48 CFR 1852.219-73 - Small business subcontracting plan.

Science.gov (United States)

2010-10-01

... Provisions and Clauses 1852.219-73 Small business subcontracting plan. As prescribed in 1819.708-70(a), insert the following provision: Small Business Subcontracting Plan (MAY 1999) (a) This provision is not... contain FAR clause 52.219-9, “Small Business Subcontracting Plan.” The apparent low bidder must submit the...

78 FR 59798 - Small Business Subcontracting: Correction

Science.gov (United States)

2013-09-30

... SMALL BUSINESS ADMINISTRATION 13 CFR Part 125 RIN 3245-AG22 Small Business Subcontracting: Correction AGENCY: U.S. Small Business Administration. ACTION: Correcting amendments. SUMMARY: This document... business subcontracting to implement provisions of the Small Business Jobs Act of 2010. This correction...

Final Report for Subcontract B539681

International Nuclear Information System (INIS)

McLean, H.

2009-01-01

This report summarizes the work performed under subcontract B539681. The scope of work described in the subcontract encompasses studies of fundamental research for fast ignition. The work statement from the from the original subcontract and the subsequent extension can be summarized in three major components: modeling of electron transport in experimental targets, development of diagnostics, and experimental implementation and analysis. All three of these areas have been addressed during the subcontract period, although the tasks detailed in the original subcontract were adapted to research conditions with guidance from the technical contact. The work performed in each of these areas is described. (1) Modeling of electron transport in experimental targets - Electron transport and x-ray generation in experimental targets were modeled with the Monte Carlo code Integrated Tiger Series 3.0 (ITS 3.0). This code package was also used to model the response of Bremsstrahlung spectrometer described in the paper. The modeling helped with target and spectrometer designs and was also used to interpret the measured data from the experiments. this work is coupled to the diagnostic development and experimental analysis and is described in the deliverable of the report. (2) Diagnostic Development - During the subcontract period a filter-stack Bremsstrahlung spectrometer using image plate dosimeters was developed, tested, and calibrated. The spectrometer design and sample data taken with the spectrometer was presented at the High Temperature Plasma Diagnostics conference (Albuquerque, NM 2008). The information was also subsequently published in the peer-reviewed conference proceedings (rev. Sci. Instrum. 79:10E305 (2008)). The diagnostic was fielded on over 10 experiments at the Jupiter Laser Facility at Lawrence Livermore and was also adapted for use on OMEGA EP, was discussed in the subcontract extension. A composition study of the image plate dosimeters was also disseminated as

48 CFR 2452.219-70 - Small business subcontracting plan compliance.

Science.gov (United States)

2010-10-01

... of Provisions and Clauses 2452.219-70 Small business subcontracting plan compliance. As prescribed in 2419.708(d), insert the following provision: Small Business Subcontracting Plan Compliance (FEB 2006... the clause at FAR 52.219-9, Small Business Subcontracting Plan. (c) The government will consider...

Small Business Subcontracting Report Validation Can Be Improved

National Research Council Canada - National Science Library

Bond, Christopher

2001-01-01

..., and evaluating accounting systems as well as management support of the subcontracting program. These assessments have found that most contractors that were reviewed are making good faith efforts to comply with their subcontracting plans...

25 CFR 900.49 - What procurement standards apply to subcontracts?

Science.gov (United States)

2010-04-01

... ASSISTANCE ACT Standards for Tribal or Tribal Organization Management Systems Procurement Management System Standards § 900.49 What procurement standards apply to subcontracts? Each subcontract entered into under the... 25 Indians 2 2010-04-01 2010-04-01 false What procurement standards apply to subcontracts? 900.49...

48 CFR 319.705-5 - Awards involving subcontracting plans.

Science.gov (United States)

2010-10-01

... SERVICES SOCIOECONOMIC PROGRAMS SMALL BUSINESS PROGRAMS Subcontracting With Small Business, Small Disadvantaged Business, and Women-Owned Small Business Concerns 319.705-5 Awards involving subcontracting plans...

48 CFR 2019.705-4 - Reviewing the subcontracting plan.

Science.gov (United States)

2010-10-01

... COMMISSION SOCIOECONOMIC PROGRAMS SMALL BUSINESS PROGRAMS Subcontracting With Small Business, Small Disadvantaged Business, and Women-Owned Small Business Concerns 2019.705-4 Reviewing the subcontracting plan...

48 CFR 49.606 - Granting subcontract settlement authorization.

Science.gov (United States)

2010-10-01

...-furnished material or articles completed but undelivered under the subcontract or purchase order, as these... articles may be disposed of without Government approval or screening if the total amount (at subcontract... retention or other disposal of termination inventory allocated to the settlement proposal. (ii) Deduct...

48 CFR 15.404-3 - Subcontract pricing considerations.

Science.gov (United States)

2010-10-01

... CONTRACTING METHODS AND CONTRACT TYPES CONTRACTING BY NEGOTIATION Contract Pricing 15.404-3 Subcontract pricing considerations. (a) The contracting officer is responsible for the determination of a fair and... 48 Federal Acquisition Regulations System 1 2010-10-01 2010-10-01 false Subcontract pricing...

Sub-Contracting in Rural Areas of Thailand

OpenAIRE

Mead, Donald C.

1982-01-01

This paper describes an arrangement where a producer undertakes certain steps in the production process done by individuals working in their own homes in Thailand. The paper also provides a description of how this system operates in four different industries, presents survey data on people engaged in subcontracting work, evaluates the subcontracting system, and determines the advantages and disadvantages of its operation.

Safety Climate and Occupational Stress According to Occupational Accidents Experience and Employment Type in Shipbuilding Industry of Korea.

Science.gov (United States)

Kim, Kyung Woo; Park, Sung Jin; Lim, Hae Sun; Cho, Hm Hak

2017-09-01

Safety climate and occupational stress are related with occupational accident. The present study tried to identify the differences in safety climate and occupational stress according to occupational accidents experience and employment type (e.g., direct workers and subcontract workers). In this study, we conducted a survey using safety climate scale and Korean Occupational Stress Scale and classified the participants into four groups: direct workers working for accident-free departments, direct workers working for accident departments, subcontract workers working for accident-free departments, and subcontract workers working for accident departments for 2 years within the same workplace in the shipbuilding industry. The direct workers and subcontract workers showed diverse results in subscales of safety climate and occupational stress. This result is supported by existing studies; however, further study is necessary for more supporting evidence and elaborative methodological approach. The necessity of management for safety climate and psychosocial factor such as occupational stress for both direct workers and subcontract workers as a whole is suggested by this study.

Photovoltaic Subcontract Program. Annual report, FY 1992

Energy Technology Data Exchange (ETDEWEB)

1993-03-01

This report summarizes the fiscal year (FY) 1992 progress of the subcontracted photovoltaic (PV) research and development (R&D) performed under the Photovoltaic Advanced Research and Development Project at the National Renewable Energy Laboratory (NREL)-formerly the Solar Energy Research Institute (SERI). The mission of the national PV program is to develop PV technology for large-scale generation of economically competitive electric power in the United States. The technical sections of the report cover the main areas of the subcontract program: the Crystalline Materials and Advanced Concepts project, the Polycrystalline Thin Films project, Amorphous Silicon Research project, the Photovoltaic Manufacturing Technology (PVMaT) project, PV Module and System Performance and Engineering project, and the PV Analysis and Applications Development project. Technical summaries of each of the subcontracted programs provide a discussion of approaches, major accomplishments in FY 1992, and future research directions.

Annual Report: Photovoltaic Subcontract Program FY 1991

Energy Technology Data Exchange (ETDEWEB)

Summers, K. A. [National Renewable Energy Lab. (NREL), Golden, CO (United States)

1992-03-01

This report summarizes the fiscal year (FY) 1991 (October 1, 1990, through September 30, 1991) progress of the subcontracted photovoltaic (PV) research and development (R&D) performed under the Photovoltaic Advanced Research and Development Project at the National Renewable Energy Laboratory (NREL)-formerly the Solar Energy Research Institute (SERI). The mission of the national PV program is to develop PV technology for large-scale generation of economically competitive electric power in the United States. The technical sections of the report cover the main areas of the subcontract program: the Amorphous Silicon Research Project, Polycrystalline Thin Films, Crystalline Silicon Materials Research, High Efficiency Concepts, the New Ideas Program, the University Participation Program, and the Photovoltaic Manufacturing Technology (PVMaT) project. Technical summaries of each of the subcontracted programs provide a discussion of approaches, major accomplishments in FY 1991, and future research directions.

48 CFR 35.009 - Subcontracting research and development effort.

Science.gov (United States)

2010-10-01

... ACQUISITION REGULATION SPECIAL CATEGORIES OF CONTRACTING RESEARCH AND DEVELOPMENT CONTRACTING 35.009 Subcontracting research and development effort. Since the selection of R&D contractors is substantially based on... 48 Federal Acquisition Regulations System 1 2010-10-01 2010-10-01 false Subcontracting research...

48 CFR 552.219-72 - Preparation, Submission, and Negotiation of Subcontracting Plans.

Science.gov (United States)

2010-10-01

..., and Negotiation of Subcontracting Plans. 552.219-72 Section 552.219-72 Federal Acquisition Regulations... Text of Provisions and Clauses 552.219-72 Preparation, Submission, and Negotiation of Subcontracting... Negotiation of Subcontracting Plans (JUN 2005) (a) An offeror, other than a small business concern, submitting...

R&D cooperation versus R&D subcontracting: empirical evidence from French survey data.

OpenAIRE

Estelle Dhont-Peltrault; Etienne Pfister

2007-01-01

This paper uses a survey of French firms active in R&D to identify the determinants of R&D outsourcing and of the ensuing trade-off between R&D subcontracting and R&D cooperation. Internal R&D expenditures increase both the probability of outsourcing and the number of R&D partners. Investment in fundamental R&D, group belonging, and the sector’s high R&D intensity positively influences the probability of R&D outsourcing but have less impact on the number of partners. R&D subcontracting is mor...

48 CFR 52.219-9 - Small business subcontracting plan.

Science.gov (United States)

2010-10-01

... Clauses 52.219-9 Small business subcontracting plan. As prescribed in 19.708(b), insert the following clause: Small Business Subcontracting Plan (OCT 2010) (a) This clause does not apply to small business... business, and women-owned small business concerns. If the offeror is submitting an individual contract plan...

Transferring the Cost of Wage Rigidity to Subcontracting Firms: The Case of Korea

Directory of Open Access Journals (Sweden)

Kwangho Woo

2016-08-01

Full Text Available We select a Korean case with ample subcontracting practices and a rigid wage system. Workplaces with subcontract transactions would have reason to impute the additional wage incremental costs associated with the seniority-based wage system (Hobong in Korea to subcontractors. Our empirical results identify the cost-transferring mechanism under which the cost of wage rigidity for contractors is transferred to subcontracting firms and aggravates the wage inequality among workers in contracting and subcontracting firms. We analyze the industrial difference in the intensity of this transferring mechanism and probe policy directions considering the improvement of both the subcontracting structure and pay system simultaneously. For the sustainability of firms, they need to reform a seniority-based wage system, an incentive-based wage system or a job-based wage system and the exploited subcontracting structure for creating share value.

Lessons learned from the EG&G consolidated hazardous waste subcontract and ESH&Q liability assessment process

Energy Technology Data Exchange (ETDEWEB)

Fix, N.J.

1995-03-01

Hazardous waste transportation, treatment, recycling, and disposal contracts were first consolidated at the Idaho National Engineering Laboratory in 1992 by EG&G Idaho, Inc. At that time, disposition of Resource, Conservation and Recovery Act hazardous waste, Toxic Substance Control Act waste, Comprehensive Environmental Response, Compensation, and Liability Act hazardous substances and contaminated media, and recyclable hazardous materials was consolidated under five subcontracts. The wastes were generated by five different INEL M&O contractors, under the direction of three different Department of Energy field offices. The consolidated contract reduced the number of facilities handling INEL waste from 27 to 8 qualified treatment, storage, and disposal facilities, with brokers specifically prohibited. This reduced associated transportation costs, amount and cost of contractual paperwork, and environmental liability exposure. EG&G reviewed this approach and proposed a consolidated hazardous waste subcontract be formed for the major EG&G managed DOE sites: INEL, Mound, Rocky Flats, Nevada Test Site, and 10 satellite facilities. After obtaining concurrence from DOE Headquarters, this effort began in March 1992 and was completed with the award of two master task subcontracts in October and November 1993. In addition, the effort included a team to evaluate the apparent awardee`s facilities for environment, safety, health, and quality (ESH&Q) and financial liability status. This report documents the evaluation of the process used to prepare, bid, and award the EG&G consolidated hazardous waste transportation, treatment, recycling, and/or disposal subcontracts and associated ESH&Q and financial liability assessments; document the strengths and weaknesses of the process; and propose improvements that would expedite and enhance the process for other DOE installations that used the process and for the re-bid of the consolidated subcontract, scheduled for 1997.

13 CFR 126.701 - Can these subcontracting percentages requirements change?

Science.gov (United States)

2010-01-01

... 13 Business Credit and Assistance 1 2010-01-01 2010-01-01 false Can these subcontracting percentages requirements change? 126.701 Section 126.701 Business Credit and Assistance SMALL BUSINESS ADMINISTRATION HUBZONE PROGRAM Contract Performance Requirements § 126.701 Can these subcontracting percentages...

The Creation of a Permanent Establishment Through the Use of Subcontracting

DEFF Research Database (Denmark)

Schmidt, Peter Koerver

2018-01-01

In a recent Danish decision, the National Tax Board found that a foreign company should be considered to have a permanent establishment in Denmark, despite the fact that the foreign company had subcontracted all its activities in Denmark to an independent third party. This contribution critically...

The nexus between OSH and subcontracting.

Science.gov (United States)

Nunes, Isabel L

2012-01-01

Subcontracting of specialized functions to external companies (e.g. cleaning or maintenance) is actually very common within several industries. These external companies' are called contractors and their contracting is often designated as outsourcing. Frequently contractors involve other companies (the sub-contractors) to assist them in fulfilling the contract, resulting in a complex chain of organizations focused on interchange of work - the contracting chain. Therefore in the same work site can coexist workers form the client-company and workers from the contractors and/or subcontractors. Since contractors perform their job in client's facilities, they can be exposed to hazards that are unknown to them. On other hand, workers of the client company can also be exposed to hazardous situations derived from the work performed by the contractors. The paper discusses how adequate occupational safety and health conditions can be assured when dealing with this kind of dynamic labor networks. Two case-studies and several examples coming from international literature will be presented.

Lessons learned from the EG ampersand G consolidated hazardous waste subcontract and ESH ampersand Q liability assessment process

International Nuclear Information System (INIS)

Fix, N.J.

1995-03-01

Hazardous waste transportation, treatment, recycling, and disposal contracts were first consolidated at the Idaho National Engineering Laboratory in 1992 by EG and G Idaho, Inc. At that time, disposition of Resource, Conservation and Recovery Act hazardous waste, Toxic Substance Control Act waste, Comprehensive Environmental Response, Compensation, and Liability Act hazardous substances and contaminated media, and recyclable hazardous materials was consolidated under five subcontracts. The wastes were generated by five different INEL M and O contractors, under the direction of three different Department of Energy field offices. The consolidated contract reduced the number of facilities handling INEL waste from 27 to 8 qualified treatment, storage, and disposal facilities, with brokers specifically prohibited. This reduced associated transportation costs, amount and cost of contractual paperwork, and environmental liability exposure. EG and G reviewed this approach and proposed a consolidated hazardous waste subcontract be formed for the major EG and G managed DOE sites: INEL, Mound, Rocky Flats, Nevada Test Site, and 10 satellite facilities. After obtaining concurrence from DOE Headquarters, this effort began in March 1992 and was completed with the award of two master task subcontracts in October and November 1993. In addition, the effort included a team to evaluate the apparent awardee's facilities for environment, safety, health, and quality (ESH and Q) and financial liability status. This report documents the evaluation of the process used to prepare, bid, and award the EG and G consolidated hazardous waste transportation, treatment, recycling, and/or disposal subcontracts and associated ESH and Q and financial liability assessments; document the strengths and weaknesses of the process; and propose improvements that would expedite and enhance the process for other DOE installations that used the process and for the re-bid of the consolidated subcontract

29 CFR 4.114 - Subcontracts.

Science.gov (United States)

2010-07-01

... Secretary of Labor LABOR STANDARDS FOR FEDERAL SERVICE CONTRACTS Application of the McNamara-O'Hara Service Contract Act Covered Contracts Generally § 4.114 Subcontracts. (a) “Contractor” as including “subcontractor... contractor undertakes a contract subject to the Act, the contractor agrees to assume the obligation that the...

