is essential to design the various safety and safety related systems and components of the plant in such a manner that they maintain their structural integrity as well as serve their functional performance during a seismic event. The pre-operational seismic walk-through helps in ensuring the installation of various seismic supports as per design intent, identifying the areas where supports are inadequate, identifying the interaction concerns between the systems of various safety classes and locating the various undesired loose, untied / unanchored components, tools, etc. used during the construction activity. A detailed procedure for the pre-operational seismic walk-through of the NPPs was therefore, prepared. Since the types and locations of seismic supports for the various systems and components of the plant had been already reviewed, the major emphasis during the walk-through was laid on their proper installation. (authors)

Pre-operative biliary drainage for obstructive jaundice

Science.gov (United States)

Fang, Yuan; Gurusamy, Kurinchi Selvan; Wang, Qin; Davidson, Brian R; Lin, He; Xie, Xiaodong; Wang, Chaohua

2014-01-01

% and 100%. There was no significant difference in mortality (40/265, weighted proportion 14.9%) in the pre-operative biliary drainage group versus the direct surgery group (34/255, 13.3%) (RR 1.12; 95% CI 0.73 to 1.71; P = 0.60). The overall serious morbidity was higher in the pre-operative biliary drainage group (60 per 100 patients in the pre-operative biliary drainage group versus 26 per 100 patients in the direct surgery group) (RaR 1.66; 95% CI 1.28 to 2.16; P = 0.0002). The proportion of patients who developed serious morbidity was significantly higher in the pre-operative biliary drainage group (75/102, 73.5%) in the pre-operative biliary drainage group versus the direct surgery group (37/94, 37.4%) (P jaundice. Pre-operative biliary drainage may increase the rate of serious adverse events. So, the safety of routine pre-operative biliary drainage has not been established. Pre-operative biliary drainage should not be used in patients undergoing surgery for obstructive jaundice outside randomised clinical trials. PMID:22972086

Summary of Tiger Team Assessment and Technical Safety Appraisal recurring concerns in the Maintenance Area

International Nuclear Information System (INIS)

1993-01-01

Tiger Team Assessments and Technical Safety Appraisals (TSA) were reviewed and evaluated for concerns in the Maintenance Area (MA). Two hundred and thirty one (231) maintenance concerns were identified by the Tiger Team Assessments and TSA reports. These recurring concerns appear below. A summary of the Noteworthy Practices that were identified and a compilation of the maintenance concerns for each performance objective that were not considered as recurring are also included. Where the Tiger Team Assessment and TSA identified the operating contractor or facility by name, the concern has been modified to remove the name while retaining the intent of the comment

Operational readiness review for the Waste Experimental Reduction Facility. Final report

International Nuclear Information System (INIS)

1993-11-01

An Operational Readiness Review (ORR) at the Idaho National Engineering Laboratory's (INEL's) Waste Experimental Reduction Facility (WERF) was conducted by EG ampersand G Idaho, Inc., to verify the readiness of WERF to resume operations following a shutdown and modification period of more than two years. It is the conclusion of the ORR Team that, pending satisfactory resolution of all pre-startup findings, WERF has achieved readiness to resume unrestricted operations within the approved safety basis. ORR appraisal forms are included in this report

Relationship Between Pre-operative Anxiety and Post-operative Psychosomatic Adjustment and Its Related Factors and Nursing Strategies%术前焦虑与术后心身康复的相关性及其心理社会影响因素

Institute of Scientific and Technical Information of China (English)

沈晓红; 姜乾金

2003-01-01

Objective:To study the relationship between pre-operative anxiety and post-operative psychosomatic adjustment and the related psyehosoeial factors in upper- abdominal surgery patients. Methods: Forty patients undergoing upper- abdominalsurgery were assessed in this report. One day before surgery, the Medical Coping Mode Questionnaire (MCMQ), Perceived Social Support Scale (PSSS), Eysenek Personality Questionnaire (EPQ), State Anxiety Inventory (SAI) of State - Trait Arixiety Invento-ry (STAI) and a self- developed patients'' pre - operative appraisal questionnaire were used. In an hour before operation,the shift of the mean value of the pulse of every ease compared with the base line measured at his (or her ) admission was also recorded. Af-ter surgery, State Anxiety Inventory (SAI) of State- Trait Anxiety Inventory (STAI), a self-developed postoperative appraisal scale were used, and the indexes of somatic adjustment, including intestinal aerofluxus, total dosage of analgesia and so on were recorded. Results:Firstly, pre - operative anxiety was remarkably correlated to many indexes of post - operative psychosomatic adjustment. Secondly, hopelessness about operation, concern over sequela, resignation coping style and psychosis personality were the significant predictors of pre- operative anxiety. Conclusion: Post- operative psychosomatic adjustment could be handicapped by pre - operative anxiety which might be influenced by stress - related psyehosocial factors.

Posiva's application for a decision in principle concerning a disposal facility for spent nuclear fuel. STUK's statement and preliminary safety appraisal

International Nuclear Information System (INIS)

Ruokola, E.

2000-03-01

In May 1999, Posiva Ltd submitted to the Government an application, pursuant to the Nuclear Energy Act, for a Decision in Principle on a disposal facility for spent nuclear fuel from the Finnish nuclear power plants. The Ministry of Trade and Industry requested the Radiation and Nuclear Safety Authority (STUK) to draw up a preliminary safety appraisal concerning the proposed disposal facility. In the beginning of this report, STUK's statement to the Ministry and Industry concerning the proposed disposal facility is given. In that statement, STUK concludes that the Decision in Principle is currently justified from the standpoint of safety. The statement is followed by a safety appraisal, where STUK deems, how the proposed disposal concept, site and facility comply with the safety requirements included in the Government's Decision (478/1999). STUK's preliminary safety appraisal was supported by contributions from a number of outside experts. A collective opinion by an international group of ten distinguished experts is appended to this report. (orig.)

An Appraisal Of The Operation And Management Of Unit Trust ...

African Journals Online (AJOL)

An Appraisal Of The Operation And Management Of Unit Trust Schemes In Nigeria. ... Open Access DOWNLOAD FULL TEXT ... instead of being invested in shares or in money market instruments as a result of widespread financial illiteracy.

Guidance for implementing an environmental, safety and health assurance program. Volume 2. A model plan for environmental, safety and health staff audits and appraisals

International Nuclear Information System (INIS)

Ellingson, A.C.

1980-09-01

This is 1 of 15 documents designed to illustrate how an Environmental, Safety and Health (ES and H) Assurance Program may be implemented. The generic definition of ES and H Assurance Programs is given in a companion document entitled An Environmental, Safety and Health Assurance Program Standard. This document is concerned with ES and H audit and appraisal activities of an ES and H Staff Organization as they might be performed in an institution whose ES and H program is based upon the ES and H Assurance Program Standard. An annotated model plan for ES and H Staff audits and appraisals is presented and discussed

Technical safety appraisal: Buildings 776/777 Rocky Flats Plant

Energy Technology Data Exchange (ETDEWEB)

Field, H C

1988-03-01

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

Technical safety appraisal: Buildings 776/777 Rocky Flats Plant

International Nuclear Information System (INIS)

Field, H.C.

1988-03-01

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

Current safety issues related to research reactor operation

International Nuclear Information System (INIS)

Alcala-Ruiz, F.

2000-01-01

The Agency has included activities on research reactor safety in its Programme and Budget (P and B) since its inception in 1957. Since then, these activities have traditionally been oriented to fulfil the Agency's functions and obligations. At the end of the decade of the eighties, the Agency's Research Reactor Safety Programme (RRSP) consisted of a limited number of tasks related to the preparation of safety related publications and the conduct of safety missions to research reactor facilities. It was at the beginning of the nineties when the RRSP was upgraded and expanded as a subprogramme of the Agency's P and B. This subprogramme continued including activities related to the above subjects and started addressing an increasing number of issues related to the current situation of research reactors (in operation and shut down) around the world such as reactor ageing, modifications and decommissioning. The present paper discusses some of the above issues as recognised by various external review or advisory groups (e.g., Peer Review Groups under the Agency's Performance Programme Appraisal System (PPAS) or the standing International Nuclear Safety Advisory Group (INSAG)) and the impact of their recommendations on the preparation and implementation of the part of the Agency's P and B relating to the above subject. (author)

Technical safety appraisal of buildings 9206 and 9212, Oak Ridge Y-12 plant

International Nuclear Information System (INIS)

1989-03-01

This report covers the results of a Safety Performance Review of the Y-12 Plant conducted during the period July 25 through August 3, 1988. A Safety Performance Review is a followup to assess changes in performance since the 1986 Technical Safety Appraisal (TSA). This review is patterned after a TSA and covered the overall safety performance at Y-12, evaluating progress to date against standards of accepted practice. The review included coverage of actions taken in response to recommendations in the TSA conducted in July--August 1986. Remaining issues were identified through an assessment of safety program deficiencies and their root causes. For each of the 14 safety-related functional areas at the Y-12 Plant, results of this review are listed in Section V. These results include a discussion, conclusions, and any new safety concerns for each program. Appendix A contains a description of the system for categorizing concerns, and the concerns are summarily tabulated in Appendix B for all programs. Appendix C describes the contractor's response and current status of each of the 59 recommendations contained in the 1986 TSA

Patient safety in the operating room: an intervention study on latent risk factors

Directory of Open Access Journals (Sweden)

van Beuzekom Martie

2012-06-01

Full Text Available Abstract Background Patient safety is one of the greatest challenges in healthcare. In the operating room errors are frequent and often consequential. This article describes an approach to a successful implementation of a patient safety program in the operating room, focussing on latent risk factors that influence patient safety. We performed an intervention to improve these latent risk factors (LRFs and increase awareness of patient safety issues amongst OR staff. Methods Latent risk factors were studied using a validated questionnaire applied to the OR staff before and after an intervention. A pre-test/post-test control group design with repeated measures was used to evaluate the effects of the interventions. The staff from one operating room of an university hospital acted as the intervention group. Controls consisted of the staff of the operating room in another university hospital. The outcomes were the changes in LRF scores, perceived incident rate, and changes in incident reports between pre- and post-intervention. Results Based on pre-test scores and participants’ key concerns about organizational factors affecting patient safety in their department the intervention focused on the following LRFs: Material Resources, Training and Staffing Recourses. After the intervention, the intervention operating room - compared to the control operating room - reported significantly fewer problems on Material Resources and Staffing Resources and a significantly lower score on perceived incident rate. The contribution of technical factors to incident causation decreased significantly in the intervention group after the intervention. Conclusion The change of state of latent risk factors can be measured using a patient safety questionnaire aimed at these factors. The change of the relevant risk factors (Material and Staffing resources concurred with a decrease in perceived and reported incident rates in the relevant categories. We conclude that

Posiva's application for a decision in principle concerning a disposal facility for spent nuclear fuel. STUK's statement and preliminary safety appraisal

Energy Technology Data Exchange (ETDEWEB)

Ruokola, E. [ed.

2000-03-01

In May 1999, Posiva Ltd submitted to the Government an application, pursuant to the Nuclear Energy Act, for a Decision in Principle on a disposal facility for spent nuclear fuel from the Finnish nuclear power plants. The Ministry of Trade and Industry requested the Radiation and Nuclear Safety Authority (STUK) to draw up a preliminary safety appraisal concerning the proposed disposal facility. In the beginning of this report, STUK's statement to the Ministry and Industry concerning the proposed disposal facility is given. In that statement, STUK concludes that the Decision in Principle is currently justified from the standpoint of safety. The statement is followed by a safety appraisal, where STUK deems, how the proposed disposal concept, site and facility comply with the safety requirements included in the Government's Decision (478/1999). STUK's preliminary safety appraisal was supported by contributions from a number of outside experts. A collective opinion by an international group of ten distinguished experts is appended to this report. (orig.)

Current practices in economic appraisal

NARCIS (Netherlands)

Mossink, J.C.M.

2000-01-01

By means of economic appraisal, the costs and the benefits of health, environment and safety management can be made clear, both at the national level and at the company level. As such it is a tool in advocating good practices. This paper explores the possibilities of economic appraisal for policy

Pre-OSART mission highlights. 1988-1990

International Nuclear Information System (INIS)

1994-09-01

The IAEA Pre-Operational Safety Review Teams (Pre-OSART) programme is part of the Operational Safety Review teams (OSART) programme and provides advice and assistance to Member States for enhancing the operational safety of nuclear power plants. OSART and Pre-OSART reviews are available to all countries with nuclear power plants in operation or approaching operation. Most of these countries have participated in the programme, by hosting one or more OSART or Pre-OSART missions or by making experts available to participate in missions. This document, which summarizes the finding of Pre-OSART reviews, covers the period from January 1988 to December 1990, and it is intended that further such documents will be prepared to cover subsequent Pre-OSART reviews

Clinical target volume delineation in glioblastomas: pre-operative versus post-operative/pre-radiotherapy MRI

Science.gov (United States)

Farace, P; Giri, M G; Meliadò, G; Amelio, D; Widesott, L; Ricciardi, G K; Dall'Oglio, S; Rizzotti, A; Sbarbati, A; Beltramello, A; Maluta, S; Amichetti, M

2011-01-01

Objectives Delineation of clinical target volume (CTV) is still controversial in glioblastomas. In order to assess the differences in volume and shape of the radiotherapy target, the use of pre-operative vs post-operative/pre-radiotherapy T1 and T2 weighted MRI was compared. Methods 4 CTVs were delineated in 24 patients pre-operatively and post-operatively using T1 contrast-enhanced (T1PRECTV and T1POSTCTV) and T2 weighted images (T2PRECTV and T2POSTCTV). Pre-operative MRI examinations were performed the day before surgery, whereas post-operative examinations were acquired 1 month after surgery and before chemoradiation. A concordance index (CI) was defined as the ratio between the overlapping and composite volumes. Results The volumes of T1PRECTV and T1POSTCTV were not statistically different (248 ± 88 vs 254 ± 101), although volume differences >100 cm3 were observed in 6 out of 24 patients. A marked increase due to tumour progression was shown in three patients. Three patients showed a decrease because of a reduced mass effect. A significant reduction occurred between pre-operative and post-operative T2 volumes (139 ± 68 vs 78 ± 59). Lack of concordance was observed between T1PRECTV and T1POSTCTV (CI = 0.67 ± 0.09), T2PRECTV and T2POSTCTV (CI = 0.39 ± 0.20) and comparing the portion of the T1PRECTV and T1POSTCTV not covered by that defined on T2PRECTV images (CI = 0.45 ± 0.16 and 0.44 ± 0.17, respectively). Conclusion Using T2 MRI, huge variations can be observed in peritumoural oedema, which are probably due to steroid treatment. Using T1 MRI, brain shifts after surgery and possible progressive enhancing lesions produce substantial differences in CTVs. Our data support the use of post-operative/pre-radiotherapy T1 weighted MRI for planning purposes. PMID:21045069

Pre-operative simulation of pediatric mastoid surgery with 3D-printed temporal bone models.

Science.gov (United States)

Rose, Austin S; Webster, Caroline E; Harrysson, Ola L A; Formeister, Eric J; Rawal, Rounak B; Iseli, Claire E

2015-05-01

As the process of additive manufacturing, or three-dimensional (3D) printing, has become more practical and affordable, a number of applications for the technology in the field of pediatric otolaryngology have been considered. One area of promise is temporal bone surgical simulation. Having previously developed a model for temporal bone surgical training using 3D printing, we sought to produce a patient-specific model for pre-operative simulation in pediatric otologic surgery. Our hypothesis was that the creation and pre-operative dissection of such a model was possible, and would demonstrate potential benefits in cases of abnormal temporal bone anatomy. In the case presented, an 11-year-old boy underwent a planned canal-wall-down (CWD) tympano-mastoidectomy for recurrent cholesteatoma preceded by a pre-operative surgical simulation using 3D-printed models of the temporal bone. The models were based on the child's pre-operative clinical CT scan and printed using multiple materials to simulate both bone and soft tissue structures. To help confirm the models as accurate representations of the child's anatomy, distances between various anatomic landmarks were measured and compared to the temporal bone CT scan and the 3D model. The simulation allowed the surgical team to appreciate the child's unusual temporal bone anatomy as well as any challenges that might arise in the safety of the temporal bone laboratory, prior to actual surgery in the operating room (OR). There was minimal variability, in terms of absolute distance (mm) and relative distance (%), in measurements between anatomic landmarks obtained from the patient intra-operatively, the pre-operative CT scan and the 3D-printed models. Accurate 3D temporal bone models can be rapidly produced based on clinical CT scans for pre-operative simulation of specific challenging otologic cases in children, potentially reducing medical errors and improving patient safety. Copyright © 2015 Elsevier Ireland Ltd. All rights

Improving operating room safety

Directory of Open Access Journals (Sweden)

Garrett Jill

2009-11-01

Full Text Available Abstract Despite the introduction of the Universal Protocol, patient safety in surgery remains a daily challenge in the operating room. This present study describes one community health system's efforts to improve operating room safety through human factors training and ultimately the development of a surgical checklist. Using a combination of formal training, local studies documenting operating room safety issues and peer to peer mentoring we were able to substantially change the culture of our operating room. Our efforts have prepared us for successfully implementing a standardized checklist to improve operating room safety throughout our entire system. Based on these findings we recommend a multimodal approach to improving operating room safety.

[Evaluation of Wits appraisal with superimposition method].

Science.gov (United States)

Xu, T; Ahn, J; Baumrind, S

1999-07-01

To compare the conventional Wits appraisal with superimposed Wits appraisal in evaluation of sagittal jaw relationship change between pre and post orthodontic treatment. The sample consists of 48-case pre and post treatment lateral head films. Computerized digitizing is used to get the cephalometric landmarks and measure conventional Wits value, superimposed Wits value and ANB angle. The correlation analysis among these three measures was done by SAS statistical package. The change of ANB angle has higher correlation with the change of superimposed Wits than that of the conventional Wits. The r-value is as high as 0.849 (P < 0.001). The superimposed Wits appraisal reflects the change of sagittal jaw relationship more objectively than the conventional one.

An anaesthetic pre-operative assessment clinic reduces pre-operative inpatient stay in patients requiring major vascular surgery.

LENUS (Irish Health Repository)

O'Connor, D B

2012-02-01

BACKGROUND: Patients undergoing major vascular surgery (MVS) require extensive anaesthetic assessment. This can require extended pre-operative stays. AIMS: We investigated whether a newly established anaesthetic pre-operative assessment clinic (PAC) would reduce the pre-operative inpatient stay, avoid unnecessary investigations and facilitate day before surgery (DBS) admissions for patients undergoing MVS. PATIENT AND METHODS: One year following and preceding the establishment of the PAC the records of patients undergoing open or endovascular aortic aneurysm repair, carotid endarterectomy and infra-inguinal bypass were reviewed to measure pre-operative length of stay (LoS). RESULTS: Pre-operative LoS was significantly reduced in the study period (1.85 vs. 4.2 days, respectively, P < 0.0001). Only 12 out of 61 patients in 2007 were admitted on the DBS and this increased to 33 out of 63 patients (P = 0.0002). No procedure was cancelled for medical reasons. CONCLUSION: The PAC has facilitated accurate outpatient anaesthetic assessment for patients requiring MVS. The pre-operative in-patient stay has been significantly reduced.

Pre-operative haematological investigations in paediatric orofacial ...

African Journals Online (AJOL)

Pre-operative haematological investigations in paediatric orofacial cleft repair: Any relevance to management outcome? ... Aim and Objectives: To determine the value of routine pre-operative haematologic investigations in children undergoing orofacial cleft repair. Background: Although routine pre-operative laboratory ...

Operational safety at the FFTF

International Nuclear Information System (INIS)

Baird, Q.L.; Hagan, J.W.; Seeman, S.E.; Baker, S.M.

1981-02-01

An extensive operational nuclear safety program has been an integral part of the design, startup, and initial operating phases of the Fast Flux Test Facility (FFTF). During the design and construction of the facility, a program of independent safety overviews and analyses assured the provision of responsible safety margins within the plant, protective systems, and engineered safety features for protection of the public, operating staff, and the facility. The program is continuing through surveillance of operations to verify continued adherence to the established operating envelope and for timely identification of any trends potentially adverse to those margins. Experience from operation of FFTF is being utilized in the development of enhanced operational nuclear safety aids for application in follow-on breeder reactor power systems. The commendable plant and personnel safety experiences of FFTF through its startup and ascension to full power demonstrate the overall effectiveness of the FFTF operational nuclear safety program

Operating experience: safety perspective

International Nuclear Information System (INIS)

Piplani, Vivek; Krishnamurthy, P.R.; Kumar, Neeraj; Upadhyay, Devendra

2015-01-01

Operating Experience (OE) provides valuable information for improving NPP safety. This may include events, precursors, deviations, deficiencies, problems, new insights to safety, good practices, lessons and corrective actions. As per INSAG-10, an OE program caters as a fundamental means for enhancing the defence-in-depth at NPPs and hence should be viewed as ‘Continuous Safety Performance Improvement Tool’. The ‘Convention on Nuclear Safety’ also recognizes the OE as a tool of high importance for enhancing the NPP safety and its Article 19 mandates each contracting party to establish an effective OE program at operating NPPs. The lessons drawn from major accidents at Three Mile Island, Chernobyl and Fukushima Daiichi NPPs had prompted nuclear stalwarts to change their safety perspective towards NPPs and to frame sound policies on issues like safety culture, severe accident prevention and mitigation. An effective OE program, besides correcting current/potential problems, help in proactively improving the NPP design, operating and maintenance procedures, practices, training, etc., and thus plays vital role in ensuring safe and efficient operation of NPPs. Further it enhances knowledge with regard to equipment operating characteristics, system performance trends and provides data for quantitative and qualitative safety analysis. Besides all above, an OE program inculcates a learning culture in the organisation and thus helps in continuously enhancing the expertise, technical competency and knowledge base of its staff. Nuclear and Radiation Facilities in India are regulated by Atomic Energy Regulatory Board (AERB). Operating Plants Safety Division (OPSD) of AERB is involved in managing operating experience activities. This paper provides insights about the operating experience program of OPSD, AERB (including its on-line data base namely OPSD STAR) and its utilisation in improving the regulations and safety at Indian NPPs/projects. (author)

Safety of nuclear power plants: Operation. Safety requirements

International Nuclear Information System (INIS)

2004-01-01

The safety of a nuclear power plant is ensured by means of its proper siting, design, construction and commissioning, followed by the proper management and operation of the plant. In a later phase, proper decommissioning is required. This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Operation, which was issued in 1988 as Safety Series No. 50-C-O (Rev. 1). The purpose of this revision was: to restructure Safety Series No. 50-C-O (Rev. 1) in the light of the basic objectives, concepts and principles in the Safety Fundamentals publication The Safety of Nuclear Installations. To be consistent with the requirements of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. And to reflect current practice and new concepts and technical developments. Guidance on fulfillment of these Safety Requirements may be found in the appropriate Safety Guides relating to plant operation. The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the basic objectives, concepts and principles that are presented in the Safety Fundamentals publication The Safety of Nuclear Installations. This publication deals with matters specific to the safe operation of land based stationary thermal neutron nuclear power plants, and also covers their commissioning and subsequent decommissioning

Safety of nuclear power plants: Operation. Safety requirements

International Nuclear Information System (INIS)

2003-01-01

The safety of a nuclear power plant is ensured by means of its proper siting, design, construction and commissioning, followed by the proper management and operation of the plant. In a later phase, proper decommissioning is required. This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Operation, which was issued in 1988 as Safety Series No. 50-C-O (Rev. 1). The purpose of this revision was: to restructure Safety Series No. 50-C-O (Rev. 1) in the light of the basic objectives, concepts and principles in the Safety Fundamentals publication The Safety of Nuclear Installations. To be consistent with the requirements of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. And to reflect current practice and new concepts and technical developments. Guidance on fulfillment of these Safety Requirements may be found in the appropriate Safety Guides relating to plant operation. The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the basic objectives, concepts and principles that are presented in the Safety Fundamentals publication The Safety of Nuclear Installations. This publication deals with matters specific to the safe operation of land based stationary thermal neutron nuclear power plants, and also covers their commissioning and subsequent decommissioning

Safety of nuclear power plants: Operation. Safety requirements

International Nuclear Information System (INIS)

2000-01-01

The safety of a nuclear power plant is ensured by means of its proper siting, design, construction and commissioning, followed by the proper management and operation of the plant. In a later phase, proper decommissioning is required. This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Operation, which was issued in 1988 as Safety Series No. 50-C-O (Rev. 1). The purpose of this revision was: to restructure Safety Series No. 50-C-O (Rev. 1) in the light of the basic objectives, concepts and principles in the Safety Fundamentals publication The Safety of Nuclear Installations; to be consistent with the requirements of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources; and to reflect current practice and new concepts and technical developments. Guidance on fulfillment of these Safety Requirements may be found in the appropriate Safety Guides relating to plant operation. The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the basic objectives, concepts and principles that are presented in the Safety Fundamentals publication The Safety of Nuclear Installations. This publication deals with matters specific to the safe operation of land based stationary thermal neutron nuclear power plants, and also covers their commissioning and subsequent decommissioning

Pre-operative evaluation for thorax surgery

International Nuclear Information System (INIS)

Silva Luis, Saenz; Morales, Oscar Alberto

2002-01-01

A pre-operative analysis of the function of the breathing system is made in the patient that will be taken to thorax surgery. The paper includes risk factors, pre-operative clinical evaluation and of breathing and cardiovascular system

Safety culture and organizational issues during transition from operation to decommissioning of NPPs

International Nuclear Information System (INIS)

Slavcheva, K.; Mori, M.; D'Amico, N.; Sollima, C.

2005-01-01

The paper highlights the critical safety issues in a Nuclear Power Plant (NPP) to be managed during the transition period from operation to decommissioning. Pre-shutdown is an important period of a NPP lifetime due to the changes and issues to be faced by the NPP management, which include safety culture issues, organizational issues, plant safety issues and nuclear waste issues. Preservation of staff competence and moral, management and organizational capability, preservation of knowledge and corporate memory, preservation of safety culture, surveillance and permanent control to maintain adequate level of nuclear and radiation safety, development of appropriate solutions for the new incoming issues are the key challenges to be timely faced. The uncertainty regarding the future of the site, the future of the workers and the incoming re-organization originate numerous additional issues including stress for the personnel. It is necessary to take appropriate actions to reduce the uncertainty. The regulatory regime continues with the same rules as during operation. Responsibility for safety remains with the licensee and the regulatory supervision continues and oversees the safe operation and security of the NPP, the safe management and storage of spent nuclear fuel and radioactive waste. Anticipated attention from the Operator and the Regulator to key organizational and safety culture issues during the pre-shutdown phase has shown to be an effective preventive action. The Operator has to aim to preserve staff competence and motivation, preserve corporate memory, safety culture, reinforce monitoring and control on the health risk of workers and population, preserve the technical part of the organization from external disturb and distractions, ensure transparency and develop strategies to solve forthcoming issues. The Regulator has to aim to reorient its supervision, train its personnel and adapt its tools to the new situation, keep adequate presence onsite, keep dialogue

Pre-Exposure Prophylaxis for HIV Prevention: Safety Concerns.

Science.gov (United States)

Tetteh, Raymond A; Yankey, Barbara A; Nartey, Edmund T; Lartey, Margaret; Leufkens, Hubert G M; Dodoo, Alexander N O

2017-04-01

Available evidence supports the efficacy of pre-exposure prophylaxis (PrEP) in decreasing the incidence of human immunodeficiency virus (HIV) infection among high-risk individuals, especially when used in combination with other behavioural preventive methods. Safety concerns about PrEP present challenges in the implementation and use of PrEP. The aim of this review is to discuss safety concerns observed in completed clinical trials on the use of PrEP. We performed a literature search on PrEP in PubMed, global advocacy for HIV prevention (Aids Vaccine Advocacy Coalition) database, clinical trials registry " http://www.clinicaltrials.gov " and scholar.google, using combination search terms 'pre-exposure prophylaxis', 'safety concerns in the use of pre-exposure prophylaxis', 'truvada use as PrEP', 'guidelines for PrEP use', 'HIV pre-exposure prophylaxis' and 'tenofovir' to identify clinical trials and literature on PrEP. We present findings associated with safety issues on the use of PrEP based on a review of 11 clinical trials on PrEP with results on safety and efficacy as at April 2016. We also reviewed findings from routine real-life practice reports. The pharmacological intervention for PrEP was tenofovir disoproxil fumarate/emtricitabine in a combined form as Truvada ® or tenofovir as a single entity. Both products are efficacious for PrEP and seem to have a good safety profile. Regular monitoring is recommended to prevent long-term toxic effects. The main adverse effects observed with PrEP are gastrointestinal related; basically mild to moderate nausea, vomiting and diarrhea. Other adverse drug effects worth monitoring are liver enzymes, renal function and bone mineral density. PrEP as an intervention to reduce HIV transmission appears to have a safe benefit-risk profile in clinical trials. It is recommended for widespread use but adherence monitoring and real-world safety surveillance are critical in the post-marketing phase to ensure that the benefits

ITER safety and operational scenario

International Nuclear Information System (INIS)

Shimomura, Y.; Saji, G.

1998-01-01

The safety and environmental characteristics of ITER and its operational scenario are described. Fusion has built-in safety characteristics without depending on layers of safety protection systems. Safety considerations are integrated in the design by making use of the intrinsic safety characteristics of fusion adequate to the moderate hazard inventories. In addition to this, a systematic nuclear safety approach has been applied to the design of ITER. The safety assessment of the design shows how ITER will safely accommodate uncertainties, flexibility of plasma operations, and experimental components, which is fundamental in ITER, the first experimental fusion reactor. The operation of ITER will progress step by step from hydrogen plasma operation with low plasma current, low magnetic field, short pulse and low duty factor without fusion power to deuterium-tritium plasma operation with full plasma current, full magnetic field, long pulse and high duty factor with full fusion power. In each step, characteristics of plasma and optimization of plasma operation will be studied which will significantly reduce uncertainties and frequency/severity of plasma transient events in the next step. This approach enhances reliability of ITER operation. (orig.)

Operation safety of complex industrial systems

International Nuclear Information System (INIS)

Zwingelstein, G.

1999-01-01

Zero fault or zero risk is an unreachable goal in industrial activities like nuclear activities. However, methods and techniques exist to reduce the risks to the lowest possible and acceptable level. The operation safety consists in the recognition, evaluation, prediction, measurement and mastery of technological and human faults. This paper analyses each of these points successively: 1 - evolution of operation safety; 2 - definitions and basic concepts: failure, missions and functions of a system and of its components, basic concepts and operation safety; 3 - forecasting analysis of operation safety: reliability data, data-banks, precautions for the use of experience feedback data; realization of an operation safety study: management of operation safety, quality assurance, critical review and audit of operation safety studies; 6 - conclusions. (J.S.)

Managing Safety and Operations: The Effect of Joint Management System Practices on Safety and Operational Outcomes.

Science.gov (United States)

Tompa, Emile; Robson, Lynda; Sarnocinska-Hart, Anna; Klassen, Robert; Shevchenko, Anton; Sharma, Sharvani; Hogg-Johnson, Sheilah; Amick, Benjamin C; Johnston, David A; Veltri, Anthony; Pagell, Mark

2016-03-01

The aim of this study was to determine whether management system practices directed at both occupational health and safety (OHS) and operations (joint management system [JMS] practices) result in better outcomes in both areas than in alternative practices. Separate regressions were estimated for OHS and operational outcomes using data from a survey along with administrative records on injuries and illnesses. Organizations with JMS practices had better operational and safety outcomes than organizations without these practices. They had similar OHS outcomes as those with operations-weak practices, and in some cases, better outcomes than organizations with safety-weak practices. They had similar operational outcomes as those with safety-weak practices, and better outcomes than those with operations-weak practices. Safety and operations appear complementary in organizations with JMS practices in that there is no penalty for either safety or operational outcomes.

Occupational Safety. Hygiene Safety. Pre-Apprenticeship Phase 1 Training.

Science.gov (United States)

Lane Community Coll., Eugene, OR.

This self-paced student training module on hygiene safety is one of a number of modules developed for Pre-apprenticeship Phase 1 Training. Purpose of the module is to familiarize students with the different types of airborne contaminants--including noise--which may be health hazards and with the proper hygienic measures for dealing with them. The…

Operational safety of nuclear power plants

International Nuclear Information System (INIS)

Tanguy, P.

1987-01-01

The operational safety of nuclear power plants has become an important safety issue since the Chernobyl accident. A description is given of the various aspects of operational safety, including the importance of human factors, responsibility, the role and training of the operator, the operator-machine interface, commissioning and operating procedures, experience feedback, and maintenance. The lessons to be learnt from Chernobyl are considered with respect to operator errors and the management of severe accidents. Training of personnel, operating experience feedback, actions to be taken in case of severe accidents, and international cooperation in the field of operational safety, are also discussed. (U.K.)

Operational and environmental safety

International Nuclear Information System (INIS)

Anon.

1978-01-01

The responsibility of the DOE Office of Operational and Environmental Safety is to assure that DOE-controlled activities are conducted in a manner that will minimize risks to the public and employees and will provide protection for property and the environment. The program supports the various energy technologies by identifying and resolving safety problems; developing and issuing safety policies, standards, and criteria; assuring compliance with DOE, Federal, and state safety regulations; and establishing procedures for reporting and investigating accidents in DOE operations. Guidelines for the radiation protection of personnel; radiation monitoring at nuclear facilities; an assessment of criticality accidents by fault tree analysis; and the preparation of environmental, safety, and health standards applicable to geothermal energy development are discussed

Operation safety at Ignalina NPP

International Nuclear Information System (INIS)

Zheltobriukh, G.

1999-01-01

An improvement of operational safety at Ignalina NPP covers: improvement of management structure and safety culture; symptom-based emergency operating procedures; staff training and full scope simulator; program of components ageing; metal inspection; improvement of fire safety. The first plan of Ignalina NPP Safety culture development for 1997 purposed to the SAR recommendation implementation was prepared and approved by the General Director

OSART mission highlights 2001-2003. Operational safety practices in nuclear power plants

International Nuclear Information System (INIS)

2005-05-01

The IAEA Operational Safety Review Team (OSART) programme provides advice and assistance to Member States in enhancing the operational safety of nuclear power plants (NPPs). Careful design and high quality of construction are prerequisites for a safe nuclear power plant. However, a plant's safety depends ultimately on the ability and conscientiousness of the operating personnel and on the plant programmes, processes and working methods. An OSART mission compares a facility's operational performance with IAEA Safety Standards and proven good international practices. The OSART reviews are available to all countries with nuclear power plants in operation, but also approaching operation, commissioning or in earlier stages of construction (Pre-OSART). Most countries have participated in the programme by hosting one or more OSART missions or by making experts available to participate in missions. Operational safety missions can also be part of the design review missions of nuclear power plants and are known as Safety Review Missions (SRMs). Teams that review only a few specific areas or a specific issue are called Expert missions. Follow-up visits are a standard part of the OSART programme and are conducted between 12 to 18 months following the OSART mission. This report continues the practice of summarizing mission results so that all the aspects of OSART missions, Pre-OSART missions and OSART good practices are to be found in one document. It also includes the results of follow-up visits. Attempts have been made in this report to highlight the most significant findings while retaining as much of the vital background information as possible. This report is in three parts: Part I summarizes the most significant observations made during the missions and follow-up visits between 2001 and 2003; Part II, in chronological order, reviews the major strengths and opportunities for improvement identified during each OSART mission and summarizes the follow-up visits performed

Pre-Operative Lugol's Iodine Treatment in the Management of Patients Undergoing Thyroidectomy for Graves' Disease: A Review of the Literature.

Science.gov (United States)

Hope, Nicholas; Kelly, Andrew

2017-02-01

To undertake a review of the relevant English literature published on the pre-operative use of Lugol's iodine in the management of patients undergoing thyroidectomy for Graves' disease. We reviewed all relevant papers found through Ovid Medline, PubMed, EMBASE and the American Thyroid Association website. Searches were limited to the English language only. The critical appraisal tool CASP was used to help analyse the papers. Following this, the evidence was ranked using the Harbour and Miller classification of hierarchy. Four papers were deemed appropriate for analysis. The evidence contained within the review is considered weak. The literature available in the public domain regarding the use of iodinated solutions in the pre-operative period for those patients about to undergo thyroidectomy for Graves' disease is scant. Having undertaken an extensive literature review, we are of the opinion that the evidence on which the American Thyroid Association's guidance on the use of preoperative Lugol's iodine is based is tenuous. There appears to be little in the way of sound clinical evidence that post-operative outcomes are any different following a course of Lugol's iodine. Given the lack of robust clinical evidence regarding the clinical need for iodine solution in the pre-operative period, it appears clear that a larger, prospective, randomised controlled trial of all relevant outcomes - clinical and scientific - is required to answer whether or not patient preparation with Lugol's iodine is in fact necessary prior to operative intervention for Graves' disease.

Safety Evakuation Of Triga-2000 Reactor Operation Viewed From Safety Culture

International Nuclear Information System (INIS)

Karliana, Itjeu

2001-01-01

The safety evaluation activities of TRIGA-2000 operation viewed from safety culture performed by questioners data collected from the operators and supervisor site of TRIGA-2000 P3TN, Bandung. There are 9 activity aspects surveyed, for instant to avail the policy of safety from their chairman, safety management, education and training, emergency aids planning, safety consultancy, accident information, safety analysis, safety devices, safety and occupational health. The surveying undertaken by filling the questioner that containing of 9 activity aspects and 20 samples of employees. The safety evaluation results' of the operation personnel in TRIGA-2000 P3TN are good implemented by both the operators and supervisors should be improve and attention need to provide the equipment's. The education and training especially for safety refreshment must be performing

Supplement to safety analysis report. 306-W building operations safety requirement

International Nuclear Information System (INIS)

Richey, C.R.

1979-08-01

The operations safety requirements (OSRs) presented in this report define the conditions, safe boundaries, and management control needed for safely conducting operations with radioactive materials in the Pacific Northwest Laboratory (PNL) 306-W building. The safety requirements are organized in five sections. Safety limits are safety-related process variables that are observable and measurable. Limiting conditions cover: equipment and technical conditions and characteristics of the facility and operations necessary for continued safe operation. Surveillance requirements prescribe the requirements for checking systems and components that are essential to safety. Equipment design controls require that changes to process equipment and systems be independently checked and approved to assure that the changes will have no adverse effect on safety. Administrative controls describe and discuss the organization and administrative systems and procedures to be used for safe operation of the facility. Details of the implementation of the operations safety requirements are prescribed by internal PNL documents such as criticality safety specifications and radiation work procedures

Operational safety reliability research

International Nuclear Information System (INIS)

Hall, R.E.; Boccio, J.L.

1986-01-01

Operating reactor events such as the TMI accident and the Salem automatic-trip failures raised the concern that during a plant's operating lifetime the reliability of systems could degrade from the design level that was considered in the licensing process. To address this concern, NRC is sponsoring the Operational Safety Reliability Research project. The objectives of this project are to identify the essential tasks of a reliability program and to evaluate the effectiveness and attributes of such a reliability program applicable to maintaining an acceptable level of safety during the operating lifetime at the plant

Safety management: a few techniques and their application

International Nuclear Information System (INIS)

Soundararajan, S.

2016-01-01

Industrial safety practice has grown in its stature tremendously since the age of industrial revolution. A number of modern techniques are available to strengthen design safety features, to review operational safety, and to critically appraise and upgrade practices of occupational safety and health management. This talk focuses on three prominent yet simple techniques and their usefulness in the overall safety management of a workplace. Any industrial set-up undergoes different stages in its life cycle-conceptual design, actual design, construction, fabrication and installation, commissioning, operation, shutdown/re-start up and decommissioning. Checklist procedure is a safety tool that can be applied at any of these stages. Thus it is a quite useful technique in safety management and accident prevention. It can serve as a form of approval from one step to another in the course of any routine or specific task. Safety Audit or Safety Review is a critical safety management appraisal tool. It gives a reasonable indication of how well a company's safety programme works, how hazards are recognised, how well employees are motivated and so on. It gives a clear picture about where a company stands as far as framing and implementation of its SHE policy is concerned. Each of the above tools is complementing each other and required to be applied at appropriate juncture in sustaining good safety management system at the workplace

A case of industrial safety appraisal for extension of service life of GTK-10-4 gas turbines used at gas transmission stations

Science.gov (United States)

Rybnikov, A. I.; Kovalev, A. G.; Kryukov, I. I.; Leont'ev, S. A.; Moshnikov, A. V.

2017-04-01

It is shown that the extended life and enhanced operational reliability of parts and subassemblies of the most popular GTK-10-4 gas transmission plants are determined by the enhanced efficiency of the control over technical condition and operational safety of turbine plants in conformity with industrial safety requirements imposed on gas pipeline compressor stations. It has been established that the materials of parts and subassemblies of gas turbine plants with different, especially with maximal operating time, shall be exposed to NDT for the purpose of determining the actual mechanical characteristics of these materials with different operating time and calculating residual life. The analysis of damageability and operating conditions has helped to identify parts and subassemblies for repair or replacement with the highest frequency of unacceptable defects. These parts and subassemblies have been shown to include base members of the axial compressor (AC), a turbine housing, an axial compressor rotor, high- and low-pressure turbine (HPT and LPT) discs, a 12-part holder, the housing of the holder of HPT and LPT guiding blades, a sealed baffler, and working and guiding AC, LPT and HPT blades. The most typical operational defects have been enumerated and analyzed. It has been determined that the primary task of the industrial safety appraisal for extending the life of GTK-10-4 with limit-exceeding operating time is to thoroughly examine HPT and LPT discs with more than 130,000 hours of operating time and establish by DT methods characteristics of materials for evaluation, taking account of their degradation, and residual life of critical turbine elements. In addition, it has been shown that the service life of HP turbine discs can be extended by replacing the disc material (EP-428 12% chromium steel) with a material with a higher linear expansion factor that somewhat exceeds the expansion factor of EI-893 nickel alloy used to melt out working blades.

[Pre-operation evaluation and intra-operation management of cochlear implantation].

Science.gov (United States)

Zhang, Dao-xing; Hu, Bao-hua; Xiao, Yu-li; Shi, Bo-ning

2004-10-01

To summarize pre-operation evaluation experiences in cochlear implantation. Performing auditory evaluation and image analysis seriously in 158 severe hearing loss or total deaf cases before cochlear implantation, comparing their performance with the findings during and post operation. Among the total 158 cases, 116 cases with normal structure, 42 cases with the abnormal findings of the inner or middle ear. Stapedial gusher happened in 6 cases, 1 case was not predicted before operation. Except 1 case with serious malformation, the findings of other 157 cases in operation were consistent with the pre-operation evaluation. We helped all patients reconstruct auditory conduction with cochlear implantation, and the average hearing level up to 37.6 dB SPL. Performing image analysis seriously before operation and planning for operation according to HRCT can do great help to cochlear implantation. The operation under the HRCT instruction has less complications.

Effects of appraisal purpose and rating format on performance appraisal accuracy

OpenAIRE

Carter, Marta L.

1989-01-01

The principle of encoding specificity states that effective information retrieval relies upon consistency of encoding and retrieval cues. The present study generalized this principle to a complex social interaction in order to investigate the relation between certain combinations of pre- and post-observational cues and their effects on information categorization, recognition accuracy, and judgment accuracy. It was hypothesized that two experimental factors, appraisal pur...

Enhancing operational nuclear safety

International Nuclear Information System (INIS)

Sengoku, Katsuhisa

2008-01-01

's safety standards and program which provides the safety objective following the 10 fundamental safety principles. The safety requirements defines the functional conditions required for safety and the safety guides provides user-friendly and up-to-date practical guidance representing good/best practices to fulfill the requirements. The IAEA provides safety review services and fields safety review teams upon request of member states for the regulatory, the International Regulatory Review Team (IRRT) and Operational Safety Review Team (OSART) and Peer Review of the Operational and Safety Performance Experience Review (PROSPER). The OSART programme's purpose is to assist member states in enhancing the operational safety of individual nuclear power plants and to promote the continuous development of operational safety within all member states by the dissemination of information on good practice. The OSART Mission Results (OSMIR) database contains the results from 73 OSART missions and 54 follow up visits from 1991 and its continually updated. The Asian Nuclear Safety Network (ANSN) was established to pool and share existing and new technical knowledge and practical experience to further improve the safety of nuclear installation in Asia. In summary, the enhancement of the GNSR is anchored in the recognition that all the states are in the same boat and the increasing importance of sharing and mutual learning, sharing knowledge and experience through regional and global networking. It requires joint and coordinated strategy by all states. The IAEA is willing and ready to support the GNSR through the establishment and application of safety standards, and safety review and advisory services and international instruments. (Author)

Operating procedures and safety culture

International Nuclear Information System (INIS)

Carnino, A.

1993-01-01

The development of new technologies in recent years has led to a tremendous increase in the information to be mastered by operators in industrial processes. The information at operators disposal both in routine situations and accidental ones needs to be well prepared and organized to ensure reliability and safety. The man-machine interface should give operators all the necessary and clear indications on the process status and evolution so that the operators can operate the installation through adequate procedures. Procedures represent the real interface and mode of action of the operators on the machine, and they are of prime importance. Although they are by essence quite different, the routine, accident, and emergency procedures have in common one attribute: They all require a good safety culture both in their development and their implementation. From the definition given by the members of the International Nuclear Safety Advisory Group (INSAG), open-quotes Safety culture is that assembly of characteristics and attitudes in organizations and individuals which establishes that, as an overriding priority, nuclear plant safety issues receive the attention warranted by their significance,close quotes one can see that two aspects are embedded, a collective attitude that in fact is reflected in the managerial framework and an individual one that is linked to personnel behavior and work practices

Research for correction pre-operative MRI images of brain during operation using particle method simulation

International Nuclear Information System (INIS)

Shino, Ryosaku; Koshizuka, Seiichi; Sakai, Mikio; Ito, Hirotaka; Iseki, Hiroshi; Muragaki, Yoshihiro

2010-01-01

In the neurosurgical procedures, surgeon formulates a surgery plan based on pre-operative images such as MRI. However, the brain is transformed by removal of the affected area. In this paper, we propose a method for reconstructing pre-operative images involving the deformation with physical simulation. First, the domain of brain is identified in pre-operative images. Second, we create particles for physical simulation. Then, we carry out the linear elastic simulation taking into account the gravity. Finally, we reconstruct pre-operative images with deformation according to movement of the particles. We show the effectiveness of this method by reconstructing the pre-operative image actually taken before surgery. (author)

Operator Actions Within a Safety Instrumented Function

International Nuclear Information System (INIS)

Suttinger, L.T.

2002-01-01

This paper presents an overview of the factors that should be considered when crediting operator action for performing a safety function or being a part of the process of enabling a safety function. Criteria for evaluating operator action, such as required time response and operator training among others, are discussed. The paper will address these and other factors that should be considered when determining the reliability of the operator to respond and perform his/her part of the safety function. The entire safety function includes the operator and the reliability of the instrumented system that provides the alarm or indication, the final control element, and support systems. The integration of the operator performance with the hardware safety availability, including the effects of the supporting systems is discussed. The analysis of these factors will provide the justification for the amount of risk reduction or safety integrity level that can be credited for the Safety Instrumented Function (SIF), including operator action

International co-operation in the field of operational safety

International Nuclear Information System (INIS)

Dupuis, M.C.

1988-10-01

Operational safety in nuclear power plants is without doubt a field where international co-operation is in constant progress. Accounting for over 80 per cent of the 400 reactors in service throughout the world, the menber countries of the OECD Nuclear Energy Agency (NEA) are constantly striving to improve the exchange and use of the wealth of information to be gained not just from power plant accidents and incidents but from the routine operation of these facilities. The Committee on the Safety of Nuclear Installations (CSNI) helps the Steering Committee for Nuclear Energy to meet the NEA's objectives in the safety field, namely: - to promote co-operation between the safety bodies of member countries - to contribute to the safety and regulation of nuclear activities. The CSNI relies on the technical back-up of several different working groups made up of experts appointed by the member countries. For the past three years I have had the honour of chairing Principal Working Group 1 (PWG 1), which deals with operating experience and human factor. It is in this capacity that I will attempt to outline the group's various activities and its findings illustrated by a few examples

Development of the NUMO pre-selection, site-specific safety case

International Nuclear Information System (INIS)

Fujiyama, Tetsuo; Suzuki, Satoru; Deguchi, Akira; Umeki, Hiroyuki

2016-01-01

Key conclusions: ◆ “The NUMO pre-selection, site-specific safety case” provides the basic structure for subsequent safety cases that will be applied to any selected site, emphasising practical approaches and methodology which will be applicable for the conditions/constraints during an actual siting process. ◆ The preliminary results of the design and safety assessment would underpin the feasibility and safety of geological disposal in Japan.

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

International Nuclear Information System (INIS)

Staats, E.B.

1980-01-01

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

Pre-operative assessment and post-operative care in elective shoulder surgery.

Science.gov (United States)

Akhtar, Ahsan; Macfarlane, Robert J; Waseem, Mohammad

2013-01-01

Pre-operative assessment is required prior to the majority of elective surgical procedures, primarily to ensure that the patient is fit to undergo surgery, whilst identifying issues that may need to be dealt with by the surgical or anaesthetic teams. The post-operative management of elective surgical patients begins during the peri-operative period and involves several health professionals. Appropriate monitoring and repeated clinical assessments are required in order for the signs of surgical complications to be recognised swiftly and adequately. This article examines the literature regarding pre-operative assessment in elective orthopaedic surgery and shoulder surgery, whilst also reviewing the essentials of peri- and post-operative care. The need to recognise common post-operative complications early and promptly is also evaluated, along with discussing thromboprophylaxis and post-operative analgesia following shoulder surgery.

Pre-operative fasting guidelines: an update

DEFF Research Database (Denmark)

Søreide, E; Eriksson, L I; Hirlekar, G

2005-01-01

Liberal pre-operative fasting routines have been implemented in most countries. In general, clear fluids are allowed up to 2 h before anaesthesia, and light meals up to 6 h. The same recommendations apply for children and pregnant women not in labour. In children......Liberal pre-operative fasting routines have been implemented in most countries. In general, clear fluids are allowed up to 2 h before anaesthesia, and light meals up to 6 h. The same recommendations apply for children and pregnant women not in labour. In children...

Criteria for safety-related operator actions

International Nuclear Information System (INIS)

Gray, L.H.; Haas, P.M.

1983-01-01

The Safety-Related Operator Actions (SROA) Program was designed to provide information and data for use by NRC in assessing the performance of nuclear power plant (NPP) control room operators in responding to abnormal/emergency events. The primary effort involved collection and assessment of data from simulator training exercises and from historical records of abnormal/emergency events that have occurred in operating plants (field data). These data can be used to develop criteria for acceptability of the use of manual operator action for safety-related functions. Development of criteria for safety-related operator actions are considered

The System of Employee Appraisal in a Company

OpenAIRE

Vaverová, Lucie

2011-01-01

This bachelor study called "The System of Employee Appraisal in a Company" deals with a general subscription of a personal process "Employee appraisal". It describes the principles of the system of employee appraisal and also covers the conditions necessary for its efficiency and operation. The bachelor study is focused on the system of employee appraisal centrally implemented in company ČEZ, a. s. This system is analyzed and compared with generally stated theoretical principles. The study in...

Safety of Nuclear Power Plants: Commissioning and Operation

International Nuclear Information System (INIS)

2011-01-01

This publication is a revision of Safety Requirements No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe operation of nuclear power plants. Over recent years there have been developments in areas such as long term operation, plant ageing, periodic safety review, probabilistic safety analysis and risk informed decision making processes. It became necessary to revise the IAEA's safety requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the Fundamental Safety Principles. Contents: 1. Introduction; 2. Safety objectives and principles; 3. The management and organizational structure of the operating organization; 4. Management of operational safety; 5. Operational safety programmes; 6. Plant commissioning; 7. Plant operations; 8. Maintenance, testing, surveillance and inspection; 9. Preparation for decommissioning.

The critical safety functions and plant operation

International Nuclear Information System (INIS)

Corcoran, W.R.; Church, J.F.; Porter, N.J.; Cross, M.T.; Guinn, W.M.

1981-01-01

The paper outlines the operator's role in nuclear safety and introduces the concept of ''safety functions''. Safety functions are a group of actions that prevent core melt or minimize radiation releases to the general public. They can be used to provide a hierarchy of practical plant protection that an operator should use. ''An accident identical to that at Three Mile Island is not going to happen again'', said the Rogovin investigators. The concepts put forward in this paper are intended to help the operator avoid serious consequence from the next unexpected threat. On the basis of the safety evaluation, the operator has three roles in assuring that the consequences of an event will be no worse than the predicted acceptable results. These three operator roles are: first, maintain plant setup in readiness to properly respond; second, operate the plant in a manner such that fewer, milder events minimize the frequency and the severity of adverse events; third, the operator needs to monitor the plant to verify that the safety functions are accomplished. The operator needs a systematic approach to mitigating the consequences of an event. The concept of ''safety function'' introduces that systematic approach and prevents a hierarchy of protection. If the operator has difficulty in identifying an event for any reason, the systematic safety function approach allows ones to accomplish the overall path of mitigating consequences. There are ten identified functions designed to protect against core melt, preserve containment integrity, prevent indirect release of radioactivity, and maintain vital auxiliaries needed to support the other safety functions. The paper describes in detail the operator's role and the safety functions, and provides many examples of the use of alternative success paths to accomplish the safety function

CloudSat Safety Operations at Vandenberg AFB

Science.gov (United States)

Greenberg, Steve

2006-01-01

CloudSat safety operations at Vendenberg AFB is given. The topics include: 1) CloudSat Project Overview; 2) Vandenberg Ground Operations; 3) Delta II Launch Vehicle; 4) The A-Train; 5) System Safety Management; 6) CALIPSO Hazards Assessment; 7) CALIPSO Supplemental Safeguards; 8) Joint System Safety Operations; 9) Extended Stand-down; 10) Launch Delay Safety Concerns; and 11) Lessons Learned.

Enhancing operational safety

Energy Technology Data Exchange (ETDEWEB)

Wiebe, J S

1997-09-01

The presentation briefly considers the following aspects concerning enhancing operational safety of NPP: licensed control room supervision, reactivity changes, personnel access to control room, simulator training.

Agreement between pre-operative and intra-operative bacteriological samples in 85 chronic peri-prosthetic infections.

Science.gov (United States)

Matter-Parrat, V; Ronde-Oustau, C; Boéri, C; Gaudias, J; Jenny, J-Y

2017-04-01

Whether pre-operative microbiological sampling contributes to the management of chronic peri-prosthetic infection remains controversial. We assessed agreement between the results of pre-operative and intra-operative samples in patients undergoing single-stage prosthesis exchange to treat chronic peri-prosthetic infection. Agreement between pre-operative and intra-operative samples exceeds 75% in patients undergoing single-stage exchange of a hip or knee prosthesis to treat chronic peri-prosthetic infection. This single-centre retrospective study included 85 single-stage prosthesis exchange procedures in 82 patients with chronic peri-prosthetic infection at the hip or knee. Agreement between pre-operative and intra-operative sample results was evaluated. Changes to the initial antibiotic regimen made based on the intra-operative sample results were recorded. Of 149 pre-operative samples, 109 yielded positive cultures, in 75/85 cases. Of 452 intra-operative samples, 354 yielded positive cultures, in 85/85 cases. Agreement was complete in 54 (63%) cases and partial in 9 (11%) cases; there was no agreement in the remaining 22 (26%) cases. The complete agreement rate was significantly lower than 75% (P=0.01). The initial antibiotic regimen was inadequate in a single case. Pre-operative sampling may contribute to the diagnosis of peri-prosthetic infection but is neither necessary nor sufficient to confirm the diagnosis and identify the causative agent. The spectrum of the initial antibiotic regimen cannot be safely narrowed based on the pre-operative sample results. We suggest the routine prescription of a probabilistic broad-spectrum antibiotic regimen immediately after the prosthesis exchange, even when a pathogen was identified before surgery. IV, retrospective study. Copyright © 2017 Elsevier Masson SAS. All rights reserved.

Sizewell 'B' PWR pre-construction safety report

International Nuclear Information System (INIS)

1982-04-01

The Pre-Construction Safety Report (PCSR) for a PWR power station to be constructed as Sizewell 'B' is presented in 13 volumes containing 16 chapters. The PCSR has been submitted to the Nuclear Installations Inspectorate in support of the Central Electricity Generating Board's application for consent to the extension at Sizewell. It describes the design and provides the safety case for the proposed station, which comprises a 4-loop pressurized water reactor with associated generating plant and supporting auxiliary equipment. A general description of the station and its site is given. The strategy for ensuring nuclear safety is set out and the general design aspects of systems and plant outlined. The plant and systems, including their safety design bases and the fault analyses carried out for the design are described. Finally the way in which the plant will be decommissioned at the end of its useful life is outlined. (U.K.)

Safety of Nuclear Power Plants: Commissioning and Operation. Specific Safety Requirements

International Nuclear Information System (INIS)

2017-01-01

This publication is a revision of IAEA Safety Standards Series No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe commissioning, operation, and transition from operation to decommissioning of nuclear power plants. Over recent years there have been developments in areas such as long term operation of nuclear power plants, plant ageing, periodic safety review, probabilistic safety analysis review and risk informed decision making processes. It became necessary to revise the IAEA’s Safety Requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles. A review of Safety Requirements publications, initiated in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan, revealed no significant areas of weakness but resulted in a small set of amendments to strengthen the requirements and facilitate their implementation. These are contained in the present publication.

The operator's role and safety functions

International Nuclear Information System (INIS)

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

1980-01-01

A nuclear power plant can be thought of as a single system with two major subsystems: equipment and people. Both play important roles in nuclear safety. Whereas, in the past, the role of equipment had been emphasized in nuclear safety, the accident at Three Mile Island and its subsequent investigations point out the vital role of the operator. This paper outlines the operator's roles in nuclear safety and suggests how the concept of safety functions can be used to reduce economic losses and increase safety margins. (auth)

Pre-Exposure Prophylaxis for HIV Prevention : Safety Concerns

NARCIS (Netherlands)

Tetteh, Raymond A; Yankey, Barbara A; Nartey, Edmund T; Lartey, Margaret; Leufkens, Hubert G M; Dodoo, Alexander N O

Available evidence supports the efficacy of pre-exposure prophylaxis (PrEP) in decreasing the incidence of human immunodeficiency virus (HIV) infection among high-risk individuals, especially when used in combination with other behavioural preventive methods. Safety concerns about PrEP present

Predicting safety culture: the roles of employer, operations manager and safety professional.

Science.gov (United States)

Wu, Tsung-Chih; Lin, Chia-Hung; Shiau, Sen-Yu

2010-10-01

This study explores predictive factors in safety culture. In 2008, a sample 939 employees was drawn from 22 departments of a telecoms firm in five regions in central Taiwan. The sample completed a questionnaire containing four scales: the employer safety leadership scale, the operations manager safety leadership scale, the safety professional safety leadership scale, and the safety culture scale. The sample was then randomly split into two subsamples. One subsample was used for measures development, one for the empirical study. A stepwise regression analysis found four factors with a significant impact on safety culture (R²=0.337): safety informing by operations managers; safety caring by employers; and safety coordination and safety regulation by safety professionals. Safety informing by operations managers (ß=0.213) was by far the most significant predictive factor. The findings of this study provide a framework for promoting a positive safety culture at the group level. Crown Copyright © 2010. Published by Elsevier Ltd. All rights reserved.

Operational safety improvement in OPR 1000

International Nuclear Information System (INIS)

Jung, Y.-E.

2005-01-01

Nuclear power operating experience management might be an important factor for the operational safety improvement. KHNP's nuclear information management system, called KONIS receives, distributes and manages all nuclear information from domestic and foreign, especially operating experience. Ulchin 3 and 4, the first units of OPR 1000 series operates several organizations regarding management of operating experience e.g. specialist group program, various task forces, equipment specialist system for operator, etc. Peer review is another contribution for nuclear safety. (author)

OSART mission highlights 1989-1990: Operational safety practices in nuclear power plants

International Nuclear Information System (INIS)

1992-12-01

The IAEA Operational Safety Review Team (OSART) programme provides advice and assistance to Member States in enhancing the operational safety of nuclear power plants. OSART reviews are available to all countries with nuclear power plants in operation or approaching operation. Most of these countries have participated in the programme, by hosting one or more OSART missions or by making experts available to participate in missions. Careful design and high quality of construction are prerequisites for a safe nuclear power plant. However, a plant's safety depends ultimately on the ability and conscientiousness of the operating personnel and on their tools and work methods. OSART missions assess a facility's operational practices in comparison with those used successfully in other countries, and exchange, at the working level, ideas for promoting safety. Both the plants reviewed and the organizations providing experts have benefited from the programme. The observations of the OSART members are documented in technical notes which are then used as source material for the official OSART Report submitted to the government of the host country. The technical notes contain recommendations for improvements and descriptions of recommendable good practices. The same notes have been used to compile the present summary report which is intended for wide distribution to all organizations constructing, operating or regulating nuclear power plants. This report is the fourth in a series following IAEA-TECDOC-458, IAEA-TECDOC-497 and IAEA-TECDOC-570 and covers the period June 1989 to December 1990. Reference is also made to a summary report of Pre-OSART missions, which is in preparation. In addition, a report presenting OSART Good Practices has been published (IAEA-TECDOC-605)

Safety of Nuclear Power Plants: Commissioning and Operation

International Nuclear Information System (INIS)

2011-01-01

The safety of a nuclear power plant is ensured by means of proper site selection, design, construction and commissioning, and the evaluation of these, followed by proper management, operation and maintenance of the plant. In a later phase, a proper transition to decommissioning is required. The organization and management of plant operations ensures that a high level of safety is achieved through the effective management and control of operational activities. This publication is a revision of the Safety Requirements publication Safety of Nuclear Power Plants: Operation, which was issued in 2000 as IAEA Safety Standards Series No. NS-R-2. The purpose of this revision was to restructure Safety Standards Series No. NS-R-2 in the light of new operating experience and new trends in the nuclear industry; to introduce new requirements that were not included in Safety Standards Series No. NS-R-2 on the operation of nuclear power plants; and to reflect current practices, new concepts and technical developments. This update also reflects feedback on the use of the standards, both from Member States and from the IAEA's safety related activities. The publication is presented in the new format for Safety Requirements publications. The present publication reflects the safety principles of the Fundamental Safety Principles. It has been harmonized with IAEA Safety Standards Series No. GS-R-3 on The Management System for Facilities and Activities. Guidance on the fulfilment of the safety requirements is provided in supporting Safety Guides. The terminology used in this publication is defined and explained in the IAEA Safety Glossary. The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the safety objective and safety principles that are established in the Fundamental Safety Principles. This

The critical safety functions and plant operation

International Nuclear Information System (INIS)

Corcoran, W.R.; Church, J.F.; Cross, M.T.; Guinn, W.M.; Porter, N.J.

1981-01-01

The operator's role in nuclear safety is outlined and the concept of ''safety functions'' introduced. Safety functions are a group of actions that prevent core melt or minimize radiation releases to the general public. They can be used to provide a hierarchy of practical plant protection that an operator should use. The plant safety evaluation uses four inputs in predicting the results of an event: the event initiator, the plant design, the initial plant conditions and setup, and the operator actions. If any of these inputs are not as assumed in the evaluation, confidence that the consequences will be as predicted is reduced. Based on the safety evaluation, the operator has three roles in assuring that the consequences of an event will be no worse than the predicted acceptable results: Maintain plant setup in readiness to properly respond. Operate the plant in a manner such that fewer, milder events minimize the frequency and the severity of adverse events. Monitor the plant to verify that the safety functions are accomplished. The operator needs a systematic approach to mitigating the consequences of an event. The concept of safety functions introduces this systematic approach and presents a hierarchy of protection. If the operator has difficulty identifying an event for any reason, the systematic safety function approach allows accomplishing the overall path of mitigating consequences. Ten functions designed to protect against core melt, preserve containment integrity, prevent indirect release of radioactivity, and maintain vital auxiliaries needed to support the other safety functions are identified

Study on Safety Assessment for TINT- Pre disposal Radioactive Waste Management Facilities by the Application of SAFRAN Software

International Nuclear Information System (INIS)

Ya-anant, Nanthavan

2011-06-01

Full text: The Radioactive Waste Management Center, Thailand Institute of Nuclear Technology (TINT) provides a centralized radioactive waste management (RWM) service in the country. The pre disposal RWM facilities are composed of low and intermediate level waste treatment and storage facilities. The benefits of this study are (1) to improve the safety of pre disposal RWM facilities (2) to experience with the SAFRAN software tool for the safety assessment of pre disposal RWM facilities, which has been developed following to the methodology from International Atomic Energy Agency (IAEA). The work was performed on collecting all waste management data, the diagram of facilities, buildings, location, procedure, waste classification, waste form, radiological/chemical/physical properties including scenarios in normal and accidental conditions. The result of normal condition is that the effective dose per year of worker and public is less than 20 mSv and 1 mSv respectively. So the TINT-RWM operation is safe, as referred to the regulation

Operational safety - the IAEA response

International Nuclear Information System (INIS)

Rosen, M.

1984-01-01

Nuclear safety is an international issue. The role of the International Atomic Energy Agency is growing because it offers a centre for contact and exchange between East and West, North and South. New initiatives are under way to intensify international co-operative safety efforts through exchange of information on abnormal events at nuclear power plants, and through greater sharing of safety research results. Emergency preparedness also lends itself to international co-operation. A report has been prepared on the need for establishing mutual emergency assistance. By analysing possible constraints to bilateral or multinational efforts in advance, a basis for agreement at the time of an emergency is being worked out. Safety standards have been developed in several areas. The NUSS Codes and Guides, now almost complete, make available to countries starting a nuclear power programme a coherent set of nuclear safety standards. A revised set of Basic Safety Standards for Radiation Protection has been issued in 1982. (author)

Association between elevated pre-operative glycosylated hemoglobin and post-operative infections after non-emergent surgery

Directory of Open Access Journals (Sweden)

Joseph M. Blankush

2016-09-01

Conclusions: The risk factors of post-operative infection are multiple and likely synergistic. While pre-operative HbA1c level is not independently associated with risk of post-operative infection, there are scenarios and patient subgroups where pre-operative HbA1c is useful in predicting an increased risk of infectious complications in the post-operative period.

The use of probabilistic safety analysis in design and operation -- Lessons learned from Sizewell B. Annex 14

International Nuclear Information System (INIS)

Buttery, N.E.

2002-01-01

Probabilistic Safety Assessments (PSAs) have been used extensively in the design and licensing of Sizewell B. This paper outlines the role of PSA in the UK licensing process and describes how it has been applied to Sizewell B during both the pre-construction and pre-operational phases. From this experience a 'Living PSA' has been formulated which continues be used to support operation. The application of PSA to Sizewell B has demonstrated that it is a powerful tool with potential for future use. Its strengths and limitations as a tool need to recognised by both users and regulators. It is not a fully mechanistic means of ensuring design safety, but is an important aid to decision making. It also has the potential to allow risk judgements to be taken in conjunction with commercial and environmental issues. (author)

Time Based Workload Analysis Method for Safety-Related Operator Actions in Safety Analysis

Energy Technology Data Exchange (ETDEWEB)

Kim, Yun Goo; Oh, Eung Se [Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of)

2016-05-15

During the design basis event, the safety system performs safety functions to mitigate the event. The most of safety system is actuated by automatic system however, there are operator manual actions that are needed for the plant safety. These operator actions are classified as important human actions in human factors engineering design. The human factors engineering analysis and evaluation is needed for these important human actions to assure that operator successfully perform their tasks for plant safety and operational goals. The work load analysis is one of the required analysis for the important human actions.

Time Based Workload Analysis Method for Safety-Related Operator Actions in Safety Analysis

International Nuclear Information System (INIS)

Kim, Yun Goo; Oh, Eung Se

2016-01-01

During the design basis event, the safety system performs safety functions to mitigate the event. The most of safety system is actuated by automatic system however, there are operator manual actions that are needed for the plant safety. These operator actions are classified as important human actions in human factors engineering design. The human factors engineering analysis and evaluation is needed for these important human actions to assure that operator successfully perform their tasks for plant safety and operational goals. The work load analysis is one of the required analysis for the important human actions.

Indicators to monitor NPP operational safety performance

International Nuclear Information System (INIS)

Gomez-Cobo, Ana

2002-01-01

Since December 1995 the IAEA activities on safety performance indicators focused on the elaboration of a framework for the establishment of an operational safety performance indicator programme. The development of this framework began with the consideration of the concept of NPP operational safety performance and the identification of operational safety attributes. For each operational safety attribute, overall indicators, envisioned as providing an overall evaluation of relevant aspects of safety performance, were established. Associated with each overall indicator is a level of strategic indicators intended to provide a bridge from overall to specific indicators. Finally each strategic indicator was supported by a set of specific indicators, which represent quantifiable measures of performance. The programme development was enhanced by pilot plant studies, conducted over a 15 month period from January 1998 to March 1999. The result of all this work is compiled in the IAEA-TECDOC-1141, to be published shortly. This paper presents a summary of this IAEA TECDOC. It describes the operational safety performance indicator framework proposed and discusses the results of and lessons learned from the pilot studies. Despite the efforts described, it is clear that additional research is still necessary in areas such as plant-specific adaptation of proposed frameworks in order to suit individual data collection systems and plant characteristics, indicator selection, indicator definition, goal setting, action thresholds, analysis of trends, indicator display systems, analysis of overall safety performance (i.e., aggregation or combination of indicators), safety culture indicators, qualitative indicators, and use of additional indicators to address issues such as industrial safety attitude and performance, staff welfare, and environmental compliance. This is the rationale for a new IAEA Coordinated Research Project on 'Development and application of indicators to monitor NPP

Operational limits and conditions and operating procedures for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

This Safety Guide was prepared as part of the Agency's programme for establishing safety standards relating to nuclear power plants. The present Safety Guide supersedes the IAEA Safety Guide on Operational Limits and Conditions for Nuclear Power Plants which was issued in 1979 as Safety Series No. 50-SG-O3. For a nuclear power plant to be operated in a safe manner, the provisions made in the final design and subsequent modifications shall be reflected in limitations on plant operating parameters and in the requirements on plant equipment and personnel. Under the responsibility of the operating organization, these shall be developed during the design safety evaluation as a set of operational limits and conditions (OLCs). A major contribution to compliance with the OLCs is made by the development and utilization of operating procedures (OPs) that are consistent with and fully implement the OLCs. The requirements for the OLCs and OPs are established in Section 5 of the IAEA Safety Requirements publication Safety of Nuclear Power Plants: Operation, which this Safety Guide supplements. The purpose of this Safety Guide is to provide guidance on the development, content and implementation of OLCs and OPs. The Safety Guide is directed at both regulators and owners/operators. This Safety Guide covers the concept of OLCs, their content as applicable to land based stationary power plants with thermal neutron reactors, and the responsibilities of the operating organization regarding their establishment, modification, compliance and documentation. The OPs to support the implementation of the OLCs and to ensure their observance are also within the scope of this Safety Guide. The particular aspects of the procedures for maintenance, surveillance, in-service inspection and other safety related activities in connection with the safe operation of nuclear power plants are outside the scope of this Safety Guide but can be found in other IAEA Safety Guides. Section 2 indicates the

Operational limits and conditions and operating procedures for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2000-01-01

This Safety Guide was prepared as part of the Agency's programme for establishing safety standards relating to nuclear power plants. The present Safety Guide supersedes the IAEA Safety Guide on Operational Limits and Conditions for Nuclear Power Plants which was issued in 1979 as Safety Series No. 50-SG-O3. For a nuclear power plant to be operated in a safe manner, the provisions made in the final design and subsequent modifications shall be reflected in limitations on plant operating parameters and in the requirements on plant equipment and personnel. Under the responsibility of the operating organization, these shall be developed during the design safety evaluation as a set of operational limits and conditions (OLCs). A major contribution to compliance with the OLCs is made by the development and utilization of operating procedures (OPs) that are consistent with and fully implement the OLCs. The requirements for the OLCs and OPs are established in Section 5 of the IAEA Safety Requirements publication Safety of Nuclear Power Plants: Operation, which this Safety Guide supplements. The purpose of this Safety Guide is to provide guidance on the development, content and implementation of OLCs and OPs. The Safety Guide is directed at both regulators and owners/operators. This Safety Guide covers the concept of OLCs, their content as applicable to land based stationary power plants with thermal neutron reactors, and the responsibilities of the operating organization regarding their establishment, modification, compliance and documentation. The OPs to support the implementation of the OLCs and to ensure their observance are also within the scope of this Safety Guide. The particular aspects of the procedures for maintenance, surveillance, in-service inspection and other safety related activities in connection with the safe operation of nuclear power plants are outside the scope of this Safety Guide but can be found in other IAEA Safety Guides. Section 2 indicates the

Safety valve opening and closing operation monitor

International Nuclear Information System (INIS)

Kodama, Kunio; Takeshima, Ikuo; Takahashi, Kiyokazu.

1981-01-01

Purpose: To enable the detection of the closing of a safety valve when the internal pressure in a BWR type reactor is a value which will close the safety valve, by inputting signals from a pressure detecting device mounted directly at a reactor vessel and a safety valve discharge pressure detecting device to an AND logic circuit. Constitution: A safety valve monitor is formed of a pressure switch mounted at a reactor pressure vessel, a pressure switch mounted at the exhaust pipe of the escape safety valve and a logic circuit and the lide. When the input pressure of the safety valve is raised so that the valve and the pressure switch mounted at the exhaust pipe are operated, an alarm is indicated, and the operation of the pressure switch mounted at a pressure vessel is eliminated. If the safety valve is not reclosed when the vessel pressure is decreased lower than the pressure at which it is to be reclosed after the safety valve is operated, an alarm is generated by the logic circuit since both the pressure switches are operated. (Sekiya, K.)

The operating organization for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2001-01-01

This Safety Guide was prepared under the IAEA programme for safety standards for nuclear power plants. The present publication is a revision of the IAEA Safety Guide on Management of Nuclear Power Plants for Safe Operation issued in 1984. It supplements Section 2 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation. Nuclear power technology is different from the customary technology of power generation from fossil fuel and by hydroelectric means. One major difference between the management of nuclear power plants and that of conventional generating plants is the emphasis that should be placed on nuclear safety, quality assurance, the management of radioactive waste and radiological protection, and the accompanying national regulatory requirements. This Safety Guide highlights the important elements of effective management in relation to these aspects of safety. The attention to be paid to safety requires that the management recognize that personnel involved in the nuclear power programme should understand, respond effectively to, and continuously search for ways to enhance safety in the light of any additional requirements socially and legally demanded of nuclear energy. This will help to ensure that safety policies that result in the safe operation of nuclear power plants are implemented and that margins of safety are always maintained. The structure of the organization, management standards and administrative controls should be such that there is a high degree of assurance that safety policies and decisions are implemented, safety is continuously enhanced and a strong safety culture is promoted and supported. The objective of this publication is to guide Member States in setting up an operating organization which facilitates the safe operation of nuclear power plants to a high level internationally. The second objective is to provide guidance on the most important organizational elements in order to contribute to a strong safety

The operating organization for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

This Safety Guide was prepared under the IAEA programme for safety standards for nuclear power plants. The present publication is a revision of the IAEA Safety Guide on Management of Nuclear Power Plants for Safe Operation issued in 1984. It supplements Section 2 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation. Nuclear power technology is different from the customary technology of power generation from fossil fuel and by hydroelectric means. One major difference between the management of nuclear power plants and that of conventional generating plants is the emphasis that should be placed on nuclear safety, quality assurance, the management of radioactive waste and radiological protection, and the accompanying national regulatory requirements. This Safety Guide highlights the important elements of effective management in relation to these aspects of safety. The attention to be paid to safety requires that the management recognize that personnel involved in the nuclear power programme should understand, respond effectively to, and continuously search for ways to enhance safety in the light of any additional requirements socially and legally demanded of nuclear energy. This will help to ensure that safety policies that result in the safe operation of nuclear power plants are implemented and that margins of safety are always maintained. The structure of the organization, management standards and administrative controls should be such that there is a high degree of assurance that safety policies and decisions are implemented, safety is continuously enhanced and a strong safety culture is promoted and supported. The objective of this publication is to guide Member States in setting up an operating organization which facilitates the safe operation of nuclear power plants to a high level internationally. The second objective is to provide guidance on the most important organizational elements in order to contribute to a strong safety

The operating organization for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2004-01-01

This Safety Guide was prepared under the IAEA programme for safety standards for nuclear power plants. The present publication is a revision of the IAEA Safety Guide on Management of Nuclear Power Plants for Safe Operation issued in 1984. It supplements Section 2 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation. Nuclear power technology is different from the customary technology of power generation from fossil fuel and by hydroelectric means. One major difference between the management of nuclear power plants and that of conventional generating plants is the emphasis that should be placed on nuclear safety, quality assurance, the management of radioactive waste and radiological protection, and the accompanying national regulatory requirements. This Safety Guide highlights the important elements of effective management in relation to these aspects of safety. The attention to be paid to safety requires that the management recognize that personnel involved in the nuclear power programme should understand, respond effectively to, and continuously search for ways to enhance safety in the light of any additional requirements socially and legally demanded of nuclear energy. This will help to ensure that safety policies that result in the safe operation of nuclear power plants are implemented and that margins of safety are always maintained. The structure of the organization, management standards and administrative controls should be such that there is a high degree of assurance that safety policies and decisions are implemented, safety is continuously enhanced and a strong safety culture is promoted and supported. The objective of this publication is to guide Member States in setting up an operating organization which facilitates the safe operation of nuclear power plants to a high level internationally. The second objective is to provide guidance on the most important organizational elements in order to contribute to a strong safety

EPRI program in water reactor safety

International Nuclear Information System (INIS)

Loewenstein, W.B.; Gelhaus, F.; Gopalakrishnan, A.

1975-01-01

The basis for EPRI's water reactor safety program is twofold. First is compilation and development of fundamental background data necessary for quantified light-water reactor (LWR) safety assurance appraisals. Second is development of realistic and experimentally bench-marked analytical procedures. The results are expected either to confirm the safety margins in current operating parameters, and to identify overly conservative controls, or, in some cases, to provide a basis for improvements to further minimize uncertainties in expected performance. Achievement of these objectives requires the synthesis of related current and projected experimental-analytical projects toward establishment of an experimentally-based analysis for the assurance of safety for LWRs

Implementation of Pre-Operative Checklist: An Effort to Reduce ...

African Journals Online (AJOL)

Implementation of Pre-Operative Checklist: An Effort to Reduce Delays in. Surgery and ... insight to develop a pre-operative checklist to ensure that patients were prepared for surgery and to minimize disruptions ... documentation audit was conducted in May 2014, showing 59% compliance in completing the checklist. Since.

Quality assurance of pre-operative assessment--a review of quality assurance activities related to pre-operative assessment in nine hospitals in The Netherlands

NARCIS (Netherlands)

Klazinga, N. S.; Helsloot, R.

1989-01-01

Pre-operative assessment of patients for surgery is one of the most prevalent topics for quality assurance by peer-review in Dutch hospitals. This article describes the experiences with pre-operative assessment in nine hospitals. It is discussed why preoperative assessment is performed, what tests

Pre-cementation of deep shaft

Science.gov (United States)

Heinz, W. F.

1988-12-01

Pre-cementation or pre-grouting of deep shafts in South Africa is an established technique to improve safety and reduce water ingress during shaft sinking. The recent completion of several pre-cementation projects for shafts deeper than 1000m has once again highlighted the effectiveness of pre-grouting of shafts utilizing deep slimline boreholes and incorporating wireline technique for drilling and conventional deep borehole grouting techniques for pre-cementation. Pre-cementation of deep shaft will: (i) Increase the safety of shaft sinking operation (ii) Minimize water and gas inflow during shaft sinking (iii) Minimize the time lost due to additional grouting operations during sinking of the shaft and hence minimize costly delays and standing time of shaft sinking crews and equipment. (iv) Provide detailed information of the geology of the proposed shaft site. Informations on anomalies, dykes, faults as well as reef (gold bearing conglomerates) intersections can be obtained from the evaluation of cores of the pre-cementation boreholes. (v) Provide improved rock strength for excavations in the immediate vicinity of the shaft area. The paper describes pre-cementation techniques recently applied successfully from surface and some conclusions drawn for further considerations.

Reactor operation safety information document

Energy Technology Data Exchange (ETDEWEB)

1990-01-01

The report contains a reactor facility description which includes K, P, and L reactor sites, structures, operating systems, engineered safety systems, support systems, and process and effluent monitoring systems; an accident analysis section which includes cooling system anomalies, radioactive materials releases, and anticipated transients without scram; a summary of onsite doses from design basis accidents; severe accident analysis (reactor core disruption); a description of operating contractor organization and emergency planning; and a summary of reactor safety evolution. (MB)

The Patient Safety Attitudes among the Operating Room Personnel

Directory of Open Access Journals (Sweden)

Cherdsak Iramaneerat

2016-07-01

Full Text Available Background: The first step in cultivating the culture of safety in the operating room is the assessment of safety culture among operating room personnel. Objective: To assess the patient safety culture of operating room personnel at the Department of Surgery, Faculty of Medicine Siriraj Hospital, and compare attitudes among different groups of personnel, and compare them with the international standards. Methods: We conducted a cross-sectional survey of safety attitudes among 396 operating room personnel, using a short form of the Safety Attitudes Questionnaire (SAQ. The SAQ employed 30 items to assess safety culture in six dimensions: teamwork climate, safety climate, stress recognition, perception of hospital management, working conditions, and job satisfaction. The subscore of each dimension was calculated and converted to a scale score with a full score of 100, where higher scores indicated better safety attitudes. Results: The response rate was 66.4%. The overall safety culture score of the operating room personnel was 65.02, higher than an international average (61.80. Operating room personnel at Siriraj Hospital had safety attitudes in teamwork climate, safety climate, and stress recognition lower than the international average, but had safety attitudes in the perception of hospital management, working conditions, and job satisfaction higher than the international average. Conclusion: The safety culture attitudes of operating room personnel at the Department of Surgery, Siriraj Hospital were comparable to international standards. The safety dimensions that Siriraj Hospital operating room should try to improve were teamwork climate, safety climate, and stress recognition.

Pre-operative pain and sensory function in groin hernia

DEFF Research Database (Denmark)

Aasvang, Eske K; Hansen, Jeanette B; Kehlet, Henrik

2009-01-01

BACKGROUND: Although persistent postherniotomy occurs in 5-10% of patients, pathogenic mechanisms remain debatable. Since pre-operative pain has been demonstrated to be a risk factor for persistent postherniotomy pain, pre-operative alterations in nociceptive function may be a potential pathogenic...... mechanism. AIMS: To investigate the correlation between pre-operative pain intensity and sensory functions in the groin hernia area. METHODS: Patients with unilateral groin hernia were examined preoperatively by quantitative sensory testing (thermal, mechanical, and pressure [detection and pain thresholds...... (7%), all whom experienced no pain or pain less than weekly. Only cool detection thresholds were significantly lower between the hernia vs. contralateral side (poperative groin hernia...