48 CFR 852.219-9 - VA Small business subcontracting plan minimum requirements.

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false VA Small business... Provisions and Clauses 852.219-9 VA Small business subcontracting plan minimum requirements. As prescribed in subpart 819.709, insert the following clause: VA Small Business Subcontracting Plan Minimum Requirements...

Companies Participating in the Department of Defense Subcontracting Program: First Half Fiscal Year 1997

National Research Council Canada - National Science Library

1997-01-01

...). Public Law (P.L.) 95-507, as amended requires that these contractors establish a small business subcontracting program and report to DoD semiannually, using standard 295, on subcontract awards. As required by P.I...

Forecast of contracting and subcontracting opportunities: Fiscal year 1998

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-01-01

This report describes procurement procedures and opportunities for small businesses with the Department of Energy (DOE). It describes both prime and subcontracting opportunities of $100,000 and above which are being set aside for 8(a) and other small business concerns. The report contains sections on: SIC codes; procurement opportunities with headquarters offices; procurement opportunities with field offices; subcontracting opportunities with major contractors; 8(a) contracts expiring in FY 1998; other opportunities to do business with DOE; management and operating contractors--expiration dates; Office of Small and Disadvantaged Business Utilization (OSDBU) staff directory; and small business survey. This document will be updated quarterly on the home page.

48 CFR 5.206 - Notices of subcontracting opportunities.

Science.gov (United States)

2010-10-01

... subcontracts, to increase participation by qualified HUBZone small business, small, small disadvantaged, women-owned small business, veteran-owned small business and service-disabled veteran-owned small business.... (b) The notices must describe— (1) The business opportunity; (2) Any prequalification requirements...

Complementary safety assessment assessment of nuclear facilities - La Hague plant - AREVA

International Nuclear Information System (INIS)

2011-01-01

This complementary safety assessment analyses the robustness of La Hague plant to extreme situations such as those that led to the Fukushima accident. Robustness is the ability for the plant to withstand events beyond which the plant was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accident sequence. Moreover, safety is not only a matter of design or engineered systems but also a matter of organizing: task organization (including subcontracting) as well as the setting of emergency plans or the inventory of nuclear materials are taken into consideration in this assessment. This report is divided into 10 main chapters: 1) the feedback experience of the Fukushima accident; 2) description of the site; 3) featuring the activities and installations; 4) accidental sequences 5) protection from the earthquake; 6) protection from the flood; 7) protection from other extreme natural disasters; 8) the loss of electrical power and of the heat sink; 9) the management of severe accidents; and 10) subcontracting policy. This study shows a globally good robustness of the plant for the considered risks and, in the case of a severe accident, specified remedial actions can be brought into play by the staff to secure the installations. (A.C.)

Photovoltaic Subcontract Program, FY 1991. Annual report, [October 1, 1990--September 30, 1991

Energy Technology Data Exchange (ETDEWEB)

1992-03-01

This report summarizes the fiscal year (FY) 1991 (October 1, 1990, through September 30, 1991) progress of the subcontracted photovoltaic (PV) research and development (R&D) performed under the Photovoltaic Advanced Research and Development Project at the National Renewable Energy Laboratory (NREL) -- formerly the Solar Energy Research Institute (SERI). The mission of the national PV program is to develop PV technology for large-scale generation of economically competitive electric power in the United States. The technical sections of the report cover the main areas of the subcontract program: the Amorphous Silicon Research Project, Polycrystalline Thin Films, Crystalline Silicon Materials Research, High-Efficiency Concepts, the New Ideas Program, the University Participation Program, and the Photovoltaic Manufacturing Technology (PVMaT) project. Technical summaries of each of the subcontracted programs provide a discussion of approaches, major accomplishments in FY 1991, and future research directions.

48 CFR 225.872-8 - Subcontracting with qualifying country sources.

Science.gov (United States)

2010-10-01

... security interest reasons, mobilization base considerations, or applicable U.S. laws or regulations (see... contractor subcontracting procedures, the contracting officer shall ensure that the contract does not...

48 CFR 212.504 - Applicability of certain laws to subcontracts for the acquisition of commercial items.

Science.gov (United States)

2010-10-01

... laws to subcontracts for the acquisition of commercial items. 212.504 Section 212.504 Federal... PLANNING ACQUISITION OF COMMERCIAL ITEMS Applicability of Certain Laws to the Acquisition of Commercial Items 212.504 Applicability of certain laws to subcontracts for the acquisition of commercial items. (a...

75 FR 34260 - Federal Acquisition Regulation; FAR Case 2005-040, Electronic Subcontracting Reporting System (eSRS)

Science.gov (United States)

2010-06-16

... plan. Failure to submit or late submission of reports shall be a breach of contract and will be...)(2) of FAR clause 52.219-9 already addresses the breach of contract issue when the contractor or... Form 294 - Subcontract Report for Individual Contracts and Standard Form 295 - Summary Subcontract...

48 CFR 12.504 - Applicability of certain laws to subcontracts for the acquisition of commercial items.

Science.gov (United States)

2010-10-01

... laws to subcontracts for the acquisition of commercial items. 12.504 Section 12.504 Federal Acquisition... Applicability of Certain Laws to the Acquisition of Commercial Items and Commercially Available Off-The-Shelf Items 12.504 Applicability of certain laws to subcontracts for the acquisition of commercial items. (a...

Tri-State Synfuels Project Review: Volume 9A. Subcontract information. [Proposed Henderson, Kentucky coal to gasoline plant; water supply and civil engineering subcontracts

Energy Technology Data Exchange (ETDEWEB)

1982-06-01

Volume 9A considers subcontract work done at the site involving hydrogeological studies with respect to water supply and geotechnical work with respect to the building foundations necessary based on boreholes drilled and the lithology of the area. (LTN)

Final Report on the Audit of Subcontract Prices on Firm-Fixed-Price Contracts Awarded to McDonnell Aircraft Company

Science.gov (United States)

1990-12-03

This is our final report on the audit of Subcontract Prices on Firm-Fixed-Price Contracts Awarded to McDonnell Aircraft Company (MCAIR). The Contract Management Directorate made the audit from October 1989 through June 1990. The objective of the audit was to compare proposed and negotiated subcontract prices and determine reasons for significant variances. We also evaluated applicable internal control procedures. For a 6-month period ending December 1989, MCAIR issued 517 subcontracts valued at $679 million.

48 CFR 52.222-11 - Subcontracts (Labor Standards).

Science.gov (United States)

2010-10-01

...: Subcontracts (Labor Standards) (JUL 2005) (a) Definition. Construction, alteration or repair, as used in this... dedicated to the construction of the building or work and is deemed part of the site of the work within the meaning of paragraph (2) of the “site of work” definition; and (5) Transportation of portions of the...

48 CFR 52.219-16 - Liquidated Damages-Subcontracting Plan.

Science.gov (United States)

2010-10-01

... following clause: Liquidated Damages—Subcontracting Plan (JAN 1999) (a) Failure to make a good faith effort... has failed to make such good faith effort, the Contracting Officer shall give the Contractor written notice specifying the failure and permitting the Contractor to demonstrate what good faith efforts have...

48 CFR 52.244-6 - Subcontracts for Commercial Items.

Science.gov (United States)

2010-10-01

... clauses in subcontracts for commercial items: (i) 52.203-13, Contractor Code of Business Ethics and.... (e) To the maximum extent practicable, when the Contractor acts as a purchasing agent for the Government with respect to a purchase that exceeds the simplified acquisition threshold, the Contractor shall...

Subcontract 8699K0013-9Q. Final progress report, July 19, 1993--July 18, 1996

International Nuclear Information System (INIS)

Humphries, S. Jr.

1996-01-01

A major activity in the subcontract was to provide theoretical and analytical support for experimental activities at Los Alamos National Laboratory. Reflecting changes in the laboratory organization, work was performed initially for Group P-14 and latter for the Agex Program Office. A second task was to develop, to supply and to support software in the areas of hydrodynamics, magnetohydrodynamics and electromagnetics. The programs are compatible with personal computers and allow simulations of experiments by laboratory personnel both on-site and in the field

Evidence report : psychiatric disorders and commercial motor vehicle driver safety.

Science.gov (United States)

2008-08-29

This report was prepared by ECRI Institute under subcontract to MANILA Consulting Group, Inc., which holds prime GS-10F-0177N/DTMC75-06-F-00039 with the Department of Transportations Federal Motor Carrier Safety Administration. ECRI Institute is a...

77 FR 29983 - Federal Acquisition Regulation; Information Collection; Subcontract Consent

Science.gov (United States)

2012-05-21

... performance of functions of the Federal Acquisition Regulation (FAR), and whether it will have practical... The objective of consent to subcontract, as discussed in FAR Part 44, is to evaluate the efficiency and effectiveness with which the contractor spends Government funds, and complies with Government...

48 CFR 3019.705 - Responsibilities for the contracting officer under the subcontracting program.

Science.gov (United States)

2010-10-01

... Regulations System DEPARTMENT OF HOMELAND SECURITY, HOMELAND SECURITY ACQUISITION REGULATION (HSAR) SOCIOECONOMIC PROGRAMS SMALL BUSINESS PROGRAMS The Small Business Subcontracting Program 3019.705...

48 CFR 1419.705-2 - Determining the need for a subcontracting plan.

Science.gov (United States)

2010-10-01

... INTERIOR SOCIOECONOMIC PROGRAMS SMALL BUSINESS PROGRAMS The Small Business Subcontracting Program 1419.705... possibilities exist for a proposed contractual action shall be reviewed by the BUDS prior to the approval by a...

Construction Tender Subcontract Selection using Case-based Reasoning

Directory of Open Access Journals (Sweden)

Due Luu

2012-11-01

Full Text Available Obtaining competitive quotations from suitably qualified subcontractors at tender tim n significantly increase the chance of w1nmng a construction project. Amidst an increasingly growing trend to subcontracting in Australia, selecting appropriate subcontractors for a construction project can be a daunting task requiring the analysis of complex and dynamic criteria such as past performance, suitable experience, track record of competitive pricing, financial stability and so on. Subcontractor selection is plagued with uncertainty and vagueness and these conditions are difficul_t o represent in generalised sets of rules. DeciSIOns pertaining to the selection of subcontr:act?s tender time are usually based on the mtu1t1onand past experience of construction estimators. Case-based reasoning (CBR may be an appropriate method of addressing the chal_lenges of selecting subcontractors because CBR 1s able to harness the experiential knowledge of practitioners. This paper reviews the practicality and suitability of a CBR approach for subcontractor tender selection through the development of a prototype CBR procurement advisory system. In this system, subcontractor selection cases are represented by a set of attributes elicited from experienced construction estimators. The results indicate that CBR can enhance the appropriateness of the selection of subcontractors for construction projects.

NIF conventional facilities construction health and safety plan

International Nuclear Information System (INIS)

Benjamin, D W

1998-01-01

The purpose of this Plan is to outline the minimum health and safety requirements to which all participating Lawrence Livermore National Laboratory (LLNL) and non-LLNL employees (excluding National Ignition Facility [NIF] specific contractors and subcontractors covered under the construction subcontract packages (e.g., CSP-9)-see Construction Safety Program for the National Ignition Facility [CSP] Section I.B. ''NIF Construction Contractors and Subcontractors'' for specifics) shall adhere to for preventing job-related injuries and illnesses during Conventional Facilities construction activities at the NIF Project. For the purpose of this Plan, the term ''LLNL and non-LLNL employees'' includes LLNL employees, LLNL Plant Operations staff and their contractors, supplemental labor, contract labor, labor-only contractors, vendors, DOE representatives, personnel matrixed/assigned from other National Laboratories, participating guests, and others such as visitors, students, consultants etc., performing on-site work or services in support of the NIF Project. Based upon an activity level determination explained in Section 1.2.18, in this document, these organizations or individuals may be required by site management to prepare their own NIF site-specific safety plan. LLNL employees will normally not be expected to prepare a site-specific safety plan. This Plan also outlines job-specific exposures and construction site safety activities with which LLNL and non-LLNL employees shall comply

2 CFR 801.220 - What contracts and subcontracts, in addition to those listed in 2 CFR 180.220, are covered...

Science.gov (United States)

2010-01-01

... 2 Grants and Agreements 1 2010-01-01 2010-01-01 false What contracts and subcontracts, in addition to those listed in 2 CFR 180.220, are covered transactions? 801.220 Section 801.220 Grants and... DEBARMENT AND SUSPENSION Covered Transactions § 801.220 What contracts and subcontracts, in addition to...

Complementary safety assessment assessment of nuclear facilities - FBFC Romans plant - AREVA

International Nuclear Information System (INIS)

2011-01-01

This complementary safety assessment analyses the robustness of the FBFC Romans plant to extreme situations such as those that led to the Fukushima accident. This plant is dedicated to the fabrication of nuclear fuels for experimental reactors. Robustness is the ability for the plant to withstand events beyond which the plant was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accidental sequence. Moreover, safety is not only a matter of design or engineered systems but also a matter of organizing: task organization (including subcontracting) as well as the setting of emergency plans or the inventory of nuclear materials are taken into consideration in this assessment. This report is divided into 10 main chapters: 1) the feedback experience of the Fukushima accident; 2) description of the site and its surroundings; 3) featuring of the site's activities and installations; 4) accidental sequences; 5) protection from earthquakes; 6) protection from floods; 7) protection from other extreme natural disasters; 8) the loss of electrical power and of the heat sink; 9) the management of severe accidents; and 10) subcontracting policy. This analysis has identified 4 main measures to be taken to limit the risks linked to natural disasters: -) the implementation of a seismic detection and cutting system; -) the seismic reinforcement of the recycling workshop (R1 building); -) the suppression of the use of recycled water in the AP2 building; -) the determination of the critical water levels admitted in the buildings in case of strong rain periods. (A.C.)

Complementary safety assessment in the light of the Fukushima accident - Laue Langevin Institute

International Nuclear Information System (INIS)

Desbriere; Caillot; Bidet

2012-01-01

This CSA (Complementary Safety Assessment) analyses the robustness of the Grenoble High Flux reactor to extreme situations such as those that led to the Fukushima accident and proposes a series of improvements. Robustness is the ability for the facility to withstand events beyond the level for which the facility was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accident sequence (cliff edge effect). Safety is not only a matter of design or of engineered systems, it is also a matter of organization. So issues like crisis organization and work organization via subcontracting are also taken into consideration. This report is divided into 9 main chapters: 1) main features of the high flux reactor, 2) macroscopic study of safety, identification of structures and equipment essential to safety, 3) earthquake risk, 4) flood risk, 5) risks due to other extreme natural disasters, 6) the loss of electrical power supplies and of cooling systems, 7) management of severe accidents, 8) subcontracting policy, 9) synthesis and improvements. This study confirms the robustness of the facility and a series of improvements and modifications is proposed to face very unlikely situations (especially plurality of failures) that were not taken into account in baseline safety studies. (A.C.)

48 CFR 252.219-7004 - Small business subcontracting plan (test program).

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Small business... AND CONTRACT CLAUSES Text of Provisions And Clauses 252.219-7004 Small business subcontracting plan (test program). As prescribed in 219.708(b)(1)(B), use the following clause: Small Business...

48 CFR 2019.705 - Responsibilities of the contracting officer under the subcontracting assistance program.

Science.gov (United States)

2010-10-01

... Regulations System NUCLEAR REGULATORY COMMISSION SOCIOECONOMIC PROGRAMS SMALL BUSINESS PROGRAMS Subcontracting With Small Business, Small Disadvantaged Business, and Women-Owned Small Business Concerns 2019.705...

48 CFR 319.705 - Responsibilities of the Contracting Officer under the subcontracting assistance program.

Science.gov (United States)

2010-10-01

... Regulations System HEALTH AND HUMAN SERVICES SOCIOECONOMIC PROGRAMS SMALL BUSINESS PROGRAMS Subcontracting With Small Business, Small Disadvantaged Business, and Women-Owned Small Business Concerns 319.705...