Safety of Nuclear Power Plants: Commissioning and Operation. Specific Safety Requirements

International Nuclear Information System (INIS)

2016-01-01

This publication describes the requirements to be met to ensure the safe operation of nuclear power plants. It takes into account developments in areas such as long term operation of nuclear power plants, plant ageing, periodic safety review, probabilistic safety analysis and risk informed decision making processes. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles. A review of Safety Requirements publications was commenced in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan. The review revealed no significant areas of weakness and resulted in just a small set of amendments to strengthen the requirements and facilitate their implementation, which are contained in the present publication

Nuclear health and safety

International Nuclear Information System (INIS)

1990-04-01

This report summarizes the responsiveness of DOE and contractors to findings contained in DOE technical safety appraisals and environmental surveys. These appraisals and surveys have been done at DOE facilities and sites to find out the extent of the environmental, safety, and health problems and to prioritize them for corrective action. As of January 1990, DOE computer data showed over 1,700 safety and health problems and almost 1,300 environmental problems. The majority of these problems, however, have not yet been corrected. GAO also looked at the extent to which DOE has developed a computerized tracking system to monitor the status of its environmental, safety, and health problems. GAO found that the computer system lacks important information, such as various field office and independent appraisals. Inclusion of this information would provide a more complete picture of the problems at the site

Transportation Safety Excellence in Operations Through Improved Transportation Safety Document

International Nuclear Information System (INIS)

Dr. Michael A. Lehto; MAL

2007-01-01

A recent accomplishment of the Idaho National Laboratory (INL) Materials and Fuels Complex (MFC) Nuclear Safety analysis group was to obtain DOE-ID approval for the inter-facility transfer of greater-than-Hazard-Category-3 quantity radioactive/fissionable waste in Department of Transportation (DOT) Type A drums at MFC. This accomplishment supported excellence in operations through safety analysis by better integrating nuclear safety requirements with waste requirements in the Transportation Safety Document (TSD); reducing container and transport costs; and making facility operations more efficient. The MFC TSD governs and controls the inter-facility transfer of greater-than-Hazard-Category-3 radioactive and/or fissionable materials in non-DOT approved containers. Previously, the TSD did not include the capability to transfer payloads of greater-than-Hazard-Category-3 radioactive and/or fissionable materials using DOT Type A drums. Previous practice was to package the waste materials to less-than-Hazard-Category-3 quantities when loading DOT Type A drums for transfer out of facilities to reduce facility waste accumulations. This practice allowed operations to proceed, but resulted in drums being loaded to less than the Waste Isolation Pilot Plant (WIPP) waste acceptance criteria (WAC) waste limits, which was not cost effective or operations friendly. An improved and revised safety analysis was used to gain DOE-ID approval for adding this container configuration to the MFC TSD safety basis. In the process of obtaining approval of the revised safety basis, safety analysis practices were used effectively to directly support excellence in operations. Several factors contributed to the success of MFC's effort to obtain approval for the use of DOT Type A drums, including two practices that could help in future safety basis changes at other facilities. (1) The process of incorporating the DOT Type A drums into the TSD at MFC helped to better integrate nuclear safety

[Operating Room Nurses' Experiences of Securing for Patient Safety].

Science.gov (United States)

Park, Kwang Ok; Kim, Jong Kyung; Kim, Myoung Sook

2015-10-01

This study was done to evaluate the experience of securing patient safety in hospital operating rooms. Experiential data were collected from 15 operating room nurses through in-depth interviews. The main question was "Could you describe your experience with patient safety in the operating room?". Qualitative data from the field and transcribed notes were analyzed using Strauss and Corbin's grounded theory methodology. The core category of experience with patient safety in the operating room was 'trying to maintain principles of patient safety during high-risk surgical procedures'. The participants used two interactional strategies: 'attempt continuous improvement', 'immersion in operation with sharing issues of patient safety'. The results indicate that the important factors for ensuring the safety of patients in the operating room are manpower, education, and a system for patient safety. Successful and safe surgery requires communication, teamwork and recognition of the importance of patient safety by the surgical team.

Operation safety of complex industrial systems. Main concepts

International Nuclear Information System (INIS)

Zwingelstein, G.

2009-01-01

Operation safety consists in knowing, evaluating, foreseeing, measuring and mastering the technological system and human failures in order to avoid their impacts on health and people's safety, on productivity, and on the environment, and to preserve the Earth's resources. This article recalls the main concepts of operation safety: 1 - evolutions in the domain; 2 - failures, missions and functions of a system and of its components: functional failure, missions and functions, industrial processes, notions of probability; 3 - basic concepts and operation safety: reliability, unreliability, failure density, failure rate, relations between them, availability, maintainability, safety. (J.S.)

Pre-operative skin preparation practices: results of the 2007 French national assessment.

Science.gov (United States)

Borgey, F; Thibon, P; Ertzscheid, M-A; Bernet, C; Gautier, C; Mourens, C; Bettinger, A; Aggoune, M; Galy, E; Lejeune, B; Kadi, Z

2012-05-01

Pre-operative skin preparation, aimed at reducing the endogenous microbial flora, is one of the main preventive measures employed to decrease the likelihood of surgical site infection. National recommendations on pre-operative management of infection risks were issued in France in 2004. To assess compliance with the French national guidelines for pre-operative skin preparation in 2007. A prospective audit was undertaken in French hospitals through interviews with patients and staff, and observation of professional practice. Compliance with five major criteria selected from the guidelines was studied: patient information, pre-operative showering, pre-operative hair removal, surgical site disinfection and documentation of these procedures. Data for 41,188 patients from all specialties at 609 facilities were analysed. Patients were issued with information about pre-operative showering in 88.2% of cases [95% confidence interval (CI) 87.9-88.5]. The recommended procedure for pre-operative showering, including hairwashing, with an antiseptic skin wash solution was followed by 70.3% of patients (95% CI 69.9-70.8); this percentage was higher when patients had received appropriate information (P pre-operative surgical hygiene, 82.3% of cases; and pre-operative site disinfection, 71.7% of cases. The essential content of the French guidelines seems to be understood, but reminders need to be issued. Some recommendations may need to be adapted for certain specialties. Copyright © 2012 The Healthcare Infection Society. Published by Elsevier Ltd. All rights reserved.

Association between elevated pre-operative glycosylated hemoglobin and post-operative infections after non-emergent surgery.

Science.gov (United States)

Blankush, Joseph M; Leitman, I Michael; Soleiman, Aron; Tran, Trung

2016-09-01

A chronic state of impaired glucose metabolism affects multiple components of the immune system, possibly leading to an increased incidence of post-operative infections. Such infections increase morbidity, length of stay, and overall cost. This study evaluates the correlation between elevated pre-operative glycosylated hemoglobin (HbA1c) and post-operative infections. Adult patients undergoing non-emergent procedures across all surgical subspecialties from January 2010 to July 2014 had a preoperative HbA1c measured as part of their routine pre-surgical assessment. 2200 patient charts (1100 operative infection (superficial surgical site infection, deep wound/surgical space abscess, pneumonia, and/or urinary tract infection as defined by Centers for Disease Control criteria) within 30 days of surgery. Patients with HbA1c infection rate (3.8% in the HbA1c infection. Elevated HbA1c was, however, predictive of significantly increased risk of post-operative infection when associated with increased age (≥81 years of age) or dirty wounds. The risk factors of post-operative infection are multiple and likely synergistic. While pre-operative HbA1c level is not independently associated with risk of post-operative infection, there are scenarios and patient subgroups where pre-operative HbA1c is useful in predicting an increased risk of infectious complications in the post-operative period.

Evaluation of the food safety training for food handlers in restaurant operations

Science.gov (United States)

Park, Sung-Hee; Kwak, Tong-Kyung

2010-01-01

This study examined the extent of improvement of food safety knowledge and practices of employee through food safety training. Employee knowledge and practice for food safety were evaluated before and after the food safety training program. The training program and questionnaires for evaluating employee knowledge and practices concerning food safety, and a checklist for determining food safety performance of restaurants were developed. Data were analyzed using the SPSS program. Twelve restaurants participated in this study. We split them into two groups: the intervention group with training, and the control group without food safety training. Employee knowledge of the intervention group also showed a significant improvement in their score, increasing from 49.3 before the training to 66.6 after training. But in terms of employee practices and the sanitation performance, there were no significant increases after the training. From these results, we recommended that the more job-specific and hand-on training materials for restaurant employees should be developed and more continuous implementation of the food safety training and integration of employee appraisal program with the outcome of safety training were needed. PMID:20198210

Pre-operative simulation of periacetabular osteotomy via a three-dimensional model constructed from salt

Directory of Open Access Journals (Sweden)

Fukushima Kensuke

2017-01-01

Full Text Available Introduction: Periacetabular osteotomy (PAO is an effective joint-preserving procedure for young adults with developmental dysplasia of the hip. Although PAO provides excellent radiographic and clinical results, it is a technically demanding procedure with a distinct learning curve that requires careful 3D planning and, above all, has a number of potential complications. We therefore developed a pre-operative simulation method for PAO via creation of a new full-scale model. Methods: The model was prepared from the patient’s Digital Imaging and Communications in Medicine (DICOM formatted data from computed tomography (CT, for construction and assembly using 3D printing technology. A major feature of our model is that it is constructed from salt. In contrast to conventional models, our model provides a more accurate representation, at a lower manufacturing cost, and requires a shorter production time. Furthermore, our model realized simulated operation normally with using a chisel and drill without easy breakage or fissure. We were able to easily simulate the line of osteotomy and confirm acetabular version and coverage after moving to the osteotomized fragment. Additionally, this model allowed a dynamic assessment that avoided anterior impingement following the osteotomy. Results: Our models clearly reflected the anatomical shape of the patient’s hip. Our models allowed for surgical simulation, making realistic use of the chisel and drill. Our method of pre-operative simulation for PAO allowed for the assessment of accurate osteotomy line, determination of the position of the osteotomized fragment, and prevented anterior impingement after the operation. Conclusion: Our method of pre-operative simulation might improve the safety, accuracy, and results of PAO.

Safety culture and organisational issues specific to the transitional phase from operation to decommissioning of the Ignalina Nuclear Power Plant

International Nuclear Information System (INIS)

Medeliene, D.

2005-01-01

The PHARE project Support to State Nuclear Power Safety Inspectorate for safety culture and organisational issues specific to the pre-shutdown phase of Ignalina Nuclear Power Plant was aimed at providing assistance to VATESI in their task to oversee that the Ignalina Nuclear Power Plant's management and staff are able to provide an acceptable level of reactor safety taking into account possible safety culture related problems that may occur due to the decision of an early closure of both units. Safety culture is used as a concept to characterise the attitudes, behaviour and perceptions of people that are important in ensuring the safety of nuclear power facility. Since the Chernobyl accident, the International Atomic Energy Agency (IAEA) has been active in creating guidance for ensuring that an adequate safety culture can be created and maintained. The transition from operation to decommissioning introduces uncertainty for both the organisation and individuals. This creates new challenges that need to be dealt with. Although safety culture and organisational issues have to be addressed during the entire life cycle of a nuclear power plant, owing to these special challenges, it should be especially highlighted during the transitional period from operation to decommissioning. Nuclear safety experts from Sweden, Finland, Italy, the UK and Germany, as well as Lithuanian specialists, participated in the project, and it proved to be a most effective way to share experience. The aim of this brochure is to provide information about: the importance of safety culture issues during the transitional phase from operation to decommissioning of Ignalina Nuclear Power Plant; the purpose, activities and results of this PHARE project; recommendations that are provided by western experts concerning the management of safety culture issues specific to the pre-decommissioning phase of Ignalina Nuclear Power Plant. (author)

Safety of Nuclear Power Plants: Commissioning and Operation. Specific Safety Requirements (Arabic Edition)

International Nuclear Information System (INIS)

2017-01-01

This publication is a revision of IAEA Safety Standards Series No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe commissioning, operation, and transition from operation to decommissioning of nuclear power plants. Over recent years there have been developments in areas such as long term operation of nuclear power plants, plant ageing, periodic safety review, probabilistic safety analysis review and risk informed decision making processes. It became necessary to revise the IAEA’s Safety Requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles. A review of Safety Requirements publications, initiated in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan, revealed no significant areas of weakness but resulted in a small set of amendments to strengthen the requirements and facilitate their implementation. These are contained in the present publication.

Research on station management in subway operation safety

Science.gov (United States)

Li, Yiman

2017-10-01

The management of subway station is an important part of the safe operation of urban subway. In order to ensure the safety of subway operation, it is necessary to study the relevant factors that affect station management. In the protection of subway safety operations on the basis of improving the quality of service, to promote the sustained and healthy development of subway stations. This paper discusses the influencing factors of subway operation accident and station management, and analyzes the specific contents of station management security for subway operation, and develops effective suppression measures. It is desirable to improve the operational quality and safety factor for subway operations.

Operational Safety Performance Indicators and Balanced Scorecard in HANARO

International Nuclear Information System (INIS)

Wu, Jong-Sup; Jung, Hoan-Sung; Ahn, Guk-Hoon; Lee, Kye-Hong; Lim, In-Cheol; Kim, Hark-Rho

2007-01-01

Research reactors need an extensive basis for ensuring their safety. The importance of a safety management in nuclear facilities and activities has been emphasized. The safety activities in HANARO have been continuously conducted to enhance its safe operation. Last year, HANARO prepared two indicator sets to measure and assess the safety status of the reactor's operation and utilization. One is Safety Performance Indicators (SPI) and the other is Balanced Scorecard (BSC). Through reviewing these indicators, we can obtain the following information; - Plant safety status - Safety parameter trends - Safety information, for example, reactor operation status and radiation safety HANARO will continuously pursue the trends of SPI and BSC

Operational characteristics of nuclear power plants - modelling of operational safety

International Nuclear Information System (INIS)

Studovic, M.

1984-01-01

By operational experience of nuclear power plants and realize dlevel of availability of plant, systems and componenst reliabiliuty, operational safety and public protection, as a source on nature of distrurbances in power plant systems and lessons drawn by the TMI-2, in th epaper are discussed: examination of design safety for ultimate ensuring of safe operational conditions of the nuclear power plant; significance of the adequate action for keeping proess parameters in prescribed limits and reactor cooling rquirements; developed systems for measurements detection and monitoring all critical parameters in the nuclear steam supply system; contents of theoretical investigation and mathematical modeling of the physical phenomena and process in nuclear power plant system and components as software, supporting for ensuring of operational safety and new access in staff education process; program and progress of the investigation of some physical phenomena and mathematical modeling of nuclear plant transients, prepared at faculty of mechanical Engineering in Belgrade. (author)

Safety of Nuclear Power Plants: Commissioning and Operation (Spanish Edition)

International Nuclear Information System (INIS)

2012-01-01

This publication is a revision of Safety Requirements No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe operation of nuclear power plants. Over recent years there have been developments in areas such as long term operation, plant ageing, periodic safety review, probabilistic safety analysis and risk informed decision making processes. It became necessary to revise the IAEA's safety requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the Fundamental Safety Principles. Contents: 1. Introduction; 2. Safety objectives and principles; 3. The management and organizational structure of the operating organization; 4. Management of operational safety; 5. Operational safety programmes; 6. Plant commissioning; 7. Plant operations; 8. Maintenance, testing, surveillance and inspection; 9. Preparation for decommissioning.

Safety of Nuclear Power Plants: Commissioning and Operation (French Edition)

International Nuclear Information System (INIS)

2012-01-01

This publication is a revision of Safety Requirements No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe operation of nuclear power plants. Over recent years there have been developments in areas such as long term operation, plant ageing, periodic safety review, probabilistic safety analysis and risk informed decision making processes. It became necessary to revise the IAEA's safety requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the Fundamental Safety Principles. Contents: 1. Introduction; 2. Safety objectives and principles; 3. The management and organizational structure of the operating organization; 4. Management of operational safety; 5. Operational safety programmes; 6. Plant commissioning; 7. Plant operations; 8. Maintenance, testing, surveillance and inspection; 9. Preparation for decommissioning.

Safety of Nuclear Power Plants: Commissioning and Operation. Arabic Edition

International Nuclear Information System (INIS)

2011-01-01

This publication is a revision of Safety Requirements No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe operation of nuclear power plants. Over recent years there have been developments in areas such as long term operation, plant ageing, periodic safety review, probabilistic safety analysis and risk informed decision making processes. It became necessary to revise the IAEA's safety requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the Fundamental Safety Principles. Contents: 1. Introduction; 2. Safety objectives and principles; 3. The management and organizational structure of the operating organization; 4. Management of operational safety; 5. Operational safety programmes; 6. Plant commissioning; 7. Plant operations; 8. Maintenance, testing, surveillance and inspection; 9. Preparation for decommissioning.

Environmental protection appraisals: a suggested guide for US Department of Energy field organization. Revision 1

International Nuclear Information System (INIS)

Barisas, S.; Polich, J.; Surles, T.; Habegger, L.; Anderson, D.; Opelka, J.; Frangos, T.

1985-03-01

This manual has been prepared to assist DOE field organizations in conducting environmental protection appraisals of activities at DOE operating-level facilities. Its primary use will be by DOE operations offices in their appraisal of facilities operating under the authority of the Atomic Energy Act. However, the manual can also be used by other DOE field organizations. This manual is organized in modules that parallel those in the internal environmental audit checklist. It is assumed that the contractor is using the guide previously described (Internal Environmental Protection Audits) and that operations office staff members will have the opportunity to review or be cognizant of the contractor's completed internal audit, and other material generated within the facility, in preparation for the appraisal. This manual was developed to facilitate the appraisal process by providing operations office staff with a choice of modules that can be used independently or as a unit. The manual gives guidelines for reviewing information submitted to the operations office before the site visit and for conducting an on-site operating-level appraisal

LMFBR operational safety: the EBR-II experience

International Nuclear Information System (INIS)

Sackett, J.I.; Allen, N.L.; Dean, E.M.; Fryer, R.M.; Larson, H.A.; Lehto, W.K.

1978-01-01

The mission of the Experimental Breeder Reactor II (EBR-II) has evolved from that of a small LMFBR demonstration plant to a major irradiation-test facility. Because of that evolution, many operational-safety issues have been encountered. The paper describes the EBR-II operational-safety experience in four areas: protection-system design, safety-document preparation, tests of off-normal reactor conditions, and tests of elements with breached cladding

Safety evaluation by living probabilistic safety assessment. Procedures and applications for planning of operational activities and analysis of operating experience

International Nuclear Information System (INIS)

Johanson, Gunnar; Holmberg, J.

1994-01-01

Living Probabilistic Safety Assessment (PSA) is a daily safety management system and it is based on a plant-specific PSA and supporting information systems. In the living use of PSA, plant status knowledge is used to represent actual plant safety status in monitoring or follow-up perspective. The PSA model must be able to express the risk at a given time and plant configuration. The process, to update the PSA model to represent the current or planned configuration and to use the model to evaluate and direct the changes in the configuration, is called living PSA programme. The main purposes to develop and increase the usefulness of living PSA are: Long term safety planning: To continue the risk assessment process started with the basic PSA by extending and improving the basic models and data to provide a general risk evaluation tool for analyzing the safety effects of changes in plant design and procedures. Risk planning of operational activities: To support the operational management by providing means for searching optimal operational maintenance and testing strategies from the safety point of view. The results provide support for risk decision making in the short term or in a planning mode. The operational limits and conditions given by technical specifications can be analyzed by evaluating the risk effects of alternative requirements in order to balance the requirements with respect to operational flexibility and plant economy. Risk analysis of operating experience: To provide a general risk evaluation tool for analyzing the safety effects of incidents and plant status changes. The analyses are used to: identify possible high risk situations, rank the occurred events from safety point of view, and get feedback from operational events for the identification of risk contributors. This report describes the methods, models and applications required to continue the process towards a living use of PSA. 19 tabs, 20 figs

A BWR Safety and Operability Improvements

International Nuclear Information System (INIS)

Sawyer, Craig D.

1993-01-01

The A BWR is the culmination of 30 years of design, development and operating experience of BWRs around the world. It represents across the board improvements is safety, operation and maintenance practices (O and M), economics, radiation exposure and rad waste generation. More than ten years and $20m5 went into the design and development of its new features, and it is now under construction in Japan. This paper concentrates on the safety and operability improvements. In the safety area, more than a decade improvement in core damage frequency (CDFR) has been assessed by formal PIRA techniques, with CDFR less than 10 -6 /year. Severe accident mitigation has also been formally addressed in the design. Plant operations were simplified by incorporation of better materials, optimum use of redundancy in mechanical and electrical equipment so that on-line maintenance can be performed, by better arrangements which account for required maintenance practices, and by an advanced control room

Nuclear safety: an operational constraint or necessity

International Nuclear Information System (INIS)

Gauvenet, A.

1983-01-01

Different aspects of the nuclear safety in the operation of power stations are analysed. There is always a danger that safety is considered as a constraint at operator level, but it is essential that human factors and working conditions be taken into consideration [fr

Pre-operative clinical assessment for anaesthesia and the effect of ...

African Journals Online (AJOL)

Background. HIV infection is common in South Africa, often remaining clinically latent and liable to be missed during clinical pre-operative assessment, despite the patient having a severe degree of immune compromise. Objectives. The primary objective was to determine the pre-operative physical status of patients ...

Upgraded safety analysis document including operations policies, operational safety limits and policy changes. Revision 2

International Nuclear Information System (INIS)

Batchelor, K.

1996-03-01

The National Synchrotron Light Source Safety Analysis Reports (1), (2), (3), BNL reports number-sign 51584, number-sign 52205 and number-sign 52205 (addendum) describe the basic Environmental Safety and Health issues associated with the department's operations. They include the operating envelope for the Storage Rings and also the rest of the facility. These documents contain the operational limits as perceived prior or during construction of the facility, much of which still are appropriate for current operations. However, as the machine has matured, the experimental program has grown in size, requiring more supervision in that area. Also, machine studies have either verified or modified knowledge of beam loss modes and/or radiation loss patterns around the facility. This document is written to allow for these changes in procedure or standards resulting from their current mode of operation and shall be used in conjunction with the above reports. These changes have been reviewed by NSLS and BNL ES and H committee and approved by BNL management

Predictive potential of pre-operative functional neuroimaging in patients treated with subthalamic stimulation

International Nuclear Information System (INIS)

Sestini, Stelvio; Castagnoli, Antonio; Pupi, Alberto; Sciagra, Roberto; Ammannati, Franco; Ramat, Silvia; Sorbi, Sandro; Mansi, Luigi

2010-01-01

The aim of this study was to investigate the predictive potential of pre-operative regional cerebral blood flow (rCBF) in the pre-supplementary motor area (pre-SMA) and clinical factors in Parkinson's disease (PD) patients treated with subthalamic nucleus (STN) stimulation. Ten patients underwent rCBF SPECT and motor Unified Parkinson's Disease Rating Scale (UPDRS) pre- and post-operatively during stimulation at 5 and 42 months. Statistical parametric mapping (SPM) was used to extract rCBF values in the pre-SMA because it is related with motor improvement. Post-operative outcomes included motor response to stimulation and percent improvement in UPDRS. Pre-operative predictors were explored by correlation test, linear regression and multivariate analyses. Higher pre-operative rCBF in the pre-SMA and younger age were associated with favourable outcomes at 5 and 42 months. Pre-operative rCBF results were significantly associated with baseline clinical factors. This study shows that PD patients with younger age have higher rCBF values in the pre-SMA and better outcome, thus giving the rationale to the hypothesis that STN stimulation could be considered early in the course of disease. (orig.)

Predictive potential of pre-operative functional neuroimaging in patients treated with subthalamic stimulation

Energy Technology Data Exchange (ETDEWEB)

Sestini, Stelvio; Castagnoli, Antonio [Ospedale Misericordia e Dolce, Department of Diagnostic Imaging, Nuclear Medicine Unit, Prato (Italy); Pupi, Alberto; Sciagra, Roberto [University of Florence, Department of Clinical Physiopathology, Nuclear Medicine Unit, Florence (Italy); Ammannati, Franco; Ramat, Silvia; Sorbi, Sandro [University of Florence, Department of Neurological and Psychiatric Sciences, Florence (Italy); Mansi, Luigi [University II Naples, Department of Diagnostic Imaging, Nuclear Medicine Unit, Naples (Italy)

2010-01-15

The aim of this study was to investigate the predictive potential of pre-operative regional cerebral blood flow (rCBF) in the pre-supplementary motor area (pre-SMA) and clinical factors in Parkinson's disease (PD) patients treated with subthalamic nucleus (STN) stimulation. Ten patients underwent rCBF SPECT and motor Unified Parkinson's Disease Rating Scale (UPDRS) pre- and post-operatively during stimulation at 5 and 42 months. Statistical parametric mapping (SPM) was used to extract rCBF values in the pre-SMA because it is related with motor improvement. Post-operative outcomes included motor response to stimulation and percent improvement in UPDRS. Pre-operative predictors were explored by correlation test, linear regression and multivariate analyses. Higher pre-operative rCBF in the pre-SMA and younger age were associated with favourable outcomes at 5 and 42 months. Pre-operative rCBF results were significantly associated with baseline clinical factors. This study shows that PD patients with younger age have higher rCBF values in the pre-SMA and better outcome, thus giving the rationale to the hypothesis that STN stimulation could be considered early in the course of disease. (orig.)

Focusing on appraisals: how and why anger and fear influence driving risk perception.

Science.gov (United States)

Lu, Jingyi; Xie, Xiaofei; Zhang, Ruogu

2013-06-01

The present research explores how and why anger and fear influence driving risk perception. Based on appraisal tendency framework, researchers hypothesized that anger and fear would influence driving risk perception in opposite directions due to their differences in appraisals. Study 1 showed that anger reduced risk perception, whereas fear increased it. In Studies 2, 3, and 4, the researchers adopted the paradigm of reappraisal to investigate the causes of the opposite effects found in Study 1. Consistent with our hypothesis, appraisals accounted for these effects: After reappraisals along the dimensions of certainty (Study 2), control (Study 3), and responsibility (Study 4), the different effects between anger and fear on driving risk perception diminished or disappeared. In addition, fearful or angry experience mediated the effects of reappraisals on driving risk perception. The findings highlight the necessity to differentiate anger and fear in road safety management. Additionally, the current research also provides feasible methods (e.g., certainty, control, or responsibility reappraisal) to intervene in driving risk perception, which is important for driving safety. Copyright © 2013 National Safety Council and Elsevier Ltd. All rights reserved.

Protocol for Appraisal of Petroleum Producing Properties on Native American Tribal Lands

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-04-27

Petroleum is currently produced on Native American Tribal Lands and has been produced on some of these lands for approximately 100 years. As these properties are abandoned at a production level that is considered the economic limit by the operator, Native American Tribes are considering this an opportunity to assume operator status to keep the properties producing. In addition to operating properties as they are abandoned, Native American Tribes also are assuming liabilities of the former operator(s) and ownership of equipment left upon abandonment. Often, operators are assumed by Native American Tribes without consideration of the liabilities left by the former operators. The purpose of this report is to provide protocols for the appraisal of petroleum producing properties and analysis of the petroleum resource to be produced after assuming operations. The appraisal protocols provide a spreadsheet for analysis of the producing property and a checklist of items to bring along before entering the property for onsite appraisal of the property. The report will provide examples of some environmental flags that may indicate potential liabilities remaining on the property left unaddressed by previous operators. It provides a starting point for appraisal and analysis of a property with a basis to make the decision to assume operations or to pursue remediation and/or closure of the liabilities of previous operators.

A Fire Safety Certification System for Board and Care Operators and Staff. SBIR Phase I: Final Report.

Science.gov (United States)

Walker, Bonnie L.

This report describes the development and pilot testing of a fire safety certification system for board and care operators and staff who serve clients with developmental disabilities. During Phase 1, training materials were developed, including a trainer's manual, a participant's coursebook a videotape, an audiotape, and a pre-/post test which was…

Operational safety evaluation for minor reactor accidents

International Nuclear Information System (INIS)

Wang, O.S.

1981-01-01

The purpose of this paper is to address a concern of applying conservatism in analysing minor reactor incidents. A so-called ''conservative'' safety analysis may exaggerate the system responses and result in a reactor scram tripped by the reactor protective system (RPS). In reality, a minor incident may lead the reactor to a new thermal hydraulic steady-state without scram, and the mitigation or termination of the incident may entirely depend on operator actions. An example on a small steamline break evaluation for a pressurized water reactor recently investigated by the staff at the Washington Public Power Supply System is presented to illustrate this point. A safety evaluation using mainly the safety-related systems to be consistent with the conservative assumptions used in the Safety Analysis Report was conducted. For comparison, a realistic analysis was also performed using both the safety- and control-related systems. The analyses were performed using the RETRAN plant simulation computer code. The ''conservative'' safety analysis predicts that the incident can be turned over by the RPS scram trips without operator intervention. However, the realistic analysis concludes that the reactor will reach a new steady-state at a different plant thermal hydraulic condition. As a result, the termination of the incident at this stage depends entirely on proper operator action. On the basis of this investigation it is concluded that, for minor incidents, ''conservative'' assumptions are not necessary, sometimes not justifiable. A realistic investigation from the operational safety point of view is more appropriate. It is essential to highlight the key transient indications for specific incident recognition in the operator training program

Investment appraisal using quantitative risk analysis.

Science.gov (United States)

Johansson, Henrik

2002-07-01

Investment appraisal concerned with investments in fire safety systems is discussed. Particular attention is directed at evaluating, in terms of the Bayesian decision theory, the risk reduction that investment in a fire safety system involves. It is shown how the monetary value of the change from a building design without any specific fire protection system to one including such a system can be estimated by use of quantitative risk analysis, the results of which are expressed in terms of a Risk-adjusted net present value. This represents the intrinsic monetary value of investing in the fire safety system. The method suggested is exemplified by a case study performed in an Avesta Sheffield factory.

Mochovce NPP safety measures evaluation from point of view of operational safety enhancement

International Nuclear Information System (INIS)

Cillik, I.; Vrtik, L.

2000-01-01

Mochovce NPP consists of four reactor units of WWER 440/V213 type and it is located in the south-middle part of Slovakia. At present first unit operated and the second one under the construction finishing. As these units represent second generation of WWER reactor design, the additional safety measures (SM) were implemented to enhance operational and nuclear safety according to the recommendations of performed international audits and operational experience based on exploitation of other similar units (as Dukovany and J. Bohunice NPPs). These requirements result into a number of SMs grouped according to their purpose to reach recent international requirements on nuclear and operational safety. The paper presents the bases used for safety measures establishing including their grouping into the comprehensive tasks covering different areas of safety goals as well as structural organization of a project management of including participating companies and work performance. More, results are given regarding contribution of selected SMs to the total core damage frequency decreasing. (author)

Safety parameter display system: an operator support system for enhancement of safety in Indian PHWRs

International Nuclear Information System (INIS)

Subramaniam, K.; Biswas, T.

1994-01-01

Ensuring operational safety in nuclear power plants is important as operator errors are observed to contribute significantly to the occurrence of accidents. Computerized operator support systems, which process and structure information, can help operators during both normal and transient conditions, and thereby enhance safety and aid effective response to emergency conditions. An important operator aid being developed and described in this paper, is the safety parameter display system (SPDS). The SPDS is an event-independent, symptom-based operator aid for safety monitoring. Knowledge-based systems can provide operators with an improved quality of information. An information processing model of a knowledge based operator support system (KBOSS) developed for emergency conditions using an expert system shell is also presented. The paper concludes with a discussion of the design issues involved in the use of a knowledge based systems for real time safety monitoring and fault diagnosis. (author). 8 refs., 4 figs., 1 tab

Dam pre-release as an important operation strategy in reducing flood impact in Malaysia

Science.gov (United States)

Hidayah Ishak, Nurul; Mustafa Hashim, Ahmad

2018-03-01

The 2014 flood was reported to be one of the worst natural disaster has ever affected several states in the northern part of Peninsular Malaysia. Overwhelming rainfall was noted as one of the main factors causing such impact, which was claimed to be unprecedented to some extent. The state of Perak, which is blessed with four cascading dams had also experienced flood damage at a scale that was considered the worst in history. The rainfall received had caused the dam to reach danger level that necessitated additional discharge to be released. Safety of the dams was of great importance and such unavoidable additional discharge was allowed to avoid catastrophic failure of the dam structures. This paper discusses the dam pre-release as a significant dam management strategy in reducing flood impact. An important balance between required dam storage to be maintained and the risk element that can be afforded is the crucial factor in such enhanced operation strategy. While further possibility in developing a carefully engineered dam pre-release strategy can be explored for dam operation in Malaysia, this has already been introduced in some developed countries. Australia and South Africa are examples where pre-release has been practiced and proven to reduce flood risk. The concept involves controlling the dam lake level throughout the year, in reference to the rainfall data and the hydrological properties for the catchment area of the dams. Plentiful data analysis need to be done in contemplation of producing the optimal pre-release model. The amount of heavy rainfalls received is beyond human control but the distribution of the discharge from the dams can be further managed with the appropriate pre-release strategy.

Aviation safety and operation problems research and technology

Science.gov (United States)

Enders, J. H.; Strickle, J. W.

1977-01-01

Aircraft operating problems are described for aviation safety. It is shown that as aircraft technology improves, the knowledge and understanding of operating problems must also improve for economics, reliability and safety.

Pre-operative optimisation of lung function

Directory of Open Access Journals (Sweden)

Naheed Azhar

2015-01-01

Full Text Available The anaesthetic management of patients with pre-existing pulmonary disease is a challenging task. It is associated with increased morbidity in the form of post-operative pulmonary complications. Pre-operative optimisation of lung function helps in reducing these complications. Patients are advised to stop smoking for a period of 4–6 weeks. This reduces airway reactivity, improves mucociliary function and decreases carboxy-haemoglobin. The widely used incentive spirometry may be useful only when combined with other respiratory muscle exercises. Volume-based inspiratory devices have the best results. Pharmacotherapy of asthma and chronic obstructive pulmonary disease must be optimised before considering the patient for elective surgery. Beta 2 agonists, inhaled corticosteroids and systemic corticosteroids, are the main drugs used for this and several drugs play an adjunctive role in medical therapy. A graded approach has been suggested to manage these patients for elective surgery with an aim to achieve optimal pulmonary function.

No effect of ambient odor on the affective appraisal of a desktop virtual environment with signs of disorder.

Directory of Open Access Journals (Sweden)

Alexander Toet

Full Text Available Desktop virtual environments (VEs are increasingly deployed to study the effects of environmental qualities and interventions on human behavior and safety related concerns in built environments. For these applications it is essential that users appraise the affective qualities of the VE similar to those of its real world counterpart. Previous studies have shown that factors like simulated lighting, sound and dynamic elements all contribute to the affective appraisal of a desktop VE. Since ambient odor is known to affect the affective appraisal of real environments, and has been shown to increase the sense of presence in immersive VEs, it may also be an effective tool to tune the affective appraisal of desktop VEs. This study investigated if exposure to ambient odor can modulate the affective appraisal of a desktop VE with signs of public disorder.Participants explored a desktop VE representing a suburban neighborhood with signs of public disorder (neglect, vandalism and crime, while being exposed to either room air or subliminal levels of unpleasant (tar or pleasant (cut grass ambient odor. Whenever they encountered signs of disorder they reported their safety related concerns and associated affective feelings.Signs of crime in the desktop VE were associated with negative affective feelings and concerns for personal safety and personal property. However, there was no significant difference between reported safety related concerns and affective connotations in the control (no-odor and in each of the two ambient odor conditions.Ambient odor did not affect safety related concerns and affective connotations associated with signs of disorder in the desktop VE. Thus, semantic congruency between ambient odor and a desktop VE may not be sufficient to influence its affective appraisal, and a more realistic simulation in which simulated objects appear to emit scents may be required to achieve this goal.

Operational radiation protection: A guide to optimization

International Nuclear Information System (INIS)

1990-01-01

The purpose of this publication is to provide practical guidance on the application of the dose limitation system contained in the Basic Safety Standards for Radiation Protection to operational situations both in large nuclear installations and in much smaller facilities. It is anticipated that this Guide will be useful to both the management and radiation protection staff of operations in which there is a potential for occupational radiation exposures and to the competent authorities with responsibilities for providing a programme of regulatory control. Contents: Dose limitation system; Optimization and its practical application to operational radiation protection; Major elements of an effective operational radiation protection programme; Review of selected parts of the basic safety standards with special reference to operational radiation protection; Optimization of radiation protection; Techniques for the systematic appraisal of operational radiation protection programmes. Refs and figs

Pre-operative irradiation with rectal carcinoma - clinical practices and results

International Nuclear Information System (INIS)

Rendl, H.

1986-01-01

The goal of this work is to portray the effect of a high-dosed short-timed pre-irradiation on intra- and post-operative therapy of rectal carcinoma and the appearance of recidivistic tumors, respectively distant metastasis. This intermediate balance should help make the decision easier as to whether to continue to use this combined treatment form. The subjects consisted of 65 rectal carcinoma patients - pre-irradiated and operated - and 95 only operated patients. The irradiation was completed using a 8 MeV linear accelerator with ultra hard x-radiation. Dosing - (more than 80%) as short-timed irradiation with 16 Gy (4 x 4 Gy in 2 days) - 25 Gy (10 x 2,5 Gy in 12 days); average field size 150 mm x 150 mm. There were no significant differences with regard to intra- and post-operative complications, late complications or distant metastasis, but there was with tumor recidivision reduced with pre-irradiated. Regarding the survival rate, there was a slight tendency in favor of the pre-irradiated. (orig./MG) [de

Safety indicators as a tool for operational safety evaluation of nuclear power plants

International Nuclear Information System (INIS)

Araujo, Jefferson Borges; Melo, Paulo Fernando Ferreira Frutuoso e; Schirru, Roberto

2009-01-01

Performance indicators have found a wide use in the conventional and nuclear industries. For the conventional industry, the goal is to optimize production, reducing loss of time with accidents, human error and equipment downtimes. In the nuclear industry, nuclear safety is an additional goal. This paper presents a general methodology to the establishment, selection and use of safety indicators for a two loop PWR plant, as Angra 1. The use of performance indicators is not new. The NRC has its own methodology and the IAEA presents methodology suggestions, but there is no detailed documentation about indicators selection, criteria and bases used. Additionally, only the NRC methodology performs a limited integrated evaluation. The study performed identifies areas considered critical for the plant operational safety. For each of these areas, strategic sub-areas are defined. For each strategic sub-area, specific safety indicators are defined. These proposed Safety Indicators are based on the contribution to risk considering a quantitative risk analysis. For each safety indicator, a goal, a bounded interval and proper bases are developed, to allow for a clear and comprehensive individual behavior evaluation. On the establishment of the intervals and boundaries, a probabilistic safety study, operational experience, international and national standards and technical specifications were used. Additionally, an integrated evaluation of the indicators, using expert systems, was done to obtain an overview of the plant general safety. This evaluation uses well-defined and clear rules and weights for each indicator to be considered. These rules were implemented by means of a computational language, on a friendly interface, so that it is possible to obtain a quick response about operational safety. This methodology can be used to identify situations where the plant safety is challenged, by giving a general overview of the plant operational condition. Additionally, this study can

The role of pre-operative and post-operative glucose control in surgical-site infections and mortality.

Directory of Open Access Journals (Sweden)

Christie Y Jeon

Full Text Available The impact of glucose control on surgical-site infection (SSI and death remains unclear. We examined how pre- and post-operative glucose levels and their variability are associated with the risk of SSI or in-hospital death.This retrospective cohort study employed data on 13,800 hospitalized patients who underwent a surgical procedure at a large referral hospital in New York between 2006 and 2008. Over 20 different sources of electronic data were used to analyze how thirty-day risk of SSI and in-hospital death varies by glucose levels and variability. Maximum pre- and post-operative glucose levels were determined for 72 hours before and after the operation and glucose variability was defined as the coefficient of variation of the glucose measurements. We employed logistic regression to model the risk of SSI or death against glucose variables and the following potential confounders: age, sex, body mass index, duration of operation, diabetes status, procedure classification, physical status, emergency status, and blood transfusion.While association of pre- and post-operative hyperglycemia with SSI were apparent in the crude analysis, multivariate results showed that SSI risk did not vary significantly with glucose levels. On the other hand, in-hospital deaths were associated with pre-operative hypoglycemia (OR = 5.09, 95% CI (1.80, 14.4 and glucose variability (OR = 1.14, 95% CI (1.03, 1.27 for 10% increase in coefficient of variation.In-hospital deaths occurred more often among those with pre-operative hypoglycemia and higher glucose variability. These findings warrant further investigation to determine whether stabilization of glucose and prevention of hypoglycemia could reduce post-operative deaths.

The role of pre-operative and post-operative glucose control in surgical-site infections and mortality.

Science.gov (United States)

Jeon, Christie Y; Furuya, E Yoko; Berman, Mitchell F; Larson, Elaine L

2012-01-01

The impact of glucose control on surgical-site infection (SSI) and death remains unclear. We examined how pre- and post-operative glucose levels and their variability are associated with the risk of SSI or in-hospital death. This retrospective cohort study employed data on 13,800 hospitalized patients who underwent a surgical procedure at a large referral hospital in New York between 2006 and 2008. Over 20 different sources of electronic data were used to analyze how thirty-day risk of SSI and in-hospital death varies by glucose levels and variability. Maximum pre- and post-operative glucose levels were determined for 72 hours before and after the operation and glucose variability was defined as the coefficient of variation of the glucose measurements. We employed logistic regression to model the risk of SSI or death against glucose variables and the following potential confounders: age, sex, body mass index, duration of operation, diabetes status, procedure classification, physical status, emergency status, and blood transfusion. While association of pre- and post-operative hyperglycemia with SSI were apparent in the crude analysis, multivariate results showed that SSI risk did not vary significantly with glucose levels. On the other hand, in-hospital deaths were associated with pre-operative hypoglycemia (OR = 5.09, 95% CI (1.80, 14.4)) and glucose variability (OR = 1.14, 95% CI (1.03, 1.27) for 10% increase in coefficient of variation). In-hospital deaths occurred more often among those with pre-operative hypoglycemia and higher glucose variability. These findings warrant further investigation to determine whether stabilization of glucose and prevention of hypoglycemia could reduce post-operative deaths.

Safety of Nuclear Power Plants: Commissioning and Operation. Specific Safety Requirements (French Edition)

International Nuclear Information System (INIS)

2016-01-01

This publication describes the requirements to be met to ensure the safe operation of nuclear power plants. It takes into account developments in areas such as long term operation of nuclear power plants, plant ageing, periodic safety review, probabilistic safety analysis and risk informed decision making processes. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles. A review of Safety Requirements publications was commenced in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan. The review revealed no significant areas of weakness and resulted in just a small set of amendments to strengthen the requirements and facilitate their implementation, which are contained in the present publication.

Operating plant safety analysis needs

International Nuclear Information System (INIS)

Young, M.Y.; Love, D.S.

1992-01-01

The primary objective for nuclear power station owners is to operate and manage their plants safely. However, there is also a need to provide economical electric power, which requires that the unit be operated as efficiently as possible, consistent with the safety requirements. The objectives cited above can be achieved through the identification and use of available margins inherent in the plant design. As a result of conservative licensing and analytical approaches taken in the past, many of these margins may be found in the safety analysis limits within which plants currently operate. Improvements in the accuracy of the safety analysis, and a more realistic treatment of plant initial and boundary conditions, can make this margin available for a variety of uses which enhance plant performance, help to reduce O and M costs, and may help to extend licensed operation. Opportunities for improvement exist in several areas in the accident analysis normally performed for Chapter 15 of the FSAR. For example, recent modifications to the ECCS rule, 10CFR50.46 and Appendix K, allow use of margins previously unavailable in the analysis of the Loss of Coolant Accident (LOCA). To take advantage of this regulatory change, new methods are being developed to analyze both the large and small break loss of coolant accident (LOCA). As this margin is used, enhancements in the analysis of other transients will become necessary. The paper discusses accident analysis methods, future development needs, and analysis margin utilization in specific accident scenarios

Plant designer's view of the operator's role in nuclear plant safety

International Nuclear Information System (INIS)

Corcoran, W.R.; Church, J.F.; Cross, M.T.; Porter, N.J.

1981-01-01

The nuclear plant operator's role supports the design assumptions and equipment with four functional tasks. He must set up th plant for predictable response to disturbances, operate the plant so as to minimize the likelihood and severity of event initiators, assist in accomplishing the safety functions, and feed back operating experiences to reinforce or redefine the safety analyses' assumptions. The latter role enhances the operator effectiveness in the former three roles. The Safety Level Concept offers a different perspective that enables the operator to view his roles in nuclear plant safety. This paper outlines the operator's role in nuclear safety and classifies his tasks using the Safety Level Concept

Operational safety performance of Slovak NPPs in 2005

International Nuclear Information System (INIS)

Tomek, J.

2006-01-01

In this presentation author presents operational safety performance of Slovak NPPs in 2005. Operation of Slovak NPPs in 2005 was safe and reliable, with: - high level of performance low risk; - minimal impact on the personnel, environment and public; - positive attitude to safety.

242-A evaporator safety analysis report

International Nuclear Information System (INIS)

CAMPBELL, T.A.

1999-01-01

This report provides a revised safety analysis for the upgraded 242-A Evaporator (the Evaporator). This safety analysis report (SAR) supports the operation of the Evaporator following life extension upgrades and other facility and operations upgrades (e.g., Project B-534) that were undertaken to enhance the capabilities of the Evaporator. The Evaporator has been classified as a moderate-hazard facility (Johnson 1990). The information contained in this SAR is based on information provided by 242-A Evaporator Operations, Westinghouse Hanford Company, site maintenance and operations contractor from June 1987 to October 1996, and the existing operating contractor, Waste Management Hanford (WMH) policies. Where appropriate, a discussion address the US Department of Energy (DOE) Orders applicable to a topic is provided. Operation of the facility will be compared to the operating contractor procedures using appropriate audits and appraisals. The following subsections provide introductory and background information, including a general description of the Evaporator facility and process, a description of the scope of this SAR revision,a nd a description of the basic changes made to the original SAR

242-A evaporator safety analysis report

Energy Technology Data Exchange (ETDEWEB)

CAMPBELL, T.A.

1999-05-17

This report provides a revised safety analysis for the upgraded 242-A Evaporator (the Evaporator). This safety analysis report (SAR) supports the operation of the Evaporator following life extension upgrades and other facility and operations upgrades (e.g., Project B-534) that were undertaken to enhance the capabilities of the Evaporator. The Evaporator has been classified as a moderate-hazard facility (Johnson 1990). The information contained in this SAR is based on information provided by 242-A Evaporator Operations, Westinghouse Hanford Company, site maintenance and operations contractor from June 1987 to October 1996, and the existing operating contractor, Waste Management Hanford (WMH) policies. Where appropriate, a discussion address the US Department of Energy (DOE) Orders applicable to a topic is provided. Operation of the facility will be compared to the operating contractor procedures using appropriate audits and appraisals. The following subsections provide introductory and background information, including a general description of the Evaporator facility and process, a description of the scope of this SAR revision,a nd a description of the basic changes made to the original SAR.

The Efficacy of Performance Appraisal to Increase Employees’ Job Satisfaction

Directory of Open Access Journals (Sweden)

Iranita Hervi Mahardayani

2016-08-01

Full Text Available This research aims to find out the effectiveness of implementation performance appraisal toward job satisfaction of employees UMKM Bordir Dahlia in Kabupaten Kudus. Sampling was done by using population studies to 16 employees of UMKM embroidery Dahlia Kudus. The type of this research is quantitative with pra experiment approached by One group pre and posttest design method. Data analysis on this research using non parametric with different test techniques Wilcoxon t-tes. The analysis result of different test scale job satisfaction before and after handling obtained Z = - 1,268, with p = 0,205 (p>0,05, so that there is no differences on job satisfaction on employees of embroidery Dahlia before and after treatment by giving performance appraisal. It means treatment by giving performance appraisal unable to increase employees job satisfaction. Therefore, the hypothesis on this research is rejected.

Radiation safety study for conventional facility and siting pre project phase of International Linear Collider

International Nuclear Information System (INIS)

Sanami, Toshiya; Ban, Syuichi; Sasaki, Shin-ichi

2015-01-01

The International Linear Collider (ILC) is a proposed high-energy collider consisting of two linear accelerators, two dumping rings, electron and positron sources, and a single colliding hall with two detectors. The total length and CMS energy of the ILC will be 31 km and 500 GeV, respectively (and 50 km and 1 TeV after future upgrade). The design of the ILC has entered the pre-project phase, which includes site-dependent design. Radiation safety design for the ILC is on-going as a part of conventional facility and siting activities of the pre-project phase. The thickness of a central wall of normal concrete is designed to be 3.5 m under a pessimistic assumption of beam loss. The beam loss scenario is under discussion. Experience and knowledge relating to shielding design and radiation control operational work at other laboratories are required. (authors)

Acute gallbladder torsion - a continued pre-operative diagnostic dilemma

Directory of Open Access Journals (Sweden)

Desrochers Randal

2011-04-01

Full Text Available Abstract Acute gallbladder volvulus continues to remain a relatively uncommon process, manifesting itself usually during exploration for an acute surgical abdomen with a presumptive diagnosis of acute cholecystitis. The pathophysiology is that of mechanical organo-axial torsion along the gallbladder's longitudinal axis involving the cystic duct and cystic artery, and with a pre-requisite of local mesenteric redundancy. The demographic tendency is septua- and octo-genarians of the female sex, and its overall incidence is increasing, this being attributed to increasing life expectancy. We discuss two cases of elderly, fragile women presenting to the emergency department complaining of sudden onset right upper quadrant abdominal pain. Their subsequent evaluation suggested acute cholecystitis. Ultimately both were taken to the operating room where the correct diagnosis of gallbladder torsion was made. Pre-operative diagnosis continues to be a major challenge with only 4 cases reported in the literature diagnosed with pre-operative imaging; the remainder were found intra-operatively. Consequently, a delay in diagnosis can have devastating patient outcomes. Herein we propose a necessary high index of suspicion for gallbladder volvulus in the outlined patient demographic with symptoms and signs mimicking acute cholecystitis.

Safety-related operator actions: methodology for developing criteria

International Nuclear Information System (INIS)

Kozinsky, E.J.; Gray, L.H.; Beare, A.N.; Barks, D.B.; Gomer, F.E.

1984-03-01

This report presents a methodology for developing criteria for design evaluation of safety-related actions by nuclear power plant reactor operators, and identifies a supporting data base. It is the eleventh and final NUREG/CR Report on the Safety-Related Operator Actions Program, conducted by Oak Ridge National Laboratory for the US Nuclear Regulatory Commission. The operator performance data were developed from training simulator experiments involving operator responses to simulated scenarios of plant disturbances; from field data on events with similar scenarios; and from task analytic data. A conceptual model to integrate the data was developed and a computer simulation of the model was run, using the SAINT modeling language. Proposed is a quantitative predictive model of operator performance, the Operator Personnel Performance Simulation (OPPS) Model, driven by task requirements, information presentation, and system dynamics. The model output, a probability distribution of predicted time to correctly complete safety-related operator actions, provides data for objective evaluation of quantitative design criteria

OSART programme highlights 1995-1996. Operational safety practices in nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-05-01

The IAEA Operational Safety Review Team (OSART) programme provides advice and assistance to Member States in enhancing the operational safety of nuclear power plants. This report continues the practice of summarizing mission results so that all the aspects of OSART missions, Pre-OSART missions and good practices are to be found in one volume. It also includes results of follow-up visits. Attempts have been made in this report to highlight the most significant findings whilst retaining as much of the vital background information as possible. This report is in four parts: Part I summarizes the most significant observations made during the missions and follow-up visits during 1995-1996; Part II, in chronological order, is an overview of the major strengths and opportunities for improvement identified during each OSART mission and summaries of follow-up visits performed during the period; Part III lists good practices that were identified during 1995 and 1996; and Part IV presents the OSART mission results (OSMIR) database. Each part of the report is intended for different levels in operating and regulatory organizations but not exclusively so. Part I is primarily to the executive management level; Part II to middle managers; and Parts III and IV to those involved in operational experience feedback. Because of widely different plant designs, operating and management styles, cultural practices, and other factors affecting plant operations, no OSART findings were applicable to all of the plants visited in 1995 and 1996. Individual findings varied considerably in scope and significance. However, the findings do reflect some common strengths and opportunities for improvement

WIPP - Pre-Licensing and Operations: Developer and Regulator Perspectives

International Nuclear Information System (INIS)

Peake, Tom; Patterson, R.

2014-01-01

The Waste Isolation Pilot Plant (WIPP) is a disposal system for defense-related transuranic (TRU) radioactive waste. Developed by the Department of Energy (DOE), WIPP is located in Southeastern New Mexico: radioactive waste is disposed of 2,150 feet underground in an ancient layer of salt with a total capacity of 6.2 million cubic feet of waste. Congress authorized the development and construction of WIPP in 1980 for the express purpose of providing a research and development facility to demonstrate the safe disposal of radioactive wastes resulting from the defense activities and programs of the United States. This paper makes a historical review of the site development, site operations (waste disposal operations started in 1999), communications between US EPA and DOE, the chronology of pre-licensing and pre-operations, the operational phase and the regulatory challenges, and the lessons learned after 12 years of operations

Pre-operative and early post-operative factors associated with surgical site infection after laparoscopic sleeve gastrectomy.

Science.gov (United States)

Ruiz-Tovar, Jaime; Oller, Inmaculada; Llavero, Carolina; Arroyo, Antonio; Muñoz, Jose Luis; Calero, Alicia; Diez, María; Zubiaga, Lorea; Calpena, Rafael

2013-08-01

Surgical procedures on obese patients are expected to have a high incidence of surgical site infection (SSI). The identification of pre-operative or early post-operative risk factors for SSI may help the surgeon to identify subjects in risk and adequately optimize their status. We conducted a study of the association of comorbidities and pre- and post-operative analytical variables with SSI following laparoscopic sleeve gastrectomy for the treatment of morbid obesity. We performed a prospective study of all morbidly obese patients undergoing laparoscopic sleeve gastrectomy as a bariatric procedure between 2007 and 2011. An association of clinical and analytical variables with SSI was investigated. The study included 40 patients with a mean pre-operative body mass index (BMI) of 51.2±7.9 kg/m(2). Surgical site infections appeared in three patients (7.5%), of whom two had an intra-abdominal abscess located in the left hypochondrium and the third had a superficial incisional SSI. Pre-operatively, a BMI >45 kg/m(2) (OR 8.7; p=0.008), restrictive disorders identified by pulmonary function tests (OR 10.0; p=0.012), a serum total protein concentration 30 mcg/dL (OR 13.0; p=0.003), and a mean corpuscular volume (MCV) operative SSI. Post-operatively, a serum glucose >128 mg/dL (OR 4.7; p=0.012) and hemoglobin operative anemia and hyperglycemia as risk factors for SSI. In these situations, the surgeon must be aware of and seek to control these risk factors.

Safety assessment for TA-48 radiochemical operations

International Nuclear Information System (INIS)

1994-08-01

The purpose of this report is to document an assessment performed to evaluate the safety of the radiochemical operations conducted at the Los Alamos National Laboratory operations area designated as TA-48. This Safety Assessment for the TA-48 radiochemical operations was prepared to fulfill the requirements of US Department of Energy (DOE) Order 5481.1B, ''Safety Analysis and Review System.'' The area designated as TA-48 is operated by the Chemical Science and Technology (CST) Division and is involved with radiochemical operations associated with nuclear weapons testing, evaluation of samples collected from a variety of environmental sources, and nuclear medicine activities. This report documents a systematic evaluation of the hazards associated with the radiochemical operations that are conducted at TA-48. The accident analyses are limited to evaluation of the expected consequences associated with a few bounding accident scenarios that are selected as part of the hazard analysis. Section 2 of this report presents an executive summary and conclusions, Section 3 presents pertinent information concerning the TA-48 site and surrounding area, Section 4 presents a description of the TA-48 radiochemical operations, and Section 5 presents a description of the individual facilities. Section 6 of the report presents an evaluation of the hazards that are associated with the TA-48 operations and Section 7 presents a detailed analysis of selected accident scenarios

The ultrastructure of tumor cells in patients with rectal cancer after pre-operative irradiation and intra-operative cryotherapy

International Nuclear Information System (INIS)

Vyinnik, Yu.O.; Kotenko, O.Je.; Nevzorov, V.P.; Chyibyisov, L.P.

2000-01-01

Electronic microscopy of the tumor cells was performed to confirm the efficacy of combined pre-operative gamma-therapy and intraoperative cryotherapy (CT). Pre-operative irradiation at the dose of 20 Gy accompanied by intra-operative cryotherapy caused the changes in the ultrastructure, the depth and degree of which allow to consider them destructive and irreversible

Safety management systems and their role in achieving high standards of operational safety

International Nuclear Information System (INIS)

Coulston, D.J.; Baylis, C.C.

2000-01-01

Achieving high standards of operational safety requires a robust management framework that is visible to all personnel with responsibility for its implementation. The structure of the management framework must ensure that all processes used to manage safety interlink in a logical and coherent manner, that is, they form a management system that leads to continuous improvement in safety performance. This Paper describes BNFL's safety management system (SMS). The SMS has management processes grouped within 5 main elements: 1. Policy, 2. Organisation, 3. Planning and Implementation, 4. Measuring and Reviewing Performance, 5. Audit. These elements reflect the overall process of setting safety objective (from Policy), measuring success and reviewing the performance. Effective implementation of the SMS requires senior managers to demonstrate leadership through their commitment and accountability. However, the SMS as a whole reflects that every employee at every level within BNFL is responsible for safety of operations under their control. The SMS therefore promotes a proactive safety culture and safe operations. The system is formally documented in the Company's Environmental, Health and Safety (EHS) Manual. Within in BNFL Group, the Company structures enables the Manual to provide overall SMS guidance and co-ordination to its range of nuclear businesses. Each business develops the SMS to be appropriate at all levels of its organisation, but ensuring that each level is consistent with the higher level. The Paper concludes with a summary of BNFL's safety performance. (author)

Safety Needs Mediate Stressful Events Induced Mental Disorders

Science.gov (United States)

Gu, Simeng; Lei, Yu; Lu, Shanshan

2016-01-01

“Safety first,” we say these words almost every day, but we all take this for granted for what Maslow proposed in his famous theory of Hierarchy of Needs: safety needs come second to physiological needs. Here we propose that safety needs come before physiological needs. Safety needs are personal security, financial security, and health and well-being, which are more fundamental than physiological needs. Safety worrying is the major reason for mental disorders, such as anxiety, phobia, depression, and PTSD. The neural basis for safety is amygdala, LC/NE system, and corticotrophin-releasing hormone system, which can be regarded as a “safety circuitry,” whose major behavior function is “fight or flight” and “fear and anger” emotions. This is similar to the Appraisal theory for emotions: fear is due to the primary appraisal, which is related to safety of individual, while anger is due to secondary appraisal, which is related to coping with the unsafe situations. If coping is good, the individual will be happy; if coping failed, the individual will be sad or depressed. PMID:27738527

Safety Needs Mediate Stressful Events Induced Mental Disorders.

Science.gov (United States)

Zheng, Zheng; Gu, Simeng; Lei, Yu; Lu, Shanshan; Wang, Wei; Li, Yang; Wang, Fushun

2016-01-01

"Safety first," we say these words almost every day, but we all take this for granted for what Maslow proposed in his famous theory of Hierarchy of Needs : safety needs come second to physiological needs. Here we propose that safety needs come before physiological needs. Safety needs are personal security, financial security, and health and well-being, which are more fundamental than physiological needs. Safety worrying is the major reason for mental disorders, such as anxiety, phobia, depression, and PTSD. The neural basis for safety is amygdala, LC/NE system, and corticotrophin-releasing hormone system, which can be regarded as a "safety circuitry," whose major behavior function is "fight or flight" and "fear and anger" emotions. This is similar to the Appraisal theory for emotions: fear is due to the primary appraisal, which is related to safety of individual, while anger is due to secondary appraisal, which is related to coping with the unsafe situations. If coping is good, the individual will be happy; if coping failed, the individual will be sad or depressed.

Safety Needs Mediate Stressful Events Induced Mental Disorders

Directory of Open Access Journals (Sweden)

Zheng Zheng

2016-01-01

Full Text Available “Safety first,” we say these words almost every day, but we all take this for granted for what Maslow proposed in his famous theory of Hierarchy of Needs: safety needs come second to physiological needs. Here we propose that safety needs come before physiological needs. Safety needs are personal security, financial security, and health and well-being, which are more fundamental than physiological needs. Safety worrying is the major reason for mental disorders, such as anxiety, phobia, depression, and PTSD. The neural basis for safety is amygdala, LC/NE system, and corticotrophin-releasing hormone system, which can be regarded as a “safety circuitry,” whose major behavior function is “fight or flight” and “fear and anger” emotions. This is similar to the Appraisal theory for emotions: fear is due to the primary appraisal, which is related to safety of individual, while anger is due to secondary appraisal, which is related to coping with the unsafe situations. If coping is good, the individual will be happy; if coping failed, the individual will be sad or depressed.

76 FR 63901 - Pre-Harvest Food Safety for Cattle; Public Meeting

Science.gov (United States)

2011-10-14

... practices. 2. Creating an increased focus on pre-harvest food safety and the identification and development... service is available at http://www.fsis.usda.gov/News_&_Events/Email_Subscription/ . Options range from... / Friday, October 14, 2011 / Notices#0;#0; [[Page 63901

Contribution of operating feedback to probabilistic safety studies

International Nuclear Information System (INIS)

Guio, J.M. de; Lannoy, A.

1992-03-01

This paper presents the method used for PWR unit operation feedback analysis and its contribution to probabilistic safety studies. The targets were as follows: - use of failure data banks to assess reliability parameters, - use of event data banks to identify and quantify main system initiating events, - determination of a standard operating profile. These studies, performed in the context of nuclear power plant safety programs, prove useful not only to safety engineers but also to equipment experts, designers, operators and maintenance specialists. They constitute basic data for studies in all these areas or the departure point for new investigations. (authors). 3 figs., 3 tabs., 3 refs

Ensuring the operational safety of finnish nuclear power plants

International Nuclear Information System (INIS)

Vuorinen, A.

1991-01-01

The Finnish nuclear energy programme has been successful both from the safety and economical point of view. These achievements are based on different factors which are discussed in the paper. Finnish Centre for Radiation and Nuclear Safety (STUK) has specified the technical requirements and procedures to be followed in the design, construction, commissioning and operation of NPPs in a series of guides. The guides are quite demanding and latest results of safety research and technical development are taken into account. Regulatory supervision of Finnish NPPs is comprehensive. As an example of this the regulatory inspection program for operational phase is presented. An important way to ensure operational safety of a NPP is to define a set of limits and conditions to identify limiting safety envelope for plant operation. Practices in Finland are reviewed in the paper. The strategy of Defence in Depth is amongst the fundamental principles of nuclear safety. Two corollary principles of defence of depth are accident prevention and accident mitigation. Means used in following these principles are discussed. (author)

Operation safety of control systems. Principles and methods

International Nuclear Information System (INIS)

Aubry, J.F.; Chatelet, E.

2008-01-01

This article presents the main operation safety methods that can be implemented to design safe control systems taking into account the behaviour of the different components with each other (binary 'operation/failure' behaviours, non-consistent behaviours and 'hidden' failures, dynamical behaviours and temporal aspects etc). To take into account these different behaviours, advanced qualitative and quantitative methods have to be used which are described in this article: 1 - qualitative methods of analysis: functional analysis, preliminary risk analysis, failure mode and failure effects analyses; 2 - quantitative study of systems operation safety: binary representation models, state space-based methods, event space-based methods; 3 - application to the design of control systems: safe specifications of a control system, qualitative analysis of operation safety, quantitative analysis, example of application; 4 - conclusion. (J.S.)

A Study of Time Response for Safety-Related Operator Actions in Non-LOCA Safety Analysis

Energy Technology Data Exchange (ETDEWEB)

Lee, Min Seok; Lee, Sang Seob; Park, Min Soo; Lee, Gyu Cheon; Kim, Shin Whan [KEPCO E and C Company, Daejeon (Korea, Republic of)

2014-10-15

The classification of initiating events for safety analysis report (SAR) chapter 15 is categorized into moderate frequency events (MF), infrequent events (IF), and limiting faults (LF) depending on the frequency of its occurrence. For the non-LOCA safety analysis with the purpose to get construction or operation license, however, it is assumed that the operator response action to mitigate the events starts at 30 minutes after the initiation of the transient regardless of the event categorization. Such an assumption of corresponding operator response time may have over conservatism with the MF and IF events and results in a decrease in the safety margin compared to its acceptance criteria. In this paper, the plant conditions (PC) are categorized with the definitions in SAR 15 and ANS 51.1. Then, the consequence of response for safety-related operator action time is determined based on the PC in ANSI 58.8. The operator response time for safety analysis regarding PC are reviewed and suggested. The clarifying alarm response procedure would be required for the guideline to reduce the operator response time when the alarms indicate the occurrence of the transient.

Positive emotion, appraisal, and the role of appraisal overlap in positive emotion co-occurrence.

Science.gov (United States)

Tong, Eddie M W; Jia, Lile

2017-02-01

Appraisal research has traditionally focused on negative emotions but has not addressed issues concerning the relationships between several positive emotions and appraisals in daily life and the extent to which co-occurrence of positive emotions can be explained by overlap in appraisals. Driven by a priori hypotheses on appraisal-emotion relationships, this study investigated 12 positive emotions and 13 appraisal dimensions using Ecological Momentary Assessment. The results provide strong evidence that positive emotions and appraisals correlate significantly in daily life. Importantly, we found that the positive emotions' overlap on theoretically relevant, as compared to irrelevant, appraisals was stronger and more predictive of their co-occurrence. Furthermore, appraisal overlap on theoretically relevant appraisals predicted the co-occurrence of positive emotions even when the appraisal of pleasantness was excluded, indicating that positive emotions do not co-occur just by virtue of their shared valence. Our findings affirmed and refined the appraisal profiles of positive emotions and underscore the importance of appraisals in accounting for the commonality and differences among positive emotions. (PsycINFO Database Record (c) 2017 APA, all rights reserved).

Impact of pre-conditioning on the qualification of safety-related equipment

International Nuclear Information System (INIS)

Isgro, J.R.

1982-01-01

This paper shares some recent experiences on the effects of preconditioning on the qualification of safety-related equipment not located in a harsh environment. Environmental and seismic qualification testing programs were conducted following the guidelines of IEEE 323-1974, IEEE 344-1975 and appropriate IEEE daughter standards, where available. The examples that follow will illustrate the degree of pre-conditioning of safety-related equipment qualified to the requirements of IEEE-323-1974, and its effect on the outcome of the qualification program

Pre-operative fasting: a nationwide survey of German anaesthesia departments.

Science.gov (United States)

Breuer, J-P; Bosse, G; Seifert, S; Prochnow, L; Martin, J; Schleppers, A; Geldner, G; Soreide, E; Spies, C

2010-03-01

Shorter pre-operative fasting improves clinical outcome without an increased risk. Since October 2004, German Anaesthesiology Societies have officially recommended a fast of 2 h for clear fluids and 6 h for solid food before elective surgery. We conducted a nationwide survey to evaluate the current clinical practice in Germany. Between July 2006 and January 2007, standardized questionnaires were mailed to 3751 Anaesthesiology Society members in leading positions requesting anonymous response. The overall response rate was 66% (n=2418). Of those, 2148 (92%) claimed familiarity with the new guidelines. About a third (n=806, 34%) reported full adherence to the new recommendations, whereas 1043 (45%) reported an eased fasting practice. Traditional Nil per os after midnight was still recommended by 157 (7%). Commonest reasons reported for adopting the new guidelines were: 'improved pre-operative comfort' (84%), and 'increased patient satisfaction' (83%); reasons against were: 'low flexibility in operation room management' (19%), and 'increased risk of aspiration' (13%). Despite the apparent understanding of the benefits from reduced pre-operative fasting, full implementation of the guidelines remains poor in German anaesthesiology departments.

Frequency probabilistic analysis of a small break LOCA due to a power operated relief valve (PORV) for Angra-1 pre-TMI and post-TMI

International Nuclear Information System (INIS)

Onusic Junior, J.

1986-01-01

After the TMI event efforts were aimed towards improvements in the operational and administrative procedures related to the power operated relief valves (PORVs) in order to decrease the probability of a small-break loss-of-coolant accident (LOCA) caused by stuck-open power operated relief valve. This paper presents a frequency probabilistic analysis of a small break LOCA due to a stuck open PORV and safety valve to the Angra I nuclear power plant in operating conditions pre-TMI and post-TMI. (Author) [pt

Summary of NRC LWR safety research programs on fuel behavior, metallurgy/materials and operational safety

International Nuclear Information System (INIS)

Bennett, G.L.

1979-09-01

The NRC light-water reactor safety-research program is part of the NRC regulatory program for ensuring the safety of nuclear power plants. This paper summarizes the results of NRC-sponsored research into fuel behavior, metallurgy and materials, and operational safety. The fuel behavior research program provides a detailed understanding of the response of nuclear fuel assemblies to postulated off-normal or accident conditions. Fuel behavior research includes studies of basic fuel rod properties, in-reactor tests, computer code development, fission product release and fuel meltdown. The metallurgy and materials research program provides independent confirmation of the safe design of reactor vessels and piping. This program includes studies on fracture mechanics, irradiation embrittlement, stress corrosion, crack growth, and nondestructive examination. The operational safety research provides direct assistance to NRC officials concerned with the operational and operational-safety aspects of nuclear power plants. The topics currently being addressed include qualification testing evaluation, fire protection, human factors, and noise diagnostics

PSA analysis focused on Mochovce NPP safety measures evaluation from operational safety point of view

International Nuclear Information System (INIS)

Cillik, I.; Vrtik, L.

2001-01-01

Mochovce NPP consists of four reactor units of WWER 440/V213 type and it is located in the south-middle part of Slovakia. At present first unit operated and the second one under the construction finishing. As these units represent second generation of WWER reactor design, the additional safety measures (SM) were implemented to enhance operational and nuclear safety according to the recommendations of performed international audits and operational experience based on exploitation of other similar units (as Dukovany and J. Bohunice NPPs). These requirements result into a number of SMs grouped according to their purpose to reach recent international requirements on nuclear and operational safety. The paper presents the bases used for safety measures establishing including their grouping into the comprehensive tasks covering different areas of safety goals as well as structural organization of a project management of including participating companies and work performance. More, results are given regarding contribution of selected SMs to the total core damage frequency decreasing.(author)

Improving operational safety management through probabilistic safety assessment on personal computers

International Nuclear Information System (INIS)

1988-10-01

The Technical Committee Meeting considered the current effort in the implementation and use of PSA information for day-to-day operational safety management on Personal Computers. Due to the very recent development of the necessary hardware and software for Personal Computers, the application of PSA information for day-to-day operational safety management on PCs is essentially still in a pioneering stage. There is at present only one such system for end users existing, the PRISIM (Plant Risk Status Information Management) program for which a limited practical application experience is available. Others are still in the development stage. The main aim of the Technical Committee Meeting was to discuss the present status of PSA based systems for operational safety management support on small computers, to consider practical aspects when implementing these systems into a nuclear installation and to address problems related to the further work in the area. A separate abstract was prepared for the summary of the Technical Committee Meeting and for the 8 papers presented by the participants. Refs, figs and tabs

Appraisal Psychology, Neurobiology, and Language.

Science.gov (United States)

Schumann, John H.

2001-01-01

Proposes that the confluence of stimulus appraisal and social cognition that is effected by the neural system in the brain has important implications for language and learning theories. Describes the anatomy and functions of this neural system and discusses how it may operate in motivation for second language acquisition and how in conjunction…

The effect of pre-operative optimization on post-operative outcome in Crohn's disease resections

DEFF Research Database (Denmark)

El-Hussuna, Alaa; Iesalnieks, Igors; Horesh, Nir

2017-01-01

BACKGROUND: The timing of surgical intervention in Crohn's disease (CD) may depend on pre-operative optimization (PO) which includes different interventions to decrease the risk for unfavourable post-operative outcome. The objective of this study was to investigate the effect of multi-model PO on...

Core instrumentation and pre-operational procedures for core conversion HEU to LEU

International Nuclear Information System (INIS)

1984-02-01

This report is intended for the reactor operator, to be used as a manual or checklist for general guidance on pre-startup activities that need to be addressed in preparation for conversion to Low Enriched Fuel (LEU). All nuclear, thermodynamic and safety calculations should have been performed prior to this stage of the core conversion process. During these calculations and certainly before ordering the new LEU fuel elements the reactor operator needs to very carefully consider additional important factors concerning the new fuel: fuel reliability, reliability of fuel fabricator, reprocessing contract or fuel element storage and disposal, economics of the new fuel cycle. At this stage, too, a preoperational experimental programme has to be developed and presented to the regulatory authorities for approval. This experimental programme could lead to additional requirements on: in-core instrumentation, out-of-core instrumentation or additional experimental devices. Detailed instructions on specific tests and measurements are not provided in this report since much information on the subject is available in the open literature

Safety evaluation of the Dalat research reactor operation

International Nuclear Information System (INIS)

Long, V.H.; Lam, P.V.; An, T.K.

1989-01-01

After an introduction presenting the essential characteristics of the Dalat Nuclear Research Reactor, the document presents i) The safety assurance condition of the reactor, ii) Its safety behaviour after 5 years of operation, iii) Safety research being realized on the reactor. Following is questionnaire of safety evaluation and a list of attachments, which concern the reactor

The problem of appraising qualitative research

OpenAIRE

Dixon-Woods, M; Shaw, R; Agarwal, S; Smith, J

2004-01-01



 Qualitative research can make a valuable contribution to the study of quality and safety in health care. Sound ways of appraising qualitative research are needed, but currently there are many different proposals with few signs of an emerging consensus. One problem has been the tendency to treat qualitative research as a unified field. We distinguish universal features of quality from those specific to methodology and offer a set of minimally prescriptive prompts to assist with the assessme...

Importance of safety review to the safe operation of a nuclear plant

International Nuclear Information System (INIS)

Brinkerhoff, L.C.

1978-01-01

Widely differing standards of construction of nuclear reactors are employed in different countries. Although the reactor vendors, including designers and construction contractors, have a vested interest in safety, the ultimate responsibility for safety rests with the reactor facility operator. Even though governmental agencies, either directly or indirectly, must take a strong lead in developing policies and practices of safe operation, the reactor facility operator must recognize and accept the full responsibility for safe operation of the facility. The policies and practices of safe operation imposed by governmental agencies must help assure the prudent operation and the adequate maintenance of those structures, systems, and components of importance to safety. Since each country has a slightly different philosophy for achieving safety and each vendor utilizes different structures, systems, and components to fulfil this philosophy, it is imperative that the facility operator adequately maintain those engineered safety features and those plant protective systems which have been engineered into achieving the desired levels of safety. An additional method of helping to assure that those structures, systems, and components of importance to safety are prudently operated and adequately maintained is to assign the full safety responsibility for the overall operations of the reactor facility to the operating organization, i.e. assigning a 'line of responsibility' within the reactor facility operator. This assurance can be further strengthened by requiring that the facility operator establish a safety review body that overviews the operation and assures that the operating organization complies with those policies and practices of safe operation which have been imposed on the reactor facility. (author)

Light Duty Utility Arm system pre-operational (cold test) test plan

International Nuclear Information System (INIS)

Bennett, K.L.

1995-01-01

The Light Duty Utility (LDUA) Cold Test Facility, located in the Hanford 400 Area, will be used to support cold testing (pre- operational tests) of LDUA subsystems. Pre-operational testing is composed of subsystem development testing and rework activities, and integrated system qualification testing. Qualification testing will be conducted once development work is complete and documentation is under configuration control. Operational (hot) testing of the LDUA system will follow the testing covered in this plan and will be covered in a separate test plan

Summary of the nuclear safety in operation

International Nuclear Information System (INIS)

2004-01-01

This summary is a collection of general information about nuclear safety of PWR type reactors exploited by EDF. Teaching aid, this work has been conceived by operators for operators, it must not be considered nor used as a doctrine document with a regulatory or prescriptive characteristic. it summarizes the great principles of nuclear safety, places them in a global approach and shows their coherence. It consists in 6 chapters and 6 annexes. The news of this edition are the chapter 2 devoted to the safety management and the annexe 6 devoted to the principal teaching coming from the feedback. At the end a glossary explains the signs and abbreviations and an index allows to find themes in the memento text from keywords. (N.C.)

Perceived nuclear risk, organizational commitment, and appraisals of management: A study of nuclear power plant personnel

International Nuclear Information System (INIS)

Kivimaeki, M.; Kalimo, R.; Salminen, S.

1995-01-01

This study examined to what extent nuclear risk perceptions, organizational commitment (OC), and appraisals of management are associated with each other among nuclear power plant personnel. The sample consisted of 428 nuclear power plant workers who completed a questionnaire at their workplace. Perceived nuclear risk and OC were most closely related to the appraisals of the top management of the organization. As the trust in and satisfaction with the top management increased, perceived nuclear safety and acceptance of the organizational goals and values heightened. This result is discussed in the context of industrial safety management. 29 refs., 2 tabs

Substitute safety rods: Physics of operation and irradiation

International Nuclear Information System (INIS)

Baumann, N.P.

1991-01-01

Under certain assumed accidents, an SRS reactor may lose most of its bulk moderator while maintaining flow to fuel assemblies. If this occurs immediately after operation at power, components normally dependent on convective heat transfer to the moderator will heat up with the possibility of melting that component. One component at risk is the currently used cadmium safety rod. A substitute safety rod consisting solely of sintered B 4 C and stainless steel has been designed which is capable of withstanding much higher temperatures. This memorandum provides the physics basis for the adequacy of the rod for reactor shutdown and provides a set of criteria for acceptance in the NTG tests. This memorandum provides physics data for other aspects of operation. These include: Heat production and helium production, along with related phenomena, resulting from inadvertent irradiation at power. Gamma heat input under drained tank conditions. An equivalent rod design suitable for charge design and safety analyses. Degradation under normal operation. Thermal flux ripple in adjacent fuel due to axial striping of alternate B 4 C and steel pellets. Possible effect on safety analyses. Safety rod withdrawal during reactor startup

Multi-objective demand side scheduling considering the operational safety of appliances

International Nuclear Information System (INIS)

Du, Y.F.; Jiang, L.; Li, Y.Z.; Counsell, J.; Smith, J.S.

2016-01-01

Highlights: • Operational safety of appliances is introduced in multi-objective scheduling. • Relationships between operational safety and other objectives are investigated. • Adopted Pareto approach is compared with Weigh and Constraint approaches. • Decision making of Pareto approach is proposed for final appliances’ scheduling. - Abstract: The safe operation of appliances is of great concern to users. The safety risk increases when the appliances are in operation during periods when users are not at home or when they are asleep. In this paper, multi-objective demand side scheduling is investigated with consideration to the appliances’ operational safety together with the electricity cost and the operational delay. The formulation of appliances’ operational safety is proposed based on users’ at-home status and awake status. Then the relationships between the operational safety and the other two objectives are investigated through the approach of finding the Pareto-optimal front. Moreover, this approach is compared with the Weigh and Constraint approaches. As the Pareto-optimal front consists of a set of optimal solutions, this paper proposes a method to make the final scheduling decision based on the relationships among the multiple objectives. Simulation results demonstrate that the operational safety is improved with the sacrifice of the electricity cost and the operational delay, and that the approach of finding the Pareto-optimal front is effective in presenting comprehensive optimal solutions of the multi-objective demand side scheduling.

The enhancement of Ignalina NPP in design and operational safety

International Nuclear Information System (INIS)

Negrivoda, G.

1999-01-01

Enhancement of Ignalina NPP design include: core design improvements; fuel channel integrity (multiple pressure tube rupture); improvements of shutdown systems; improvements of instrumentation and control devices; containment strength and tightness; design basis accident analysis; improvements of safety and support systems; seismic safety enhancement; Year 2000 project; cracks in pipes. Enhancement of operational safety includes: quality assurance; configuration management; safety management and safety culture; emergency operating procedures; training and full scope simulator; in-service inspection; fire protection and ageing monitoring and management

IAEA Leads Operational Safety Mission to Armenian Nuclear Power Plant

International Nuclear Information System (INIS)

2011-01-01

Full text: An international team of nuclear installation safety experts, led by the International Atomic Energy Agency (IAEA), has reviewed the Armenian Nuclear Power Plant (ANPP) near Metsamor for its safety practices and has noted a series of good practices, as well as recommendations to reinforce them. The IAEA assembled an international team of experts at the request of the Government of the Republic of Armenia to conduct an Operational Safety Review (OSART) of the NPP. Under the leadership of the IAEA's Division of Nuclear Installation Safety, the OSART team performed an in-depth operational safety review from 16 May to 2 June 2011. The team was made up of experts from Finland, France, Lithuania, Hungary, Netherlands, Slovakia, UK, USA, EC and the IAEA. An OSART mission is designed as a review of programmes and activities essential to operational safety. It is not a regulatory inspection, nor is it a design review or a substitute for an exhaustive assessment of the plant's overall safety status. Experts participating in the IAEA's June 2010 International Conference on Operational Safety of Nuclear Power Plants (NPP) reviewed the experience of the OSART programme and concluded: In OSART missions NPPs are assessed against IAEA safety standards which reflect the current international consensus on what constitutes a high level of safety; and OSART recommendations and suggestions are of utmost importance for operational safety improvement of NPPs. Armenia is commended for openness to the international nuclear community and for actively inviting IAEA safety review missions to submit their activities to international scrutiny. Examples of IAEA safety reviews include: Design Safety Review in 2003; Review of Probabilistic Safety Assessment in 2007; and Assessment of Seismic Safety Re-Evaluation in 2009. The team at ANPP conducted an in-depth review of the aspects essential to the safe operation of the plant, which is largely under the control of the site management

Pre-operative pain and sensory function in groin hernia

DEFF Research Database (Denmark)

Aasvang, Eske K; Hansen, Jeanette B; Kehlet, Henrik

2009-01-01

(rho=-0.413, p=0.049), indicating a paradoxical association between level of mechanical pain threshold and magnitude of spontaneous pain. No other sensory modality was significantly correlated to pain intensity. New/increased pain during repetitive pinprick stimulation (wind-up) was seen in 3 patients...... mechanism. AIMS: To investigate the correlation between pre-operative pain intensity and sensory functions in the groin hernia area. METHODS: Patients with unilateral groin hernia were examined preoperatively by quantitative sensory testing (thermal, mechanical, and pressure [detection and pain thresholds...... pain is not related to findings of hyperalgesia or other changes in sensory function that may support pain-induced pre-operative neuroplasticity as a pathogenic mechanism for the development of persistent postherniotomy pain....

Clinical evaluation of music perception, appraisal and experience in cochlear implant users.

Science.gov (United States)

Drennan, Ward R; Oleson, Jacob J; Gfeller, Kate; Crosson, Jillian; Driscoll, Virginia D; Won, Jong Ho; Anderson, Elizabeth S; Rubinstein, Jay T

2015-02-01

The objectives were to evaluate the relationships among music perception, appraisal, and experience in cochlear implant users in multiple clinical settings and to examine the viability of two assessments designed for clinical use. Background questionnaires (IMBQ) were administered by audiologists in 14 clinics in the United States and Canada. The CAMP included tests of pitch-direction discrimination, and melody and timbre recognition. The IMBQ queried users on prior musical involvement, music listening habits pre and post implant, and music appraisals. One-hundred forty-five users of Advanced Bionics and Cochlear Ltd cochlear implants. Performance on pitch direction discrimination, melody recognition, and timbre recognition tests were consistent with previous studies with smaller cohorts, as well as with more extensive protocols conducted in other centers. Relationships between perceptual accuracy and music enjoyment were weak, suggesting that perception and appraisal are relatively independent for CI users. Perceptual abilities as measured by the CAMP had little to no relationship with music appraisals and little relationship with musical experience. The CAMP and IMBQ are feasible for routine clinical use, providing results consistent with previous thorough laboratory-based investigations.