75 FR 65439 - Defense Federal Acquisition Regulation Supplement; Electronic Subcontracting Reporting System

Science.gov (United States)

2010-10-25

... Accounting Service or Missile Defense Agency. (2) For DoD, the authority to acknowledge receipt or reject... DEPARTMENT OF DEFENSE Defense Acquisition Regulations System 48 CFR Parts 219 and 252 [DFARS Case 2009-D002] Defense Federal Acquisition Regulation Supplement; Electronic Subcontracting Reporting...

Photovoltaic manufacturing technology (PVMaT). Annual subcontract report, March 31, 1994--June 30, 1995

Energy Technology Data Exchange (ETDEWEB)

Holley, W A [Springborn Labs., Inc., Enfield, CT (United States)

1996-01-01

This report describes work performed under a subcontract to the National Renewable Energy Laboratory under the Photovoltaic Manufacturing Technology Project. The objectives of this subcontract are to (1) define the problem of yellowing/browning of EVA-based encapsulants; (2) determine probable mechanisms and the role of various parameters such as heat, UV exposure, module construction, EVA interfaces, and EVA thickness, in the browning of EVA-based encapsulants; (3) develop stabilization strategies for various module constructions to protect the encapsulant from degradative failure; (4) conduct laboratory, accelerated outdoor, and field testing of encapsulant, laminated test coupons, and full modules to demonstrate the functional adequacy of the stabilization strategies; and (5) implement these strategies. This report summarizes the accomplishments related to the above goals for the reporting period.

Additional safety assessments. Report by the Nuclear Safety Authority - December 2011

International Nuclear Information System (INIS)

2011-12-01

The first part of this voluminous report proposes an assessment of targeted audits performed in French nuclear installations (water pressurized reactors on the one hand, laboratories, factories and waste and dismantling installations on the other hand) on issues related to the Fukushima accident. The examined issues were the protection against flooding and against earthquake, and the loss of electricity supplies and of cooling sources. The second part addresses the additional safety assessments of the reactors and the European resistance tests: presentation of the French electronuclear stock, earthquake, flooding and natural hazards (installation sizing, safety margin assessment), loss of electricity supplies and cooling systems, management of severe accidents, subcontracting conditions. The third part addresses the same issues for nuclear installations other than nuclear power reactors

48 CFR 252.219-7003 - Small business subcontracting plan (DoD contracts).

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Small business... AND CONTRACT CLAUSES Text of Provisions And Clauses 252.219-7003 Small business subcontracting plan (DoD contracts). As prescribed in 219.708(b)(1)(A), use the following clause: Small Business...

DOE Defense Program (DP) safety programs. Final report, Task 003

International Nuclear Information System (INIS)

1998-01-01

The overall objective of the work on Task 003 of Subcontract 9-X52-W7423-1 was to provide LANL with support to the DOE Defense Program (DP) Safety Programs. The effort included the identification of appropriate safety requirements, the refinement of a DP-specific Safety Analysis Report (SAR) Format and Content Guide (FCG) and Comprehensive Review Plan (CRP), incorporation of graded approach instructions into the guidance, and the development of a safety analysis methodologies document. All tasks which were assigned under this Task Order were completed. Descriptions of the objectives of each task and effort performed to complete each objective is provided here

Two cases of methyl alcohol intoxication by sub-chronic inhalation and dermal exposure during aluminum CNC cutting in a small-sized subcontracted factory.

Science.gov (United States)

Ryu, Jia; Lim, Key Hwan; Ryu, Dong-Ryeol; Lee, Hyang Woon; Yun, Ji Young; Kim, Seoung-Wook; Kim, Ji-Hoon; Jung-Choi, Kyunghee; Kim, Hyunjoo

2016-01-01

Methyl alcohol poisoning has been mainly reported in community. Two cases of methyl alcohol poisoning occurred in a small-sized subcontracted factory which manufactured smartphone parts in Korea. One young female patient presented with dyspnea and visual disturbance. Another young male patient presented with visual disturbance and myalgia. They treated with sodium bicarbonate infusion and hemodialysis for metabolic acidosis. In addition, he received ethyl alcohol per oral treatment. Her and his urinary methyl alcohol concentration was detected as 7.632 mg/L, 46.8 mg/L, respectively, although they were treated hemodialysis. Results of the working environment measurement showed that the concentration of methyl alcohol (1030.1-2220.5 ppm) in the air exceeded the time weighted average (200 ppm). They were diagnosed with optic neuropathy due to methyl alcohol poisoning and still have visual impairment. Workers who hired as dispatched employees in a small-sized subcontracted factory were exposed to high concentrations of methyl alcohol. The workplace had poor ventilation system. In addition, workers did not wear proper personal protect equipment. Working environment measurement and annual chekups for workers were not performed. They were in a blind spot to occupational safety and health. More attention is needed to protect vulnerable workers' health.

Complementary safety assessment assessment of nuclear facilities - Tricastin facility - AREVA

International Nuclear Information System (INIS)

2011-01-01

This complementary safety assessment analyses the robustness of the Areva part of the Tricastin nuclear site to extreme situations such as those that led to the Fukushima accident. This study includes the following facilities: Areva NC Pierrelatte, EURODIF production, Comurhex Pierrelatte, Georges Besse II plant and Socatri. Robustness is the ability for the plant to withstand events beyond which the plant was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accidental sequence. Moreover, safety is not only a matter of design or engineered systems but also a matter of organizing: task organization (including subcontracting) as well as the setting of emergency plans or the inventory of nuclear materials are taken into consideration in this assessment. This report is divided into 10 main chapters: 1) the feedback experience of the Fukushima accident; 2) description of the site and its surroundings; 3) featuring of the site's activities and installations; 4) accidental sequences; 5) protection from earthquakes; 6) protection from floods; 7) protection from other extreme natural disasters; 8) the loss of electrical power and of the heat sink; 9) the management of severe accidents; and 10) subcontracting policy. This analysis has identified 5 main measures to be taken to limit the risks linked to natural disasters: -) continuing the program for replacing the current conversion plant and the enrichment plant; -) renewing the storage of hydrofluoric acid at the de-fluorination workshop; -) assessing the seismic behaviour of some parts of the de-fluorination workshop and of the fluorine fabrication workshop; -) improving the availability of warning and information means in case of emergency; and -) improving the means to mitigate accidental gaseous releases. (A.C.)

Nuclear safety culture in Finland and Sweden - Developments and challenges

International Nuclear Information System (INIS)

Reiman, T.; Pietikaeinen, E.; Kahlbom, U.; Rollenhagen, C.

2011-02-01

The project aimed at studying the concept of nuclear safety culture and the Nordic nuclear branch safety culture. The project also aimed at looking how the power companies and the regulators view the current responsibilities and role of subcontractors in the Nordic nuclear safety culture as well as to inspect the special demands for safety culture in subcontracting chains. Interview data was collected in Sweden (n = 14) and Finland (n = 16) during 2009. Interviewees represented the major actors in the nuclear field (regulators, power companies, expert organizations, waste management organizations). Results gave insight into the nature and evaluation of safety culture in the nuclear industry. Results illustrated that there is a wide variety of views on matters that are considered important for nuclear safety within the Nordic nuclear community. However, the interviewees considered quite uniformly such psychological states as motivation, mindfulness, sense of control, understanding of hazards and sense of responsibility as important for nuclear safety. Results also gave insight into the characteristics of Nordic nuclear culture. Various differences in safety cultures in Finland and Sweden were uncovered. In addition to the differences, historical reasons for the development of the nuclear safety cultures in Finland and Sweden were pointed out. Finally, results gave implications that on the one hand subcontractors can bring new ideas and improvements to the plants' practices, but on the other hand the assurance of necessary safety attitudes and competence of the subcontracting companies and their employees is considered as a challenge. The report concludes that a good safety culture requires a deep and wide understanding of nuclear safety including the various accident mechanisms of the power plants as well as a willingness to continuously develop one's competence and understanding. An effective and resilient nuclear safety culture has to foster a constant sense of

EDF - The Inspector General's report on Nuclear Safety and Radiation Protection 2009

International Nuclear Information System (INIS)

2010-01-01

After a first chapter in which the Inspector General states his own vision of facts and results regarding nuclear safety and radiation protection for 2009, the relationship with the ASN (Nuclear safety authority), and also gives his own impression on the whole EDF nuclear system, the next chapters more particularly address the following topics: safety management, radiation protection of interveners, abilities and education for new challenges, the exploitation quality, the implementation of new regulatory arrangements, the extension of exploitation duration, the EPR project, the doctors as actors of safety management, service providing or subcontracting companies and fleet performance, prevention and struggle against fire, the activity of British Energy which is part of the EDF group, events which occurred within the EDF group (exposure of an intervener, incidents involving fuel components, biases in work monitoring, a fire on a turbo generator, an incident in Dungeness), lessons drawn from other industrial events (in a Russian hydroelectric station and in a refinery in Texas), and visits in China and in Japan

48 CFR 226.370-8 - Goals and incentives for subcontracting with HBCU/MIs.

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Goals and incentives for subcontracting with HBCU/MIs. 226.370-8 Section 226.370-8 Federal Acquisition Regulations System DEFENSE ACQUISITION REGULATIONS SYSTEM, DEPARTMENT OF DEFENSE SOCIOECONOMIC PROGRAMS OTHER SOCIOECONOMIC PROGRAMS Historically Black Colleges and...

Safety activities in small businesses

Science.gov (United States)

Sinclair, Raymond C.; Cunningham, Thomas R.

2015-01-01

Background Workplace injuries occur at higher rates in smaller firms than in larger firms, and the number of workplace safety activities appear to be inversely associated with those rates. Predictors of safety activities are rarely studied. Methods This study uses data from a national random survey of firms (n = 722) with less than 250 employees conducted in 2002. Results We found that, regardless of firm size or industry, safety activities were more common in 2002 than they were in a similar 1983 study. Having had an OSHA inspection in the last five years and firm size were stronger predictors of safety activities than industry hazardousness and manager’s perceptions of hazardousness. All four variables were significant predictors (β range .19 to .28; R2 = .27). Conclusions Further progress in the prevention of injuries in small firms will require attention to factors likely subsumed within the firm size variable, especially the relative lack of slack resources that might be devoted to safety activities. PMID:26339124

13 CFR 121.410 - What are the size standards for SBA's Section 8(d) Subcontracting Program?

Science.gov (United States)

2010-01-01

... Size Eligibility Requirements for Government Procurement § 121.410 What are the size standards for SBA... Small Business Act, a concern is small for subcontracts which relate to Government procurements if it...

External PCR, ASN's decision

International Nuclear Information System (INIS)

Anon.

2012-01-01

The French law imposes in some situations the presence of a person skilled in radiation protection (PCR). This article describes the cases when this person must belong to the staff of the enterprise or when this person may be sub-contracted. For instance in most nuclear facilities the PCR must be on the payroll, for enterprises dedicated to nuclear transport the PCR's job can be sub-contracted. A decision given by the ASN (French Nuclear Safety Authority) sets the minimal requests (in terms of training, job contract, activities) of the sub-contracted PCR. (A.C.)

Safety assessment for facilities and activities. General safety requirements. Pt. 4

International Nuclear Information System (INIS)

2009-01-01

The Safety Fundamentals publication, Fundamental Safety Principles, establishes principles for ensuring the protection of workers, the public and the environment, now and in the future, from harmful effects of ionizing radiation. The objective of this Safety Requirements publication is to establish the generally applicable requirements to be fulfilled in safety assessment for facilities and activities, with special attention paid to defence in depth, quantitative analyses and the application of a graded approach to the ranges of facilities and of activities that are addressed. The publication also addresses the independent verification of the safety assessment that needs to be carried out by the originators and users of the safety assessment. This publication is intended to provide a consistent and coherent basis for safety assessment across all facilities and activities, which will facilitate the transfer of good practices between organizations conducting safety assessments and will assist in enhancing the confidence of all interested parties that an adequate level of safety has been achieved for facilities and activities. The requirements, which are derived from the Fundamental Safety Principles, relate to any human activity that may cause people to be exposed to radiation risks arising from facilities and activities, as follows: Facilities includes: (a) Nuclear power plants; (b) Other reactors (such as research reactors and critical assemblies); (c) Enrichment facilities and fuel fabrication facilities; (d) Conversion facilities used to generate UF 6 ; (e) Storage and reprocessing plants for irradiated fuel; (f) Facilities for radioactive waste management where radioactive waste is treated, conditioned, stored or disposed of; (g) Any other places where radioactive materials are produced, processed, used, handled or stored; (h) Irradiation facilities for medical, industrial, research and other purposes, and any places where radiation generators are installed; (i

Safety Assessment for Facilities and Activities. General Safety Requirements. Pt. 4

International Nuclear Information System (INIS)

2009-01-01

The Safety Fundamentals publication, Fundamental Safety Principles, establishes principles for ensuring the protection of workers, the public and the environment, now and in the future, from harmful effects of ionizing radiation. The objective of this Safety Requirements publication is to establish the generally applicable requirements to be fulfilled in safety assessment for facilities and activities, with special attention paid to defence in depth, quantitative analyses and the application of a graded approach to the ranges of facilities and of activities that are addressed. The publication also addresses the independent verification of the safety assessment that needs to be carried out by the originators and users of the safety assessment. This publication is intended to provide a consistent and coherent basis for safety assessment across all facilities and activities, which will facilitate the transfer of good practices between organizations conducting safety assessments and will assist in enhancing the confidence of all interested parties that an adequate level of safety has been achieved for facilities and activities. The requirements, which are derived from the Fundamental Safety Principles, relate to any human activity that may cause people to be exposed to radiation risks arising from facilities and activities, as follows: Facilities includes: (a) Nuclear power plants; (b) Other reactors (such as research reactors and critical assemblies); (c) Enrichment facilities and fuel fabrication facilities; (d) Conversion facilities used to generate UF6; (e) Storage and reprocessing plants for irradiated fuel; (f) Facilities for radioactive waste management where radioactive waste is treated, conditioned, stored or disposed of; (g) Any other places where radioactive materials are produced, processed, used, handled or stored; (h) Irradiation facilities for medical, industrial, research and other purposes, and any places where radiation generators are installed; (i

Safety Assessment for Facilities and Activities. General Safety Requirements. Pt. 4

International Nuclear Information System (INIS)

2010-01-01

The Safety Fundamentals publication, Fundamental Safety Principles, establishes principles for ensuring the protection of workers, the public and the environment, now and in the future, from harmful effects of ionizing radiation. The objective of this Safety Requirements publication is to establish the generally applicable requirements to be fulfilled in safety assessment for facilities and activities, with special attention paid to defence in depth, quantitative analyses and the application of a graded approach to the ranges of facilities and of activities that are addressed. The publication also addresses the independent verification of the safety assessment that needs to be carried out by the originators and users of the safety assessment. This publication is intended to provide a consistent and coherent basis for safety assessment across all facilities and activities, which will facilitate the transfer of good practices between organizations conducting safety assessments and will assist in enhancing the confidence of all interested parties that an adequate level of safety has been achieved for facilities and activities. The requirements, which are derived from the Fundamental Safety Principles, relate to any human activity that may cause people to be exposed to radiation risks arising from facilities and activities, as follows: Facilities includes: (a) Nuclear power plants; (b) Other reactors (such as research reactors and critical assemblies); (c) Enrichment facilities and fuel fabrication facilities; (d) Conversion facilities used to generate UF6; (e) Storage and reprocessing plants for irradiated fuel; (f) Facilities for radioactive waste management where radioactive waste is treated, conditioned, stored or disposed of; (g) Any other places where radioactive materials are produced, processed, used, handled or stored; (h) Irradiation facilities for medical, industrial, research and other purposes, and any places where radiation generators are installed; (i

Safety Assessment for Facilities and Activities. General Safety Requirements. Pt. 4

International Nuclear Information System (INIS)

2009-01-01

The Safety Fundamentals publication, Fundamental Safety Principles, establishes principles for ensuring the protection of workers, the public and the environment, now and in the future, from harmful effects of ionizing radiation.? read more The objective of this Safety Requirements publication is to establish the generally applicable requirements to be fulfilled in safety assessment for facilities and activities, with special attention paid to defence in depth, quantitative analyses and the application of a graded approach to the ranges of facilities and of activities that are addressed. The publication also addresses the independent verification of the safety assessment that needs to be carried out by the originators and users of the safety assessment. This publication is intended to provide a consistent and coherent basis for safety assessment across all facilities and activities, which will facilitate the transfer of good practices between organizations conducting safety assessments and will assist in enhancing the confidence of all interested parties that an adequate level of safety has been achieved for facilities and activities. The requirements, which are derived from the Fundamental Safety Principles, relate to any human activity that may cause people to be exposed to radiation risks arising from facilities and activities, as follows: Facilities includes: (a) Nuclear power plants; (b) Other reactors (such as research reactors and critical assemblies); (c) Enrichment facilities and fuel fabrication facilities; (d) Conversion facilities used to generate UF6; (e) Storage and reprocessing plants for irradiated fuel; (f) Facilities for radioactive waste management where radioactive waste is treated, conditioned, stored or disposed of; (g) Any other places where radioactive materials are produced, processed, used, handled or stored; (h) Irradiation facilities for medical, industrial, research and other purposes, and any places where radiation generators are

Reactor safety; Description and evaluation of safety activities in Nordic countries

International Nuclear Information System (INIS)

Wahlstroem, B.; Gunsell, L.

1998-03-01

The report gives a description of safety activities in the nuclear power industry. The study has been carried out as a part of the four year programme in Nordic Safety Research (NKS) which was completed in 1997. The objective of the NKS/RAK-1.1 project 'A survey and an evaluation of safety activities in nuclear power' was to make a broad description of various activities important for safety and to make an assessment of their efficiency. A special consideration was placed on a comparison of practices in Finland and Sweden, and between their nuclear utilities. The study has been divided into two parts, one theoretical part in which a model of the relationships between various activities important for safety has been constructed and one practical part where a total of 62 persons have been interviewed at the authorities, the nuclear utilities and one reactor vendor. To restrict the amount of work two activities, safety analysis and experience feedback, were selected. A few cases connected to incidents at nuclear power plants were discussed in more detail. The report has been structured around a simple model of nuclear safety consisting of the concepts of goals, means and outcomes. This model illustrates the importance of goal formulation, systematic planning and feedback of operational experience as major components in nuclear safety. In assessing organisation and management at authorities and the power utilities there is a clear trend of decentralisation and delegation of authority. The general impression from the study is that the safety activities in Finland and Sweden are efficient and well targeted. The experience from the methodology is favourable and the comparison of practices gives a good ground for a discussion of contents and targeting of safety activities. (EG) activities. (EG)

Additional safety assessment of ITER - Addition safety investigation of the INB ITER

International Nuclear Information System (INIS)

2012-01-01

This assessment aims at re-assessing safety margins in the light of events which occurred in Fukushima Daiichi, i.e. extreme natural events challenging the safety of installations. After a presentation of some characteristics of the ITER installation (location, activities, buildings, premise detritiation systems, electric supply, handling means, radioactive materials, chemical products, nuclear risks, specific risks), the report addresses the installation robustness by identifying cliff-edge effect risks which can be related to a loss of confinement of radioactive materials, explosions, a significant increase of exposure level, a possible effect on water sheets, and so on. The next part addresses the various aspects related to a seismic risk: installation sizing (assessment methodology, seismic risk characterization in Cadarache), sizing protection measures, installation compliance, and margin assessment. External flooding is the next addressed risk: installation sizing with respect to this specific risk, protection measures, installation compliance, margin assessment, and studied additional measures. Other extreme natural phenomena are considered (meteorological conditions, earthquake and flood) which may have effects on other installations (dam, canal). Then, the report addresses technical risks like the loss of electric supplies and cooling systems, the way a crisis is managed in terms of technical and human means and organization in different typical accidental cases. Subcontracting practices are also discussed. A synthesis proposes an overview of this additional safety assessment and discusses the impact which could have additional measures which could be implemented

Nuclear safety culture in Finland and Sweden - Developments and challenges

Energy Technology Data Exchange (ETDEWEB)

Reiman, T.; Pietikaeinen, E. (Technical Research Centre of Finland, VTT (Finland)); Kahlbom, U. (RiskPilot AB (Sweden)); Rollenhagen, C. (Royal Institute of Technology (KTH) (Sweden))

2011-02-15

The project aimed at studying the concept of nuclear safety culture and the Nordic nuclear branch safety culture. The project also aimed at looking how the power companies and the regulators view the current responsibilities and role of subcontractors in the Nordic nuclear safety culture as well as to inspect the special demands for safety culture in subcontracting chains. Interview data was collected in Sweden (n = 14) and Finland (n = 16) during 2009. Interviewees represented the major actors in the nuclear field (regulators, power companies, expert organizations, waste management organizations). Results gave insight into the nature and evaluation of safety culture in the nuclear industry. Results illustrated that there is a wide variety of views on matters that are considered important for nuclear safety within the Nordic nuclear community. However, the interviewees considered quite uniformly such psychological states as motivation, mindfulness, sense of control, understanding of hazards and sense of responsibility as important for nuclear safety. Results also gave insight into the characteristics of Nordic nuclear culture. Various differences in safety cultures in Finland and Sweden were uncovered. In addition to the differences, historical reasons for the development of the nuclear safety cultures in Finland and Sweden were pointed out. Finally, results gave implications that on the one hand subcontractors can bring new ideas and improvements to the plants' practices, but on the other hand the assurance of necessary safety attitudes and competence of the subcontracting companies and their employees is considered as a challenge. The report concludes that a good safety culture requires a deep and wide understanding of nuclear safety including the various accident mechanisms of the power plants as well as a willingness to continuously develop one's competence and understanding. An effective and resilient nuclear safety culture has to foster a constant

Safety Culture Activities of HANARO in 2007

Energy Technology Data Exchange (ETDEWEB)

Wu, Jong Sup [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2008-05-15

One of the important aims of a management system for nuclear facilities is to foster a strong safety culture. The safety culture activities in HANARO have been continuously conducted to enhance its safe operation. The following activities and events on a safety culture were performed last year; - Seminars and lectures on safety for the 'Nuclear Safety Check Day' every month - Development of safety culture indicators - Development of operational SPIs (Safety Performance Indicators) - Preparation of an e-Learning program for safety education. In this paper, the safety culture activities in HANARO of KAERI are described, and the efforts necessary for a safety improvement are presented.

48 CFR 252.244-7000 - Subcontracts for Commercial Items and Commercial Components (DoD Contracts).

Science.gov (United States)

2010-10-01

... under this contract: (a) 252.225-7009 Restriction on Acquisition of Certain Articles Containing... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Subcontracts for Commercial Items and Commercial Components (DoD Contracts). 252.244-7000 Section 252.244-7000 Federal...

105-N Basin sediment removal subcontract acquisition strategy plan

International Nuclear Information System (INIS)

Wilsey, D.J.

1997-01-01

The 105-N Basin Sediment Removal Subcontract Acquisition Strategy Plan provides a detailed set of actions to specify and procure services and equipment for removal of approximately 400 ft 3 (wet) of radioactive sediment. The plan outlines a cost-effective approach to remove this sediment safely and within an aggressive schedule. This 105-N Basin Sediment Removal Strategy Plan includes the following key elements: a current vendor survey of capabilities and interest in this type of work, confirming that qualified, competitive sources are available, and in the time frame required; a systematic review of the various options for sediment disposal in enough detail to exhaustively uncover pros and cons of each approach; use of a workshop approach to assess different ways to accomplish the work and ensure the disposal options considered are cost and schedule effective; integration of the complicated sampling and characterization process, which is essential to successful execution of the procurement scheme; review of the various subcontracting options to maximize the use of existing technology, existing equipment, and specialized expertise; detailed early planning and strategizing for early identification of problems that can be solved early before they become restraints or potential added costs; tailored design schedule to cover three alternate approaches so that sample characterization will not delay engineering preparation for disposal; support required from various organizations onsite as well as subcontractors, well in advance of the need for that support, improving availability of the proper personnel to support schedule and cost objectives; and provides the possible opportunity to process the sediment in the valve pit and pump pit through this same subcontractor's process

Phenix plant - Complementary safety assessment of the Phenix plant (INB 71) in the light of the Fukushima accident

International Nuclear Information System (INIS)

2011-01-01

This CSA (Complementary Safety Assessment) analyses the robustness of the Phenix reactor to extreme situations such as those that led to the Fukushima accident and proposes a series of improvements. The Phenix reactor stands on the Marcoule site of CEA and was stopped definitely in 2009 for electricity production. Robustness is the ability for the facility to withstand events beyond the level for which the facility was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accident sequence (cliff edge effect). Safety is not only a matter of design or of engineered systems, it is also a matter of organization. So issues like crisis organization and work organization via subcontracting are also taken into consideration. This report is divided into 9 main chapters: 1) main features of the Phenix facility, 2) identification of cliff edge risks as well as structures and equipment essential to safety, 3) earthquake risk, 4) flood risk, 5) risks due to other extreme natural disasters, 6) the loss of electrical power supplies and of cooling systems, 7) management of severe accidents, 8) subcontracting policy, 9) synthesis. This study shows that it is necessary to take some measures to reinforce the robustness of the plant concerning flood risks. (A.C.)

Jules Horowitz reactor - Complementary safety assessment in the light of the Fukushima accident

International Nuclear Information System (INIS)

2011-01-01

This CSA (Complementary Safety Assessment) analyses the robustness of the Jules Horowitz reactor (RJH) to extreme situations such as those that led to the Fukushima accident and proposes a series of improvements. RJH is being built on the Cadarache CEA's site. Robustness is the ability for the facility to withstand events beyond the level for which the facility was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accident sequence (cliff edge effect). Safety is not only a matter of design or of engineered systems, it is also a matter of organization. So issues like RJH's crisis organization, the organization of radiation protection, and work organization via subcontracting are also taken into consideration. This report is divided into 9 main chapters: 1) main features of the RJH facility, 2) identification of cliff edge risks and of equipment essential for safety, 3) earthquake risk, 4) flood risk, 5) risks due to other extreme natural disasters, 6) the loss of electrical power supplies and of cooling systems, 7) management of severe accidents, 8) subcontracting policy, 9) synthesis and list of improvements. This study shows a globally good robustness of the RJH for the considered risks. Nevertheless it can considered relevant to increase the robustness of the plant on a few points: -) to increase the seismic safety margins of some pieces of equipment, -) to increase the robustness of the internal electrical power supplies, -) to increase the fuel cooling capacity, and -) to improve the management of the post-accidental period. (A.C.)

EDA activities related to safety

International Nuclear Information System (INIS)

Gordon, C.; Raeder, J.

2001-01-01

This article reviews the accomplishments in ITER safety analysis during the course of the Engineering Design Activities (EDA). The key aspects of ITER safety analysis are: effluents and emissions from normal operation, including planned maintenance activities; occupational safety for workers at the facility; radioactive materials and wastes generated during operation and from decommissioning ; potential incidents and accidents and the resulting transients. As a result of the work during the EDA it is concluded that ITER is safe

48 CFR 970.1907 - Subcontracting with Small Business, Small Disadvantaged Business and Woman-Owned Small Business...

Science.gov (United States)

2010-10-01

... MANAGEMENT AND OPERATING CONTRACTS Small, Small Disadvantaged and Women-Owned Small Business Concerns 970.1907 Subcontracting with Small Business, Small Disadvantaged Business and Woman-Owned Small Business... Business, Small Disadvantaged Business and Woman-Owned Small Business Concerns. 970.1907 Section 970.1907...

IAEA safety requirements for safety assessment of fuel cycle facilities and activities

International Nuclear Information System (INIS)

Jones, G.

2013-01-01

The IAEA's Statute authorises the Agency to establish standards of safety for protection of health and minimisation of danger to life and property. In that respect, the IAEA has established a Safety Fundamentals publication which contains ten safety principles for ensuring the protection of workers, the public and the environment from the harmful effects of ionising radiation. A number of these principles require safety assessments to be carried out as a means of evaluating compliance with safety requirements for all nuclear facilities and activities and to determine the measures that need to be taken to ensure safety. The safety assessments are required to be carried out and documented by the organisation responsible for operating the facility or conducting the activity, are to be independently verified and are to be submitted to the regulatory body as part of the licensing or authorisation process. In addition to the principles of the Safety Fundamentals, the IAEA establishes requirements that must be met to ensure the protection of people and the environment and which are governed by the principles in the Safety Fundamentals. The IAEA's Safety Requirements publication 'Safety Assessment for Facilities and Activities', establishes the safety requirements that need to be fulfilled in conducting and maintaining safety assessments for the lifetime of facilities and activities, with specific attention to defence in depth and the requirement for a graded approach to the application of these safety requirements across the wide range of fuel cycle facilities and activities. Requirements for independent verification of the safety assessment that needs to be carried out by the operating organisation, including the requirement for the safety assessment to be periodically reviewed and updated are also covered. For many fuel cycle facilities and activities, environmental impact assessments and non-radiological risk assessments will be required. The

Under pressure, out of control, or home alone? Reviewing research and policy debates on the occupational health and safety effects of outsourcing and home-based work.

Science.gov (United States)

Quinlan, Michael; Bohle, Philip

2008-01-01

The practice of outsourcing or subcontracting of work has grown rapidly in most countries over the past two decades. Outsourcing, de-institutionalization, and a range of other practices have also resulted in a growth of home-based work. Home-based workers, even when not part of a subcontracting process, operate in an isolated situation remote from their employer and other workers. Do such work arrangements expose workers to greater risk of injury, illness, or assault? The authors reviewed international studies of the occupational health and safety (OHS) effects of subcontracting and home-based work undertaken over the past 20 years. Of the 25 studies analyzed, 92 percent found poorer OHS outcomes. The studies were examined for clues about the reasons for these negative outcomes. The authors also identified similarities and differences between subcontracting and home-based work. Despite the evidence of poor OHS outcomes, research into outsourcing has stalled in recent years. With notable exceptions, governments have taken little account of findings on these work arrangements in their laws and policies, in part because neoliberal ideas dominate national and global policy agendas. The authors examine policy challenges and regulatory responses and make suggestions for future research and policy interventions.

Planned activities to improve safety

International Nuclear Information System (INIS)

1998-01-01

This document presents the fulfilling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 6 of the document contains some details about the planed activities to safety improvements

A solar regenerative thermoelectrochemical converter (RTEC). Executive summary of final subcontract report

Energy Technology Data Exchange (ETDEWEB)

Townsend, C.W.; McHardy, J. [Hughes Aircraft Co., El Segundo, CA (United States)

1992-02-01

This is an executive summary of a final subcontract report that describes the successful completion of a closed-loop demonstration of a regenerative thermoelectromechanical device using solar heat input for the production of electricity. The full report, which contains a detailed description of the two-year effort, is currently subject to a government secrecy order which precludes public release of the information. Copies of the full report will be made available for general release whenever the secrecy order is lifted.

48 CFR 212.570 - Applicability of certain laws to contracts and subcontracts for the acquisition of commercially...

Science.gov (United States)

2010-10-01

..., DEPARTMENT OF DEFENSE ACQUISITION PLANNING ACQUISITION OF COMMERCIAL ITEMS Applicability of Certain Laws to the Acquisition of Commercial Items 212.570 Applicability of certain laws to contracts and... laws to contracts and subcontracts for the acquisition of commercially available off-the-shelf items...