Does pre-operative psychological distress affect patient satisfaction after primary total hip arthroplasty?

Directory of Open Access Journals (Sweden)

Nolan John

2011-06-01

Full Text Available Abstract Background There are concerns that pre-operative psychological distress might be associated with reduced patient satisfaction after total hip replacement (THR. Methods We investigated this in a multi-centre prospective study between January 1999 and January 2002. We dichotomised the patients into the mentally distressed (MHS ≤ 56 and the not mentally distressed (MHS > 56 groups based on their pre-operative Mental Health Score (MHS of SF36. Results 448 patients (340 not distressed and 108 distressed completed the patient satisfaction survey. Patient satisfaction rate at five year was 96.66% (415/448. There was no difference in patient satisfaction or willingness to have the surgery between the two groups. None of pre-operative variables predicted five year patient satisfaction in logistic regression. Conclusions Patient satisfaction after surgery may not be adversely affected by pre-operative psychological distress.

JET Tokamak, preparation of a safety case for tritium operations

Energy Technology Data Exchange (ETDEWEB)

Boyer, Helen, E-mail: helen.boyer@ccfe.ac.uk [CCFE, Culham Science Centre (United Kingdom); Plummer, David; Johnston, Jane [CCFE, Culham Science Centre (United Kingdom)

2016-11-01

Highlights: • A safety case incorporating technical and ITER related upgrades. • Hazard analysis reworked to include new modelling assessments. • Fitness for purpose assessment of safety controls. - Abstract: A new Safety Case is required to permit tritium operations on JET during the forthcoming DTE2 campaign. The outputs, benefits and lessons learned associated with the production of this Safety Case are presented. The changes that have occurred to the Safety Case methodology since the last JET tritium Safety Case are reviewed. Consideration is given to the effects of modifications, particularly ITER related changes, made to the JET and the impact these have on the hazard assessments as well as normal operations. Several specialized assessments, including recent MELCOR modelling, have been undertaken to support the production of this Safety Case and the impact of these assessments is outlined. Discussion of the preliminary actions being taken to progress implementation of this Safety Case is provided, highlighting new methods to improve the dissemination of the key Safety Case results to the plant operators. Finally, the work required to complete this Safety Case, before the next tritium campaign, is summarized.

NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security, Issue no. 12, September 2009

International Nuclear Information System (INIS)

2009-09-01

The current issue presents information about the following topics: Nuclear Security Report 2009; G8 Nuclear Safety and Security Group (NSSG); Uranium Production Site Appraisal Team (UPSAT); New Entrant Nuclear Power Programmes Safety Guide on the Establishment of the Safety Infrastructure (DS424)

Affecting others: social appraisal and emotion contagion in everyday decision making.

Science.gov (United States)

Parkinson, Brian; Simons, Gwenda

2009-08-01

In a diary study of interpersonal affect transfer, 41 participants reported on decisions involving other people over 3 weeks. Reported anxiety and excitement were reliably related to the perceived anxiety and excitement of another person who was present during decision making. Risk and importance appraisals partially mediated effects of other's anxiety on own anxiety as predicted by social appraisal theory. However, other's emotion remained a significant independent predictor of own emotion after controlling for appraisals, supporting the additional impact of more direct forms of affect transfer such as emotion contagion. Significant affect-transfer effects remained even after controlling for participants' perceptions of the other's emotion in addition to all measured appraisals, confirming that affect transfer does not require explicit registration of someone else's feelings. This research provides some of the clearest evidence for the operation of both social appraisal and automatic affect transfer in everyday social life.

Effect of investments on fundamentals and market reaction on pre-operational and operational Brazilian companies for the period 2006-2012

Directory of Open Access Journals (Sweden)

Marco Antonio Pereira

2016-03-01

Full Text Available ABSTRACT This paper provides evidence on the market reaction to corporate investment decisions whose shareholder value is largely attributed to growth options. The exploratory research raised pre-operational companies and their operational pairs on the same economy segments. It had the purpose of investigating the existence of statistical differentiation from financial indicators that reflect the installed assets and growth assets, and then study the market reaction to changes in fixed assets as a signaling element about investment decisions. The formation process of operational assets and shareholder value almost exclusively dependent on asset growth stands out in the pre-operational companies. As a result, differentiation tests confirmed that the pre-operational companies had their value especially derived on growth options. The market reaction was particularly bigger in pre-operational companies with abnormal negative stock returns, while the operational companies had positive returns, which may indicate that the quality of the investment is judged based on the financial disclosure. Additionally, operational companies' investors await the disclosure to adjust their prices. We conclude that the results are consistent with the empirical evidence and the participants in financial markets to long-term capital formation investments should give that special attention.

EGP contribution to Mochovce completion, safety enhancement and operation

International Nuclear Information System (INIS)

Letko, A.; Matula, P.

2000-01-01

The Re-Evaluation Programme of Mochovce NPP was created in 1995 as an integral part of the completion of the Unit 1 and Unit 2. This program analyzed the general fulfillment of the principle of nuclear safety in the NPP Mochovce project. The analysis has required new corrections of the project, so that the project met the higher safety requirements when starting production. 87 safety measures represent the 'Program'. The basis for their creation were the international missions from 1992 to 1995 which defined. The final safety aim was represented by 'The Technical Specification of the Safety Measures' supported by The Nuclear Power Plant Research Institute and recommended by The Nuclear Regulatory Authority of the Slovak Republic. The technical specification served as a qualified base for the next steps in the pre-project, project and realization stages. (author)

Indicators for monitoring of safety operation and condition of nuclear power stations

International Nuclear Information System (INIS)

Manova, D.

2001-01-01

A common goal of all employees in the nuclear power field is safety operation of nuclear power stations. The evaluation and control of NPP safety operation are a part of the elements of safety management. The present report is related only to a part of the total assessment and control of the plant safety operation, namely - the indicator system for monitoring of Kozloduy NPP operation and condition. (author)

12 CFR 564.5 - Appraiser independence.

Science.gov (United States)

2010-01-01

... 12 Banks and Banking 5 2010-01-01 2010-01-01 false Appraiser independence. 564.5 Section 564.5 Banks and Banking OFFICE OF THRIFT SUPERVISION, DEPARTMENT OF THE TREASURY APPRAISALS § 564.5 Appraiser independence. (a) Staff appraisers. If an appraisal is prepared by a staff appraiser, that appraiser must be...

Control strategy for power management, efficiency-optimization and operating-safety of a 5-kW solid oxide fuel cell system

International Nuclear Information System (INIS)

Zhang, Lin; Jiang, Jianhua; Cheng, Huan; Deng, Zhonghua; Li, Xi

2015-01-01

Highlights: • Efficiency optimization associated with simultaneous power and thermal management. • Fast load tracing, fuel starvation, high efficiency and operating safety are considered. • Open loop pre-conditioning current strategy is proposed for load step-up transients. • Feedback control scheme is proposed for load step-up transients. - Abstract: The slow power tracking, operating safety, especially the fuel exhaustion, and high efficiency considerations are the key issues for integrated solid oxide fuel cell (SOFC) systems during power step up transients, resulting in the relatively poor dynamic capabilities and make the transient load following very challenging and must be enhanced. To this end, this paper first focus on addressing the efficiency optimization associated with simultaneous power and thermal management of a 5-kW SOFC system. Particularly, a traverse optimization process including cubic convolution interpolation algorithm are proposed to obtain optimal operating points (OOPs) with the maximum efficiency. Then this paper investigate the current implications on system step-up transient performance, then a two stage pre-conditioning current strategy and a feedback power reference control scheme is proposed for load step-up transients to balance fast load following and fuel starvation, after that safe thermal transient is validated. Simulation results show the efficacy of the control design by demonstrating the fast load following ability while maintaining the safe operation, thus safe; efficient and fast load transition can be achieved

Self-assessment of operational safety for nuclear power plants

International Nuclear Information System (INIS)

1999-12-01

Self-assessment processes have been continuously developed by nuclear organizations, including nuclear power plants. Currently, the nuclear industry and governmental organizations are showing an increasing interest in the implementation of this process as an effective way for improving safety performance. Self-assessment involves the use of different types of tools and mechanisms to assist the organizations in assessing their own safety performance against given standards. This helps to enhance the understanding of the need for improvements, the feeling of ownership in achieving them and the safety culture as a whole. Although the primary beneficiaries of the self-assessment process are the plant and operating organization, the results of the self-assessments are also used, for example, to increase the confidence of the regulator in the safe operation of an installation, and could be used to assist in meeting obligations under the Convention on Nuclear Safety. Such considerations influence the form of assessment, as well as the type and detail of the results. The concepts developed in this report present the basic approach to self-assessment, taking into consideration experience gained during Operational Safety Review Team (OSART) missions, from organizations and utilities which have successfully implemented parts of a self-assessment programme and from meetings organized to discuss the subject. This report will be used in IAEA sponsored workshops and seminars on operational safety that include the topic of self-assessment

Deterministic Safety Analysis for Nuclear Power Plants. Specific Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2012-01-01

The IAEA's Statute authorizes the Agency to establish safety standards to protect health and minimize danger to life and property - standards which the IAEA must use in its own operations, and which a State can apply by means of its regulatory provisions for nuclear and radiation safety. A comprehensive body of safety standards under regular review, together with the IAEA's assistance in their application, has become a key element in a global safety regime. In the mid-1990s, a major overhaul of the IAEA's safety standards programme was initiated, with a revised oversight committee structure and a systematic approach to updating the entire corpus of standards. The new standards that have resulted are of a high calibre and reflect best practices in Member States. With the assistance of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its safety standards. Safety standards are only effective, however, if they are properly applied in practice. The IAEA's safety services - which range in scope from engineering safety, operational safety, and radiation, transport and waste safety to regulatory matters and safety culture in organizations - assist Member States in applying the standards and appraise their effectiveness. These safety services enable valuable insights to be shared and I continue to urge all Member States to make use of them. Regulating nuclear and radiation safety is a national responsibility, and many Member States have decided to adopt the IAEA's safety standards for use in their national regulations. For the contracting parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions. The standards are also applied by designers, manufacturers and operators around the world to enhance nuclear and radiation safety in power generation, medicine, industry, agriculture, research and education

Test Takers' Performance Appraisals, Appraisal Calibration, and Cognitive and Metacognitive Strategy Use

Science.gov (United States)

Phakiti, Aek

2016-01-01

The current study explores the nature and relationships among test takers' performance appraisals, appraisal calibration, and reported cognitive and metacognitive strategy use in a language test situation. Performance appraisals are executive processes of strategic competence for judging test performance (e.g., evaluating the correctness or…

IAEA Operational Safety Team Reviews Cattenom Nuclear Power Plant

International Nuclear Information System (INIS)

2011-01-01

Full text: An international team of nuclear installation safety experts led by the International Atomic Energy Agency (IAEA) has reviewed operational safety at France's Cattenom Nuclear Power Plant (NPP) noting a series of good practices as well as recommendations and suggestions to reinforce them. The IAEA assembled an international team of experts at the request of the Government of France to conduct an Operational Safety Review (OSART) of Cattenom NPP. Under the leadership of the IAEA's Division of Nuclear Installation Safety in Vienna, the OSART team performed an in-depth operational safety review of the plant from 14 November to 1 December 2011. The team was made up of experts from Belgium, the Czech Republic, Finland, Germany, Hungary, Japan, Russia, Slovakia, South Africa, Sweden, Ukraine, the United Kingdom and the IAEA. The team at Cattenom conducted an in-depth review of the aspects essential to the safe operation of the NPP, which is largely under the control of the site management. The conclusions of the review are based on the IAEA's Safety Standards. The review covered the areas of Management, Organization and Administration; Training and Qualification; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry; Emergency Planning and Preparedness; and Severe Accident Management. Cattenom is the first plant in Europe to voluntarily undertake a Severe Accident Management review during an OSART review. The OSART team has identified good plant practices, which will be shared with the rest of the nuclear industry for consideration of their application. Examples include: Sheets are displayed in storage areas where combustible material is present - these sheets are updated readily and accurately by the area owner to ensure that the fire limits are complied with; A simple container is attached to the neutron source handling device to ensure ease and safety of operations and reduce possible radiation exposure during use

Operating safety requirements for the intermediate level liquid waste system

International Nuclear Information System (INIS)

1980-07-01

The operation of the Intermediate Level Liquid Waste (ILW) System, which is described in the Final Safety Analysis, consists of two types of operations, namely: (1) the operation of a tank farm which involves the storage and transportation through pipelines of various radioactive liquids; and (2) concentration of the radioactive liquids by evaporation including rejection of the decontaminated condensate to the Waste Treatment Plant and retention of the concentrate. The following safety requirements in regard to these operations are presented: safety limits and limiting control settings; limiting conditions for operation; and surveillance requirements. Staffing requirements, reporting requirements, and steps to be taken in the event of an abnormal occurrence are also described

The work of the Operational Safety Review Team (OSART)

International Nuclear Information System (INIS)

Hide, K.W.

1996-01-01

The Operational Safety Review Team (OSART) programme was set up by the IAEA in 1982 to assist Member States to enhance the operational safety of nuclear power plants. Each team is staffed by senior experts in the relevant fields. The review team discusses with plant staff the existing operational programmes for plant which may be under construction, being commissioned or already operating. Following a detailed examination of a safety programme, the OSART team lists strengths and weaknesses and makes recommendations on how to overcome the latter. Since their conclusions are based on the best prevailing international practice, they may be more stringent than those based on national criteria. The results of the 77 missions conducted at 62 plants in 28 countries by the end of 1994 are summarised. (UK)

Economic aspects of risk assessment in chemical safety

Energy Technology Data Exchange (ETDEWEB)

Drummond, M F; Shannon, H S

1986-05-01

This paper considers how the economic aspects of risk assessment in chemical safety can be strengthened. Its main focus is on how economic appraisal techniques, such as cost-benefit and cost-effectiveness analysis, can be adapted to the requirements of the risk-assessment process. Following a discussion of the main methodological issues raised by the use of economic appraisal, illustrated by examples from the health and safety field, a number of practical issues are discussed. These include the consideration of the distribution of costs, effects and benefits, taking account of uncertainty, risk probabilities and public perception, making the appraisal techniques useful to the early stages of the risk-assessment process and structuring the appraisal to permit continuous feedback to the participants in the risk-assessment process. It is concluded that while the way of thinking embodied in economic appraisal is highly relevant to the consideration of choices in chemical safety, the application of these principles in formal analysis of risk reduction procedures presents a more mixed picture. The main suggestions for improvement in the analyses performed are the undertaking of sensitivity analyses of study results to changes in the key assumptions, the presentation of the distribution of costs and benefits by viewpoint, the comparison of health and safety measures in terms of their incremental cost per life-year (or quality-adjusted life-year) gained and the more frequent retrospective review and revision of the economic analyses that are undertaken.

Evaluation of Pre-marketing Factors to Predict Post-marketing Boxed Warnings and Safety Withdrawals.

Science.gov (United States)

Schick, Andreas; Miller, Kathleen L; Lanthier, Michael; Dal Pan, Gerald; Nardinelli, Clark

2017-06-01

An important goal in drug regulation is understanding serious safety issues with new drugs as soon as possible. Achieving this goal requires us to understand whether information provided during the Food and Drug Administration (FDA) drug review can predict serious safety issues that are usually identified after the product is approved. However, research on this topic remains understudied. In this paper, we examine whether any pre-marketing drug characteristics are associated with serious post-marketing safety actions. We study this question using an internal FDA database containing every new small molecule drug submitted to the FDA's Center for Drug Evaluation and Research (CDER) on or after November 21, 1997, and approved and commercially launched before December 31, 2009. Serious post-marketing safety actions include whether these drugs ever experienced either a post-marketing boxed warning or a withdrawal from the market due to safety concerns. A random effects logistic regression model was used to test whether any pre-marketing characteristics were associated with either post-marketing safety action. A total of 219 new molecular entities were analyzed. Among these drugs, 11 experienced a safety withdrawal and 30 received boxed warnings by July 31, 2016. Contrary to prevailing hypotheses, we find that neither clinical trial sample sizes nor review time windows are associated with the addition of a post-marketing boxed warning or safety withdrawal. However, we do find that new drugs approved with either a boxed warning or priority review are more likely to experience post-marketing boxed warnings. Furthermore, drugs approved with boxed warnings tend to receive post-marketing boxed warnings resulting from new safety information that are unrelated to the original warning. Drugs approved with a boxed warning are 3.88 times more likely to receive a post-marketing boxed warning, while drugs approved with a priority review are 3.51 times more likely to receive a post

Waste Encapsulation and Storage Facility interim operational safety requirements

CERN Document Server

Covey, L I

2000-01-01

The Interim Operational Safety Requirements (IOSRs) for the Waste Encapsulation and Storage Facility (WESF) define acceptable conditions, safe boundaries, bases thereof, and management or administrative controls required to ensure safe operation during receipt and inspection of cesium and strontium capsules from private irradiators; decontamination of the capsules and equipment; surveillance of the stored capsules; and maintenance activities. Controls required for public safety, significant defense-in-depth, significant worker safety, and for maintaining radiological consequences below risk evaluation guidelines (EGs) are included.

Evaluation of operating experience with safety values

International Nuclear Information System (INIS)

Bung, W.; Hoemke, P.; Oberender, W.; Paul, H.; Rueter, W.

1985-01-01

This report describes statistical investigations of 2076 functional tests carried out on power operated safety valves in conventional power plants in 1972 until 1983 with special regard to Common Mode-Failures. The results clearly show that Common Mode-Failures play an important part of non-availability for the controlled safety valves, especially in the control system. The 'Deutsche Risikostudie' does not consider any Common Mode-Failures of the primary safety valves. However there is no significant increase of the risk resulted by the primary safety valves in the 'Referenzanlage' if the calculated Common Mode-Failures probabilities are considered. (orig.) [de

Preparation of the initial safety case

International Nuclear Information System (INIS)

Hensley, G.

1987-01-01

In British Nuclear Fuels plc (BNFL), the design of nuclear chemical plants for construction and subsequent operation at Sellafield Works is carried out by the Engineering Division of the Spent Fuel Management Services Group based at Risley, Warrington. Plant construction cannot take place, nor plant commissioning, until it has been demonstrated in the initial (design) safety case that the chosen design will allow the plant to be operated in an adequately safe manner, corresponding to an extremely low level of risk. The safety documentation procedure is described. A Preliminary Design Safety Appraisal is made of the initial design proposal to give an early indication of the order of risk that might prevail. The risk from each hazard is compared with an allocated risk target which makes up a proportion of the total plant risk which is quantified in BNFL's risk criteria. Where the risk appears unacceptable, appropriate modifications are made to the design. Prior to commissioning, a comprehensive, detailed risk assessment is carried out. The methodology of probabilistic risk assessment is described and examples given of how different hazards are assessed. (author)

12 CFR 564.3 - Appraisals required; transactions requiring a State certified or licensed appraiser.

Science.gov (United States)

2010-01-01

... 12 Banks and Banking 5 2010-01-01 2010-01-01 false Appraisals required; transactions requiring a State certified or licensed appraiser. 564.3 Section 564.3 Banks and Banking OFFICE OF THRIFT SUPERVISION, DEPARTMENT OF THE TREASURY APPRAISALS § 564.3 Appraisals required; transactions requiring a State...

I. Reactor safety (including comments on criticisms of WASH-1400)

International Nuclear Information System (INIS)

1976-01-01

A major concern in any nuclear power programme is a reactor accident resulting in a large release of radioactivity to the environment. Serious reactor accidents are possible and the risk of such accidents cannot be reduced to zero i.e. absolute safety cannot be assured. All that can be expected is that the measures used to ensure safety in the design and operation of a reactor are such that the risk of accident is reduced to acceptably low levels. No member of the general public is known to have died or been injured as a result of an accident in over 1000 commercial nuclear power reactor-years. Some accidents in power reactors in operation today have come close enough to an environmental release of radioactivity to cause serious public concern about future safety. Apparent inadequacies in safety practices disclosed by former members of the nuclear power industry have added to this concern. To obtain an objective appraisal of the reactor safety issue this report examines the measures taken in the design and operation of nuclear reactors to reduce the probability of accident to acceptably low levels

A comparison of radiological and historical findings in osteosarcomas following pre-operative chemotherapy

International Nuclear Information System (INIS)

Sommer, H.J.; Riebel, T.; Winkler, K.; Heise, U.; Delling, G.; Hamburg Univ.; Hamburg Univ.

1985-01-01

Since the introduction of pre-operative chemotherapy, osteosarcomas have shown a more favourable prognosis. Reaction of the tumour due to chemotherapy is judged pre-operative primarily by radiology (plain films, angiography, CT, scintigraphy). There is little evidence concerning the radiological appearances after pre-operative chemotherapy and morphological changes, particularly in respect of tumour regression. Specific radiological changes were therefore compared with pathological findings following chemotherapy and operation in 17 patients with osteosarcomas. Tumours were examined which showed radiological evidence of intra- and extra-osseous sclerosis or lysis and which still were classified as vital tumour tissue. Tumour planes were reconstructed from large histological sections of the operative specimen and compared with the radiological appearances. Sclerosis was found to be due to reactive new bone formation or to mineralisation of the osteosarcomatous tissue. Lysis correlated with persistent vital tumour, or in connective tissue. Nine out of ten cases, regarded as vital on radiological evidence, showed vital tumour cells on histological section. Lyses and scleroses were not reliable indications of the pre-operative state of the osteosarcoma following chemotherapy. On the other hand, combined qualitative radiological criteria for assesing tumour vitality, proved to be helpful. (orig.) [de

Oswer integrated health and safety standard operating practices. Directive

International Nuclear Information System (INIS)

1993-02-01

The directive implements the OSWER (Office of Solid Waste and Emergency Response) Integrated Health and Safety Standards Operating Practices in conjunction with the OSHA (Occupational Safety and Health Act) Worker Protection Standards, replacing the OSWER Integrated Health and Safety Policy

Integrated Safety in ''SARAF'

International Nuclear Information System (INIS)

Dickstein, P.; Grof, Y.; Machlev, M.; Pernick, A.

2004-01-01

As of the very early stages of the accelerator project at the Soreq Nuclear Research Center ''SARAF'' a safety group was established which has been an inseparable participant in the planning and design of the new facility. The safety group comprises of teams responsible for the shielding, radiation protection and general industrial safety aspects of ''SARAF''. The safety group prepared and documented the safety envelope for the accelerator, dealing with the safety requirements and guidelines for the first, pre-operational, stages of the project. The safety envelope, though based upon generic principles, took into account the accelerator features and the expected modes of operation. The safety envelope was prepared in a hierarchical structure, containing Basic Principles, Basic Guidelines, General Principles for Safety Implementation, Safety Requirements and Safety Underlining Issues. The above safety envelope applies to the entire facility, which entails the accelerator itself and the experimental areas and associated plant and equipment utilizing and supporting the production of the accelerated particle beams

Defence in depth in nuclear safety learning from 'pre-symptomatic diseases'

International Nuclear Information System (INIS)

Fukuyama, Shigeru

2011-01-01

Traditional Chinese medicine argued 'pre-symptomatic diseases', which encouraged for a physician to treat before the ailment occurred. This article described such prophylactic concept was compared to that of defense in depth in nuclear safety, which suggested encouragement of daily activities with safety awareness, preventive maintenance and appropriate treatment for incidents of aged plants would reduce or mitigate their effects. Area of safety culture was also included. Importance of human resources development for safety culture and need of establishment of database concerning new knowledge and experiences were highly recommended. In reality various slight events, whose level of the International Nuclear Event Scale (INES) were less than 2, occurred before a large accident happened to occur. Efforts to reduce events whose level of INES was less than 2 or precursor of accidents would prevent level 3 serious accidents as maximum accident of defense in depth or mitigate the extension to a larger accident. (T. Tanaka)

Appraisal Report

DEFF Research Database (Denmark)

Schleimann, Finn; Enemark, Ulrika; Vagnby, Bo Hellisen

Appraisal of continued support to Ghana's health sector for a third phase covering 2003 - 2007. Funding recommended with DKK 340 million over five years.......Appraisal of continued support to Ghana's health sector for a third phase covering 2003 - 2007. Funding recommended with DKK 340 million over five years....

A critical appraisal of instruments to measure outcomes of interprofessional education.

Science.gov (United States)

Oates, Matthew; Davidson, Megan

2015-04-01

Interprofessional education (IPE) is believed to prepare health professional graduates for successful collaborative practice. A range of instruments have been developed to measure the outcomes of IPE. An understanding of the psychometric properties of these instruments is important if they are to be used to measure the effectiveness of IPE. This review set out to identify instruments available to measure outcomes of IPE and collaborative practice in pre-qualification health professional students and to critically appraise the psychometric properties of validity, responsiveness and reliability against contemporary standards for instrument design. Instruments were selected from a pool of extant instruments and subjected to critical appraisal to determine whether they satisfied inclusion criteria. The qualitative and psychometric attributes of the included instruments were appraised using a checklist developed for this review. Nine instruments were critically appraised, including the widely adopted Readiness for Interprofessional Learning Scale (RIPLS) and the Interdisciplinary Education Perception Scale (IEPS). Validity evidence for instruments was predominantly based on test content and internal structure. Ceiling effects and lack of scale width contribute to the inability of some instruments to detect change in variables of interest. Limited reliability data were reported for two instruments. Scale development and scoring protocols were generally reported by instrument developers, but the inconsistent application of scoring protocols for some instruments was apparent. A number of instruments have been developed to measure outcomes of IPE in pre-qualification health professional students. Based on reported validity evidence and reliability data, the psychometric integrity of these instruments is limited. The theoretical test construction paradigm on which instruments have been developed may be contributing to the failure of some instruments to detect change in

Evaluation of BOR-60 operation safety

International Nuclear Information System (INIS)

Minakov, A.A.; Antipin, G.K.; Efimov, V.N.; Kuzin, G.G.; Eschenko, L.V.; Eschenko, S.N.

1987-12-01

In this communication, BOR-60 reactor operation anomalies capable to produce a dangerous overheating of the core (SDC) is examined. On bases of calculations and reactor operation experience an event tree for SDC is built. Evaluations of probable anomalies entering in the event tree and reactor parameters modifications in case of anomalies are presented. In conclusion BOR-60 agree with the sovietic nuclear safety [fr

Improving plant state information for better operational safety

International Nuclear Information System (INIS)

Girard, C.; Olivier, E.; Grimaldi, X.

1994-01-01

Nuclear Power Plant (NPP) safety is strongly dependent on components' reliability and particularly on plant state information reliability. This information, used by the plant operators in order to produce appropriate actions, have to be of a high degree of confidence, especially in accidental conditions where safety is threatened. In this perspective, FRAMATOME, EDF and CEA have started a joint research program to prospect different solutions aiming at a better reliability for critical information needed to safety operate the plant. This paper gives the main results of this program and describes the developments that have been made in order to assess reliability of different information systems used in a Nuclear Power Plant. (Author)

Operation of Finnish nuclear power plants. Quarterly report, 1st quarter 1998

International Nuclear Information System (INIS)

Tossavainen, K.

1998-11-01

Quarterly reports on the operation of Finnish NPPs describe events and observations relating to nuclear and radiation safety that the Radiation and Nuclear Safety Authority (STUK) considers safety significant. Safety improvements at the plants are also described. The report includes a summary of the radiation safety of plant personnel and the environment and tabulated data on the plants' production and load factors. The Finnish NPP units were in power operation for the whole first quarter of 1998. All the units were in long-term test operation at uprated power level authorised by STUK. The load factor average of the plant units was 100.8%. An oil leak at Olkiluoto NPP Unit 2 caused an ignition that was promptly extinguished. A subsequent appraisal of the event disclosed deficiencies in the functioning of the plant unit's operating organization and the event was classified INES level 1. Other events in this quarter had no bearing on nuclear or radiation safety. Occupational doses and radioactive releases off-site were below authorized limits. Radioactive substances were measurable in samples collected around the plants in such quantities only as have no bearing on the radiation exposure of the population. (orig.)

Operational safety performance indicators for nuclear power plants

International Nuclear Information System (INIS)

2000-05-01

Since the late 1980s, the IAEA has been actively sponsoring work in the area of indicators to monitor nuclear power plant (NPP) operational safety performance. The early activities were mainly focused on exchanging ideas and good practices in the development and use of these indicators at nuclear power plants. Since 1995 efforts have been directed towards the elaboration of a framework for the establishment of an operational safety performance indicator programme. The result of this work, compiled in this publication, is intended to assist NPPs in developing and implementing a monitoring programme, without overlooking the critical aspects related to operational safety performance. The framework proposed in this report was presented at two IAEA workshops on operational safety performance indicators held in Ljubljana, Slovenia, in September 1998 and at the Daya Bay NPP, Szenzhen, China, in December 1998. During these two workshops, the participants discussed and brainstormed on the indicator framework presented. These working sessions provided very useful insights and ideas which where used for the enhancement of the framework proposed. The IAEA is acknowledging the support and contribution of all the participants in these two activities. The programme development was enhanced by pilot plant studies. Four plants from different countries with different designs participated in this study with the objective of testing the applicability, usefulness and viability of this approach

The mediating role of integration of safety by activity versus operator between organizational culture and safety climate.

Science.gov (United States)

Auzoult, Laurent; Gangloff, Bernard

2018-04-20

In this study, we analyse the impact of the organizational culture and introduce a new variable, the integration of safety, which relates to the modalities for the implementation and adoption of safety in the work process, either through the activity or by the operator. One hundred and eighty employees replied to a questionnaire measuring the organizational climate, the safety climate and the integration of safety. We expected that implementation centred on the activity or on the operator would mediate the relationship between the organizational culture and the safety climate. The results support our assumptions. A regression analysis highlights the positive impact on the safety climate of organizational values of the 'rule' and 'support' type, as well as of integration by the operator and activity. Moreover, integration mediates the relation between these variables. The results suggest to take into account organizational culture and to introduce different implementation modalities to improve the safety climate.

Fuel Supply Shutdown Facility Interim Operational Safety Requirements

International Nuclear Information System (INIS)

BENECKE, M.W.

2000-01-01

The Interim Operational Safety Requirements for the Fuel Supply Shutdown (FSS) Facility define acceptable conditions, safe boundaries, bases thereof, and management of administrative controls to ensure safe operation of the facility

A New Approach to Feasibility Risk Assessment within Transport Infrastructure Appraisal

DEFF Research Database (Denmark)

Salling, Kim Bang

2013-01-01

This paper introduces a new approach of applying feasibility risk assessment within transport project infrastructure appraisal. The procedure is based upon quantitative risk analysis and Monte Carlo simulation in combination with conventional cost-benefit analysis converting deterministic benefit...... are, hereby, often basing their decisions on wrongful material. The presented approach to transport infrastructure appraisal is to include uncertainties and risks in the evaluation. Correspondingly, the handling of uncertainties and risk within transport project assessment are often made up...... by sensitivity tests producing deterministically based output values. Research has proven that traditional sensitivity analysis seldomnly captures the total variability especially as concerns the costs and demands estimated in the pre-stage of the evaluation. Therefore, this paper introduces an approach...

Changes in safety climate and teamwork in the operating room after implementation of a revised WHO checklist: a prospective interventional study.

Science.gov (United States)

Erestam, Sofia; Haglind, Eva; Bock, David; Andersson, Annette Erichsen; Angenete, Eva

2017-01-01

Inter-professional teamwork in the operating room is important for patient safety. The World Health Organization (WHO) checklist was introduced to improve intraoperative teamwork. The aim of this study was to evaluate the safety climate in a Swedish operating room setting before and after an intervention, using a revised version of the WHO checklist to improve teamwork. This study is a single center prospective interventional study. Participants were personnel working in operating room teams including surgeons, anesthesiologists, scrub nurses, nurse anaesthetists and nurse assistants. The study started with pre-interventional observations of the WHO checklist use followed by education on safety climate, the WHO checklist, and non-technical skills in the operating room. Thereafter a revised version of the WHO checklist was introduced. Post-interventional observations regarding the performance of the WHO checklist were carried out. The Safety Attitude Questionnaire was used to assess safety climate at baseline and post-intervention. At baseline we discovered a need for improved teamwork and communication. The participants considered teamwork to be important for patient safety, but had different perceptions of good teamwork between professions. The intervention, a revised version of the WHO checklist, did not affect teamwork climate. Adherence to the revision of the checklist was insufficient, dominated by a lack of structure. There was no significant change in teamwork climate by use of the revised WHO checklist, which may be due to insufficient implementation, as a lack of adherence to the WHO checklist was detected. We found deficiencies in teamwork and communication. Further studies exploring how to improve safety climate are needed. NCT02329691.

Attitudes to teamwork and safety among Italian surgeons and operating room nurses.

Science.gov (United States)

Prati, Gabriele; Pietrantoni, Luca

2014-01-01

Previous studies have shown that surgical team members' attitudes about safety and teamwork in the operating theatre may play a role in patient safety. The aim of this study was to assess attitudes about teamwork and safety among Italian surgeons and operating room nurses. Fifty-five surgeons and 48 operating room nurses working in operating theatres at one hospital in Italy completed the Operating Room Management Attitudes Questionnaire (ORMAQ). Results showed several discrepancies in attitudes about teamwork and safety between surgeons and operating room nurses. Surgeons had more positive views on the quality of surgical leadership, communication, teamwork, and organizational climate in the theatre than operating room nurses. Operating room nurses reported that safety rules and procedures were more frequently disregarded than the surgeons. The results are only partially aligned with previous ORMAQ surveys of surgical teams in other countries. The differences emphasize the influence of national culture, as well as the particular healthcare system. This study shows discrepancies on many aspects in attitudes to teamwork and safety between surgeons and operating room nurses. The findings support implementation and use of team interventions and human factor training. Finally, attitude surveys provide a method for assessing safety culture in surgery, for evaluating the effectiveness of training initiatives, and for collecting data for a hospital's quality assurance programme.

Method of operator safety assessment for underground mobile mining equipment

Science.gov (United States)

Działak, Paulina; Karliński, Jacek; Rusiński, Eugeniusz

2018-01-01

The paper presents a method of assessing the safety of operators of mobile mining equipment (MME), which is adapted to current and future geological and mining conditions. The authors focused on underground mines, with special consideration of copper mines (KGHM). As extraction reaches into deeper layers of the deposit it can activate natural hazards, which, thus far, have been considered unusual and whose range and intensity are different depending on the field of operation. One of the main hazards that affect work safety and can become the main barrier in the exploitation of deposits at greater depths is climate threat. The authors have analysed the phenomena which may impact the safety of MME operators, with consideration of accidents that have not yet been studied and are not covered by the current safety standards for this group of miners. An attempt was made to develop a method for assessing the safety of MME operators, which takes into account the mentioned natural hazards and which is adapted to current and future environmental conditions in underground mines.

Method of operator safety assessment for underground mobile mining equipment

Directory of Open Access Journals (Sweden)

Działak Paulina

2018-01-01

Full Text Available The paper presents a method of assessing the safety of operators of mobile mining equipment (MME, which is adapted to current and future geological and mining conditions. The authors focused on underground mines, with special consideration of copper mines (KGHM. As extraction reaches into deeper layers of the deposit it can activate natural hazards, which, thus far, have been considered unusual and whose range and intensity are different depending on the field of operation. One of the main hazards that affect work safety and can become the main barrier in the exploitation of deposits at greater depths is climate threat. The authors have analysed the phenomena which may impact the safety of MME operators, with consideration of accidents that have not yet been studied and are not covered by the current safety standards for this group of miners. An attempt was made to develop a method for assessing the safety of MME operators, which takes into account the mentioned natural hazards and which is adapted to current and future environmental conditions in underground mines.

Fuel supply shutdown facility interim operational safety requirements

International Nuclear Information System (INIS)

Besser, R.L.; Brehm, J.R.; Benecke, M.W.; Remaize, J.A.

1995-01-01

These Interim Operational Safety Requirements (IOSR) for the Fuel Supply Shutdown (FSS) facility define acceptable conditions, safe boundaries, bases thereof, and management or administrative controls to ensure safe operation. The IOSRs apply to the fuel material storage buildings in various modes (operation, storage, surveillance)

Safety upgrades for NSRRC beamlines in the upcoming top-up operation

International Nuclear Information System (INIS)

Liu, Joseph C.; Sheu, R.-J.; Wang, J.-P.; Chen, C.-R.; Chang, F.-D.; Kao, S.-P.

2006-01-01

The original beamline shielding of NSRRC was designed for the decay mode operation that safety shutter was closed during injection. The proposed top-up operation that opens safety shutter during top-up injection will introduce additional beam loss scenarios and radiation sources, especially when the injection efficiency needs to be improved. Careful comparison was made to differentiate the radiation doses into beamlines for both operation modes. Detailed evaluation was made to identify the possible inadequacies of the old beamline shielding and safety control procedures. Remedy actions and safety upgrades for each individual beamline were issued to ensure that dose limit of 2 mSv/yr for users can be fulfilled when running top-up operation

Operational safety experience feedback by means of unusual event reports

International Nuclear Information System (INIS)

1996-07-01

Operational experience of nuclear power plants can be used to great advantage to enhance safety performance provided adequate measures are in place to collect and analyse it and to ensure that the conclusions drawn are acted upon. Feedback of operating experience is thus an extremely important tool to ensure high standards of safety in operational nuclear power plants and to improve the capability to prevent serious accidents and to learn from minor deviations and equipment failures - which can serve as early warnings -to prevent even minor events from occurring. Mechanisms also need to be developed to ensure that operating experience is shared both nationally as well as internationally. The operating experience feedback process needs to be fully and effectively established within the nuclear power plant, the utility, the regulatory organization as well as in other institutions such as technical support organizations and designers. The main purpose of this publication is to reflect the international consensus as to the general principles and practices in the operational safety experience feedback process. The examples of national practices for the whole or for particular parts of the process are given in annexes. The publication complements the IAEA Safety Series No.93 ''Systems for Reporting Unusual Events in Nuclear Power Plants'' (1989) and may also give a general guidance for Member States in fulfilling their obligations stipulated in the Nuclear Safety Convention. Figs, tabs

Operational safety experience feedback by means of unusual event reports

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-07-01

Operational experience of nuclear power plants can be used to great advantage to enhance safety performance provided adequate measures are in place to collect and analyse it and to ensure that the conclusions drawn are acted upon. Feedback of operating experience is thus an extremely important tool to ensure high standards of safety in operational nuclear power plants and to improve the capability to prevent serious accidents and to learn from minor deviations and equipment failures - which can serve as early warnings -to prevent even minor events from occurring. Mechanisms also need to be developed to ensure that operating experience is shared both nationally as well as internationally. The operating experience feedback process needs to be fully and effectively established within the nuclear power plant, the utility, the regulatory organization as well as in other institutions such as technical support organizations and designers. The main purpose of this publication is to reflect the international consensus as to the general principles and practices in the operational safety experience feedback process. The examples of national practices for the whole or for particular parts of the process are given in annexes. The publication complements the IAEA Safety Series No.93 ``Systems for Reporting Unusual Events in Nuclear Power Plants`` (1989) and may also give a general guidance for Member States in fulfilling their obligations stipulated in the Nuclear Safety Convention. Figs, tabs.

Safety in the Utilization and Modification of Research Reactors. Specific Safety Guide

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-07-15

This Safety Guide is a revision of Safety Series No. 35-G2 on safety in the utilization and modification of research reactors. It provides recommendations on meeting the requirements for the categorization, safety assessment and approval of research reactor experiments and modification projects. Specific safety considerations in different phases of utilization and modification projects are covered, including the pre-implementation, implementation and post-implementation phases. Guidance is also provided on the operational safety of experiments, including in the handling, dismantling, post-irradiation examination and disposal of experimental devices. Examples of the application of the safety categorization process for experiments and modification projects and of the content of the safety analysis report for an experiment are also provided. Contents: 1. Introduction; 2. Management system for the utilization and modification of a research reactor; 3. Categorization, safety assessment and approval of an experiment or modification; 4. Safety considerations for the design of an experiment or modification; 5. Pre-implementation phase of a modification or utilization project; 6. Implementation phase of a modification or utilization project; 7. Post-implementation phase of a utilization or modification project; 8. Operational safety of experiments at a research reactor; 9. Safety considerations in the handling, dismantling, post-irradiation examination and disposal of experimental devices; 10. Safety aspects of out-of-reactor-core installations; Annex I: Example of a checklist for the categorization of an experiment or modification at a research reactor; Annex II: Example of the content of the safety analysis report for an experiment at a research reactor; Annex III: Examples of reasons for a modification at a research reactor.

Safety in the Utilization and Modification of Research Reactors. Specific Safety Guide

International Nuclear Information System (INIS)

2012-01-01

This Safety Guide is a revision of Safety Series No. 35-G2 on safety in the utilization and modification of research reactors. It provides recommendations on meeting the requirements for the categorization, safety assessment and approval of research reactor experiments and modification projects. Specific safety considerations in different phases of utilization and modification projects are covered, including the pre-implementation, implementation and post-implementation phases. Guidance is also provided on the operational safety of experiments, including in the handling, dismantling, post-irradiation examination and disposal of experimental devices. Examples of the application of the safety categorization process for experiments and modification projects and of the content of the safety analysis report for an experiment are also provided. Contents: 1. Introduction; 2. Management system for the utilization and modification of a research reactor; 3. Categorization, safety assessment and approval of an experiment or modification; 4. Safety considerations for the design of an experiment or modification; 5. Pre-implementation phase of a modification or utilization project; 6. Implementation phase of a modification or utilization project; 7. Post-implementation phase of a utilization or modification project; 8. Operational safety of experiments at a research reactor; 9. Safety considerations in the handling, dismantling, post-irradiation examination and disposal of experimental devices; 10. Safety aspects of out-of-reactor-core installations; Annex I: Example of a checklist for the categorization of an experiment or modification at a research reactor; Annex II: Example of the content of the safety analysis report for an experiment at a research reactor; Annex III: Examples of reasons for a modification at a research reactor.

Evaluating North Carolina Food Pantry Food Safety-Related Operating Procedures.

Science.gov (United States)

Chaifetz, Ashley; Chapman, Benjamin

2015-11-01

Almost one in seven American households were food insecure in 2012, experiencing difficulty in providing enough food for all family members due to a lack of resources. Food pantries assist a food-insecure population through emergency food provision, but there is a paucity of information on the food safety-related operating procedures used in the pantries. Food pantries operate in a variable regulatory landscape; in some jurisdictions, they are treated equivalent to restaurants, while in others, they operate outside of inspection regimes. By using a mixed methods approach to catalog the standard operating procedures related to food in 105 food pantries from 12 North Carolina counties, we evaluated their potential impact on food safety. Data collected through interviews with pantry managers were supplemented with observed food safety practices scored against a modified version of the North Carolina Food Establishment Inspection Report. Pantries partnered with organized food bank networks were compared with those that operated independently. In this exploratory research, additional comparisons were examined for pantries in metropolitan areas versus nonmetropolitan areas and pantries with managers who had received food safety training versus managers who had not. The results provide a snapshot of how North Carolina food pantries operate and document risk mitigation strategies for foodborne illness for the vulnerable populations they serve. Data analysis reveals gaps in food safety knowledge and practice, indicating that pantries would benefit from more effective food safety training, especially focusing on formalizing risk management strategies. In addition, new tools, procedures, or policy interventions might improve information actualization by food pantry personnel.

Can the pre-operative Western Ontario and McMaster score predict patient satisfaction following total hip arthroplasty?

Science.gov (United States)

Rogers, B A; Alolabi, B; Carrothers, A D; Kreder, H J; Jenkinson, R J

2015-02-01

In this study we evaluated whether pre-operative Western Ontario and McMaster Universities (WOMAC) osteoarthritis scores can predict satisfaction following total hip arthroplasty (THA). Prospective data for a cohort of patients undergoing THA from two large academic centres were collected, and pre-operative and one-year post-operative WOMAC scores and a 25-point satisfaction questionnaire were obtained for 446 patients. Satisfaction scores were dichotomised into either improvement or deterioration. Scatter plots and Spearman's rank correlation coefficient were used to describe the association between pre-operative WOMAC and one-year post-operative WOMAC scores and patient satisfaction. Satisfaction was compared using receiver operating characteristic (ROC) analysis against pre-operative, post-operative and δ WOMAC scores. We found no relationship between pre-operative WOMAC scores and one-year post-operative WOMAC or satisfaction scores, with Spearman's rank correlation coefficients of 0.16 and -0.05, respectively. The ROC analysis showed areas under the curve (AUC) of 0.54 (pre-operative WOMAC), 0.67 (post-operative WOMAC) and 0.43 (δ WOMAC), respectively, for an improvement in satisfaction. We conclude that the pre-operative WOMAC score does not predict the post-operative WOMAC score or patient satisfaction after THA, and that WOMAC scores can therefore not be used to prioritise patient care. ©2015 The British Editorial Society of Bone & Joint Surgery.

Safety culture in the gynecology robotics operating room.

Science.gov (United States)

Zullo, Melissa D; McCarroll, Michele L; Mendise, Thomas M; Ferris, Edward F; Roulette, G D; Zolton, Jessica; Andrews, Stephen J; von Gruenigen, Vivian E

2014-01-01

To measure the safety culture in the robotics surgery operating room before and after implementation of the Robotic Operating Room Computerized Checklist (RORCC). Prospective study. Gynecology surgical staff (n = 32). An urban community hospital. The Safety Attitudes Questionnaire domains examined were teamwork, safety, job satisfaction, stress recognition, perceptions of management, and working conditions. Questions and domains were described using percent agreement and the Cronbach alpha. Paired t-tests were used to describe differences before and after implementation of the checklist. Mean (SD) staff age was 46.7 (9.5) years, and most were women (78%) and worked full-time (97%). Twenty respondents (83% of nurses, 80% of surgeons, 66% of surgical technicians, and 33% of certified registered nurse anesthetists) completed the Safety Attitudes Questionnaire; 6 were excluded because of non-matching identifiers. Before RORCC implementation, the highest quality of communication and collaboration was reported by surgeons and surgical technicians (100%). Certified registered nurse anesthetists reported only adequate levels of communication and collaboration with other positions. Most staff reported positive responses for teamwork (48%; α = 0.81), safety (47%; α = 0.75), working conditions (37%; α = 0.55), stress recognition (26%; α = 0.71), and perceptions of management (32%; α = 0.52). No differences were observed after RORCC implementation. Quality of communication and collaboration in the gynecology robotics operating room is high between most positions; however, safety attitude responses are low overall. No differences after RORCC implementation and low response rates may highlight lack of staff support. Copyright © 2014. Published by Elsevier Inc.

Pre-operative antibiotic use reduces surgical site infection.

Science.gov (United States)

Toor, Asad Ali; Farooka, Muhammad Waris; Ayyaz, Mahmood; Sarwar, Hassan; Malik, Awais Amjad; Shabbir, Faisal

2015-07-01

To assess the efficacy of World Health Organisation Surgical Safety Checklist as a simple, reliable and effective tool to ensure appropriate administration of intravenous antibiotics. The prospective interventional study was conducted in three phases at Mayo Hospital, Lahore, from May 2011 to January 2012. The first phase comprised baseline data collection, followed by implementation of World Health Organisation Surgical Safety Checklist, and finally post-implementation data collection. The duration of each phase was 3 months. Primary end points were discharge from hospital, 30 days or death of the patient. Of the 613 patients in the study, 303(49.4%) were in the pre-implementation phase and 310(50.5%) in post-implementation phase. Adherence of optimal administration of antibiotic increased from 114(37.6%) to 282(91%) (poperative infection fell from 99(32.7%) to 47(15.2%) (psite infection by more than half. Hospital stay was shortened by 1.3 days on average which results in considerable reduction in morbidity, mortality and costs.

Pre- and post-operative values of serum CRP in patients undergoing surgery for brain tumour

International Nuclear Information System (INIS)

Syeda, T.; Rizvi, H.A.; Hashim, A.S.

2014-01-01

Objective: To determine the concentration of C-reactive protein in pre- and post-operative serum samples of brain tumour patients in order to detect the potential risks of post-operative infections. Methods: Serum C-reactive protein was measured on pre- and post-operative Day 1, Day 2 and Day 7 in 18 patients who underwent surgery for brain tumours. The study was performed at the Neurosurgical Ward, Jinnah Postgraduate Medical Centre, Karachi, from May 2007 to April 2008. Mean pre-operative patients and control values were compared using Mann-Whitney or Wilcoxon tests for comparing between pre- and post-operative values. P-value was considered significant at 5.0mg/L but no statistically significant difference was found when compared with healthy controls, with mean 4.4+-6.6 and 0.9+-0.7, respectively. Significantly raised serum concentrations were observed in all post-operative samples when compared with pre-operative samples. Serum CRP concentrations significantly increased post-operatively on Day 1, with mean value of 102.9+-82.0mg/L (p<0.0005), and further increased on Day 2 with mean value of 166.9+-128.1mg/L (p<0.0005), but declined on Day 7, with mean value of 42.7+-63.6mg/L (p<0.005). Conclusion: Pre-operative serum C-reactive protein concentrations of 28% of the patients were elevated, suggesting an association with brain tumours. Post-operative serum concentrations were significantly higher than those noted before the surgery. Absence of a fall of concentration from peak value on post-operative Day 2 or a secondary rise from post-operative Day 7 could be alarming for inter-current infection. (author)

USAEC Controls for Nuclear Criticality Safety

Energy Technology Data Exchange (ETDEWEB)

McCluggage, W. C. [Division of Operational Safety, United States Atomic Energy Commission Washington, DC (United States)

1966-05-15

This is a paper written to provide a broad general view of the United States Atomic Energy Commission's controls for nuclear criticality safety within its own facilities. Included also is a brief' discussion of the USAEC's methods of obtaining assurance that the controls are being applied. The body of the document contains three sections. The first two describe the functions of the USAEC; the third deals with the contractors. The provisions of the Atomic Energy Act applicable to health and safety are discussed in relation to nuclear criticality safety. The use of United States Atomic Energy Commission manual chapters and Federal regulations is described. The functions of the USAEC Headquarters' offices and the operations offices are briefly outlined. Comments regarding the USAEC's inspection, auditing and appraisal programmes are included. Also briefly mentioned are the basic qualifications which must be met to become a contractor to possess and process or use fissionable materials. On the plant, factory or facility level the duties and responsibilities of industrial management are briefly outlined. The fundamental standards and their origin, together with the principal documents and guides are mentioned. The chief methods of control used by contractors operating large USAEC facilities and plants are described and compared. These include diagrams of how a typical nuclear criticality safety problem is handled from inception, design, construction and finally plant operation. Also included is a brief discussion of the contractors' methods of assuring strict employee compliance with the operating rules and limits. (author)

Clinical evaluation of music perception, appraisal and experience in cochlear implant users

Science.gov (United States)

Drennan, Ward. R.; Oleson, Jacob J.; Gfeller, Kate; Crosson, Jillian; Driscoll, Virginia D.; Won, Jong Ho; Anderson, Elizabeth S.; Rubinstein, Jay T.

2014-01-01

Objectives The objectives were to evaluate the relationships among music perception, appraisal, and experience in cochlear implant users in multiple clinical settings and to examine the viability of two assessments designed for clinical use. Design Background questionnaires (IMBQ) were administered by audiologists in 14 clinics in the United States and Canada. The CAMP included tests of pitch-direction discrimination, and melody and timbre recognition. The IMBQ queried users on prior musical involvement, music listening habits pre and post implant, and music appraisals. Study sample One-hundred forty-five users of Advanced Bionics and Cochlear Ltd cochlear implants. Results Performance on pitch direction discrimination, melody recognition, and timbre recognition tests were consistent with previous studies with smaller cohorts, as well as with more extensive protocols conducted in other centers. Relationships between perceptual accuracy and music enjoyment were weak, suggesting that perception and appraisal are relatively independent for CI users. Conclusions Perceptual abilities as measured by the CAMP had little to no relationship with music appraisals and little relationship with musical experience. The CAMP and IMBQ are feasible for routine clinical use, providing results consistent with previous thorough laboratory-based investigations. PMID:25177899

Association between elevated pre-operative glycosylated hemoglobin and post-operative infections after non-emergent surgery

OpenAIRE

Blankush, Joseph M.; Leitman, I. Michael; Soleiman, Aron; Tran, Trung

2016-01-01

Background: A chronic state of impaired glucose metabolism affects multiple components of the immune system, possibly leading to an increased incidence of post-operative infections. Such infections increase morbidity, length of stay, and overall cost. This study evaluates the correlation between elevated pre-operative glycosylated hemoglobin (HbA1c) and post-operative infections. Study design: Adult patients undergoing non-emergent procedures across all surgical subspecialties from January...

The development of NPP operational safety training courses

International Nuclear Information System (INIS)

Lee, Chang Kun; Lee, Duk Sun; Lee, Byung Sun; Lee, Won Koo; Juhn, Heng Run; Moon, Byung Soo; Cho, Min Sik; Lee, Han Young; Moon, Hak Won; Seo, Yeon Ho

1987-12-01

The objective of the project is to develop a training course text for the betterment of reactor operation and assurance of its safety in general by providing training materials of the advanced compact nuclear simulator which will become operation in September 1988. Main scope and contents of the project are as follows: - compilation of basic data related to simulator operation and maintenance as well as the comparative analysis with respect to simulator materials in foreign countries - method of training by simulator - review the training status by simulator in foreign countries - development of training course in the field of reactor safety It is expected that the results will be reflected to the actual training and retraining of the reactor operating crew so as to improve and update their capabilities in training fashion. (Author)

Safety related experience in FFTF startup and operation

International Nuclear Information System (INIS)

Peterson, R.E.; Halverson, T.G.; Daughtry, J.W.

1982-06-01

The Fast Flux Test Facility (FFTF) is a 400 MW(t) sodium cooled fast reactor operating at the Hanford Engineering Development Laboratory, Richland, Washington, to conduct fuels and materials testing in support of the US LMFBR program. Startup and initial power ascension testing of the facility involved a comprehensive series of readiness reviews and acceptance tests, many of which relate to the inherent safety of the plant. Included are physics measurements, natural circulation, integrated containment leakage, shielding effectiveness, fuel failure detection, and plant protection system tests. Described are the measurements taken to confirm the design safety margins upon which the operating authorization of the plant was based. These measurements demonstrate that large margins of safety are available in the FFTF design

Integrated model of port oil piping transportation system safety including operating environment threats

Directory of Open Access Journals (Sweden)

Kołowrocki Krzysztof

2017-06-01

Full Text Available The paper presents an integrated general model of complex technical system, linking its multistate safety model and the model of its operation process including operating environment threats and considering variable at different operation states its safety structures and its components safety parameters. Under the assumption that the system has exponential safety function, the safety characteristics of the port oil piping transportation system are determined.

Integrated model of port oil piping transportation system safety including operating environment threats

OpenAIRE

Kołowrocki, Krzysztof; Kuligowska, Ewa; Soszyńska-Budny, Joanna

2017-01-01

The paper presents an integrated general model of complex technical system, linking its multistate safety model and the model of its operation process including operating environment threats and considering variable at different operation states its safety structures and its components safety parameters. Under the assumption that the system has exponential safety function, the safety characteristics of the port oil piping transportation system are determined.

OPERATIONAL RESTRICTIONS FOR REDUCING NOISE AND THE SAFETY OF AIR OPERATIONS

Directory of Open Access Journals (Sweden)

Anna KWASIBORSKA

2017-03-01

Full Text Available Many European airports are located in close proximity to residential or protected areas. Aircraft noise emissions caused by the landing and taking off of aircraft are a big problem in these areas. From an operational point of view, the method for reducing noise is to reduce traffic volume or change its organization, especially during the night. Some procedures and tools have been developed to support air traffic management in the implementation of operational constraints necessary to maintain noise at an acceptable level. The objective of this paper is to analyse the effectiveness of these tools. For this purpose, we have analysed existing methods of operational noise reduction, taking into account their influence on the structure, smoothness, punctuality and, especially, the safety of air traffic. As a result, existing risks have been identified, while methods have been proposed to combine two important air traffic service tasks: ensuring safety, while taking into account the environmental constraints, especially in relation to the acoustic climate.

Safety of oral tenofovir disoproxil fumarate-based pre-exposure prophylaxis for HIV prevention.

Science.gov (United States)

Mugwanya, Kenneth K; Baeten, Jared M

2016-01-01

Tenofovir disoproxil fumarate (TDF)-based pre-exposure prophylaxis is a novel HIV prevention strategy for individuals at increased sexual risk for HIV infection. For any biomedical prevention intervention, the bar for tolerating adverse effects in healthy persons is high compared to therapeutic interventions. We provide a concise summary of the clinical safety of TDF-based pre-exposure prophylaxis with focus on TDF-related effects on tolerability, kidney function, bone density, HIV resistance, sexual and reproductive health. The evidence base for this review is derived from a literature search of both randomized and observational studies evaluating efficacy and safety of TDF-based PrEP, TDF alone or in combination with emtricitabine, identified from PUBMED and EMBASE electronic databases, clinicaltrials.gov and major HIV conferences. TDF-based pre-exposure prophylaxis is a potent intervention against HIV acquisition when taken which is generally safe and well tolerated. The risk of the small, non-progressive, and reversible decline in glomerular filtration rate and bone mineral density as well as the potential selection for drug resistance associated with PrEP are outweighed, at the population level and broadly for individuals, by PrEP's substantial reduction in the risk of HIV infection.

Safety of research reactors (Design and Operation)

International Nuclear Information System (INIS)

Dirar, H. M.

2012-06-01

The primary objective of this thesis is to conduct a comprehensive up-to-date literature review on the current status of safety of research reactor both in design and operation providing the future trends in safety of research reactors. Data and technical information of variety selected historical research reactors were thoroughly reviewed and evaluated, furthermore illustrations of the material of fuel, control rods, shielding, moderators and coolants used were discussed. Insight study of some historical research reactors was carried with considering sample cases such as Chicago Pile-1, F-1 reactor, Chalk River Laboratories,. The National Research Experimental Reactor and others. The current status of research reactors and their geographical distribution, reactor category and utilization is also covered. Examples of some recent advanced reactors were studied like safety barriers of HANARO of Korea including safety doors of the hall and building entrance and finger print identification which prevent the reactor from sabotage. On the basis of the results of this research, it is apparent that a high quality of safety of nuclear reactors can be attained by achieving enough robust construction, designing components of high levels of efficiency, replacing the compounds of the reactor in order to avoid corrosion and degradation with age, coupled with experienced scientists and technical staffs to operate nuclear research facilities.(Author)

Enhancing Safety at Airline Operations Control Centre

Directory of Open Access Journals (Sweden)

Lukáš Řasa

2015-04-01

Full Text Available In recent years a new term of Safety Management System (SMS has been introduced into aviation legislation. This system is being adopted by airline operators. One of the groundbased actors of everyday operations is Operations Control Centre (OCC. The goal of this article has been to identify and assess risks and dangers which occur at OCC and create a template for OCC implementation into SMS.

Joint operating agreements - health and safety and employment issues

International Nuclear Information System (INIS)

Molnar, L.F.

1999-01-01

The extent of non-operator exposure to health and safety and other employment liability is considered. Under the terms of the Canadian Association of Petroleum Landman agreements, the designated operator is the sole employer for joint operations. By these terms, the placement of responsibility for employees involved in a joint operation appears clear. It is to rest with the operator alone. As such, one would expect that the non-operator would be free from liabilities arising out of the employment relations of a project. It has been held, in cases of interrelated companies, that an individual can be an employee of more than one company at the same time. Alberta's Occupational Health and Safety Act, as well as the similar Acts in other provinces, impose a hierarchy of duties and obligations not only on employers but also upon contractors, suppliers and workers to ensure that safety is secured. Relevant definitions in the Act state this. An employer of an employee is vicariously liable for torts committed by the employee in the course of his employment. The questions are asked of what happens if a non-operator lends an employee to the operator and the employee tortiously injures a third party, and if the temporary employer, the operator, becomes the employer in the event of vicarious liability. 20 refs

Mobile Phone Network Operators' Actions on RF Safety (invited paper)

International Nuclear Information System (INIS)

Causebrook, J.H.

1999-01-01

The current and possible future global penetration of mobile phone usage is given. Health and safety aspects relate to both the statutory requirements for the operation of their networks and the public perception of risks in using services provided by the operators. The coordination of this work nationally through trade associations is mentioned. GSM is the predominant standard used for the provision of global mobile phone services. The GSM MoU Association is introduced as the operators' coordination body worldwide for dealing with radio frequency (RF) health and safety issues through its sub-group, EBRC. The scope of the EBRC group is presented with the considerations used to determine if external research should be supported by the GSM MoU Association. A personal view is provided on the present quality of worldwide research on RF health and safety and some consideration is given as to what constitutes 'good' research. The mobile phone network operators' involvement in the science and application of epidemiological research is considered. Consideration is given to introducing risk/benefit analysis into the debate on the health and safety of mobile phone usage. The media presentation of the results of scientific work on this topic often leads to a falsely negative public perception of the perceived risks. This is made worse when such perceptions are used for the purposes of objecting to the deployment of network infrastructure. The operators' approach to RF health and safety procedures is outlined, with a clarification of the distinctions between near-field and far-field methodologies for the calculation of physical exclusion zones. It is concluded that the mobile phone operators are part of an industry which is safe and who work to ensure that their operations are seen to be safe in the context of the best available worldwide scientific knowledge and safety guidelines. (author)

SECOT-GEDOS consensus on pre-surgical pain management in knee and hip arthrosis.

Science.gov (United States)

Ruiz Ibán, M A; Maculé, F; Torner, P; Gil Garay, E; Oteo-Álvaro, A; López Millán, J M; Díaz Heredia, J; Loza, E

2015-01-01

To develop recommendations, based on best evidence and experience, on pain management in patients undertaking total knee or hip replacement. Nominal group methodology was followed. A group of experts was selected (5 orthopedics, 1 anesthesiologist), who defined the scope, users, topics, preliminary recommendations, and 3 systematic reviews: efficacy and safety of pre-surgical analgesia regarding to post-surgical pain, efficacy and safety of pre-emptive analgesia and pre-operative factors of post-operative pain. The level of evidence and grade of recommendation was established using the Oxford Centre for Evidence Based Medicine, and the level of agreement with the Delphi technique (2 rounds). The Delphi was extended to 39 orthopedics and anesthesiologists. The whole document was reviewed by all the experts. A total of 21 recommendations were produced. They include specific pharmacological treatment, as well as the evaluation and monitoring of patients on this treatment, and post-operative pre-emptive treatment. Agreement above 70% was reached in 19 recommendations. In patients undergoing total knee or hip replacement, a proper evaluation, follow-up, pharmacological and non-pharmacological treatment of predictors of poor surgical outcomes should be performed, especially those related to pre-operative pain. This can improve post-operative pain and surgery outcomes. Copyright © 2014 SECOT. Published by Elsevier Espana. All rights reserved.

Pre-operative assessment of patients undergoing endoscopic, transnasal, transsphenoidal pituitary surgery.

Science.gov (United States)

Lubbe, D; Semple, P

2008-06-01

To demonstrate the importance of pre-operative ear, nose and throat assessment in patients undergoing endoscopic, transsphenoidal surgery for pituitary tumours. Literature pertaining to the pre-operative otorhinolaryngological assessment and management of patients undergoing endoscopic anterior skull base surgery is sparse. We describe two cases from our series of 59 patients undergoing endoscopic pituitary surgery. The first case involved a young male patient with a large pituitary macroadenoma. His main complaint was visual impairment. He had no previous history of sinonasal pathology and did not complain of any nasal symptoms during the pre-operative neurosurgical assessment. At the time of surgery, a purulent nasal discharge was seen emanating from both middle meati. Surgery was abandoned due to the risk of post-operative meningitis, and postponed until the patient's chronic rhinosinusitis was optimally managed. The second patient was a 47-year-old woman with a large pituitary macroadenoma, who presented to the neurosurgical department with a main complaint of diplopia. She too gave no history of previous nasal problems, and she underwent uneventful surgery using the endoscopic, transnasal approach. Two weeks after surgery, she presented to the emergency unit with severe epistaxis. A previous diagnosis of hereditary haemorrhagic telangiectasia was discovered, and further surgical and medical intervention was required before the epistaxis was finally controlled. Pre-operative otorhinolaryngological assessment is essential prior to endoscopic pituitary or anterior skull base surgery. A thorough otorhinolaryngological history will determine whether any co-morbid diseases exist which could affect the surgical field. Nasal anatomy can be assessed via nasal endoscopy and sinusitis excluded. Computed tomography imaging is a valuable aid to decisions regarding additional procedures needed to optimise access to the pituitary fossa.

Process hazards analysis (PrHA) program, bridging accident analyses and operational safety

International Nuclear Information System (INIS)

Richardson, J.A.; McKernan, S.A.; Vigil, M.J.

2003-01-01

Recently the Final Safety Analysis Report (FSAR) for the Plutonium Facility at Los Alamos National Laboratory, Technical Area 55 (TA-55) was revised and submitted to the US. Department of Energy (DOE). As a part of this effort, over seventy Process Hazards Analyses (PrHAs) were written and/or revised over the six years prior to the FSAR revision. TA-55 is a research, development, and production nuclear facility that primarily supports US. defense and space programs. Nuclear fuels and material research; material recovery, refining and analyses; and the casting, machining and fabrication of plutonium components are some of the activities conducted at TA-35. These operations involve a wide variety of industrial, chemical and nuclear hazards. Operational personnel along with safety analysts work as a team to prepare the PrHA. PrHAs describe the process; identi fy the hazards; and analyze hazards including determining hazard scenarios, their likelihood, and consequences. In addition, the interaction of the process to facility systems, structures and operational specific protective features are part of the PrHA. This information is rolled-up to determine bounding accidents and mitigating systems and structures. Further detailed accident analysis is performed for the bounding accidents and included in the FSAR. The FSAR is part of the Documented Safety Analysis (DSA) that defines the safety envelope for all facility operations in order to protect the worker, the public, and the environment. The DSA is in compliance with the US. Code of Federal Regulations, 10 CFR 830, Nuclear Safety Management and is approved by DOE. The DSA sets forth the bounding conditions necessary for the safe operation for the facility and is essentially a 'license to operate.' Safely of day-to-day operations is based on Hazard Control Plans (HCPs). Hazards are initially identified in the PrI-IA for the specific operation and act as input to the HCP. Specific protective features important to worker

Evaluation of operating experience for early recognition of deteriorating safety performance

International Nuclear Information System (INIS)

Beckmerhagen, I.A.; Berg, H.P.

2004-01-01

One of the most difficult challenges facing nuclear power plants is to recognize the early signs of degrading safety performance before regulatory requirements are imposed or serious incidents or accidents occur. Today, the nuclear industry is striving for collecting more information on occurrences that could improve the operational safety performance. To achieve this, the reporting threshold has been lowered from incidents to anomalies with minor or no impact to safety. Industry experience (also outside nuclear industry) has shown that these are typical issues which should be considered when looking for such early warning signs. Therefore, it is important that nuclear power plant operators have the capability to trend, analyse and recognize early warning signs of deteriorating performance. It is necessary that plant operators are sensitive to these warning signs which may not be immediately evident. Reviewing operating experience is one of the main tasks for plant operators in their daily activities. Therefore, self assessment should be at the centre of any operational safety performance programme. One way of applying a self assessment program is through the following four basic elements: operational data, events, safety basis, and related experience. This approach will be described in the paper in more details. (authors)

International conference on the operational safety performance in nuclear installations. Contributed papers

International Nuclear Information System (INIS)

2005-01-01

In 2001, the IAEA organized an 'International Conference on Topical Issues in Nuclear Safety'. The issues discussed during the conference were: (1) risk- informed decision-making; (2) influence of external factors on safety; (3) safety of fuel cycle facilities; (4) safety of research reactors; and (5) safety performance indicators. Senior nuclear safety decision makers reviewed the issues and formulated recommendations for future actions by national and international organizations. In 2004, the IAEA organized an 'International Conference on Topical Issues in Nuclear Safety' in Beijing China. The issues discussed during the conference were: (1) changing environment - coping with diversity and globalization; (2) operating experience - managing changes effectively; (3) regulatory management systems - adapting to changes in the environment; and (4) long term operations - maintaining safety margins while extending plant lifetimes. The results of this conference confirmed the importance of operators and regulators of nuclear facilities meeting periodically to share experience and opinion on emerging issues and future challenges of the nuclear industry. Substantial progress has been made, and continues to be made by Member States in enhancing the safety of nuclear installations worldwide. At the same time, more attention is being given to other areas of nuclear safety. The safety standards for research reactors are being updated and new standards are planned on the safety of other facilities in the nuclear fuel cycle. The Agency has taken a lead role in this effort and is receiving much support from its Member States to gain international consensus in these areas. The objective of the conference is to foster the exchange of information on operational safety performance and operating experience in nuclear installations, with the aim of consolidating an international consensus on: - the present status of these issues; - emerging issues with international implications

Context-aware system for pre-triggering irreversible vehicle safety actuators.

Science.gov (United States)

Böhmländer, Dennis; Dirndorfer, Tobias; Al-Bayatti, Ali H; Brandmeier, Thomas

2017-06-01

New vehicle safety systems have led to a steady improvement of road safety and a reduction in the risk of suffering a major injury in vehicle accidents. A huge leap forward in the development of new vehicle safety systems are actuators that have to be activated irreversibly shortly before a collision in order to mitigate accident consequences. The triggering decision has to be based on measurements of exteroceptive sensors currently used in driver assistance systems. This paper focuses on developing a novel context-aware system designed to detect potential collisions and to trigger safety actuators even before an accident occurs. In this context, the analysis examines the information that can be collected from exteroceptive sensors (pre-crash data) to predict a certain collision and its severity to decide whether a triggering is entitled or not. A five-layer context-aware architecture is presented, that is able to collect contextual information about the vehicle environment and the actual driving state using different sensors, to perform reasoning about potential collisions, and to trigger safety functions upon that information. Accident analysis is used in a data model to represent uncertain knowledge and to perform reasoning. A simulation concept based on real accident data is introduced to evaluate the presented system concept. Copyright © 2017 Elsevier Ltd. All rights reserved.

Experience gained in enhancing operational safety at ComEd's nuclear power plants

International Nuclear Information System (INIS)

Elias, D.

1997-01-01

The following aspects of experience gained in enhancing operational safety at Comed's nuclear power plants are discussed: nuclear safety policy; centralization/decentralization; typical nuclear operating organization; safety review boards; human performance enhancement; elements of effective nuclear oversight

Nuclear electric power safety, operation, and control aspects

CERN Document Server

Knowles, J Brian

2013-01-01

Assesses the engineering of renewable sources for commercial power generation and discusses the safety, operation, and control aspects of nuclear electric power From an expert who advised the European Commission and UK government in the aftermath of Three Mile Island and Chernobyl comes a book that contains experienced engineering assessments of the options for replacing the existing, aged, fossil-fired power stations with renewable, gas-fired, or nuclear plants. From geothermal, solar, and wind to tidal and hydro generation, Nuclear Electric Power: Safety, Operation, and Control Aspects ass

Operational safety analysis status of Novi Han repository

International Nuclear Information System (INIS)

Boiadjiev, A.

2000-01-01

This article presents the status of the safety studies and activities related to Novi Han repository. The case of this facility is such that no clear boundary exists between post-closure safety assessment and operational safety assessment. The major findings of these activities are given. The Safety Analysis Report (SAR) for Novi Han repository is developed by Risk Engineering Ltd. under a contract with the Committee on the Use of Atomic Energy for Peaceful Purposes. The general structure and main conclusions and recommendations of the SAR are presented. (author)

Effect of communication on the reliability of nuclear power plant control room operations - pre study

International Nuclear Information System (INIS)

Kettunen, Jari; Pyy, Pekka

1999-01-01

The objective of the study presented in this paper is to investigate communication practices and their impact on human reliability and plant safety in a nuclear power plant environment. The study aims at developing a general systems approach towards the issue. The ultimate goal of the study is to contribute to the development of probabilistic safety assessment methodologies in the area of communications and crew co-operation. This paper outlines the results of the pre-study. The study is based on the use and further development of different modelling techniques and the application of generic systems engineering as well as crew resource management (CRM) principles. The results so far include a concise literature review on communication and crew performance, a presentation of some potential theoretical concepts and approaches for studying communication in relation to organisational reliability, causal failure sequences and human failures mechanisms, and an introduction of a General Communications Model (GCM) that is presented as a promising approach for studying the reliability and adequacy of communication transactions. Finally, some observations and recommendation concerning next phases of the study are made (author) (ml)

Safety margins of operating reactors. Analysis of uncertainties and implications for decision making

International Nuclear Information System (INIS)

2003-01-01

Maintaining safety in the design and operation of nuclear power plants (NPPs) is a very important task under the conditions of a challenging environment, affected by the deregulated electricity market and implementation of risk informed regulations. In Member States, advanced computer codes are widely used as safety analysis tools in the framework of licensing of new NPP projects, safety upgrading programmes of existing NPPs, periodic safety reviews, renewal of operating licences, use of the safety margins for reactor power uprating, better utilization of nuclear fuel and higher operational flexibility, for justification of lifetime extensions, development of new emergency operating procedures, analysis of operational events, and development of accident management programmes. The issue of inadequate quality of safety analysis is becoming important due to a general tendency to use advanced tools for better establishment and utilization of safety margins, while the existence of such margins assure that NPPs operate safely in all modes of operation and at all times. The most important safety margins relate to physical barriers against release of radioactive material, such as fuel matrix and fuel cladding, reactor coolant system boundary, and the containment. Typically, safety margins are determined with use of computational tools for safety analysis. Advanced best estimate computer codes are suggested e.g. in the IAEA Safety Guide on Safety Assessment and Verification for Nuclear Power Plants to be used for current safety analysis. Such computer codes require their careful application to avoid unjustified reduction in robustness of the reactor safety. The issue of uncertainties in safety analyses and their impact on evaluation of safety margins is addressed in a number of IAEA guidance documents, in particular in the Safety Report on Accident Analysis for Nuclear Power Plants. It is also discussed in various technical meetings and workshops devoted to this area. The

Research on Integration of NPP Operational Safety Management Performance Systems

International Nuclear Information System (INIS)

Chi, Miao; Shi, Liping

2014-01-01

The operational safety management of Nuclear Power Plants demands systematic planning and integrated control. NPPs are following the well-developed safety indicator systems proposed by IAEA Operational Safety Performance Indicator Programme, NRC Reactor Oversight Process or the other institutions. Integration of the systems is proposed to benefiting from the advantages of both systems and avoiding improper application into the real world. The authors analyzed the possibility and necessity for system integration, and propose an indicator system integrating method

Health systems guidance appraisal--a critical interpretive synthesis.

Science.gov (United States)

Ako-Arrey, Denis E; Brouwers, Melissa C; Lavis, John N; Giacomini, Mita K

2016-01-22

Health systems guidance (HSG) are systematically developed statements that assist with decisions about options for addressing health systems challenges, including related changes in health systems arrangements. However, the development, appraisal, and reporting of HSG poses unique conceptual and methodological challenges related to the varied types of evidence that are relevant, the complexity of health systems, and the pre-eminence of contextual factors. To address this gap, we are conducting a program of research that aims to create a tool to support the appraisal of HSG and further enhance HSG development and reporting. The focus of this paper was to conduct a knowledge synthesis of the published and grey literatures to determine quality criteria (concepts) relevant for this process. We applied a critical interpretive synthesis (CIS) approach to knowledge synthesis that enabled an iterative, flexible, and dynamic analysis of diverse bodies of literature in order to generate a candidate list of concepts that will constitute the foundational components of the HSG tool. Using our review questions as compasses, we were able to guide the search strategy to look for papers based on their potential relevance to HSG appraisal, development, and reporting. The search strategy included various electronic databases and sources, subject-specific journals, conference abstracts, research reports, book chapters, unpublished data, dissertations, and policy documents. Screening the papers and data extraction was completed independently and in duplicate, and a narrative approach to data synthesis was executed. We identified 43 papers that met eligibility criteria. No existing review was found on this topic, and no HSG appraisal tool was identified. Over one third of the authors implicitly or explicitly identified the need for a high-quality tool aimed to systematically evaluate HSG and contribute to its development/reporting. We identified 30 concepts that may be relevant to the

Improvement of safety approach for accident during operation of LILW disposal facility: Application for operational safety assessment of the near-surface LILW disposal facility in Korea

Energy Technology Data Exchange (ETDEWEB)

Kim, Hyun Joo; Kim, Min Seong; Park, Jin Beak [Korea Radioactive Waste Agency, Daejeon (Korea, Republic of)

2017-06-15

To evaluate radiological impact from the operation of a low- and intermediate-level radioactive waste disposal facility, a logical presentation and explanation of expected accidental scenarios is essential to the stakeholders of the disposal facility. The logical assessment platform and procedure, including analysis of the safety function of disposal components, operational hazard analysis, operational risk analysis, and preparedness of remedial measures for operational safety, are improved in this study. In the operational risk analysis, both design measures and management measures are suggested to make it possible to connect among design, operation, and safety assessment within the same assessment platform. For the preparedness of logical assessment procedure, classifcation logic of an operational accident is suggested based on the probability of occurrence and consequences of assessment results. The improved assessment platform and procedure are applied to an operational accident analysis of the Korean low- and intermediate-level radioactive waste disposal facility and partly presented in this paper.

Improvement of safety approach for accident during operation of LILW disposal facility: Application for operational safety assessment of the near-surface LILW disposal facility in Korea

International Nuclear Information System (INIS)

Kim, Hyun Joo; Kim, Min Seong; Park, Jin Beak

2017-01-01

To evaluate radiological impact from the operation of a low- and intermediate-level radioactive waste disposal facility, a logical presentation and explanation of expected accidental scenarios is essential to the stakeholders of the disposal facility. The logical assessment platform and procedure, including analysis of the safety function of disposal components, operational hazard analysis, operational risk analysis, and preparedness of remedial measures for operational safety, are improved in this study. In the operational risk analysis, both design measures and management measures are suggested to make it possible to connect among design, operation, and safety assessment within the same assessment platform. For the preparedness of logical assessment procedure, classifcation logic of an operational accident is suggested based on the probability of occurrence and consequences of assessment results. The improved assessment platform and procedure are applied to an operational accident analysis of the Korean low- and intermediate-level radioactive waste disposal facility and partly presented in this paper

Safety analysis of the post-operational phase

International Nuclear Information System (INIS)

Berg, H.P.; Ehrlich, D.

1991-01-01

The safety analysis of normal operation covers an analytical study of the system parts ultimate repository - waste forms of the ultimate repository system under normal and accidental operation. On that basis a requirement concept has been developed which entails reactions on planning and design of the repository, and requirements of waste products, packagings and permissible activities. The procedure for the operational phase is explained giving the Konrad repository project as an example. (DG) [de

Small nuclear reactor safety design requirements for autonomous operation

International Nuclear Information System (INIS)

Kozier, K.S.; Kupca, S.

1997-01-01

Small nuclear power reactors offer compelling safety advantages in terms of the limited consequences that can arise from major accident events and the enhanced ability to use reliable, passive means to eliminate their occurrence by design. Accordingly, for some small reactor designs featuring a high degree of safety autonomy, it may be-possible to delineate a ''safety envelope'' for a given set of reactor circumstances within which safe reactor operation can be guaranteed without outside intervention for time periods of practical significance (i.e., days or weeks). The capability to operate a small reactor without the need for highly skilled technical staff permanently present, but with continuous remote monitoring, would aid the economic case for small reactors, simplify their use in remote regions and enhance safety by limiting the potential for accidents initiated by inappropriate operator action. This paper considers some of the technical design options and issues associated with the use of small power reactors in an autonomous mode for limited periods. The focus is on systems that are suitable for a variety of applications, producing steam for electricity generation, district heating, water desalination and/or marine propulsion. Near-term prospects at low power levels favour the use of pressurized, light-water-cooled reactor designs, among which those having an integral core arrangement appear to offer cost and passive-safety advantages. Small integral pressurized water reactors have been studied in many countries, including the test operation of prototype systems. (author)

Safety management of a complex R and D ground operating system

Science.gov (United States)

Connors, J. F.; Maurer, R. A.

1975-01-01

A perspective on safety program management was developed for a complex R&D operating system, such as the NASA-Lewis Research Center. Using a systems approach, hazardous operations are subjected to third-party reviews by designated-area safety committees and are maintained under safety permit controls. To insure personnel alertness, emergency containment forces and employees are trained in dry-run emergency simulation exercises. The keys to real safety effectiveness are top management support and visibility of residual risks.

Operator reliability study for Probabilistic Safety Analysis of an operating research reactor

International Nuclear Information System (INIS)

Mohamed, F.; Hassan, A.; Yahaya, R.; Rahman, I.; Maskin, M.; Praktom, P.; Charlie, F.

2015-01-01

Highlights: • Human Reliability Analysis (HRA) for Level 1 Probabilistic Safety Analysis (PSA) is performed on research nuclear reactor. • Implemented qualitative HRA framework is addressed. • Human Failure Events of significant impact to the reactor safety are derived. - Abstract: A Level 1 Probabilistic Safety Analysis (PSA) for the TRIGA Mark II research reactor of Malaysian Nuclear Agency has been developed to evaluate the potential risk in its operation. In conjunction to this PSA development, Human Reliability Analysis (HRA) is performed in order to determine human contribution to the risk. The aim of this study is to qualitatively analyze human actions (HAs) involved in the operation of this reactor according to the qualitative part of the HRA framework for PSA which is namely the identification, qualitative screening and modeling of HAs. By performing this framework, Human Failure Events (HFEs) of significant impact to the reactor safety are systematically analyzed and incorporated into the PSA structure. A part of the findings in this study will become the input for the subsequent quantitative part of the HRA framework, i.e. the Human Error Probability (HEP) quantification

Relation between water chemistry and operational safety

International Nuclear Information System (INIS)

Oliveira, M.F. de.