Subcontracted Forms and “Intermediary” Agents of Employment Relationships: Foremen in the Construction Sector

Directory of Open Access Journals (Sweden)

Elife Kart

2016-12-01

Full Text Available Integration of flexible and precarious structure of employment conditions and relations with subcontracting strategies enables companies to conserve their competitive power in one sense; it also introduces the conditions, which are increasingly irregulated, temporal and destabilized, with regards to the labour power. On the other hand subcontracting, as a strategy of fragmenting, individualizing and isolating labour power in itself means that working conditions have been becoming more manageable in terms of capital. In this study, focusing on the positions of intermediary persons, defined as foremen in the labour market, especially in the construction sector, the strategies with which employment relationships become increasingly unsteady, indefinite and temporal are discussed. On the one hand, depending on the efforts of capital to reproduce itself on a global scale, the effects of capital on labour power are considered on the other, how these efforts produce the intermediary agents and through them how the labour power is instrumentilized as a tool of profit and productivity are analyzed. And the fabrication of the intermediary agents, which make the new forms of domination in employment relationships visible, is studied. The study is discussed through data gathered from in-depth interviews with subcontractors

Additional safety assessment of the ATALANTE installation (INB nr 148) with respect to the accident which occurred in the Fukushima-Daiichi power station

International Nuclear Information System (INIS)

2012-01-01

After a presentation of some characteristics of the ATALANTE base nuclear installation (site, activities, buildings, laboratories, materials, status with respect to the additional safety assessment), this document reports the identification of cliff-edge risks and of critical structures and equipment. Then, it addresses the different risks: earthquake (installation sizing, margin assessment, earthquake-induced risks), flooding (different origins, alarm measures), other extreme natural events (lightning, rain falls, extreme earthquake with induced flooding), loss of electric supplies and of cooling systems (separately or combined). The next parts address the organization and means of intervention for severe accident management, and subcontracting practices

Regulatory Activities for Licensee's Safety Culture

International Nuclear Information System (INIS)

Choi, Young Sung; Choi, Kwang Sik

2008-01-01

Weaknesses in safety culture have contributed to a number of incidents/accidents in the nuclear and other high hazard sectors worldwide in the past. These events have fostered an increasing awareness of the need for licensees to develop a strong safety culture to support successful and sustainable nuclear safety performance. Regulatory bodies are taking a growing interest in this issue, and several are actively working to develop and implement approaches to maintaining regulatory oversight of licensee safety culture. However, these approaches are not yet well-established, and it was considered prudent to share experiences and developing methodologies in order to disseminate good practices and avoid potential pitfalls. This paper presents the findings, conclusions and recommendations of international meetings and other countries' activities on safety culture and gives some suggestions for regulators to consider when planning regulatory oversight for licensee's safety culture

Security of payment in Malaysian construction industry: issues on sub-contract's direct payment

OpenAIRE

Supardi, Azizan; Adnan, Hamimah

2011-01-01

In Malaysia, sub-contractors have to bear with the current structure of payment mechanisms in the standard forms of contract, which are payment upon certification, direct payment from the employer, and contingent or conditional payment. However, „direct payment‟ provision is applied for in most of the nominated sub-contracts and not to the domestic sub-contractors; thus the Construction Industry Payment and Adjudication (CIPA) Act is proposed. This paper, though, is to disclose the findings o...

Using subcontractors: the experience of IRSN and INRS

International Nuclear Information System (INIS)

Jeffroy, Francois; Hery, Michel

2014-01-01

This article discusses the current status and assessment of risks and opportunities associated with subcontracting in nuclear installations as perceived and addressed by the IRSN (Institut de Radioprotection et de Surete Nucleaire) and the INRS (Institut National de Recherche et de Securite). A first part recalls how these issues have been addressed since the 1990's. The author notices that subcontracting is associated with different terminologies for the IRSN and the INRS. In the next part, the author discusses the debate about subcontracting. He outlines that the organisation of the client must be examined, notably with respect to safety, to the way ability and traceability of subcontractor activities are considered and addressed. He comments the relationships between the client and its subcontractors. He briefly comments how the IRSN and the INRS address differently these issues related to subcontracting

Risk communication activities toward nuclear safety in Tokai: your safety is our safety

International Nuclear Information System (INIS)

Tsuchiya, T.

2007-01-01

As several decades have passed since the construction of nuclear power plants began, residents have become gradually less interested in nuclear safety. The Tokai criticality accident in 1909, however, had roused residents in Tokai-Mura to realize that they live with nuclear technology risks. To prepare a field of risk communication, the Tokai-Mura C 3 project began as a pilot research project supported by NISA. Alter the project ended, we are continuing risk. communication activities as a non-profit organisation. The most important activity of C 3 project is the citizen's inspection programme for nuclear related facilities. This programme was decided by participants who voluntarily applied to the project. The concept of the citizen's inspection programme is 'not the usual facility tours'. Participants are involved from the planning stage and continue to communicate with workers of the inspected nuclear facility. Since 2003, we have conducted six programmes for five nuclear related organisations. Participants evaluated that radiation protection measures were near good but there were some problems concerning the worker's safety and safety culture, and proposed a mixture of advice based on personal experience. Some advice was accepted and it did improve the facility's safety measures. Other suggestions were not agreed upon by nuclear organisations. The reason lies in the difference of concept between the nuclear expert's 'safety' and the citizen's 'safety'. Residents do not worry about radiation only, but also about the facility's safety as a whole including the worker's safety. They say, 'If the workers are not safe, you also are unable to protect us'. Although the disagreement remained, the participants and the nuclear industry learned much about each other. Participating citizens received a substantial amount of knowledge about the nuclear industry and its safety measures, and feel the credibility and openness of the nuclear industry. On the other hand, the nuclear

Poor Government Oversight of Anham and Its Subcontracting Procedures Allowed Questionable Costs To Go Undetected

Science.gov (United States)

2011-07-30

contractor purchasing system review of Anham. Management Comments and Audit Response The Defense Contract Mangement Agency and the U.S. Central... Introduction 1  Background 1  Government Agency Roles and Oversight Responsibilities 4  Objectives 7  Weak Government Oversight Resulted in Significant...Subcontracting Procedures Allowed Questionable Costs To Go Undetected SIGIR 11-022 July 30, 2011 Introduction Since 2003, the United States Government

Safety culture activities in HANARO

International Nuclear Information System (INIS)

Lim, I. C.; Park, C.; Hwang, S. R.; Choi, H. Y.; Jeon, B. J.

2002-01-01

The yearly operation time and the number of users in HANARO are increasing since its initial criticality has been achieved in 1995. This achievement is partly in debt to the spread of safety culture to operators and reactor users. In this paper, the activities done by the reactor operation organization on safety culture are described, and their further efforts identified to be necessary for the improvement and dissemination of safety culture and are presented

IAEA activities on research reactor safety

International Nuclear Information System (INIS)

Alcala-Ruiz, F.

1995-01-01

Since its inception in 1957, the International Atomic Energy Agency (IAEA) has included activities in its programme to address aspects of research reactors such as safety, utilization and fuel cycle considerations. These activities were based on statutory functions and responsibilities, and on the current situation of research reactors in operation around the world; they responded to IAEA Member States' general or specific demands. At present, the IAEA activities on research reactors cover the above aspects and respond to specific and current issues, amongst which safety-related are of major concern to Member States. The present IAEA Research Reactor Safety Programme (RRSP) is a response to the current situation of about 300 research reactors in operation in 59 countries around the world. (orig.)

Golfech plant - Report on the complementary safety assessment of nuclear facilities in the light of the Fukushima accident

International Nuclear Information System (INIS)

2011-01-01

This CSA (Complementary Safety Assessment) analyses the robustness of the Golfech plant to extreme situations such as those that led to the Fukushima accident and proposes a series of improvements. Robustness is the ability for the plant to withstand events beyond the level for which the plant was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accident sequence. Safety is not only a matter of design or of engineered systems, it is also a matter of organization. So issues like EDF's crisis organization, the organization of radiation protection, and work organization via subcontracting are also taken into consideration. The creation of a nuclear rapid action force (FARN) is proposed: this will be a national emergency force made up of specialized teams equipped to intervene in less than 24 hours on a nuclear site hit by an accident. This report is divided into 8 main chapters: 1) features of the site, 2) earthquake risk, 3) flooding risk, 4) risks due to other extreme natural disasters, 5) the loss of electrical power supplies and of heat sink, 6) management of severe accidents (accidents with core melt), 7) task subcontracting policy, 8) synthesis and list of improvements. 4 following appendices review: EDF's crisis organization, the FARN, radiation protection organization and accidental event trees. (A.C.)

Tricastin plant - Report on the complementary safety assessment of nuclear facilities in the light of the Fukushima accident

International Nuclear Information System (INIS)

2011-01-01

This CSA (Complementary Safety Assessment) analyses the robustness of the Tricastin plant to extreme situations such as those that led to the Fukushima accident and proposes a series of improvements. Robustness is the ability for the plant to withstand events beyond the level for which the plant was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accident sequence. Safety is not only a matter of design or of engineered systems, it is also a matter of organization. So issues like EDF's crisis organization, the organization of radiation protection, and work organization via subcontracting are also taken into consideration. The creation of a nuclear rapid action force (FARN) is proposed: this will be a national emergency force made up of specialized teams equipped to intervene in less than 24 hours on a nuclear site hit by an accident. This report is divided into 8 main chapters: 1) features of the site, 2) earthquake risk, 3) flooding risk, 4) risks due to other extreme natural disasters, 5) the loss of electrical power supplies and of heat sink, 6) management of severe accidents (accidents with core melt), 7) task subcontracting policy, 8) synthesis and list of improvements. 4 following appendices review: EDF's crisis organization, the FARN, radiation protection organization and accidental event trees. (A.C.)

Bugey plant - Report on the complementary safety assessment of nuclear facilities in the light of the Fukushima accident

International Nuclear Information System (INIS)

2011-01-01

This CSA (Complementary Safety Assessment) analyses the robustness of the Bugey plant to extreme situations such as those that led to the Fukushima accident and proposes a series of improvements. Robustness is the ability for the plant to withstand events beyond the level for which the plant was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accident sequence. Safety is not only a matter of design or of engineered systems, it is also a matter of organization. So issues like EDF's crisis organization, the organization of radiation protection, and work organization via subcontracting are also taken into consideration. The creation of a nuclear rapid action force (FARN) is proposed: this will be a national emergency force made up of specialized teams equipped to intervene in less than 24 hours on a nuclear site hit by an accident. This report is divided into 8 main chapters: 1) features of the site, 2) earthquake risk, 3) flooding risk, 4) risks due to other extreme natural disasters, 5) the loss of electrical power supplies and of heat sink, 6) management of severe accidents (accidents with core melt), 7) task subcontracting policy, 8) synthesis and list of improvements. 4 following appendices review: EDF's crisis organization, the FARN, radiation protection organization and accidental event trees. (A.C.)

Fessenheim plant - Report on the complementary safety assessment of nuclear facilities in the light of the Fukushima accident

International Nuclear Information System (INIS)

2011-01-01

This CSA (Complementary Safety Assessment) analyses the robustness of the Fessenheim plant to extreme situations such as those that led to the Fukushima accident and proposes a series of improvements. Robustness is the ability for the plant to withstand events beyond the level for which the plant was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accident sequence. Safety is not only a matter of design or of engineered systems, it is also a matter of organization. So issues like EDF's crisis organization, the organization of radiation protection, and work organization via subcontracting are also taken into consideration. The creation of a nuclear rapid action force (FARN) is proposed: this will be a national emergency force made up of specialized teams equipped to intervene in less than 24 hours on a nuclear site hit by an accident. This report is divided into 8 main chapters: 1) features of the site, 2) earthquake risk, 3) flooding risk, 4) risks due to other extreme natural disasters, 5) the loss of electrical power supplies and of heat sink, 6) management of severe accidents (accidents with core melt), 7) task subcontracting policy, 8) synthesis and list of improvements. 4 following appendices review: EDF's crisis organization, the FARN, radiation protection organization and accidental event trees. (A.C.)

Chinon plant - Report on the complementary safety assessment of nuclear facilities in the light of the Fukushima accident

International Nuclear Information System (INIS)

2011-01-01

This CSA (Complementary Safety Assessment) analyses the robustness of the Chinon B plant to extreme situations such as those that led to the Fukushima accident and proposes a series of improvements. Robustness is the ability for the plant to withstand events beyond the level for which the plant was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accident sequence. Safety is not only a matter of design or of engineered systems, it is also a matter of organization. So issues like EDF's crisis organization, the organization of radiation protection, and work organization via subcontracting are also taken into consideration. The creation of a nuclear rapid action force (FARN) is proposed: this will be a national emergency force made up of specialized teams equipped to intervene in less than 24 hours on a nuclear site hit by an accident. This report is divided into 8 main chapters: 1) features of the site, 2) earthquake risk, 3) flooding risk, 4) risks due to other extreme natural disasters, 5) the loss of electrical power supplies and of heat sink, 6) management of severe accidents (accidents with core melt), 7) task subcontracting policy, 8) synthesis and list of improvements. 4 following appendices review: EDF's crisis organization, the FARN, radiation protection organization and accidental event trees. (A.C.)

Blayais plant - Report on the complementary safety assessment of nuclear facilities in the light of the Fukushima accident

International Nuclear Information System (INIS)

2011-01-01

This CSA (Complementary Safety Assessment) analyses the robustness of the Blayais plant to extreme situations such as those that led to the Fukushima accident and proposes a series of improvements. Robustness is the ability for the plant to withstand events beyond the level for which the plant was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accident sequence. Safety is not only a matter of design or of engineered systems, it is also a matter of organization. So issues like EDF's crisis organization, the organization of radiation protection, and work organization via subcontracting are also taken into consideration. The creation of a nuclear rapid action force (FARN) is proposed: this will be a national emergency force made up of specialized teams equipped to intervene in less than 24 hours on a nuclear site hit by an accident. This report is divided into 8 main chapters: 1) features of the site, 2) earthquake risk, 3) flooding risk, 4) risks due to other extreme natural disasters, 5) the loss of electrical power supplies and of heat sink, 6) management of severe accidents (accidents with core melt), 7) task subcontracting policy, 8) synthesis and list of improvements. 4 following appendices review: EDF's crisis organization, the FARN, radiation protection organization and accidental event trees. (A.C.)

Civaux plant - Report on the complementary safety assessment of nuclear facilities in the light of the Fukushima accident

International Nuclear Information System (INIS)

2011-01-01

This CSA (Complementary Safety Assessment) analyses the robustness of the Civaux plant to extreme situations such as those that led to the Fukushima accident and proposes a series of improvements. Robustness is the ability for the plant to withstand events beyond the level for which the plant was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accident sequence. Safety is not only a matter of design or of engineered systems, it is also a matter of organization. So issues like EDF's crisis organization, the organization of radiation protection, and work organization via subcontracting are also taken into consideration. The creation of a nuclear rapid action force (FARN) is proposed: this will be a national emergency force made up of specialized teams equipped to intervene in less than 24 hours on a nuclear site hit by an accident. This report is divided into 8 main chapters: 1) features of the site, 2) earthquake risk, 3) flooding risk, 4) risks due to other extreme natural disasters, 5) the loss of electrical power supplies and of heat sink, 6) management of severe accidents (accidents with core melt), 7) task subcontracting policy, 8) synthesis and list of improvements. 4 following appendices review: EDF's crisis organization, the FARN, radiation protection organization and accidental event trees. (A.C.)

Cattenom plant - Report on the complementary safety assessment of nuclear facilities in the light of the Fukushima accident

International Nuclear Information System (INIS)

2011-01-01

This CSA (Complementary Safety Assessment) analyses the robustness of the Cattenom plant to extreme situations such as those that led to the Fukushima accident and proposes a series of improvements. Robustness is the ability for the plant to withstand events beyond the level for which the plant was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accident sequence. Safety is not only a matter of design or of engineered systems, it is also a matter of organization. So issues like EDF's crisis organization, the organization of radiation protection, and work organization via subcontracting are also taken into consideration. The creation of a nuclear rapid action force (FARN) is proposed: this will be a national emergency force made up of specialized teams equipped to intervene in less than 24 hours on a nuclear site hit by an accident. This report is divided into 8 main chapters: 1) features of the site, 2) earthquake risk, 3) flooding risk, 4) risks due to other extreme natural disasters, 5) the loss of electrical power supplies and of heat sink, 6) management of severe accidents (accidents with core melt), 7) task subcontracting policy, 8) synthesis and list of improvements. 4 following appendices review: EDF's crisis organization, the FARN, radiation protection organization and accidental event trees. (A.C.)

Gravelines plant - Report on the complementary safety assessment of nuclear facilities in the light of the Fukushima accident

International Nuclear Information System (INIS)

2011-01-01

This CSA (Complementary Safety Assessment) analyses the robustness of the Gravelines plant to extreme situations such as those that led to the Fukushima accident and proposes a series of improvements. Robustness is the ability for the plant to withstand events beyond the level for which the plant was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accident sequence. Safety is not only a matter of design or of engineered systems, it is also a matter of organization. So issues like EDF's crisis organization, the organization of radiation protection, and work organization via subcontracting are also taken into consideration. The creation of a nuclear rapid action force (FARN) is proposed: this will be a national emergency force made up of specialized teams equipped to intervene in less than 24 hours on a nuclear site hit by an accident. This report is divided into 8 main chapters: 1) features of the site, 2) earthquake risk, 3) flooding risk, 4) risks due to other extreme natural disasters, 5) the loss of electrical power supplies and of heat sink, 6) management of severe accidents (accidents with core melt), 7) task subcontracting policy, 8) synthesis and list of improvements. 4 following appendices review: EDF's crisis organization, the FARN, radiation protection organization and accidental event trees. (A.C.)

Small Business: Action Needed to Determine Whether DOD’s Comprehensive Subcontracting Plan Test Program Should Be Made Permanent

Science.gov (United States)

2015-11-01

plan to mean “willful or intentional failure to perform in accordance with the requirements of the subcontracting plan, or willful or intentional ...Shaheen Ranking Member Committee on Small Business and Entrepreneurship United States Senate The Honorable Mac Thornberry Chairman The Honorable

UMTRA Project environmental, health, and safety plan

International Nuclear Information System (INIS)

1989-02-01

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

High Throughput Manufacturing of Thin-Film CdTe Photovoltaic Materials; Final Subcontract Report, 16 November 1993-31 December 1998

International Nuclear Information System (INIS)

Sandwisch, D.W.

1999-01-01

This report describes work performed by Solar Cells, Inc. (SCI), during this Photovoltaic Manufacturing Technology (PVMaT) subcontract. Cadmium telluride (CdTe) is recognized as one of the leading materials for low-cost photovoltaic modules. SCI has developed this technology and is preparing to scale its pilot production capabilities to a multi-megawatt level. This four-phase PVMaT subcontract supports these efforts. The work was related to product definition, process definition, equipment engineering, and support programs development. In the area of product definition and demonstration, two products were specified and demonstrated-a grid-connected, frameless, high-voltage product that incorporates a pigtail potting design and a remote low-voltage product that may be framed and may incorporate a junction box. SCI produced a 60.3-W thin-film CdTe module with total-area efficiency of 8.4%; SCI also improved module pass rate on the interim qualification test protocol from less than 20% to 100% as a result of work related to the subcontract. In the manufacturing process definition area, the multi-megawatt manufacturing process was defined, several of the key processes were demonstrated, and the process was refined and proven on a 100-kW pilot line that now operates as a 250-kW line. In the area of multi-megawatt manufacturing-line conceptual design review, SCI completed a conceptual layout of the multi-megawatt lines. The layout models the manufacturing line and predicts manufacturing costs. SCI projected an optimized capacity, two-shift/day operation of greater than 25 MW at a manufacturing cost of below$1.00/W

High Throughput Manufacturing of Thin-Film CdTe Photovoltaic Materials; Final Subcontract Report, 16 November 1993-31 December 1998

Energy Technology Data Exchange (ETDEWEB)

Sandwisch, D. W. (Solar Cells, Inc.)

1999-09-02

This report describes work performed by Solar Cells, Inc. (SCI), during this Photovoltaic Manufacturing Technology (PVMaT) subcontract. Cadmium telluride (CdTe) is recognized as one of the leading materials for low-cost photovoltaic modules. SCI has developed this technology and is preparing to scale its pilot production capabilities to a multi-megawatt level. This four-phase PVMaT subcontract supports these efforts. The work was related to product definition, process definition, equipment engineering, and support programs development. In the area of product definition and demonstration, two products were specified and demonstrated-a grid-connected, frameless, high-voltage product that incorporates a pigtail potting design and a remote low-voltage product that may be framed and may incorporate a junction box. SCI produced a 60.3-W thin-film CdTe module with total-area efficiency of 8.4%; SCI also improved module pass rate on the interim qualification test protocol from less than 20% to 100% as a result of work related to the subcontract. In the manufacturing process definition area, the multi-megawatt manufacturing process was defined, several of the key processes were demonstrated, and the process was refined and proven on a 100-kW pilot line that now operates as a 250-kW line. In the area of multi-megawatt manufacturing-line conceptual design review, SCI completed a conceptual layout of the multi-megawatt lines. The layout models the manufacturing line and predicts manufacturing costs. SCI projected an optimized capacity, two-shift/day operation of greater than 25 MW at a manufacturing cost of below $1.00/W.

IAEA activities in nuclear safety: future perspectives. Spanish Nuclear Safety Council, Madrid, 28 May 1998

International Nuclear Information System (INIS)

ElBaradei, M.

1998-01-01

The document represents the conference given by the Director General of the IAEA at the Spanish Nuclear Safety Council in Madrid, on 28 May 1998, on Agency's activities in nuclear safety. The following aspects are emphasized: Agency's role in creating a legally binding nuclear safety regime, non-binding safety standards, services provided by the Agency to assist its Member States in the Application of safety standards, Agency's nuclear safety strategy, and future perspective concerning safety aspects related to radioactive wastes, residues of past nuclear activities, and security of radiological sources

Saint-Alban plant - Report on the complementary safety assessment of nuclear facilities in the light of the Fukushima accident

International Nuclear Information System (INIS)

2011-01-01

This CSA (Complementary Safety Assessment) analyses the robustness of the Saint-Alban plant to extreme situations such as those that led to the Fukushima accident and proposes a series of improvements. Robustness is the ability for the plant to withstand events beyond the level for which the plant was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accident sequence. Safety is not only a matter of design or of engineered systems, it is also a matter of organization. So issues like EDF's crisis organization, the organization of radiation protection, and work organization via subcontracting are also taken into consideration. The creation of a nuclear rapid action force (FARN) is proposed: this will be a national emergency force made up of specialized teams equipped to intervene in less than 24 hours on a nuclear site hit by an accident. This report is divided into 8 main chapters: 1) features of the site, 2) earthquake risk, 3) flooding risk, 4) risks due to other extreme natural disasters, 5) the loss of electrical power supplies and of heat sink, 6) management of severe accidents (accidents with core melt), 7) task subcontracting policy, 8) synthesis and list of improvements. 4 following appendices review: EDF's crisis organization, the FARN, radiation protection organization and accidental event trees. (A.C.)

National Assembly - 2012-2013 regular session, 255. sitting, Sitting of Thursday 30 May 2013, verbatim record: Debate on nuclear safety

International Nuclear Information System (INIS)

Chevet, Pierre-Franck; Repussard, Jacques; Miniere, Dominique; Chanteguet, Jean-Paul; Batho, Delphine; Baupin, Denis; Chassaigne, Andre; Bouillon, Christophe; Mariton, Herve; Sas, Eva; Reynier, Franck; Roig, Frederic; Lambert, Francois-Michel; Valter, Clotilde; Massonneau, Veronique; Pompili, Barbara; Laponche, Bernard; Molac, Paul

2013-01-01

This document publishes the verbatim of a debate on nuclear safety in the French National Assembly. Interveners who belong to different parties and to different bodies and institutions (notably ASN, IRSN, EDF), of researchers, notably discussed the degradation of nuclear safety in France, the necessary review of the French nuclear safety framework, the implication of the ASN in the debate on energy transition, the nuclear plant lifetime, the present governance of nuclear safety, the ageing issue, the renewal of personnel abilities and qualifications, the issue of subcontracting, the possibility of a nuclear accident in France, the role of the different bodies and institutions, the evolution of the French nuclear fleet. Questions and answers are also reported

Uranium Mill Tailings Remedial Action Project (UMTRAP), Slick Rock, Colorado, Revision 1. Bid schedule, special conditions, specifications, and subcontract drawings

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-10-01

This volume contains: bidding requirements; terms and conditions; specifications for Division 1 -- general requirements; specifications for Division 2 -- sitework; specifications for Divisions 5 -- metals; subcontract drawings, (general, Union Carbide processing site, North Continent processing site, and Burro Canyon disposal site).

Uranium Mill Tailings Remedial Action Project (UMTRAP), Slick Rock, Colorado, Revision 1. Bid schedule, special conditions, specifications, and subcontract drawings

International Nuclear Information System (INIS)

1995-01-01

This volume contains: bidding requirements; terms and conditions; specifications for Division 1 -- general requirements; specifications for Division 2 -- sitework; specifications for Divisions 5 -- metals; subcontract drawings, (general, Union Carbide processing site, North Continent processing site, and Burro Canyon disposal site)

The motivation of subcontracted workers: a never-ending paradox La motivación de los trabajadores subcontratados. Una paradoja incesante

Directory of Open Access Journals (Sweden)

Alina Marcela Bustamente Salazar

2010-12-01

Full Text Available Certain considerations come about the subcontracted workers motivation when the Strategic Human Resource Management is used as a point of reference for diverse analysis. This article shows two faces of Human Resource Management. On one hand, the article indicates how important worker motivation has been for Human Resource Management and its direct association with worker productivity and efficacy. On the other hand, it points out the increasing importance that subcontracting has had as an alternative that allows companies the flexibilization and minimization of labor costs. Even though a structural contradiction comes up in this context, subcontracting seems to strive for feelings of affiliation and pride of belonging which are key elements to motivate the personnel. Apart from the literature review, the study was based on an ethnographic methodology of executives, contractors and subcontracted workers; and the results aim to contribute to streams of Organizational Theory and Human Resource Management.En el artículo se presentan consideraciones acerca de la motivación de los trabajadores subcontratados, en el marco de referencia de la “Gestión Humana Estratégica”. Se exponendos facetas de la administración de personal: por un lado, lo importante que ha sido lamotivación de los trabajadores para la Gestión Humana, como también la asociacióndirecta de esta con la productividad y la eficacia. Por otra parte, el auge creciente que hatenido la subcontratación como alternativa que permite a las empresas la flexibilizacióny minimización de sus costos laborales. Sin embargo, en este contexto, aparece unacontradicción estructural: la subcontratación parece atentar contra los sentimientos deafiliación y pertenencia organizacional, elementos claves para la motivación del personal.Además de la revisión documental, se llevó a cabo un trabajo etnometodológico conejecutivos, contratistas y empleados subcontratados. Los

Subcontracting strategy for the decontamination and decommissioning of Savannah River Site's First Tritium Extraction Facility, 232-F

International Nuclear Information System (INIS)

Smith, C.W. Jr.; Dowd, A.S. Jr.; Hinds, S.S.; Johnson, S.V.

1994-01-01

The Savannah River Site (SRS) has been actively proceeding with the decontamination and decommissioning (D and D) of various facilities and structures which were instrumental in the success of past missions at the site. The most ambitious of these efforts involves the subcontracting of the complete D and D of the first SRS Tritium Extraction Facility, identified as building 232-F. This facility operated in the mid 1950's and discontinued operations permanently in 1958. The approach utilized for this effort attempts to invoke the novel principle of open-quotes As Commercial As Reasonably Achievableclose quotes or open-quotes ACARAclose quotes. This concept of ACARA applies only the minimum essential requirements necessary to successfully perform the D and D task. Integral to this approach is the subcontractor provision for maximum flexibility in the identification of and adherence to the requirements of applicable DOE Orders, federal, state and local laws and regulations, as well as site specific procedures without violating the site contractual requirements. The technical specification prepared for this effort provides the basis for a competitively bid contract to perform the entire D and D evolution, including initial facility characterization, waste stream characterization and certification, D and D and waste disposal. Preparation and development of this specification and the subsequent Request For Proposal (RFP) was a successful team oriented endeavor. The schedule for this fast-track undertaking took three months to complete. Successful initiation of this task will be the first D and D of a facility containing both radioactive and hazardous material at an operating site within the DOE Weapons Complex. The strategy for preparing the D and D subcontract for the 232-F structure was facilitated by applying the ACARA principle. This approach resulted in the accelerated development of the specification and RFP documents, as well as minimized the complexities of

Research reactor management. Safety improvement activities in HANARO

International Nuclear Information System (INIS)

Wu, Jong-Sup; Jung, Hoan-Sung; Hong, Sung Taek; Ahn, Guk-Hoon

2012-01-01

Safety activities in HANARO have been continuously conducted to enhance its safe operation. Great effort has been placed on a normalization and improvement of the safety attitude of the regular staff and other employees working at the reactor and other experimental facilities. This paper introduces the activities on safety improvement that were performed over the last few years. (author)

Dampierre-en-Burly plant - Report on the complementary safety assessment of nuclear facilities in the light of the Fukushima accident

International Nuclear Information System (INIS)

2011-01-01

This CSA (Complementary Safety Assessment) analyses the robustness of the Dampierre-en-Burly plant to extreme situations such as those that led to the Fukushima accident and proposes a series of improvements. Robustness is the ability for the plant to withstand events beyond the level for which the plant was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accident sequence. Safety is not only a matter of design or of engineered systems, it is also a matter of organization. So issues like EDF's crisis organization, the organization of radiation protection, and work organization via subcontracting are also taken into consideration. The creation of a nuclear rapid action force (FARN) is proposed: this will be a national emergency force made up of specialized teams equipped to intervene in less than 24 hours on a nuclear site hit by an accident. This report is divided into 8 main chapters: 1) features of the site, 2) earthquake risk, 3) flooding risk, 4) risks due to other extreme natural disasters, 5) the loss of electrical power supplies and of heat sink, 6) management of severe accidents (accidents with core melt), 7) task subcontracting policy, 8) synthesis and list of improvements. 4 following appendices review: EDF's crisis organization, the FARN, radiation protection organization and accidental event trees. (A.C.)

Belleville-sur-Loire plant - Report on the complementary safety assessment of nuclear facilities in the light of the Fukushima accident

International Nuclear Information System (INIS)

2011-01-01

This CSA (Complementary Safety Assessment) analyses the robustness of the Belleville-sur-Loire plant to extreme situations such as those that led to the Fukushima accident and proposes a series of improvements. Robustness is the ability for the plant to withstand events beyond the level for which the plant was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accident sequence. Safety is not only a matter of design or of engineered systems, it is also a matter of organization. So issues like EDF's crisis organization, the organization of radiation protection, and work organization via subcontracting are also taken into consideration. The creation of a nuclear rapid action force (FARN) is proposed: this will be a national emergency force made up of specialized teams equipped to intervene in less than 24 hours on a nuclear site hit by an accident. This report is divided into 8 main chapters: 1) features of the site, 2) earthquake risk, 3) flooding risk, 4) risks due to other extreme natural disasters, 5) the loss of electrical power supplies and of heat sink, 6) management of severe accidents (accidents with core melt), 7) task subcontracting policy, 8) synthesis and list of improvements. 4 following appendices review: EDF's crisis organization, the FARN, radiation protection organization and accidental event trees. (A.C.)

Nogent-sur-Seine plant - Report on the complementary safety assessment of nuclear facilities in the light of the Fukushima accident

International Nuclear Information System (INIS)

2011-01-01

This CSA (Complementary Safety Assessment) analyses the robustness of the Nogent-sur-Seine plant to extreme situations such as those that led to the Fukushima accident and proposes a series of improvements. Robustness is the ability for the plant to withstand events beyond the level for which the plant was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accident sequence. Safety is not only a matter of design or of engineered systems, it is also a matter of organization. So issues like EDF's crisis organization, the organization of radiation protection, and work organization via subcontracting are also taken into consideration. The creation of a nuclear rapid action force (FARN) is proposed: this will be a national emergency force made up of specialized teams equipped to intervene in less than 24 hours on a nuclear site hit by an accident. This report is divided into 8 main chapters: 1) features of the site, 2) earthquake risk, 3) flooding risk, 4) risks due to other extreme natural disasters, 5) the loss of electrical power supplies and of heat sink, 6) management of severe accidents (accidents with core melt), 7) task subcontracting policy, 8) synthesis and list of improvements. 4 following appendices review: EDF's crisis organization, the FARN, radiation protection organization and accidental event trees. (A.C.)

IAEA activities in the field of research reactors safety

International Nuclear Information System (INIS)

Ciuculescu, C.; Boado Magan, H.J.