1991-01-01

This report describes the relation between chemistry/radiochemistry and operational safety, the technics bases for chemical and radiochemical parameters and an analysis of the Annual Report of Angra I Operation and OSRAT Mission report to 1989 in this area too. Furthermore it contains the transcription of the technical Specifications related to the chemistry and radiochemistry for Angra I. (author)

Safety relevant failure mechanisms in the post-operational phase

International Nuclear Information System (INIS)

Mayer, Gerhard; Stiller, Jan Christopher; Roemer, Sarah

2017-03-01

When the 13"t"h amendment of the Atomic Energy Act came into force, eight Germ an nuclear power plant units had their power operating licences revoked and are now in the so-called post operation phase. Of the remaining nuclear power plants, one have by now also entered the post operation phase, with those left in operation bound for entering this phase sometime between now and the end of 2022. Therefore, failure mechanisms that are particularly relevant for post operation were to be identified and described in the frame of the present project. To do so, three major steps were taken: Firstly, recent national and international pertinent literature was evaluated to obtain indications of failure mechanisms in the post operation phase. It turned out that most of the national and international literature deals with the general procedure of the transition from power operation to decommissioning and dismantling. However, there were also some documents providing detailed indications of possible failure mechanisms in post operation. This includes e.g. the release of radioactive materials caused by the drop of containers, chemical impacts on systems important to safety in connection with decontamination work, and corrosion in connection with the storage of the core in the spent fuel pool, with the latter leading to the jamming of the fuel assemblies in the storage racks and a possible reduction of coolant circulation. In a second step, three safety analyses of pressurised water reactors prepared by the respective plant operators were evaluated to identify failure mechanisms based on systems engineering. The failure mechanisms that were found here include e.g. faults in the boric acid concentration of the reactor coolant, damage to the equipment airlock upon the unloading of Castor casks, leakages in connection with primary system decontamination, and the drop of packages holding radioactive residual materials or waste with subsequent mobilisation of radioactive aerosols

Appraising the value of independent EIA follow-up verifiers

Energy Technology Data Exchange (ETDEWEB)

Wessels, Jan-Albert, E-mail: janalbert.wessels@nwu.ac.za [School of Geo and Spatial Sciences, Department of Geography and Environmental Management, North-West University, C/O Hoffman and Borcherd Street, Potchefstroom, 2520 (South Africa); Retief, Francois, E-mail: francois.retief@nwu.ac.za [School of Geo and Spatial Sciences, Department of Geography and Environmental Management, North-West University, C/O Hoffman and Borcherd Street, Potchefstroom, 2520 (South Africa); Morrison-Saunders, Angus, E-mail: A.Morrison-Saunders@murdoch.edu.au [School of Geo and Spatial Sciences, Department of Geography and Environmental Management, North-West University, C/O Hoffman and Borcherd Street, Potchefstroom, 2520 (South Africa); Environmental Assessment, School of Environmental Science, Murdoch University, Australia. (Australia)

2015-01-15

Independent Environmental Impact Assessment (EIA) follow-up verifiers such as monitoring agencies, checkers, supervisors and control officers are active on various construction sites across the world. There are, however, differing views on the value that these verifiers add and very limited learning in EIA has been drawn from independent verifiers. This paper aims to appraise how and to what extent independent EIA follow-up verifiers add value in major construction projects in the developing country context of South Africa. A framework for appraising the role of independent verifiers was established and four South African case studies were examined through a mixture of site visits, project document analysis, and interviews. Appraisal results were documented in the performance areas of: planning, doing, checking, acting, public participating and integration with other programs. The results indicate that independent verifiers add most value to major construction projects when involved with screening EIA requirements of new projects, allocation of financial and human resources, checking legal compliance, influencing implementation, reporting conformance results, community and stakeholder engagement, integration with self-responsibility programs such as environmental management systems (EMS), and controlling records. It was apparent that verifiers could be more creatively utilized in pre-construction preparation, providing feedback of knowledge into assessment of new projects, giving input to the planning and design phase of projects, and performance evaluation. The study confirms the benefits of proponent and regulator follow-up, specifically in having independent verifiers that disclose information, facilitate discussion among stakeholders, are adaptable and proactive, aid in the integration of EIA with other programs, and instill trust in EIA enforcement by conformance evaluation. Overall, the study provides insight on how to harness the learning opportunities

Appraising the value of independent EIA follow-up verifiers

International Nuclear Information System (INIS)

Wessels, Jan-Albert; Retief, Francois; Morrison-Saunders, Angus

2015-01-01

Independent Environmental Impact Assessment (EIA) follow-up verifiers such as monitoring agencies, checkers, supervisors and control officers are active on various construction sites across the world. There are, however, differing views on the value that these verifiers add and very limited learning in EIA has been drawn from independent verifiers. This paper aims to appraise how and to what extent independent EIA follow-up verifiers add value in major construction projects in the developing country context of South Africa. A framework for appraising the role of independent verifiers was established and four South African case studies were examined through a mixture of site visits, project document analysis, and interviews. Appraisal results were documented in the performance areas of: planning, doing, checking, acting, public participating and integration with other programs. The results indicate that independent verifiers add most value to major construction projects when involved with screening EIA requirements of new projects, allocation of financial and human resources, checking legal compliance, influencing implementation, reporting conformance results, community and stakeholder engagement, integration with self-responsibility programs such as environmental management systems (EMS), and controlling records. It was apparent that verifiers could be more creatively utilized in pre-construction preparation, providing feedback of knowledge into assessment of new projects, giving input to the planning and design phase of projects, and performance evaluation. The study confirms the benefits of proponent and regulator follow-up, specifically in having independent verifiers that disclose information, facilitate discussion among stakeholders, are adaptable and proactive, aid in the integration of EIA with other programs, and instill trust in EIA enforcement by conformance evaluation. Overall, the study provides insight on how to harness the learning opportunities

Use of safety analysis results to support process operation

International Nuclear Information System (INIS)

Karvonen, I.; Heino, P.

1990-01-01

Safety and risk analysis carried out during the design phase of a process plant produces useful knowledge about the behavior and the disturbances of the system. This knowledge, however, often remains to the designer though it would be of benefit to the operators and supervisors of the process plant, too. In Technical Research Centre of Finland a project has been started to plan and construct a prototype of an information system to make use of the analysis knowledge during the operation phase. The project belongs to a Nordic KRM project (Knowledge Based Risk Management System). The information system is planned to base on safety and risk analysis carried out during the design phase and completed with operational experience. The safety analysis includes knowledge about potential disturbances, their causes and consequences in the form of Hazard and Operability Study, faut trees and/or event trees. During the operation disturbances can however, occur, which are not included in the safety analysis, or the causes or consequences of which have been incompletely identified. Thus the information system must also have an interface for the documentation of the operational knowledge missing from the analysis results. The main tasks off the system when supporting the management of a disturbance are to identify it (or the most important of the coexistent ones) from the stored knowledge and to present it in a proper form (for example as a deviation graph). The information system may also be used to transfer knowledge from one shift to another and to train process personnel

Human and organization factors: engineering operating safety into offshore structures

International Nuclear Information System (INIS)

Bea, Robert G.

1998-01-01

History indicates clearly that the safety of offshore structures is determined primarily by the humans and organizations responsible for these structures during their design, construction, operation, maintenance, and decommissioning. If the safety of offshore structures is to be preserved and improved, then attention of engineers should focus on to how to improve the reliability of the offshore structure 'system,' including the people that come into contact with the structure during its life-cycle. This article reviews and discusss concepts and engineering approaches that can be used in such efforts. Two specific human factor issues are addressed: (1) real-time management of safety during operations, and (2) development of a Safety Management Assessment System to help improve the safety of offshore structures

Safety and emergency preparedness considerations for geotechnical field operations

Energy Technology Data Exchange (ETDEWEB)

Wemple, R.P.

1989-04-01

The GEO Energy Technology Department at Sandia National Laboratories is involved in several remote-site drilling and/or experimental operations each year. In 1987, the Geothermal Research Division of the Department developed a general set of Safe Operating Procedures (SOPs) that could be applied to a variety of projects. This general set is supplemented by site-specific SOPs as needed. Effective field operations require: integration of safety and emergency preparedness planning with overall project planning, training of field personnel and inventorying of local emergency support resources, and, developing a clear line of responsibility and authority to enforce the safety requirements. Copies of SOPs used in recent operations are included as examples of working documents for the reader.

A histopathological effectiveness of pre-operative irradiation for biliary tract cancer

International Nuclear Information System (INIS)

Mizusaki, Kaoru

1993-01-01

There is almost no report on pre-operative irradiation therapy in biliary tract cancer. For the purpose of attaining improved operative results, pre-operative irradiation has so for been performed in our department. We experienced 106 cases of biliary tract cancer during the period from January 1982 to December 1990, including 30 cases treated by pre-operative irradiation. Among 30 cases, 20 cases, including 9 cases of gallbladder cancer and 11 cases of bile duct cancer, were resectable. Final histopathological findings were obtained in 8 cases of gallbladder cancer and 9 cases of bile duct cancer. The effectiveness of irradiation was evaluated according to the histopathological criteria proposed by Ohboshi and Shimosato in 1971. Four cases were Grade I, 2 cases were Grade IIA, and 2 cases were Grade IIB, and 1 case was Grade III of bile duct cancer. In both groups, no correlation was observed between the exposure doses and their effects. Although no correlation was noted between the degree of differentiation of tubular adenocarcinoma of microscopic pathological findings and the irradiation effects, 1 case of poorly differentiated tubular adenocarcinoma of the bile duct was evaluated as Grade III. Mucinous adenocarcinoma and papillary adenocarcinoma of the gallbladder were revealed to be Grade I. According to the main affected site of bile duct cancer, a good irradiation effect was obtained in patients with upper to middle bile duct cancer. The irradiation effect on the gallbladder and the bile duct wall was predominant on the mucous side but less effective on the serous side. From the histopathological findings, the effectiveness of pre-operative irradiation was suggested. These results suggested that the further clinical evaluation, such as rates of resection or prognostic outcome would be relevant. (author)

Joint road safety operations in tunnels and open roads

Science.gov (United States)

Adesiyun, Adewole; Avenoso, Antonio; Dionelis, Kallistratos; Cela, Liljana; Nicodème, Christophe; Goger, Thierry; Polidori, Carlo

2017-09-01

The objective of the ECOROADS project is to overcome the barrier established by the formal interpretation of the two Directives 2008/96/EC and 2004/54/EC, which in practice do not allow the same Road Safety Audits/Inspections to be performed inside tunnels. The projects aims at the establishment of a common enhanced approach to road infrastructure and tunnel safety management by using the concepts and criteria of the Directive 2008/96/CE on road infrastructure safety management and the results of related European Commission (EC) funded projects. ECOROADS has already implemented an analysis of national practices regarding Road Safety Inspections (RSI), two Workshops with the stakeholders, and an exchange of best practices between European tunnel experts and road safety professionals, which led to the definition of common agreed safety procedures. In the second phase of the project, different groups of experts and observers applied the above common procedures by inspecting five European road sections featuring both open roads and tunnels in Belgium, Albania, Germany, Serbia and Former Yugoslav Republic of Macedonia. This paper shows the feedback of the 5 joint safety operations and how they are being used for a set of - recommendations and guidelines for the application of the RSA and RSI concepts within the tunnel safety operations.

OSART Guidelines. 2015 Edition. Reference Report for IAEA Operational Safety Review Teams (OSARTs)

International Nuclear Information System (INIS)

2016-01-01

The IAEA works to provide a global nuclear safety and security framework for the protection of people and the environment from the effects of ionizing radiation, the minimization of the likelihood of accidents that could endanger life and property, and effective mitigation of the effects of any such events, should they occur. The strategic approach to achieving such a framework involves continual improvement in four areas: national and international safety infrastructures; the establishment and global acceptance of IAEA safety standards; an integrated approach to the provision for the application of the safety standards; and a global network of knowledge and experience. The IAEA Operational Safety Review Team (OSART) programme provides advice and assistance to Member States to enhance the safety of nuclear power plants during commissioning and operation. The OSART programme, initiated in 1982, is available to all Member States with nuclear power plants under commissioning or in operation. Conservative design, careful manufacture and sound construction are all prerequisites for the safe operation of nuclear power plants. However, the safety of the plant also depends ultimately on: sound management, policies, procedures, processes and practices; the capability and reliability of commissioning and operating personnel; comprehensive instructions; sound accident management and emergency preparedness; and adequate resources. Finally, a positive attitude and conscientiousness on the part of all staff in discharging their responsibilities is important to safety. The OSART programme is based on the safety standards applicable to nuclear power plants. IAEA safety standards reflect the consensus of Member States on nuclear safety matters. The reports of the International Nuclear Safety Group identify important current nuclear safety issues and also serve as references during an OSART review. The publication OSART Guidelines provides overall guidance on the conduct of OSART

First Contact: the intersection of demographics, knowledge, and appraisal of treatment at the initial infertility visit

Science.gov (United States)

CHILDRESS, Krista J.; LAWSON, Angela K.; GHANT, Marissa S.; MENDOZA, Gricelda; CARDOZO, Eden R.; CONFINO, Edmond; MARSH, Erica E.

2015-01-01

Objective To determine the impact of the initial infertility visit on treatment-related knowledge, patient anxiety, and appraisals of treatment. Study Design Prospective survey. Setting Academic medical center. Patients 234 English-speaking women, ages 18-50, attending their first infertility visit Intervention(s) Participants completed a survey assessing health literacy, knowledge, anxiety, and appraisals of the treatment process before and after their infertility visit. Main Outcome Measure(s) 1) Knowledge of infertility and treatment and, 2) Anxiety and appraisal scores. Results Most participants were white and earned >$100,000/year and had at least a college education. Baseline knowledge of reproductive anatomy, ART, and fertility factors was modest, but improved after the initial visit. Factors associated with higher knowledge included higher education and income, White or Asian ethnicity, and English as their primary language. Patient appraisals of treatment represented by the positive (Challenge) and negative (Threat and Loss) subscale scores on the Appraisal of Life Events (ALE) scale, changed from the pre-visit survey to the post-visit survey. Negative appraisals of treatment and anxiety scores decreased and positive appraisals of treatment increased after the initial visit. Lower knowledge was associated with higher positive appraisal scores lower health literacy was associated with higher anxiety and appraisal scores (positive and negative) post-visit. Black women had higher Challenge scores compared to White and Asian women. Hispanic women had higher anxiety scores than non-Hispanic women. Conclusions Infertility patients have modest baseline knowledge of fertility and infertility treatment. The initial infertility visit can improve this knowledge and decrease both negative appraisals of treatment and anxiety levels. Differences in knowledge and appraisal were seen across ethnic groups and other demographic variables. Physicians should individualize

Improvements in operational safety performance of the Magnox power stations

Energy Technology Data Exchange (ETDEWEB)

Marchese, C.J. [BNFL Magnox Generation, Berkeley (United Kingdom)

2000-10-01

In the 43 years since commencement of operation of Calder Hall, the first Magnox power station, there remain eight Magnox stations and 20 reactors still in operation, owned by BNFL Magnox Generation. This paper describes how the operational safety performance of these stations has significantly improved over the last ten years. This has been achieved against a background of commercial competition introduced by privatization and despite the fact that the Magnox base design belongs to the past. Finally, the company's future plans for continued improvements in operational safety performance are discussed. (author)

A reliability program approach to operational safety

International Nuclear Information System (INIS)

Mueller, C.J.; Bezella, W.A.

1985-01-01

A Reliability Program (RP) model based on proven reliability techniques is being formulated for potential application in the nuclear power industry. Methods employed under NASA and military direction, commercial airline and related FAA programs were surveyed and a review of current nuclear risk-dominant issues conducted. The need for a reliability approach to address dependent system failures, operating and emergency procedures and human performance, and develop a plant-specific performance data base for safety decision making is demonstrated. Current research has concentrated on developing a Reliability Program approach for the operating phase of a nuclear plant's lifecycle. The approach incorporates performance monitoring and evaluation activities with dedicated tasks that integrate these activities with operation, surveillance, and maintenance of the plant. The detection, root-cause evaluation and before-the-fact correction of incipient or actual systems failures as a mechanism for maintaining plant safety is a major objective of the Reliability Program. (orig./HP)

Uranium-mill appraisal program

International Nuclear Information System (INIS)

Everett, R.J.; Cain, C.L.

1982-08-01

The results of special team appraisals at NRC-licensed uranium mills in the period May to November 1981 are reported. Since the Three Mile Island accident, NRC management has instituted a program of special team appraisals of radiation protection programs at certain NRC-licensed facilities. These appraisals were designed to identify weaknesses and strengths in NRC-licensed programs, including those areas not covered by explicit regulatory requirements. The regulatory requirements related to occupational radiation protection and environmental monitoring at uranium mills have been extensively upgraded in the past few years. In addition, there was some NRC staff concern with respect to the effectiveness of NRC licensing and inspection programs. In response to this concern and to changes in mill requirements, the NRC staff recommended that team appraisals be conducted at mills to determine the adequacy of mill programs, the effectiveness of the new requirements, and mill management implementation of programs and requirements. This report describes the appraisal scope and methodology as well as summary findings and conclusions. Significant weaknesses identified during the mill appraisals are discussed as well as recommendations for improvements in uranium mill programs and mill licensing and inspection

76 FR 72306 - Federal Housing Administration (FHA) Appraiser Roster: Appraiser Qualifications for Placement on...

Science.gov (United States)

2011-11-23

... disciplinary action in any state in which the appraiser is certified; * * * * * (c) * * * (1) Appraisers subject to state disciplinary action. An appraiser whose state certification in any state has been revoked, suspended, or surrendered as a result of a state disciplinary action is automatically suspended from the...

Effective corrective actions to enhance operational safety of nuclear installations

International Nuclear Information System (INIS)

2005-07-01

The safe operation of nuclear power plants around the world and the prevention of incidents in these installations remain key concerns for the nuclear community. In this connection the feedback of operating experience plays a major role: every nuclear plant operator needs to have a system in place to identify and feed back the lessons learned from operating experience and to implement effective corrective actions to prevent safety events from reoccurring. An effective operating experience programme also includes a proactive approach that is aimed at preventing the first-time occurrence of safety events. In April 2003, the IAEA issued the PROSPER guidelines for nuclear installations to strengthen and enhance their own operating experience process and for self-assessment on the effectiveness of the feedback process. Subsequently, in the course of the Operational Safety Review Teams missions conducted by the IAEA that focused on the operational safety practices of nuclear power plants, the IAEA enhanced the review of the operating experience in nuclear power plants by implementing a new module that is derived from these guidelines. In order to highlight the effective implementation of the operating experience programme and to provide practical assistance in this area, the IAEA organized workshops and conferences to discuss recent trends in operating experience. The IAEA also performed assistance and review missions at plants and corporate organizations. The IAEA is further developing advice and assistance on operating experience feedback programmes and is reporting on good practices. The present publication is the outcome of two years of coordinated effort involving the participation of experts of nuclear organizations in several Member States. It provides information and good practices for successfully establishing an effective corrective actions programme. This publication forms part of a series that develops the principles set forth in these guidelines

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... motor carriers that applied to participate in the Agency's long-haul pilot program to test and... intent to proceed with the initiation of a United States- Mexico cross-border long-haul trucking pilot...

Behavioral determinants of mothers' safety measures to prevent injuries of pre-school children.

NARCIS (Netherlands)

Wortel, E.; Geus, G.H. de; Kok, G.

1995-01-01

Home-related injuries are a major threat to pre-school children in the western world. In this study the behavioral determinants of 18 parental safety measures were assessed. To select behavioral determinants, the Attitude-Social influence-Self-efficacy/barriers model was used with the inclusion of

IAEA Leads Operational Safety Mission to Muehleberg Nuclear Power Plant

International Nuclear Information System (INIS)

2012-01-01

Full text: An international team of nuclear safety experts led by the International Atomic Energy Agency today concluded a review of the safety practices at the Muehleberg Nuclear Power Plant (NPP) near Bern in Switzerland. The team noted a series of good practices and made recommendations and suggestions to reinforce them. The IAEA assembled the Operational Safety Review Team at the request of the Swiss government. The team, led by the IAEA's Division of Nuclear Installation Safety, performed an in-depth operational safety review from 8 to 25 October 2012. The team comprised experts from Belgium, the Czech Republic, Finland, Germany, Hungary, Slovakia, Sweden, the United Kingdom and the United States as well as experts from the IAEA. The team conducted an in-depth review of the aspects essential to the safe operation of the Muehleberg NPP. The conclusions of the review are based on the IAEA's Safety Standards and proven good international practices. The review covered the areas of Management, Organization and Administration; Training; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry, Emergency Planning and Preparedness, Severe Accident Management and Long-Term Operation. The OSART team made 10 recommendations and 11 suggestions related to areas where operations of Muehleberg NPP could be further improved, for example: - Plant management could improve the operating experience program and methods throughout the plant to ensure corrective actions are taken in a timely manner; - In the area of Long-Term Operation, the ageing management review for some systems and components is not complete and the environmental qualification of originally installed safety cables has not yet been revalidated for long-term operation; and - The plant provisions for the protection of persons on the site during an emergency with radioactive release can be improved to minimize health risks to plant personnel. The team also identified 10 good

An appraisal profile of nostalgia.

Science.gov (United States)

van Tilburg, Wijnand A P; Bruder, Martin; Wildschut, Tim; Sedikides, Constantine; Göritz, Anja S

2018-03-05

The authors aimed to (a) identify the cognitive appraisals underlying nostalgia and (b) compare nostalgia with other emotions in terms of its appraisal profile. In Study 1, participants (N = 1,125) generated narratives. Next, they reported the level of nostalgia and 31 other emotions that these narratives elicited. Subsequently, participants evaluated the narrative events on several cognitive appraisals. Events that elicited nostalgia were pleasant, involved an irretrievable loss, felt psychologically distant, and were unique-an appraisal profile that differed from all other emotions. In Study 2 (N = 1,261), the authors experimentally varied these appraisals in a vignette paradigm and measured anticipated nostalgia and 10 other emotions. Participants anticipated most nostalgia when events were pleasant, involved irretrievable loss, were distant, and were unique-a profile shared only with longing. In Study 3 (N = 994), the authors used a guided autobiographical recall procedure in which they manipulated appraisals and measured the resultant emotions. Corroborating Studies 1-2, nostalgia was most intense for events that were pleasant, irretrievably lost, temporally distant, and unique. This appraisal profile was not shared by other emotions. The findings delineate the distinguishing cognitive appraisal profile of nostalgia. Nostalgia occupies a special place in the pantheon of emotions. (PsycINFO Database Record (c) 2018 APA, all rights reserved).

The Radiation Safety Interlock System for Top-Up Mode Operation at NSRRC

CERN Document Server

Chen Chien Rong; Kao, Sheau-Ping; Liu, Joseph; Sheu, Rong-Jiun; Wang, Jau-Ping

2005-01-01

The radiation safety interlock systems of NSRRC have been operated for more than a decade. Some modification actions have been implemented in the past to perfect the safe operation. The machine and its interlock system were originally designed to operate at the decay mode. Recently some improvement programs to make the machine injection from original decay mode to top-up mode at NSRRC has initiated. For users at experimental area the radiation dose resulted from top-up re-fill injections where safety shutters of beam-lines are opened will dominate. In addition to radiation safety action plans such as upgrading the shielding, enlarging the exclusion zones and improving the injection efficiency, the interlock system for top-up operation is the most important to make sure that injection efficiency is acceptable. To ensure the personnel radiation safety during the top-up mode, the safety interlock upgrade and action plans will be implemented. This paper will summarize the original design logic of the safety inter...

Guidance for preparation of safety analysis reports for nonreactor facilities and operations

International Nuclear Information System (INIS)

1992-01-01

Department of Energy (DOE) Orders 5480.23, ''Nuclear Safety Analysis Reports,'' and 5481.1B, ''Safety Analysis and Review System'' require the preparation of appropriate safety analyses for each DOE operation and subsequent significant modifications including decommissioning, and independent review of each safety analysis. The purpose of this guide is to assist in the preparation and review of safety documentation for Oak Ridge Field Office (OR) nonreactor facilities and operation. Appendix A lists DOE Orders, NRC Regulatory Guides and other documents applicable to the preparation of safety analysis reports

Development of a Novel Nuclear Safety Culture Evaluation Method for an Operating Team Using Probabilistic Safety Analysis

Energy Technology Data Exchange (ETDEWEB)

Han, Sangmin; Lee, Seung Min; Seong, Poong Hyun [KAIST, Daejeon (Korea, Republic of)

2015-05-15

IAEA defined safety culture as follows: 'Safety Culture is that assembly of characteristics and attitudes in organizations and individuals which establishes that, as an overriding priority, nuclear plant safety issues receive the attention warranted by their significance'. Also, celebrated behavioral scientist, Cooper, defined safety culture as,'safety culture is that observable degree of effort by which all organizational members direct their attention and actions toward improving safety on a daily basis' with his internal psychological, situational, and behavioral context model. With these various definitions and criteria of safety culture, several safety culture assessment methods have been developed to improve and manage safety culture. To develop a new quantitative safety culture evaluation method for an operating team, we unified and redefined safety culture assessment items. Then we modeled a new safety culture evaluation by adopting level 1 PSA concept. Finally, we suggested the criteria to obtain nominal success probabilities of assessment items by using 'operational definition'. To validate the suggested evaluation method, we analyzed the collected audio-visual recording data collected from a full scope main control room simulator of a NPP in Korea.

Development of a Novel Nuclear Safety Culture Evaluation Method for an Operating Team Using Probabilistic Safety Analysis

International Nuclear Information System (INIS)

Han, Sangmin; Lee, Seung Min; Seong, Poong Hyun

2015-01-01

IAEA defined safety culture as follows: 'Safety Culture is that assembly of characteristics and attitudes in organizations and individuals which establishes that, as an overriding priority, nuclear plant safety issues receive the attention warranted by their significance'. Also, celebrated behavioral scientist, Cooper, defined safety culture as,'safety culture is that observable degree of effort by which all organizational members direct their attention and actions toward improving safety on a daily basis' with his internal psychological, situational, and behavioral context model. With these various definitions and criteria of safety culture, several safety culture assessment methods have been developed to improve and manage safety culture. To develop a new quantitative safety culture evaluation method for an operating team, we unified and redefined safety culture assessment items. Then we modeled a new safety culture evaluation by adopting level 1 PSA concept. Finally, we suggested the criteria to obtain nominal success probabilities of assessment items by using 'operational definition'. To validate the suggested evaluation method, we analyzed the collected audio-visual recording data collected from a full scope main control room simulator of a NPP in Korea

Current trends in codal requirements for safety in operation of nuclear power plants

International Nuclear Information System (INIS)

Srivasista, K.; Shah, Y.K.; Gupta, S.K.

2006-01-01

The Code of practice on safety in nuclear power plant operation states the requirements to be met during operation of a nuclear power plant for assuring safety. Among various stages of authorization, regulatory body issues authorization for operation of a nuclear power plant, monitors and enforces regulatory requirements. The responsible organization shall have overall responsibility and the plant management shall have the primary responsibility for ensuring safe and efficient operation of its nuclear power plants. A set of codal requirements covering technical and administrative aspects are mandatory for the plant management to implement to ensure that the nuclear power plant is operated in accordance with the design intent. Requirements on operating procedures and instructions establish operation and maintenance, inspection and testing of the plant in a planned and systematic way. The requirements on emergency preparedness programme establish with a reasonable assurance that, in the event of an emergency situation, appropriate measures can be taken to mitigate the consequences. Commissioning requirements verify performance criteria during commissioning to ensure that the design intent and QA requirements are met. Several modifications in systems important to safety required during operation of a nuclear power plant are regulated. However new operational codal requirements arising out of periodic safety review, operational experience feedback, life management, probabilistic safety assessment, physical security, safety convention and obligations and decommissioning are not covered in the present code of practice for safety in nuclear power plant operation. Codal provisions on 'Review by operating organization on aspects of design having implications on operability' are also required to be addressed. The merits in developing such a methodology include acceptance of the design by operating organization, ensuring maintainability, proper layout etc. in the new designs

Pre-operative use of anti-TNF-alpha agents and the risk of post-operative complications in patients with Crohn's disease--a nationwide cohort study

DEFF Research Database (Denmark)

Nørgård, Bente Mertz; Nielsen, J.; Qvist, N.

2013-01-01

BACKGROUND: A possible negative role of pre-operative use of antitumour necrosis factor-alpha (anti-TNF-alpha) agents on post-operative outcomes in Crohn's disease (CD) patients is still debated. AIM: To examine the impact of pre-operative anti-TNF-alpha agents on post-operative outcomes 30 and 6...

AEC controlled area safety program

Energy Technology Data Exchange (ETDEWEB)

Hendricks, D W [Nevada Operations Office, Atomic Energy Commission, Las Vegas, NV (United States)

1969-07-01

The detonation of underground nuclear explosives and the subsequent data recovery efforts require a comprehensive pre- and post-detonation safety program for workers within the controlled area. The general personnel monitoring and environmental surveillance program at the Nevada Test Site are presented. Some of the more unusual health-physics aspects involved in the operation of this program are also discussed. The application of experience gained at the Nevada Test Site is illustrated by description of the on-site operational and safety programs established for Project Gasbuggy. (author)

AEC controlled area safety program

International Nuclear Information System (INIS)

Hendricks, D.W.

1969-01-01

The detonation of underground nuclear explosives and the subsequent data recovery efforts require a comprehensive pre- and post-detonation safety program for workers within the controlled area. The general personnel monitoring and environmental surveillance program at the Nevada Test Site are presented. Some of the more unusual health-physics aspects involved in the operation of this program are also discussed. The application of experience gained at the Nevada Test Site is illustrated by description of the on-site operational and safety programs established for Project Gasbuggy. (author)

Operational safety review programmes for nuclear power plants. Guidelines for assessment

International Nuclear Information System (INIS)

2002-01-01

The IAEA has been offering the Operational Safety Review Team (OSART) programme to provide advice and assistance to Member States in enhancing the operational safety of nuclear power plants (NPPs). Simultaneously, the IAEA has encouraged self-assessment and review by Member States of their own nuclear power plants to continuously improve nuclear safety. Currently, some utilities have been implementing safety review programmes to independently review their own plants. Corporate or national operational safety review programmes may be compliance or performance based. Successful utilities have found that both techniques are necessary to provide assurance that (i) as a minimum the NPP meets specific corporate and legal requirements and (ii) management at the NPP is encouraged to pursue continuous improvement principles. These programmes can bring nuclear safety benefits to the plants and utilities. The IAEA has conducted two pilot missions to assess the effectiveness of the operational review programme. Based on these missions and on the experience gained during OSART missions, this document has been developed to provide guidance on and broaden national/corporate safety review programmes in Member States, and to assist in maximizing their benefits. These guidelines are intended primarily for the IAEA team to conduct assessment of a national/corporate safety review programme. However, this report may also be used by a country or utility to establish its own national/corporate safety review programme. The guidelines may likewise be used for self-assessment or for establishing a baseline when benchmarking other safety review programmes. This report consists of four parts. Section 2 addresses the planning and preparation of an IAEA assessment mission and Sections 3 and 4 deal with specific guidelines for conducting the assessment mission itself

Developments in safety and operations culture in BNFL's thorp reprocessing plant, Sellafield, Cumbria

International Nuclear Information System (INIS)

Kett, P.J.

2000-01-01

One of the best descriptions of Culture is 'how we do things around here'. In a stable organisation it is extremely difficult to change any type of culture, whether it is an operations, customer service or safety culture. To change culture one of two elements are essential. There must be either a significant external pressure felt by all in the organisation or a change in senior management, with authority to set a new direction for the organisation. BNFL had a unique opportunity through the commissioning and operation of the Thorp Reprocessing Plant at Sellafield to shape a new Safety and Operations Culture. Both the key elements for change were present. Thorp was a high profile flagship plant that had attracted multinational investment. It incorporated new technology. The workforce had volunteered to operate the plant. A strong senior management team was specially selected. The plant was being commissioned in an environment where there was significant opposition by 'anti nuclear' groups. It was essential to both BNFL and the wider international nuclear community that Thorp was commissioned and operated safely. A strong operating culture was developed with safety as the corner stone. The culture comprises three key components. Rigorous plant safety case and risk assessments before work commences and modifications to the plant occur; A high level of involvement by all levels of the workforce in both operations and safety matters; Strong supportive leadership which does not allow safety standards to be compromised and encourages open debate on how to improve. During commissioning and early operation of Thorp the robustness of the Safety and Operations Culture was demonstrated. On several occasions, despite intense commercial pressure, operations were halted until the situation was resolved both technically and procedurally. This paper describes how the Safety and Operations Culture was developed. The key factors for success include recruitment, team selection

Use of operational experience in fire safety assessment of nuclear power plants

International Nuclear Information System (INIS)

2000-01-01

Fire hazard has been identified as a major contributor to a plant's operational risk and the international nuclear power industry has been studying and developing tools for defending against this hazard. Considerable progress in design and regulatory requirements for fire safety, in fire protection technology and in related analytical techniques has been made in the past two decades. Substantial efforts have been undertaken worldwide to implement these advances in the interest of improving fire safety both at new and existing nuclear power plants. To assist in these efforts, the IAEA initiated a programme on fire safety that was intended to provide assistance to Member States in improving fire safety in nuclear power plants. In order to achieve this general objective, the IAEA programme aimed at the development of guidelines and good practices, the promotion of advanced fire safety assessment techniques, the exchange of state of the art information between practitioners and the provision of engineering safety advisory services and training in the implementation of internationally accepted practices. During the period 1993-1994, the IAEA activities related to fire safety concentrated on the development of guidelines and good practice documents related to fire safety and fire protection of operating plants. One of the first tasks was the development of a Safety Guide that formulates specific requirements with regard to the fire safety of operating nuclear power plants. Several documents, which provide advice on fire safety inspection, were developed to assist in its implementation. In the period 1995-1996, the programme focused on the preparation of guidelines for the systematic analysis of fire safety at nuclear power plants (NPPs). The IAEA programme on fire safety for 1997-1998 includes tasks aimed at promoting systematic assessment of fire safety related occurrences and dissemination of essential insights from this assessment. One of the topics addressed is the

OSART guidelines - 2005 edition. Reference report for IAEA Operational Safety Review Teams (OSARTs)

International Nuclear Information System (INIS)

2005-01-01

The International Atomic Energy Agency (IAEA) has put forward the vision of a global nuclear safety regime that provides for the protection of people and the environment from the effects of ionizing radiation from nuclear facilities, the minimization of the likelihood of accidents that could endanger life and property and effective mitigation of the effects of any such events should they occur. The strategic approach for achieving the vision of enhancing this regime involves four elements and aims at ensuring that the overall nuclear safety level in Member States continues to improve: - Improvement of national and international safety infrastructures: - Establishment and global acceptance of IAEA safety standards; - Integrated approach to the provision for the application of safety standards; and - Global network of knowledge and experience. The IAEA Operational Safety Review Team (OSART) programme provides advice and assistance to Member States to enhance the safety of nuclear power plants during commissioning and operation. The OSART programme, initiated in 1982, is available to all Member States with nuclear power plants under commissioning or in operation. The OSART methodology and its safety services may also be applied to other nuclear installations (e.g. fuel cycle facilities, research reactors). Conservative design, careful manufacture and sound construction are all prerequisites for safe operation of nuclear power plants. However, the safety of the plant depends ultimately on sound policies, procedures, processes and practices; on the capability and reliability of the commissioning and operating personnel; on comprehensive instructions; and on adequate resources. A positive attitude and conscientiousness on the part of the management and staff in discharging their responsibilities is important to safety. OSART missions consider these aspects in assessing a facility's operational practices in comparison with those used successfully in other countries and

OSART guidelines - 2005 edition. Reference report for IAEA Operational Safety Review Teams (OSARTs)

International Nuclear Information System (INIS)

2007-01-01

The International Atomic Energy Agency (IAEA) has put forward the vision of a global nuclear safety regime that provides for the protection of people and the environment from the effects of ionizing radiation from nuclear facilities, the minimization of the likelihood of accidents that could endanger life and property and effective mitigation of the effects of any such events should they occur. The strategic approach for achieving the vision of enhancing this regime involves four elements and aims at ensuring that the overall nuclear safety level in Member States continues to improve: - Improvement of national and international safety infrastructures: - Establishment and global acceptance of IAEA safety standards. - Integrated approach to the provision for the application of safety standards. And - Global network of knowledge and experience. The IAEA Operational Safety Review Team (OSART) programme provides advice and assistance to Member States to enhance the safety of nuclear power plants during commissioning and operation. The OSART programme, initiated in 1982, is available to all Member States with nuclear power plants under commissioning or in operation. The OSART methodology and its safety services may also be applied to other nuclear installations (e.g. fuel cycle facilities, research reactors). Conservative design, careful manufacture and sound construction are all prerequisites for safe operation of nuclear power plants. However, the safety of the plant depends ultimately on sound policies, procedures, processes and practices. On the capability and reliability of the commissioning and operating personnel. On comprehensive instructions. And on adequate resources. A positive attitude and conscientiousness on the part of the management and staff in discharging their responsibilities is important to safety. OSART missions consider these aspects in assessing a facility's operational practices in comparison with those used successfully in other countries and

OSART guidelines - 2005 edition. Reference report for IAEA Operational Safety Review Teams (OSARTs)

International Nuclear Information System (INIS)

2008-01-01

The International Atomic Energy Agency (IAEA) has put forward the vision of a global nuclear safety regime that provides for the protection of people and the environment from the effects of ionizing radiation from nuclear facilities, the minimization of the likelihood of accidents that could endanger life and property and effective mitigation of the effects of any such events should they occur. The strategic approach for achieving the vision of enhancing this regime involves four elements and aims at ensuring that the overall nuclear safety level in Member States continues to improve: - Improvement of national and international safety infrastructures: - Establishment and global acceptance of IAEA safety standards. - Integrated approach to the provision for the application of safety standards. And - Global network of knowledge and experience. The IAEA Operational Safety Review Team (OSART) programme provides advice and assistance to Member States to enhance the safety of nuclear power plants during commissioning and operation. The OSART programme, initiated in 1982, is available to all Member States with nuclear power plants under commissioning or in operation. The OSART methodology and its safety services may also be applied to other nuclear installations (e.g. fuel cycle facilities, research reactors). Conservative design, careful manufacture and sound construction are all prerequisites for safe operation of nuclear power plants. However, the safety of the plant depends ultimately on sound policies, procedures, processes and practices. On the capability and reliability of the commissioning and operating personnel. On comprehensive instructions. And on adequate resources. A positive attitude and conscientiousness on the part of the management and staff in discharging their responsibilities is important to safety. OSART missions consider these aspects in assessing a facility's operational practices in comparison with those used successfully in other countries and

7 CFR 4279.144 - Appraisals.

Science.gov (United States)

2010-01-01

... value of the collateral. All real property appraisals associated with Agency guaranteed loanmaking and... appraise the property in question. All appraisals will include consideration of the potential effects from... value of the collateral. For additional guidance and information concerning the completion of real...

14 CFR 417.121 - Safety critical preflight operations.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 4 2010-01-01 2010-01-01 false Safety critical preflight operations. 417.121 Section 417.121 Aeronautics and Space COMMERCIAL SPACE TRANSPORTATION, FEDERAL AVIATION... surveillance. A launch operator must implement its hazard area surveillance and clearance plan, of § 417.111(j...

Code on the safety of nuclear research reactors: Operation

International Nuclear Information System (INIS)

1992-01-01

The purpose of this publication is to provide the essential requirements and recommendations for the safe operation of research reactors, with emphasis on the supervisory and managerial aspects. However, the publication also provides some guidance and information on topics concerning all the organizations involved in operation. These objectives are expressed in terms of requirements and recommendations for the safe operation of research reactors. Emphasis is placed on the safety requirements that shall be met rather than on the ways in which they can be met. The requirements and recommendations may form the foundation necessary for a Member State to develop regulations and safety criteria for its research reactor programme.

Safety and operation of the Stade nuclear power plant

International Nuclear Information System (INIS)

Salcher, H.

1991-01-01

The concept of PreussenElektra is to continuously increase the existing safety standard of the Stade nuclear power station using experience gained from faults and operation in nuclear power stations and the progressive state of the art. Modifications to achieve the most gentle operation of the plant have been completed and other are on-going. To do so instruments were attached to those components which are susceptible to fatigue to record the transients and extensive calculatory records were kept. Although the plant has almost 20 years successful operation behind it, it can still stand up well to comparisons with more recent plants as far as safety aspects are concerned. 6 figs

Operable severe obstructive jaundice: How should we use pre ...

African Journals Online (AJOL)

Obstructive jaundice is a common surgical problem, and surgery in jaundiced patients is associated with a higher risk of postoperative complications than surgery in non-jaundiced patients. However, the efficacy of pre-operative biliary drainage (PBD) for patients with obstructive jaundice remains controversial. Many studies ...

Categorization of safety related motor operated valve safety significance for Ulchin Unit 3

International Nuclear Information System (INIS)

Kang, D. I.; Kim, K. Y.

2002-03-01

We performed a categorization of safety related Motor Operated Valve (MOV) safety significance for Ulchin Unit 3. The safety evaluation of MOV of domestic nuclear power plants affects the generic data used for the quantification of MOV common cause failure ( CCF) events in Ulchin Units 3 PSA. Therefore, in this study, we re-estimated the MGL(Multiple Greek Letter) parameter used for the evaluation of MOV CCF probabilities in Ulchin Units 3 Probabilistic Safety Assessment (PSA) and performed a classification of the MOV safety significance. The re-estimation results of the MGL parameter show that its value is decreased by 30% compared with the current value in Ulchin Unit 3 PSA. The categorization results of MOV safety significance using the changed value of MGL parameter shows that the number of HSSCs(High Safety Significant Components) is decreased by 54.5% compared with those using the current value of it in Ulchin Units 3 PSA

Cumulative Trauma and Adjustment in Women Exposed to a Campus Shooting: Examining the Role of Appraisals and Social Support.

Science.gov (United States)

Boykin, Derrecka M; Dunn, Qweandria T; Orcutt, Holly K

2017-05-01

Experiencing repeated trauma can have increasingly detrimental effects on psychosocial functioning after subsequent stressors. These effects may be intensified for victims of interpersonal traumas given that these events are often associated with heightened risk for adverse outcomes. To better understand this relationship, the present study prospectively examined the effect of pre-shooting trauma exposure (i.e., interpersonal vs. non-interpersonal trauma) on psychological functioning (i.e., posttraumatic stress symptoms, depression) following a mass campus shooting. Based on previous research, it was expected that negative appraisals and social support would mediate this relationship. A sample of 515 college women reporting prior trauma exposure was assessed at four time points following the shooting (i.e., pre-shooting, 1-month, 6-months, and 12-months post-shooting). Bootstrap analyses with bias-corrected confidence intervals were conducted. Contrary to expectation, pre-shooting trauma exposure was unrelated to 12-month post-shooting outcomes and neither negative appraisals nor social support at 6-months post-shooting emerged as mediators. Interestingly, a history of non-interpersonal trauma was associated with greater post-shooting family and friend support than a history of interpersonal trauma. Ad hoc analyses showed that pre-shooting symptom severity and level of exposure to the shooting had indirect effects on post-shooting outcomes via post-shooting negative appraisals. These findings support that cumulative trauma, regardless of type, may not have an additive effect unless individuals develop clinically significant symptoms following previous trauma. Trauma severity also appears to play a meaningful role.