2004-01-01

IAEA activities in the field of research reactor safety are included in the programme of the Division of Nuclear Installations Safety. Following the objectives of the Division, the results of the IAEA missions and the recommendations from International Advisory Groups, the IAEA has conducted in recent years a certain number of activities aiming to enhance the safety of research reactors. The following activities will be presented: (a) the new Requirements for the Safety of Research Reactors, main features and differences with previous standards (SS-35-S1 and SS-35-S2) and the grading approach for implementation; (b) new documents being developed (safety guides, safety reports and TECDOC's); (c) activities related to the Incident Reporting System for Research Reactor (IRSRR); (d) the new features implemented for the INSARR missions; (e) the Code of Conduct on the Safety of Research Reactors adopted by the Board of Governors on 8 March 2004, following the General Conference Resolution GC(45)/RES/10; and (f) the survey on the safety of research reactors published on the IAEA website on February 2003 and the results obtained. (author)

Use of time and materials and cost reimbursement subcontracts for remedial actions under the alternative remedial contracting strategy contracts. Directive

International Nuclear Information System (INIS)

1992-01-01

The directive is intended to establish agency guidance on the use of time and materials and cost reimbursement contracts for remedial actions in general and to provide specific instruction regarding the use of these approaches in subcontracting under the Alternative Remedial Contracting Strategy (ARCS) contracts

Complementary safety assessment assessment of nuclear facilities - Tricastin facility - AREVA; Evaluation complementaire de la surete des installations nucleaires de base - Site du Tricastin - AREVA

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

This complementary safety assessment analyses the robustness of the Areva part of the Tricastin nuclear site to extreme situations such as those that led to the Fukushima accident. This study includes the following facilities: Areva NC Pierrelatte, EURODIF production, Comurhex Pierrelatte, Georges Besse II plant and Socatri. Robustness is the ability for the plant to withstand events beyond which the plant was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accidental sequence. Moreover, safety is not only a matter of design or engineered systems but also a matter of organizing: task organization (including subcontracting) as well as the setting of emergency plans or the inventory of nuclear materials are taken into consideration in this assessment. This report is divided into 10 main chapters: 1) the feedback experience of the Fukushima accident; 2) description of the site and its surroundings; 3) featuring of the site's activities and installations; 4) accidental sequences; 5) protection from earthquakes; 6) protection from floods; 7) protection from other extreme natural disasters; 8) the loss of electrical power and of the heat sink; 9) the management of severe accidents; and 10) subcontracting policy. This analysis has identified 5 main measures to be taken to limit the risks linked to natural disasters: -) continuing the program for replacing the current conversion plant and the enrichment plant; -) renewing the storage of hydrofluoric acid at the de-fluorination workshop; -) assessing the seismic behaviour of some parts of the de-fluorination workshop and of the fluorine fabrication workshop; -) improving the availability of warning and information means in case of emergency; and -) improving the means to mitigate accidental gaseous releases. (A.C.)

Saint-Laurent-des-Eaux plant - Report on the complementary safety assessment of nuclear facilities in the light of the Fukushima accident

International Nuclear Information System (INIS)

2011-01-01

This CSA (Complementary Safety Assessment) analyses the robustness of the Saint-Laurent-des-Eaux plant to extreme situations such as those that led to the Fukushima accident and proposes a series of improvements. Robustness is the ability for the plant to withstand events beyond the level for which the plant was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accident sequence. Safety is not only a matter of design or of engineered systems, it is also a matter of organization. So issues like EDF's crisis organization, the organization of radiation protection, and work organization via subcontracting are also taken into consideration. The creation of a nuclear rapid action force (FARN) is proposed: this will be a national emergency force made up of specialized teams equipped to intervene in less than 24 hours on a nuclear site hit by an accident. This report is divided into 8 main chapters: 1) features of the site, 2) earthquake risk, 3) flooding risk, 4) risks due to other extreme natural disasters, 5) the loss of electrical power supplies and of heat sink, 6) management of severe accidents (accidents with core melt), 7) task subcontracting policy, 8) synthesis and list of improvements. 4 following appendices review: EDF's crisis organization, the FARN, radiation protection organization and accidental event trees. (A.C.)

Safety Oversight of Decommissioning Activities at DOE Nuclear Sites

International Nuclear Information System (INIS)

Zull, Lawrence M.; Yeniscavich, William

2008-01-01

The Defense Nuclear Facilities Safety Board (Board) is an independent federal agency established by Congress in 1988 to provide nuclear safety oversight of activities at U.S. Department of Energy (DOE) defense nuclear facilities. The activities under the Board's jurisdiction include the design, construction, startup, operation, and decommissioning of defense nuclear facilities at DOE sites. This paper reviews the Board's safety oversight of decommissioning activities at DOE sites, identifies the safety problems observed, and discusses Board initiatives to improve the safety of decommissioning activities at DOE sites. The decommissioning of former defense nuclear facilities has reduced the risk of radioactive material contamination and exposure to the public and site workers. In general, efforts to perform decommissioning work at DOE defense nuclear sites have been successful, and contractors performing decommissioning work have a good safety record. Decommissioning activities have recently been completed at sites identified for closure, including the Rocky Flats Environmental Technology Site, the Fernald Closure Project, and the Miamisburg Closure Project (the Mound site). The Rocky Flats and Fernald sites, which produced plutonium parts and uranium materials for defense needs (respectively), have been turned into wildlife refuges. The Mound site, which performed R and D activities on nuclear materials, has been converted into an industrial and technology park called the Mound Advanced Technology Center. The DOE Office of Legacy Management is responsible for the long term stewardship of these former EM sites. The Board has reviewed many decommissioning activities, and noted that there are valuable lessons learned that can benefit both DOE and the contractor. As part of its ongoing safety oversight responsibilities, the Board and its staff will continue to review the safety of DOE and contractor decommissioning activities at DOE defense nuclear sites

Periodic safety review of the experimental fast reactor JOYO. Review of the activity for safety

International Nuclear Information System (INIS)

Maeda, Yukimoto; Kashimura, Youichi; Suzuki, Toshiaki; Isozaki, Kazunori; Hoshiba, Hideaki; Kitamura, Ryoichi; Nakano, Tomoyuki; Takamatsu, Misao; Sekine, Takashi

2005-02-01

Periodic safety review (Review of the activity for safety) which consisted of 'Comprehensive evaluation of operation experience' and Incorporation of the latest technical knowledge' was carried out up to January 2005. 1. Comprehensive evaluation of operation experience. It was confirmed that the effectual activities for safety through the operation of JOYO were carried out in terms of (1) Operation management, (2) Maintenance management, (3) Fuel management, (4) Radiation management, (5) Radioactive waste management, (6) Emergency planning and (7) Feedback of incidents and failures. 2. Reflection of the latest technical knowledge. It was confirmed that the latest technical knowledge including regulation and guide line established by Nuclear Safety Commission of Japan until March 31st. 2003 were properly reflected in impressing the safety of the reactor. As a result, it was evaluated that the activity for safety was carried out effectually, and no additional measure was identified continual safe operation of the reactor. (author)

NEA activities in safety and regulation

International Nuclear Information System (INIS)

Stadie, K.B.

1983-01-01

The NEA programme on Safety and Regulations is briefly reviewed. It encompasses four main areas - nuclear safety technology; nuclear licensing; radiation protection; and waste management - with three principal objectives: to promote exchanges of technical information in order to enlarge the data base for national decision making; to improve co-ordination of national R and D activities with emphasis on international standard problem exercises, and to promote international projects; to develop common technical, administrative and legal approaches to improve compatibility of safety and regulatory practices

Recent Activities on Global Nuclear Safety Regime

International Nuclear Information System (INIS)

Cho, Kun-Woo; Park, Jeong-Seop; Kim, Do-Hyoung

2006-01-01

Recently, rapid progress on the globalization of the nuclear safety issues is being made in IAEA (International Atomic Energy Agency) and its member states. With the globalization, the need for international cooperation among international bodies and member states continues to grow for resolving these universal nuclear safety issues. Furthermore, the importance of strengthening the global nuclear safety regime is emphasized through various means, such as efforts in application of IAEA safety standards to all nuclear installations in the world and in strengthening the code of conduct and the convention on nuclear safety. In this regards, it is important for us to keep up with the activities related with the global nuclear safety regime as an IAEA member state and a leading country in nuclear safety regulation

Safety Cultures in Water-Based Outdoor Activities in Denmark

DEFF Research Database (Denmark)

Andkjær, Søren; Arvidsen, Jan

2015-01-01

In this paper, we report on the study Safe in Nature (Tryg i naturen) in which the aim was to analyze and discuss risk and safety related to outdoor recreation in the coastal regions of Denmark. A cultural perspective is applied to risk management and the safety cultures related to three selected...... water-based outdoor activities: small boat fishing, sea kayaking, and kite surfing. The theoretical framework used was cultural analysis and the methodological approach was mixed methods using case studies with survey and qualitative interviews. The study indicates that safety is a complex matter...... and that safety culture can be understood as the sum and interaction among six categories. The safety culture is closely related to the activity and differs widely among activities. We suggest a broad perspective be taken on risk management wherein risk and safety can be managed at different levels. Small boat...

Nuclear safety activities in SR Slovenia in 1985

International Nuclear Information System (INIS)

1986-09-01

Currently Yugoslavia has one 632 MWe nuclear power plant of PWR design, located at Krsko in the Socialist Republic of Slovenia. NPP Krsko, which is a two-loop plant, started power operation in 1981. In general, reactor safety activities in SR Slovenia are mostly related to upgrading the safety of our NPP Krsko and to develop capabilities to be used for the future units. This report presents safety related organizations in SR Slovenia and their activities performed in 1985. (author)

Nuclear safety activities in SR Slovenia in 1985

Energy Technology Data Exchange (ETDEWEB)

NONE

1986-09-15

Currently Yugoslavia has one 632 MWe nuclear power plant of PWR design, located at Krsko in the Socialist Republic of Slovenia. NPP Krsko, which is a two-loop plant, started power operation in 1981. In general, reactor safety activities in SR Slovenia are mostly related to upgrading the safety of our NPP Krsko and to develop capabilities to be used for the future units. This report presents safety related organizations in SR Slovenia and their activities performed in 1985. (author)

Current activities on safety improvement at Ukrainian NPPs

International Nuclear Information System (INIS)

Stovbun, V.V.

2000-01-01

This report describes general development status of the national programs on safety improvement of the Ukrainian NPPs, basic approaches adopted for planning and implementation of safety improvement works, and state of implementation of principal technical activities aimed at safety improvement of Ukrainian NPPs. (author)

Flamanville plant - Report on the complementary safety assessment of nuclear facilities in the light of the Fukushima accident

International Nuclear Information System (INIS)

2011-01-01

This CSA (Complementary Safety Assessment) analyses the robustness of the Flamanville plant to extreme situations such as those that led to the Fukushima accident and proposes a series of improvements. Robustness is the ability for the plant to withstand events beyond the level for which the plant was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accident sequence. Safety is not only a matter of design or of engineered systems, it is also a matter of organization. So issues like EDF's crisis organization, the organization of radiation protection, and work organization via subcontracting are also taken into consideration. The creation of a nuclear rapid action force (FARN) is proposed: this will be a national emergency force made up of specialized teams equipped to intervene in less than 24 hours on a nuclear site hit by an accident. This report is divided into 2 parts: one part dedicated to the first 2 reactors of the plant and the second part to the EPR that is being built. Each part is divided into 8 main chapters: 1) features of the site, 2) earthquake risk, 3) flooding risk, 4) risks due to other extreme natural disasters, 5) the loss of electrical power supplies and of heat sink, 6) management of severe accidents (accidents with core melt), 7) task subcontracting policy, 8) synthesis and list of improvements. 4 following appendices review: EDF's crisis organization, the FARN, radiation protection organization and accidental event trees. (A.C.)

CEC activities in the field of LMFBR safety

International Nuclear Information System (INIS)

Balz, W.; Finzi, S.; Klersy, R.

1976-01-01

The aim of the ECC is to reach a common LMFBR Safety strategy in Europe. To this end the Commission promotes collaboration between the different fast reactor projects in the Community through working groups and collaborative arrangements and contributes with a research activity executed in its Joint Research Centre Ispra. A short description is given of the activity in the working groups and of the Ispra programme on LMFBR Safety. This programme covers: LMFBR thermohydraulics, fuel coolant interactions, dynamic structure loading and response, safety related material properties and whole core accident code development

Defining and Measuring Safety Climate: A Review of the Construction Industry Literature.

Science.gov (United States)

Schwatka, Natalie V; Hecker, Steven; Goldenhar, Linda M

2016-06-01

Safety climate measurements can be used to proactively assess an organization's effectiveness in identifying and remediating work-related hazards, thereby reducing or preventing work-related ill health and injury. This review article focuses on construction-specific articles that developed and/or measured safety climate, assessed safety climate's relationship with other safety and health performance indicators, and/or used safety climate measures to evaluate interventions targeting one or more indicators of safety climate. Fifty-six articles met our inclusion criteria, 80% of which were published after 2008. Our findings demonstrate that researchers commonly defined safety climate as perception based, but the object of those perceptions varies widely. Within the wide range of indicators used to measure safety climate, safety policies, procedures, and practices were the most common, followed by general management commitment to safety. The most frequently used indicators should and do reflect that the prevention of work-related ill health and injury depends on both organizational and employee actions. Safety climate scores were commonly compared between groups (e.g. management and workers, different trades), and often correlated with subjective measures of safety behavior rather than measures of ill health or objective safety and health outcomes. Despite the observed limitations of current research, safety climate has been promised as a useful feature of research and practice activities to prevent work-related ill health and injury. Safety climate survey data can reveal gaps between management and employee perceptions, or between espoused and enacted policies, and trigger communication and action to narrow those gaps. The validation of safety climate with safety and health performance data offers the potential for using safety climate measures as a leading indicator of performance. We discuss these findings in relation to the related concept of safety culture and

Safety Analysis Report for Ignalina NPP

International Nuclear Information System (INIS)

Negrivoda, G.

1997-01-01

In December 1994 an agreement was signed between the European Bank for Reconstruction and Development and the Republic of Lithuania for the grant of 32.86 MECU for the safety Improvement at Ignalina NPP. One of the conditions for the provision of the grant, was a requirement for an in-depth analysis of the safety level at Ignalina NPP in the scope and according to the standards acceptable for a western nuclear power plant, and to publish a Safety Analysis Report (SAR). The report should investigate and analyze any factor that could limit a safe operation of the plant, and provide recommendations for actual safety improvements. According to the agreement, Lithuania had to finalize the SAR until 31 December, 1995. The bank has also organized and financed investigation of safety at Ignalina NPP and preparation of the SAR. EBRD made an agreement with Sweden's Vattenfall, which subcontracted well-known companies from Canada, USA, Germany, etc., and also the Russian Research and Development Institute of Power Engineering (NIKIET), reactor designer of Ignalina NPP. The SAR is a very comprehensive document and contains about 8000 pages of text, diagrams and tables. The main findings of the SAR are provided in the article. A large number of discrepancies with modern rules and western practices was detected, but they were not proved to be serious enough to require reactors shutdown. Based on the recommendations of the SAR Ignalina NPP has worked out Safety Improvement Program No. 2 (SIP-2), which is planned for three years and will cost 486 MLT. (author)

Design of an Active Automotive Safety System

Directory of Open Access Journals (Sweden)

Y. Wang

2013-07-01

Full Text Available With the development of the national economy, the people's standard of living got corresponding improvement, cars has been one of the indispensable traffic tools in many families. An active safety system is proposed, which can real-time detect the vehicle's running status and judge the security status of the vehicle. The system, which takes single-chip microcomputer as the controlling core and combines with millimeter-wave and ultrasonic distance measurement technology, can detect the distance from vehicle to vehicle and judge the security status of the vehicle. The hardware composition of the system and the data acquiring circuit are proposed, the mathematic model for different situation is established, and the controlling algorithm is completed. This system can accurately measure speed and distance between vehicles; the active safety control system can meet the relevant data measurement and transmission requirement; and can meet the functional requirement of the active safety control system

Nuclear safety regulation on nuclear safety equipment activities in relation to human and organizational factors

International Nuclear Information System (INIS)

Li Tianshu

2013-01-01

Based on years of knowledge in nuclear safety supervision and experience of investigating and dealing with violation events in repair welding of DFHM, this paper analyzes major faults in manufacturing and maintaining activities of nuclear safety equipment in relation to human and organizational factors. It could be deducted that human and organizational factors has definitely become key features in the development of nuclear energy and technology. Some feasible measures to reinforce supervision on nuclear safety equipment activities have also been proposed. (author)

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.

The Organizing and Market Development of a Subcontracting Project to Vietnam : a Developing Export Market for Finland

OpenAIRE

Le, Thien

2010-01-01

Vietnam is one of the fastest developing countries in the world. Finland and Finnish companies have been doing more and more business in Vietnam in recent years. Understanding the environment and the business culture of the country of the utmost importance before entering the market. The goal of this project was to find a suitable subcontracting partner for the client company and thus to find information about the Vietnamese business culture. This project was carried out for Finpro which ...

Active pedestrian safety by automatic braking and evasive steering

NARCIS (Netherlands)

Keller, C.; Dang, T.; Fritz, H.; Joos, A.; Rabe, C.; Gavrila, D.M.