Operating experience feedback from safety significant events at research reactors

Energy Technology Data Exchange (ETDEWEB)

Shokr, A.M. [Atomic Energy Authority, Abouzabal (Egypt). Egypt Second Research Reactor; Rao, D. [Bhabha Atomic Research Centre, Mumbai (India)

2015-05-15

Operating experience feedback is an effective mechanism to provide lessons learned from the events and the associated corrective actions to prevent recurrence of events, resulting in improving safety in the nuclear installations. This paper analyzes the events of safety significance that have been occurred at research reactors and discusses the root causes and lessons learned from these events. Insights from literature on events at research reactors and feedback from events at nuclear power plants that are relevant to research reactors are also presented along with discussions. The results of the analysis showed the importance of communication of safety information and exchange of operating experience are vital to prevent reoccurrences of events. The analysis showed also the need for continued attention to human factors and training of operating personnel, and the need for establishing systematic ageing management programmes of reactor facilities, and programmes for safety management of handling of nuclear fuel, core components, and experimental devices.

Operating experience feedback from safety significant events at research reactors

International Nuclear Information System (INIS)

Shokr, A.M.

2015-01-01

Operating experience feedback is an effective mechanism to provide lessons learned from the events and the associated corrective actions to prevent recurrence of events, resulting in improving safety in the nuclear installations. This paper analyzes the events of safety significance that have been occurred at research reactors and discusses the root causes and lessons learned from these events. Insights from literature on events at research reactors and feedback from events at nuclear power plants that are relevant to research reactors are also presented along with discussions. The results of the analysis showed the importance of communication of safety information and exchange of operating experience are vital to prevent reoccurrences of events. The analysis showed also the need for continued attention to human factors and training of operating personnel, and the need for establishing systematic ageing management programmes of reactor facilities, and programmes for safety management of handling of nuclear fuel, core components, and experimental devices.

Pre-operative Asymptomatic Bacteriuria: A Risk Factor For Prosthetic Joint Infection?

Science.gov (United States)

Weale, R; El-Bakri, F; Saeed, Kordo

2018-04-13

Infection is a rare complication following implantation of prosthetic material into a joint. The impact of asymptomatic bacteriuria (ASB) before elective operations and the subsequent risk of prosthetic joint infection (PJI) are not well understood. • Assess the prevalence of ASB amongst patients undergoing total arthroplasty of the hip and knee. • Determine the rates of PJI diagnosed within two years of the arthroplasty and if ASB is an independent risk factor for developing PJI. Patients who had total/unicondylar knee or total hip arthroplasty were retrospectively reviewed over a five-year period. Pre-operative urine samples within one year of surgery were analysed and those with ASB identified. Primary outcome was prosthetic joint infection (PJI) within the first postoperative year. 5542 patients were included. 4368 had a pre-operative urine culture recorded. The prevalence of ASB was 140 of 4368 (3.2%). The overall PJI rate was 56 of 5542 (1.01%). Of those with a PJI, 33 had a pre-operative urine sample recorded. The infection rate in the ASB group was 5% (7 of 140), in the no-ASB group it was 0.61% (26 of 4228) and in the group without a urine sample it was 1.96% (23 of 1174) (p value prosthetic joint, suggestive the relationship is unlikely causal. Copyright © 2018. Published by Elsevier Ltd.

IAEA Leads Operational Safety Mission To Gravelines Nuclear Power Plant, France

International Nuclear Information System (INIS)

2012-01-01

Full text: An IAEA-led international team of experts today began an in-depth operational safety review of the Gravelines Nuclear Power Plant in France. The review, conducted at the invitation of the French government, focuses on programmes and activities essential to the safe operation of the nuclear power plant. The three-week review will cover the areas of Management, Organization and Administration; Training and Qualification; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry; Emergency Planning and Preparedness; and Severe Accident Management. The conclusions of the review will be based on the IAEA Safety Standards and on well-established international good practices. The mission is not a regulatory inspection, a design review or a substitute for an exhaustive assessment of the plant's overall safety status. The team, led by the IAEA's Division of Nuclear Installation Safety, comprises experts from Bulgaria, China, Germany, Hungary, Japan, Romania, Slovakia, South Africa, Spain and Ukraine. The Gravelines mission is the 173rd conducted as part of the IAEA's Operational Safety Review Team programme, which began in 1982. France participates actively in the programme and the Gravelines mission is the 24th hosted by the country. General information about OSART missions can be found on the IAEA Website: OSART Missions. (IAEA)

Operation of TRR-1/M1 for 25 years and lessons learned in management of safety and safety culture

International Nuclear Information System (INIS)

Keinmeesuke, Sirichai

2002-01-01

The first Thai Research Reactor, TRR-1, was installed and put into operation in 1962. In 1975 the reactor was converted to a 2 MW TRIGA Mark III by replacing of the reactor core and the control system. The renamed TRR-1/M1 research reactor went critical again in November 1977. TRR-1/M1 has been operated safely for 25 years with its main utilization in research, isotope production and training. Safety management and safety culture have been implemented for 25 years both in the legislation level and the operation level. There was no nuclear incident and there were a few radiological incidents during the 25 years of operation of TRR-1/M1. The lessons learned from the incident events such as the release of N-16 and Ar-41, the release of radioactive Bromine gave valued opportunities to improve our operation procedure, safety procedure and safety culture. All type of activities with respect to safety culture such as individual awareness, commitment, motivation, supervision and responsibility have been seriously reviewed and being set as normal practices. (author)

Pre-operative use of anti-TNF-α agents and the risk of post-operative complications in patients with ulcerative colitis - a nationwide cohort study

DEFF Research Database (Denmark)

Nørgård, B M; Nielsen, J; Qvist, N

2012-01-01

It is still controversial whether pre-operative anti-tumour necrosis factor-alpha (anti-TNF-α) agents increase post-operative complications in patients with ulcerative colitis (UC).......It is still controversial whether pre-operative anti-tumour necrosis factor-alpha (anti-TNF-α) agents increase post-operative complications in patients with ulcerative colitis (UC)....

IAEA Leads Operational Safety Mission to Smolensk Nuclear Power Plant

International Nuclear Information System (INIS)

2011-01-01

Full text: An international team of nuclear safety experts led by the International Atomic Energy Agency (IAEA) has reviewed the Smolensk Nuclear Power Plant (NPP) near Desnogorsk, in Russia's Smolensk region, for its safety practices and has noted a series of good practices as well as recommendations and suggestions to reinforce them. The IAEA assembled the team at the request of the Government of the Russian Federation to conduct an Operational Safety Review (OSART) of the NPP. Under the leadership of the IAEA's Division of Nuclear Installation Safety, the OSART team performed an in-depth operational safety review from 5 to 22 September 2011. The team was made up of experts from China, India, Lithuania, Slovakia, South Africa, Sweden, UK, USA, the World Association of Nuclear Operators and the IAEA. The team conducted an in-depth review of the aspects essential to the safe operation of the Smolensk NPP. The conclusions of the review are based on the IAEA's Safety Standards and proven good international practices. The review covered the areas of Management, Organization and Administration; Training; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; and Chemistry. Throughout the review, the exchange of information between the OSART experts and plant personnel was very open, professional and productive. The plant's staff were found to be motivated, well trained, knowledgeable and experienced. The OSART team has identified good plant practices which will be shared with the rest of the nuclear industry for consideration of their application. Examples include the following: Illuminated hot-spot wire to identify higher radiation levels is used in the radiation-controlled area to reduce exposures when working in the controlled area; Modern and state-of-the-art training infrastructure and facilities are available at the plant. These include: maintenance training centre; multimedia simulator for the refueling machine; and safety

Procedures for self-assessment of operational safety

International Nuclear Information System (INIS)

1997-08-01

Self-assessment processes have been continuously developed by nuclear organizations, including nuclear power plants. Currently, the nuclear industry and governmental organizations are showing an increasing interest in the implementation of this process as an effective way for improving safety performance. Self-assessment involves the use of different types of tools and mechanisms to assist the organizations in assessing their own safety performance against given standards. This helps to enhance the understanding of the need for improvements, the feeling of ownership in achieving them and and the safety culture as a whole. The concepts developed in this report present the basic approach to self-assessment taking into consideration experience gained during Operational Safety Review Team (OSART) missions, from organizations and utilities which have successfully implemented parts of a self-assessment programme and from meetings organized to discuss the subject

The IRSN experience feedback for the transport package design safety appraisals

International Nuclear Information System (INIS)

Sert, G.

2007-01-01

The activity of transportation of radioactive materials is in constant evolution; air transport of radio elements for medical use is growing rapidly as well as transport of instruments equipped with radioactive sources for inspections of buildings (controls of presence of lead in paintings) and in industry (non destructive examination of welding by gammagraphy, controls of density on building sites). Transports associated with the recycling of plutonium for the production of electricity by nuclear energy are now accomplished in routine. Globally, 900.000 packages are shipped each year in France; among them, approximately 100.000 packages belong to the category for which design approval is required. To maintain a high level of safety for this activity by limiting the probability of occurrence, the severity and consequences of the incidents and accidents, strict rules are implemented by users under the control of the Safety Authority According to the systematic approach of defence in depth, which is defined by the three principles of safety in design, of operational reliability and of effectiveness of emergency response, the robustness of the design of the package is of primary importance. It is based on regulatory requirements relating to the functions of safety (containment of radioactivity, protection against radiation and prevention of the risks of criticality) that must be ensured by the package in conditions of transport as well as in accident conditions. These rules and the way of applying them evolve with time. Indeed, on the one hand the regulation is reexamined periodically; on the other hand, the technical knowledge on the behaviour of the packages subject to the above mentioned conditions and the means of evaluation of this behaviour progress permanently

Safety and operating experience at EBR-II: lessons for the future

International Nuclear Information System (INIS)

Sackett, J.I.; Golden, G.H.

1981-01-01

EBR-II is a small LMFBR power plant that has performed safely and reliably for 16 years. Much has been learned from operating it to facilitate the design, licensing, and operation of large commercial LMFBR power plants in the US. EBR-II has been found relatively easy to keep in conformity with evolving safety requirements, largely because of inherent safety features of the plant. Such features reduce dependence on active safety systems to protect against accidents. EBR-II has experienced a number of plant-transient incidents, some planned, others inadvertent; none has resulted in any significant plant damage. The operating experience with EBR-II has led to the formulation of an Operational Reliability Test Program (ORTP), aimed at showing inherently safe performance of fuel and plant systems

Experience gained in enhancing operational safety at ComEd`s nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Elias, D [Commonwealth Edison Co. (United States)

1997-09-01

The following aspects of experience gained in enhancing operational safety at Comed`s nuclear power plants are discussed: nuclear safety policy; centralization/decentralization; typical nuclear operating organization; safety review boards; human performance enhancement; elements of effective nuclear oversight.

Categorization of Radioactive Sources. Safety Guide

International Nuclear Information System (INIS)

2009-01-01

The IAEA's Statute authorizes the Agency to establish safety standards to protect health and minimize danger to life and property - standards which the IAEA must use in its own operations, and which a State can apply by means of its regulatory provisions for nuclear and radiation safety. A comprehensive body of safety standards under regular review, together with the IAEA's assistance in their application, has become a key element in a global safety regime. In the mid-1990s, a major overhaul of the IAEA's safety standards programme was initiated, with a revised oversight committee structure and a systematic approach to updating the entire corpus of standards. The new standards that have resulted are of a high calibre and reflect best practices in Member States. With the assistance of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its safety standards. Safety standards are only effective, however, if they are properly applied in practice. The IAEA's safety services - which range in scope from engineering safety, operational safety, and radiation, transport and waste safety to regulatory matters and safety culture in organizations - assist Member States in applying the standards and appraise their effectiveness. These safety services enable valuable insights to be shared and I continue to urge all Member States to make use of them. Regulating nuclear and radiation safety is a national responsibility, and many Member States have decided to adopt the IAEA's safety standards for use in their national regulations. For the Contracting Parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions. The standards are also applied by designers, manufacturers and operators around the world to enhance nuclear and radiation safety in power generation, medicine, industry, agriculture, research and education

International comparison of safety criteria applied to radwaste repositories. Safety aspects of the post-operational phase

International Nuclear Information System (INIS)

Baltes, B.

1994-01-01

There is a generally accepted system of framework safety conditions governing the construction, operation, and post-operational monitoring of radwaste repositories. Although the development of these framework conditions may vary from country to country, the resulting criteria are based on the commonly accepted system of priciples and purposes established for ultimate radioactive waste disposal. The experience accumulated by GRS in the course of the plan approval procedure for the Konrad mine site and the safety-relevant studies performed for the planned Morsleben repository clearly show demand for further development of the safety criteria. In Germany, it is especially the safety criteria and detailed requirements filling the framework safety conditions that need revision and in-depth definition, as well as comparison and harmonisation with internationally applied criteria. These activities will particularly consider the international convention on radioactive waste management currently in preparation under the auspieces of the IAEA. (orig.) [de

Relations between the safety authority and the nuclear power plant operators

International Nuclear Information System (INIS)

Laverie, M.; Flandrin, R.

1991-01-01

The French experience has led the safety authority to pay particular attention to the competence of a nuclear operator and to the exercise of his responsibility. In this context, safety does not seem to be improved by the imposition of too many regulations and control activities. On the contrary, an excessive regulatory framework may blunt the operator's awareness of his responsibility. It is the duty of the safety authority to fix the safety objectives. It is the operator's duty to establish the practical conditions for attaining these objectives and to justify these conditions to the safety authority. It is also his duty to implement them correctly. The authority must then verify the quality of this implementation by random inspection methods. Each of the two partners, each conforming to his role and exercise of his particular responsibilities, must remain vigilant. These different actions necessitate a permanent technical dialogue which is not in contradiction with the exercise of strict regulatory control. (orig.)

Study on operational safety issues in the Japanese disposal concept

International Nuclear Information System (INIS)

Suzuki, Satoru; Kitagawa, Yoshito; Hyodo, Hideaki; Kubota, Shigeru; Iijima, Masayoshi; Tamura, Akio; Ishiguro, Katsuhiko; Fujihara, Hiroshi

2014-01-01

In Japan, vitrified high-level radioactive waste (HLW) and certain types of low-level radioactive waste that results from the reprocessing of spent fuel and classified as TRU waste will be disposed of in deep geological formations. NUMO aims to ensure the safety of local residents and workers during the operational phase and after repository closure and will therefore establish a safety case for the geological disposal programme at the end of each stage of the stepwise siting process. Although the Japanese programme is still in the stage before initiation of the siting process, updating the generic (non-site-specific) safety case is required for building confidence among stakeholders. This study focuses on operational safety issues for the Japanese HLW disposal concept. (authors)

Integrating Safety, Operations, Security, and Safeguards (ISOSS) into the design of small modular reactors : a handbook.

Energy Technology Data Exchange (ETDEWEB)

Middleton, Bobby D. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Mendez, Carmen Margarita [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2013-10-01

The existing regulatory environment for nuclear reactors impacts both the facility design and the cost of operations once the facility is built. Delaying the consideration of regulatory requirements until late in the facility design - or worse, until after construction has begun - can result in costly retrofitting as well as increased operational costs to fulfill safety, security, safeguards, and emergency readiness requirements. Considering the scale and scope, as well as the latest design trends in the next generation of nuclear facilities, there is an opportunity to evaluate the regulatory requirements and optimize the design process for Small Modular Reactors (SMRs), as compared to current Light Water Reactors (LWRs). To this end, Sandia has embarked on an initiative to evaluate the interactions of regulations and operations as an approach to optimizing the design of SMR facilities, supporting operational efficiencies, as well as regulatory requirements. The early stages of this initiative consider two focus areas. The first focus area, reported by LaChance, et al. (2007), identifies the regulatory requirements established for the current fleet of LWR facilities regarding Safety, Security, Operations, Safeguards, and Emergency Planning, and evaluates the technical bases for these requirements. The second focus area, developed in this report, documents the foundations for an innovative approach that supports a design framework for SMR facilities that incorporates the regulatory environment, as well as the continued operation of the facility, into the early design stages, eliminating the need for costly retrofitting and additional operating personnel to fulfill regulatory requirements. The work considers a technique known as Integrated Safety, Operations, Security and Safeguards (ISOSS) (Darby, et al., 2007). In coordination with the best practices of industrial operations, the goal of this effort is to develop a design framework that outlines how ISOSS

Periodic safety review of operational nuclear power plants. A publication within the NUSS programme

International Nuclear Information System (INIS)

1994-01-01

This Safety Guide which supplements the IAEA Safety Fundamentals: The Safety of Nuclear Installations and the Code on the Safety of Nuclear Power Plants: Operation, forms part of the Agency's programme, referred to as the NUSS programme, for establishing Codes and Guides relating to nuclear power plants. A list of NUSS publications is given at the end of this book. This Guide was drafted on the basis of a systematic review approach that was endorsed by the IAEA Conference on the Safety of Nuclear Power: Strategy for the Future. The purpose of this Safety Guide is to provide guidance on the conduct of Periodic Safety Reviews (PSRs) for an operational nuclear power plant. The Guide is directed at both owners/operators and regulators. This Safety Guide deals with the PSR of an operational nuclear power plant. A PSR is a comprehensive safety review addressing all important aspects of safety, carried out at regular intervals. 22 refs, 4 figs

Recent Trends In The Methods Of Safety Assessment Of Rad Waste Treatment And Disposal

International Nuclear Information System (INIS)

Mahmoud, N.S.

2012-01-01

Radioactive waste management system involves a huge variety of processes and activities. This includes; collection and segregation, pretreatment, treatment, conditioning, storage and finally disposal. To assure the safety of the different facility of each step in the waste management system, the operator should prepare a safety analysis report to be assessed by the national regulatory body. The content of the safety analysis report must include all data about the site, facility design, operational phase, waste materials, and safety assessment methodologies. Safety assessment methodologies are iterative processes involving site-specific, prospective modeling evaluations of the pre-operational, operational, and post-closure time in case of disposal facilities. The safety assessment focuses primarily on a decision about compliance with performance objectives, rather than the much more difficult problem of predicting actual radiological impacts on the public at far future times. The recent organization processes of the safety assessment are improved by the ISAM working group from IAEA for waste disposal site. These safety assessment methodologies have been modified within SADRWMS IAEA project for the establishment of safety methodologies for the pre-disposal facilities (treatment and storage facilities) and the disposal site.

Online training course on critical appraisal for nurses: adaptation and assessment.

Science.gov (United States)

Reviriego, Eva; Cidoncha, María Angeles; Asua, José; Gagnon, Marie Pierre; Mateos, Maider; Gárate, Lucía; de Lorenzo, Elena; González, Rosa María

2014-07-05

Research is an essential activity for improving quality and efficiency in healthcare. The objective of this study was to train nurses from the public Basque Health Service (Osakidetza) in critical appraisal, promoting continuous training and the use of research in clinical practice. This was a prospective pre-post test study. The InfoCritique course on critical appraisal was translated and adapted. A sample of 50 nurses and 3 tutors was recruited. Educational strategies and assessment instruments were established for the course. A course website was created that contained contact details of the teaching team and coordinator, as well as a course handbook and videos introducing the course. Assessment comprised the administration of questionnaires before and after the course, in order to explore the main intervention outcomes: knowledge acquired and self-learning readiness. Satisfaction was also measured at the end of the course. Of the 50 health professionals recruited, 3 did not complete the course for personal or work-related reasons. The mean score on the pre-course knowledge questionnaire was 70.5 out of 100, with a standard deviation of 11.96. In general, participants' performance on the knowledge questionnaire improved after the course, as reflected in the notable increase of the mean score, to 86.6, with a standard deviation of 10.00. Further, analyses confirmed statistically significant differences between pre- and post-course results (p tools for research, promote a research culture, and encourage critical thinking for evidence-based decision making.

IRSN safety research carried out for reviewing safety cases

International Nuclear Information System (INIS)

Serres, Ch.

2010-01-01

Christophe Serres from IRSN (France) described the independent role of the IRSN regarding research related to nuclear safety in the context of the French Planning Act of 28 June 2006 foreseeing a licence application to be submitted in 2015 for the creation of a deep geological repository. IRSN research programme is organised along research activities devoted to addressing independently-identified k ey safety issues . These 'key issues' should also be of prime concern for the implementer since they relate to the demonstration of the overall safety of the repository, and the level of funding that the implementer should afford to research activities of concern for safety. He explained that the quality and independency of the research programme carried out by IRSN allow building and improving a set of scientific knowledge and technical skills that serves the public mission of delivering technical appraisal and advice, e.g., on behalf of the national safety authority. In particular they contribute to improving the decisional process by making possible scientific dialogue with stakeholders independently from regulator or implementer. The current IRSN R and D programme is developed along the following lines: - Test the adequacy of experimental methods for which feedback is not sufficient. - Develop basic scientific knowledge in the fields where there is a need for better understanding of complex phenomena and interactions. - Develop and use numerical modelling tools to support studies on complex phenomena and interactions. - Perform specific experimental tests aiming at assessing the key parameters that may warrant the performances of the different components of the repository. These studies are carried out by means of experiments performed either at IRSN surface laboratories, or in the Tournemire Experimental Station (TES), an underground facility operated by IRSN in the south-east of France. Targeted actions on research related to operational safety and reversibility

A two-factor method for appraising building renovation and energy efficiency improvement projects

International Nuclear Information System (INIS)

Martinaitis, Vytautas; Kazakevicius, Eduardas; Vitkauskas, Aloyzas

2007-01-01

The renovation of residential buildings usually involves a variety of measures aiming at reducing energy and building maintenance bills, increasing safety and market value, and improving comfort and aesthetics. A significant number of project appraisal methods in current use-such as calculations of payback time, net present value, internal rate of return or cost of conserved energy (CCE)-only quantify energy efficiency gains. These approaches are relatively easy to use, but offer a distorted view of complex modernization projects. On the other hand, various methods using multiple criteria take a much wider perspective but are usually time-consuming, based on sometimes uncertain assumptions and require sophisticated tools. A 'two-factor' appraisal method offers a compromise between these two approaches. The main idea of the method is to separate investments into those related to energy efficiency improvements, and those related to building renovation. Costs and benefits of complex measures, which both influence energy consumption and improve building constructions, are separated by using a building rehabilitation coefficient. The CCE is used for the appraisal of energy efficiency investments, while investments in building renovation are appraised using standard tools for the assessment of investments in maintenance, repair and rehabilitation

Sex differences in principal farm operators' tractor driving safety beliefs and behaviors.

Science.gov (United States)

Cole, H P; Westneat, S C; Browning, S R; Piercy, L R; Struttmann, T

2000-01-01

To examine the widely accepted hypothesis that farm women are more concerned with safety issues and behaviors than their male counterparts are. A telephone survey was administered to a random sample of Kentucky principal farm operators, 90 of whom were women. Participants were questioned about their tractor safety beliefs and practices. No significant sex differences in tractor safety perceptions and behavior were observed. Socialization of women to the role of principal farm operator may override their typically greater sensitivity to safety issues, an important consideration when designing safety campaigns for this population.

Safety in Liquefied Natural Gas (LNG) Operations

Energy Technology Data Exchange (ETDEWEB)

Buhrow, C. [Technische Univ. Bergakademie, Freiberg (Germany). Lehrstuhl Bergbau/Tiefbau; Niemann-Delius, C.; Okafor, E. [Technische Hochschule Aachen (Germany). Lehrstuhl und Inst. fuer Bergbaukunde 3

2005-07-01

Germany needs an LNG receiving terminal to import LNG and supplement expected future gas supply shortages. Enormous economic benefits also abound if Germany is to install an LNG receiving terminal. Jobs will be created for several hundred people. New tax revenues will be generated for state and local governments and this will further enhance the economic competitiveness of Germany. Additionally, it will provide Germany with a reliable source of clean-burning energy. Any proposed LNG receiving terminal should incorporate safety right from the start. These safety requirements will: ensure that certain public land uses, people, and structures outside the LNG facility boundaries are protected in the event of LNG fire, prevent vapour clouds associated with an LNG spill from reaching a property line that can be built upon, prevent severe burns resulting from thermal radiation, specify requirements for design, construction and use of LNG facilities and other equipments, and promote safe, secure and reliable LNG operations. The German future LNG business will not be complete without the evolution of both local and international standards that can apply to LNG operations. Currently existing European standards also appear inadequate. With an OHSAS 18001 management system integrated with other existing standards we can better control our LNG occupational health and safety risks, and improve performance in the process. Additionally, an OHSAS 18001 System will help future German LNG contractors and operators safeguard their most important assets - their employees. (orig.)

Safety aspects and operating experience of LWR plants in Japan

International Nuclear Information System (INIS)

Aoki, S.; Hinoki, M.

1977-01-01

From the outset of nuclear power development in Japan, major emphasis has been placed on the safety of the nuclear power plants. There are now twelve nuclear power plants in operation with a total output of 6600 MWe. Their operating records were generally satisfactory, but in the 1974 to 1975 period, they experienced somewhat declined availability due to the repair work under the specific circumstances. After investigation of causes of troubles and the countermeasures thereof were made to ensure safety, they are now keeping good performance. In Japan, nuclear power plants are strictly subject to sufficient and careful inspection in compliance with the safety regulation, and are placed under stringent radiation control of employees. Under the various circumstances, however, the period of annual inspection tends to be prolonged more than originally planned, and this consequently is considered to be one of the causes of reduced availability. In order to develop nuclear power generation for the future, it is necessary to put further emphasis on the assurance of safety and to endeavor to devise measures to improve availability of the plants, based on the careful analysis of causes which reduce plant availability. This paper discusses the results of studies made for the following items from such viewpoints: (1) Safety and Operating Experience of LWR Nuclear Power Plants in Japan; a) Operating experience with light water reactors b) Improvements in design of light water reactors during the past ten years c) Analysis of the factors which affect plant availability; 2) Assurance of Safety and Measures to Increase Availability a) Measures for safety and environmental protection b) Measures to reduce radiation exposure of employees c) Appropriateness of maintenance and inspection work d) Measures to increase plant availability e) Measures to improve reliability of equipments and components; and 3) Future Technical Problems

The importance for nuclear safety of efficient feedback of operational experience

International Nuclear Information System (INIS)

1987-09-01

Experience of practical operation is a valuable source of information for improving and optimizing the safety and reliability of nuclear power plants. Therefore it is essential to collect information on abnormal events occurring at plants during operation and on all deviations from normal performance by systems and personnel that could be precursors of accidents. For this purpose it is necessary to establish hierarchical systems to feedback operational safety experience at utility, national and international levels and to make these systems as effective as possible. The present report attempts to identify the safety objectives of these systems, to analyse the difficulties presently encountered and to suggest possible improvements

Assessment of 99Tcm-ethylenedicysteine diuretic renography in pre-and post-operative pediatric congenital hydronephrosis

International Nuclear Information System (INIS)

Ye Zhiyi; Wang Hui; Li Jianing; Fu Hongliang; Wu Jingchuan

2010-01-01

Objective: To investigate the clinical value of 99 Tc m -ethylenedicysteine (EC) diuretic renography (DR) in pre-and post-operative pediatric congenital hydronephrosis. Methods: The DR with injection of Furosemide at 15 min of forty children with hydronephrosis was retrospectively studied. The preoperative renal blood perfusion rate (BPR), effective renal plasma flow (ERPF), grade of hydronephrosis,renogram and renal dynamic imaging of pre- and post-operative kidneys were compared. The t-test and Mann-Whitney test were used for data analysis. Results: (1) Of 40 pathological kidneys, the BPR increased 5.99% (t=-5.13, P<0.01) from pre-operative to post-operative: (34.05 ± 11.07)% to (40.04 ± 8.56)%. The ERPF increased 12.48 ml/min (t=-4.35, P<0.01) from pre-operative to post-operative: (57.81 ± 34.32) ml/min to (70.29 ± 5.37) ml/min. (2) The grade of hydronephrosis of 40 pathological kidneys improved significantly(Z=-2.64, P<0.01) with the mean sum of ranks of 47.21 pre-operatively to 33.79 post-operatively.(3) As the hydronephrosis worsened, the collecting system became bigger, the renal parenchyma became thinner, the extent of intrarenal parenchymal photopenia became larger and the response to diuretic challenge in pathological kidneys decreased or became totally irresponsive. (4)Thirty-seven cases of obstruction at ureteropelvic junction (UPJO) and 3 cases at ureterovesical junction (UVJO) were diagnosed by DR, which were all confirmed by surgery. Conclusions: DR is a reliable method to evaluate pediatric congenital hydronephrosis.It can accurately reflect the grade and (or) severity of the disease, guide therapy and assess the therapeutic success of operation. (authors)

Radiological safety aspects of the operation of neutron generators

International Nuclear Information System (INIS)

Boggs, R.F.

1976-01-01

The purpose of the manual is to provide some basic guidelines to persons with a minimum of training in radiological health or health physics, on some safety aspects of the operation of sealed-tube and Cockcroft-Walton type neutron generators. The manual does not state rules or regulations but presents a description of the most likely hazards. It is relevant to those relatively compact neutron generators which usually operate at less than 150-200 kV for the purpose of producing 14-MeV neutrons. The scope is limited to basic discussions of hazards and measurement techniques. Separate chapters are devoted to the characteristics and use of neutron generators; radiation hazards and safety considerations; radiation monitoring and interpretation of measurements; and requirements for an effective safety programme. Two appendices deal with non-radiation hazards and safety considerations, and with a neutron generator laboratory, respectively. An extensive list of bibliographic references is included

The use of CT scan in the pre-operative staging of bronchogenic carcinoma

International Nuclear Information System (INIS)

Pada, C.C.

1992-01-01

Surgery remains the treatment of choice in patients with localized bronchogenic carcinoma. Pre-operative identification of inoperability spares the patient from unnecessary surgery. This prospective study was carried out to determine the correctness of judgement regarding a patient's operability or inoperability based on the pre-operative staging of CT scan; to find out the sensitivity, specificity and overall accuracy of the CT scan in estimating tumor description, nodal status and metastatic spread to the chest. Staging was done by 3 senior radiologists aware of the diagnosis. Both the surgical and histopathologic findings and staging were gathered and used as measurement of truth in arriving at the CT scan's accuracy. Overall accuracy rate of CT scan in determining operability or inoperability is 80%; tumor description accuracy of assessment is 87% and nodal status estimation has an accuracy of 60%. Sensitivity of CT scan is assessment of metastatic spread to the chest is 93%. There is no statistically significant difference in the judgement of operability or interpretability by CT scan compared to surgical and histopathologic results. The CT scan is recommended as a valuable tool in the pre-operative staging of patients with bronchogenic carcinoma who are candidates for surgery. (auth.). 21 refs.; 8 tabs

Criticality safety of high-level tank waste

International Nuclear Information System (INIS)

Rogers, C.A.

1995-01-01

Radioactive waste containing low concentrations of fissile isotopes is stored in underground storage tanks on the Hanford Site in Washington State. The goal of criticality safety is to ensure that this waste remains subcritical into the indefinite future without supervision. A large ratio of solids to plutonium provides an effective way of ensuring a low plutonium concentration. Since the first waste discharge, a program of audits and appraisals has ensured that operations are conducted according to limits and controls applied to them. In addition, a program of surveillance and characterization maintains watch over waste after discharge

Branchial cleft anomalies: accuracy of pre-operative diagnosis, clinical presentation and management.

Science.gov (United States)

Guldfred, L-A; Philipsen, B B; Siim, C

2012-06-01

To examine the accuracy of the pre-operative diagnosis of branchial cleft anomalies, and also to describe their occurrence, clinical presentation and management. Retrospective review of the records of patients diagnosed with a branchial cleft anomaly between 1997 and 2006. One hundred and twenty-six patients were included. Pre-operative diagnosis had a positive predictive value of 0.856 (95 per cent confidence interval, 0.771-0.918) and a sensitivity of 0.944 (95 per cent confidence interval, 0.869-0.979). These patients' demographic data, investigations, findings and management are presented, along with a possible strategy for dealing with solitary cystic masses in the neck. As pre-operative diagnosis has a positive predictive value of 86 per cent, cystic lesions in the neck should be presumed to be carcinomatous until proven otherwise. Branchial fistulae and sinuses seem to be a disease of childhood, while branchial cysts occur mainly in adults. Branchial cleft anomalies are equally frequent in men and women, and equally distributed on the left and right side of the neck.

Teaching critical appraisal skills for nursing research.

Science.gov (United States)

Jones, Sandra C; Crookes, Patrick A; Johnson, Keryn M

2011-09-01

Evidence-based practice is a major focus in nursing, yet the literature continues to document a research-practice gap. Reasons for this gap stem partly from a lack of skills to critique and synthesize the literature, a lack of search skills and difficulty in understanding research articles, and limited knowledge of research by nursing professionals. An innovative and quality driven subject to improve critical appraisal and critical thinking skills was developed for the School of Nursing, Midwifery and Indigenous Health at the University of Wollongong, based on formative research with postgraduate students and supervisors. Through face-to-face and online teaching modules students worked through a structured process of analysing the key aspects of published papers using structured analysis tools for each study design. Pre and post surveys of students found improvements in perceived knowledge of all key skills of critical appraisal. External independent evaluation determined that it was a high quality subject showing many hallmarks of good assessment practice and good practice in use of information and communication technology (ICT) in support of the learning outcomes. Copyright © 2011 Elsevier Ltd. All rights reserved.

Nuclear safety requirements for operation licensing of Egyptian research reactors

International Nuclear Information System (INIS)

Ahmed, E.E.M.; Rahman, F.A.

2000-01-01

From the view of responsibility for health and nuclear safety, this work creates a framework for the application of nuclear regulatory rules to ensure safe operation for the sake of obtaining or maintaining operation licensing for nuclear research reactors. It has been performed according to the recommendations of the IAEA for research reactor safety regulations which clearly states that the scope of the application should include all research reactors being designed, constructed, commissioned, operated, modified or decommissioned. From that concept, the present work establishes a model structure and a computer logic program for a regulatory licensing system (RLS code). It applies both the regulatory inspection and enforcement regulatory rules on the different licensing process stages. The present established RLS code is then applied to the Egyptian Research Reactors, namely; the first ET-RR-1, which was constructed and still operating since 1961, and the second MPR research reactor (ET-RR-2) which is now in the preliminary operation stage. The results showed that for the ET-RR-1 reactor, all operational activities, including maintenance, in-service inspection, renewal, modification and experiments should meet the appropriate regulatory compliance action program. Also, the results showed that for the new MPR research reactor (ET-RR-2), all commissioning and operational stages should also meet the regulatory inspection and enforcement action program of the operational licensing safety requirements. (author)

The potential benefit of pre-operative assessment of amputation ...

African Journals Online (AJOL)

The potential benefit of pre-operative assessment of amputation wound healing potential in peripheral vascular disease. M. Mars, R. P. Mills, J. V. Robbs. Abstract. Choosing the most distal amputation level that will heal is difficult in patients with peripheral vascular disease. From 1984 to 1988,965 patients underwent 1 563 ...

Higher operational safety of nuclear power plants by evaluating the behaviour of operating personnel

International Nuclear Information System (INIS)

Mertins, M.; Glasner, P.

1990-01-01

In the GDR power reactors have been operated since 1966. Since that time operational experiences of 73 cumulative reactor years have been collected. The behaviour of operating personnel is an essential factor to guarantee the safety of operation of the nuclear power plant. Therefore a continuous analysis of the behaviour of operating personnel has been introduced at the GDR nuclear power plants. In the paper the overall system of the selection, preparation and control of the behaviour of nuclear power plant operating personnel is presented. The methods concerned are based on recording all errors of operating personnel and on analyzing them in order to find out the reasons. The aim of the analysis of reasons is to reduce the number of errors. By a feedback of experiences the nuclear safety of the nuclear power plant can be increased. All data necessary for the evaluation of errors are recorded and evaluated by a computer program. This method is explained thoroughly in the paper. Selected results of error analysis are presented. It is explained how the activities of the personnel are made safer by means of this analysis. Comparisons with other methods are made. (author). 3 refs, 4 figs

Conduct of Operations at Nuclear Power Plants. Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2012-01-01

This Safety Guide identifies the main responsibilities and practices of nuclear power plant (NPP) operations departments in relation to their responsibility for the safe functioning of the plant. The guide presents the factors to be considered in structuring the operations department of an NPP; setting high standards of performance; making safety related decisions in an effective manner; conducting control room and field activities in a thorough and professional manner; and maintaining an NPP within established operational limits and conditions. Contents: 1. Introduction; 2. Management and organization of plant operations; 3. Shift complement and functions; 4. Shift routines and operating practices; 5. Control of equipment and plant status; 6. Operations equipment and operator aids; 7. Work control and authorization.

Cognitive appraisals of alcohol use in early adolescence: Psychosocial predictors and reciprocal associations with alcohol use.

Science.gov (United States)

Colder, Craig R; Read, Jennifer P; Wieczorek, William F; Eiden, Rina D; Lengua, Liliana J; Hawk, Larry W; Trucco, Elisa M; Lopez-Vergara, Hector I

2017-04-01

Early adolescence is a dynamic period for the development of alcohol appraisals (expected outcomes of drinking and subjective evaluations of expected outcomes), yet the literature provides a limited understanding of psychosocial factors that shape these appraisals during this period. This study took a comprehensive view of alcohol appraisals and considered positive and negative alcohol outcome expectancies, as well as subjective evaluations of expected outcomes. Developmental-ecological theory guided examination of individual, peer, family, and neighborhood predictors of cognitive appraisals of alcohol and use. A community sample of 378 adolescents (mean age 11.5 years at Wave 1, 52% female) was assessed annually for 4 years. Longitudinal path analysis suggested that the most robust predictors of alcohol appraisals were peer norms. Furthermore, perceived likelihood of positive and negative alcohol outcomes prospectively predicted increases in drinking. There was limited support for appraisals operating as mediators of psychosocial risk and protective factors.

Safety aspects and operating experience of LWR plants in Japan

International Nuclear Information System (INIS)

Aoki, S.; Yoshioka, T.; Toyota, M.; Hinoki, M.

1977-01-01

To develop nuclear power generation for the future, it is necessary to put further emphasis on safety assurance and to endeavour to devise measures to improve plant availability, based on the careful analysis of causes that reduce plant availability. The paper discusses the results of studies on the following items from such viewpoints: (1) Safety and operating experience of LWR nuclear power plants in Japan: operating experience with LWRs; improvements in LWR design during the past ten years; analysis of the factors affecting plant availability; (2) Assurance of safety and measures to increase availability: measures for safety and environmental protection; measures to reduce radiation exposure of employees; appropriateness of maintenance and inspection work; measures to increase plant availability; measures to improve reliability of equipment and components; (3) Future technical problems. (author)

Safety requirements for long term operation of NPPs

International Nuclear Information System (INIS)

Houdre, T.; Osouf, N.; Juvin, J.-C.

2012-01-01

In the future, the reactors operating at present will run alongside reactors of the EPR type or their equivalent, designed for a significantly higher level of safety. This raises the question of the acceptability of continued operation of reactors beyond 40 years when there is an available technology that is safer. Two objectives are therefore imperative. First, a re-evaluation of the safety level in the light of that required of EPR type reactors or their equivalent is necessary, with proposals to bring about significant and relevant improvements to the reactors. R and D work in France and elsewhere is already indicating orientations that could lead to answers, and improvements that would provide significant reductions in release in case of severe accident are being studied. Second, strict compliance of the reactors with the applicable regulations must be demonstrated. At the same time, ageing and obsolescence of the equipment will have to be managed. Where these two points are concerned, ASN expects far-reaching proposals from the licensee. With a view to a request for continued operation beyond 40 years, ASN has referred the matter to the Advisory Committee for nuclear reactors which will meet at the end of 2011 to establish the safety requirements for reactors at their fourth ten-yearly outage. (author)

Combining task-evoked and spontaneous activity to improve pre-operative brain mapping with fMRI

Science.gov (United States)

Fox, Michael D.; Qian, Tianyi; Madsen, Joseph R.; Wang, Danhong; Li, Meiling; Ge, Manling; Zuo, Huan-cong; Groppe, David M.; Mehta, Ashesh D.; Hong, Bo; Liu, Hesheng

2016-01-01

Noninvasive localization of brain function is used to understand and treat neurological disease, exemplified by pre-operative fMRI mapping prior to neurosurgical intervention. The principal approach for generating these maps relies on brain responses evoked by a task and, despite known limitations, has dominated clinical practice for over 20 years. Recently, pre-operative fMRI mapping based on correlations in spontaneous brain activity has been demonstrated, however this approach has its own limitations and has not seen widespread clinical use. Here we show that spontaneous and task-based mapping can be performed together using the same pre-operative fMRI data, provide complimentary information relevant for functional localization, and can be combined to improve identification of eloquent motor cortex. Accuracy, sensitivity, and specificity of our approach are quantified through comparison with electrical cortical stimulation mapping in eight patients with intractable epilepsy. Broad applicability and reproducibility of our approach is demonstrated through prospective replication in an independent dataset of six patients from a different center. In both cohorts and every individual patient, we see a significant improvement in signal to noise and mapping accuracy independent of threshold, quantified using receiver operating characteristic curves. Collectively, our results suggest that modifying the processing of fMRI data to incorporate both task-based and spontaneous activity significantly improves functional localization in pre-operative patients. Because this method requires no additional scan time or modification to conventional pre-operative data acquisition protocols it could have widespread utility. PMID:26408860