2011-01-01

Active safety systems hold great potential for reducing accident frequency and severity by warning the driver and/or exerting automatic vehicle control ahead of crashes. This paper presents a novel active pedestrian safety system that combines sensing, situation analysis, decision making, and

Recent development in safety regulation of nuclear fuel cycle activities

International Nuclear Information System (INIS)

Kato, S.

2001-01-01

Through the effort of deliberation and legislation over five years, Japanese government structure was reformed this January, with the aim of realizing simple, efficient and transparent administration. Under the reform, the Agency for Nuclear and Industrial Safety (ANIS) was founded in the Ministry of Economy, Trade and Industry (METI) to be responsible for safety regulation of energy-related nuclear activities, including nuclear fuel cycle activities, and industrial activities, including explosives, high-pressure gasses and mining. As one of the lessons learned from the JCO criticality accident of September 1999, it was pointed out that the government's inspection function was not enough for fuel fabrication facilities. Accordingly, new statutory regulatory activities were introduced, namely, inspection of observance of safety rules and procedures for all kinds of nuclear operators and periodic inspection of fuel fabrication facilities. In addition, in order to cope with insufficient safety education and training of workers in nuclear facilities, licensees of nuclear facilities are required by law to specify safety education and training for their workers. ANIS is committed to enforce these new regulatory activities effectively and efficiently. In addition, it is going to be prepared, in its capacity as safety regulatory authority, for future development of Japanese fuel cycle activities, including commissioning of JNFL Rokkasho reprocessing plant and possible application for licenses for JNFL MOX fabrication plant and for spent fuel interim storage facilities. (author)

75 FR 53733 - Pipeline Safety: Information Collection Activities

Science.gov (United States)

2010-09-01

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2010-0246] Pipeline Safety: Information Collection Activities AGENCY: Pipeline and Hazardous... liquefied natural gas, hazardous liquid, and gas transmission pipeline systems operated by a company. The...

Safety performance indicators used by the Russian Safety Regulatory Authority in its practical activities on nuclear power plant safety regulation

International Nuclear Information System (INIS)

Khazanov, A.L.

2005-01-01

The Sixth Department of the Nuclear, Industrial and Environmental Regulatory Authority of Russia, Scientific and Engineering Centre for Nuclear and Radiation Safety process, analyse and use the information on nuclear power plants (NPPs) operational experience or NPPs safety improvement. Safety performance indicators (SPIs), derived from processing of information on operational violations and analysis of annual NPP Safety Reports, are used as tools to determination of trends towards changing of characteristics of operational safety, to assess the effectiveness of corrective measures, to monitor and evaluate the current operational safety level of NPPs, to regulate NPP safety. This report includes a list of the basic SPIs, those used by the Russian safety regulatory authority in regulatory activity. Some of them are absent in list of IAEA-TECDOC-1141 ('Operational safety performance indicators for nuclear power plants'). (author)

PSA in design of passive/active safety reactors

International Nuclear Information System (INIS)

Sato, T.; Tanabe, A.; Kondo, S.

1995-01-01

PSAs in the design of advanced reactors are applied mainly in level 1 PSA areas. However, even in level 1 PSA, there are certain areas where special care must be taken depending on plant design concepts. This paper identifies these areas both for passive and active safety reactor concepts. For example, 'long-term PSA' and shutdown PSA are very important for a passive safety reactor concept from the standpoint of effectiveness of a grace period and passive safety systems. External events are also important for an active safety reactor concept. These kinds of special PSAs are difficult to conduct precisely in a conceptual design stage. This paper shows methods of conducting these kinds of special PSAs simply and conveniently and the use of acquired insights for the design of advanced reactors. This paper also clarifies the meaning or definition of a grace period from the standpoint of PSA

Nuclear safety activities in the SR of Slovenia in 1986

Energy Technology Data Exchange (ETDEWEB)

Susnik, J [Inst. Jozef Stefan, Ljubljana (Slovenia)

1987-06-15

Currently Yugoslavia has one 632 MWe nuclear power plant (NPP) of PWR design, located at Krsko in the Socialist Republic (SR) of Slovenia. Krsko NPP, which is a two-loop plant, started power operation in 1981. In general, reactor safety activities in the SR of Slovenia are mostly related to upgrading the safety of our Krsko NPP and to developing capabilities for use in future units. This report presents the nuclear safety related legislation and organization of the corresponding regulatory body, and the activities related to nuclear safety of the participating organizations in the SR of Slovenia in 1986. (author)

Nuclear safety activities in the SR of Slovenia in 1986

International Nuclear Information System (INIS)

Susnik, J.

1987-06-01

Currently Yugoslavia has one 632 MWe nuclear power plant (NPP) of PWR design, located at Krsko in the Socialist Republic (SR) of Slovenia. Krsko NPP, which is a two-loop plant, started power operation in 1981. In general, reactor safety activities in the SR of Slovenia are mostly related to upgrading the safety of our Krsko NPP and to developing capabilities for use in future units. This report presents the nuclear safety related legislation and organization of the corresponding regulatory body, and the activities related to nuclear safety of the participating organizations in the SR of Slovenia in 1986. (author)

The CEA Cadarache site. Additional safety assessment with respect to the accident which occurred in the Fukushima-Daiichi nuclear power station

International Nuclear Information System (INIS)

2012-01-01

After a presentation of some characteristics of the CEA Cadarache site (internal and external industrial environment, crisis management organization at the CEA level and at the local level), this document reports the identification of structures and equipment concerned by crisis management (site support functions, critical structures and equipment concerned by additional safety assessments). Then, it addresses the different risks: earthquake (sizing of critical structures and equipment, margin assessment), flooding (possible origins, alarm measures), other extreme natural events (extreme meteorological conditions, extreme earthquake with induced flooding, forest fire), and loss of electric supplies and of cooling systems. The last parts address the organization of accident management in situation typically related to additional safety management), and subcontracting conditions and practices

Safety research activities on radioactive waste management in JNES

International Nuclear Information System (INIS)

Otsuka, Ichiro; Aoki, Hiroomi; Suko, Takeshi; Onishi, Yuko; Masuda, Yusuke; Kato, Masami

2010-01-01

Research activities in safety regulation of radioactive waste management are presented. Major activities are as follows. As for the geological disposal, major research areas are, developing 'safety indicators' to judge the adequacy of site investigation results presented by an implementer (NUMO), compiling basic requirements of safety design and safety assessment needed to make a safety review of the license application and developing an independent safety assessment methodology. In proceeding research, JNES, Japan Atomic Energy Agency (JAEA) and the National Institute of Advanced Industrial Science and Technology (AIST) signed an agreement of cooperative study on geological disposal in 2007. One of the ongoing joint studies under this agreement has been aimed at investigating regional-scale hydrogeological modeling using JAEA's Horonobe Underground Research Center. In the intermediate depth disposal, JNES conducted example analysis of reference facility and submitted the result to Nuclear Safety Commission of Japan (NSC). JNES is also listing issues to be addressed in the safety review of the license application and tries to make criteria of the review. Furthermore, JNES is developing analysis tool to evaluate long term safety of the facility and conducting an experiment to investigate long term behavior of engineered barrier system. In the near surface disposal of waste package, it must be confirmed by a regulatory inspector whether each package meets safety requirements. JNES continuously updates the confirmation methodology depending on new processing technologies. The clearance system was established in 2005. Two stages of regulatory involvement were adapted, 1) approval for measurement and judgment methods developed by the nuclear operator and 2) confirmation of measurement and judgment results based on approved methods. JNES is developing verification methodology for each stage. As for decommissioning, based on the regulatory needs and a research program

Regulatory Activities on Civil Nuclear Safety Equipment in China

International Nuclear Information System (INIS)

Gaoshang, Lu; Choi, Kwang Sik

2011-01-01

It is stipulated in IAEA Fundamental Safety Principles (SF1) that the fundamental safety objective is to protect people and the environment from harmful effects of ionizing radiation. The fundamental safety objective applies for all facilities and activities and for all stages over the lifetime of a facility or radiation source, including planning, sitting, design, manufacturing, construction, commissioning and operation, as well as decommissioning and closure. So, according to the requirement, the related activities such as design, manufacturing, installation and non-destructive test that conducted on civil nuclear equipment should be well controlled by the vendors, the owner of the nuclear power plants and the regulatory body. To insure the quality of those equipment, Chinese government had taken a series of measures to regulate the related activities on them

Application of the management system for facilities and activities. Safety guide

International Nuclear Information System (INIS)

2006-01-01

This Safety Guide supports the Safety Requirements publication on The Management System for Facilities and Activities. It provides generic guidance to aid in establishing, implementing, assessing and continually improving a management system that complies with the requirements established. In addition to this Safety Guide, there are a number of Safety Guides for specific technical areas. Together these provide all the guidance necessary for implementing these requirements. This publication supersedes Safety Series No. 50-SG-Q1-Q7 (1996). The guidance provided here may be used by organizations in the following ways: - To assist in the development of the management systems of organizations directly responsible for operating facilities and activities and providing services for: Nuclear facilities; Activities using sources of ionizing radiation; Radioactive waste management; The transport of radioactive material; Radiation protection activities; Any other practices or circumstances in which people may be exposed to radiation from naturally occurring or artificial sources; The regulation of such facilities and activities; - To assist in the development of the management systems of the relevant regulatory bodies; - By the operator, to specify to a supplier, via contractual documentation, any guidance of this Safety Guide that should be included in the supplier's management system for the supply and delivery of products

Safety risk assessment for vertical concrete formwork activities in civil engineering construction.

Science.gov (United States)

López-Arquillos, Antonio; Rubio-Romero, Juan Carlos; Gibb, Alistair G F; Gambatese, John A

2014-01-01

The construction sector has one of the worst occupational health and safety records in Europe. Of all construction tasks, formwork activities are associated with a high frequency of accidents and injuries. This paper presents an investigation of the activities and related safety risks present in vertical formwork for in-situ concrete construction in the civil engineering sector. Using the methodology of staticized groups, twelve activities and ten safety risks were identified and validated by experts. Every safety risk identified in this manner was quantified for each activity using binary methodology according to the frequency and severity scales developed in prior research. A panel of experts was selected according to the relevant literature on staticized groups. The results obtained show that the activities with the highest risk in vertical formwork tasks are: Plumbing and leveling of forms, cutting of material, handling materials with cranes, and climbing or descending ladders. The most dangerous health and safety risks detected were falls from height, cutting and overexertion. The research findings provide construction practitioners with further evidence of the hazardous activities associated with concrete formwork construction and a starting point for targeting worker health and safety programmes.

Crime, perceived safety, and physical activity: A meta-analysis.

Science.gov (United States)

Rees-Punia, Erika; Hathaway, Elizabeth D; Gay, Jennifer L

2018-06-01

Perceived safety from crime and objectively-measured crime rates may be associated with physical inactivity. The purpose of this meta-analysis is to estimate the odds of accumulating high levels of physical activity (PA) when the perception of safety from crime is high and when objectively-measured crime is high. Peer-reviewed studies were identified through PubMed, Web of Science, ProQuest Criminal Justice, and ScienceDirect from earliest record through 2016. Included studies measured total PA, leisure-time PA, or walking in addition to perceived safety from crime or objective measures of crime. Mean odds ratios were aggregated with random effects models, and meta-regression was used to examine effects of potential moderators: country, age, and crime/PA measure. Sixteen cross-sectional studies yielded sixteen effects for perceived safety from crime and four effects for objective crime. Those reporting feeling safe from crime had a 27% greater odds of achieving higher levels of physical activity (OR=1.27 [1.08, 1.49]), and those living in areas with higher objectively-measured crime had a 28% reduced odds of achieving higher levels of physical activity (OR=0.72 [0.61, 0.83]). Effects of perceived safety were highly heterogeneous (I 2 =94.09%), but explored moderators were not statistically significant, likely because of the small sample size. Despite the limited number of effects suitable for aggregation, the mean association between perceived safety and PA was significant. As it seems likely that perceived lack of safety from crime constrains PA behaviors, future research exploring moderators of this association may help guide public health recommendations and interventions. Copyright © 2017 Elsevier Inc. All rights reserved.

Additional safety assessment of common means or support of the Marcoule centre

International Nuclear Information System (INIS)

2012-01-01

This report first presents some characteristics of the Marcoule centre: location and environment, base nuclear installations and other installations, technical installations and installations classified for protection of the environment which could affect the safety of nearby installations, demographic and industrial environment and risks generated for the site's installations, general description of crisis management means. The second part addresses situations to be considered, functional needs related to additional safety assessments, needs in terms of support functions, and critical structures and equipment. The next parts address the seismic risk (structure and equipment sizing, margin assessment, flooding due to an earthquake, loss of electric supply due to an earthquake), the flooding risk (flooding sources, main alarm measures, structure and equipment sizing and availability for crisis management during a flooding from different origins), other extreme phenomena (lightning, hail, wind, external fire), the loss of electric supplies and the loss of cooling systems, the organisation of accident management, and subcontracting practices

Specialists' meeting on passive and active safety features of LMFRs

Energy Technology Data Exchange (ETDEWEB)

NONE

1991-07-01

The objective of the meeting was to discuss and exchange information on passive and active safety concepts and to find some reasonable coupling of these concept, aiming at firmer establishment of plant safety and at the same time of plant cost reduction. The following main topical areas were discussed by delegates: (1) Overview - review of national status on the safety design approaches of LMFRs (2) Safety characteristics of decay heat removal system (DHRS) (3) Safety characteristics of reactor protection system (RPS) and reactor shutdown system (RSS) (4) Core safety characteristics.

Specialists' meeting on passive and active safety features of LMFRs

International Nuclear Information System (INIS)

1991-01-01

The objective of the meeting was to discuss and exchange information on passive and active safety concepts and to find some reasonable coupling of these concept, aiming at firmer establishment of plant safety and at the same time of plant cost reduction. The following main topical areas were discussed by delegates: (1) Overview - review of national status on the safety design approaches of LMFRs (2) Safety characteristics of decay heat removal system (DHRS) (3) Safety characteristics of reactor protection system (RPS) and reactor shutdown system (RSS) (4) Core safety characteristics

Nuclear power reactor safety research activities in CIAE

International Nuclear Information System (INIS)

Pu Shendi; Huang Yucai; Xu Hanming; Zhang Zhongyue

1994-01-01

The power reactor safety research activities in CIAE are briefly reviewed. The research work performed in 1980's and 1990's is mainly emphasised, which is closely related to the design, construction and licensing review of Qinshan Nuclear Power Plant and the safety review of Guangdong Nuclear Power Station. Major achievements in the area of thermohydraulics, nuclear fuel, probabilistic safety assessment and severe accident researches are summarized. The foreseeable research plan for the near future, relating to the design and construction of 600 MWe PWR NPP at Qinshan Site (phase II development) is outlined

Activities of the PNC Nuclear Safety Working Group

International Nuclear Information System (INIS)

Kato, W.Y.

1991-01-01

The Nuclear Safety Working Group of the Pacific Nuclear Council promotes nuclear safety cooperation among its members. Status of safety research, emergency planning, development of lists of technical experts, severe accident prevention and mitigation have been the topics of discussion in the NSWG. This paper reviews and compares the severe accident prevention and mitigation program activities in some of the areas of the Pacific Basin region based on papers presented at a special session organized by the NSWG at an ANS Topical Meeting as well as papers from other sources

The NASA Plan: To award eight percent of prime and subcontracts to socially and economically disadvantaged businesses

Science.gov (United States)

1990-01-01

It is NASA's intent to provide small disadvantaged businesses, including women-owned, historically black colleges and universities and minority education institutions the maximum practicable opportunity to receive a fair proportion of NASA prime and subcontracted awards. Annually, NASA will establish socioeconomic procurement goals including small disadvantaged business goals, with a target of reaching the eight percent level by the end of FY 1994. The NASA Associate Administrators, who are responsible for the programs at the various NASA Centers, will be held accountable for full implementation of the socioeconomic procurement plans. Various aspects of this plan, including its history, are discussed.

Implementing and measuring safety goals and safety culture. 4. Utility's Activities for Better Safety Culture After the JCO Accident

International Nuclear Information System (INIS)

Omoto, Akira

2001-01-01

The criticality accident at the JCO plant prompted the Government to enact a law for nuclear emergency preparedness. The nuclear industry established NSnet to facilitate opportunities for peer review among its members. This paper describes the activities by NSnet and TEPCO's Kashiwazaki-Kariwa nuclear power station (NPS) for a better safety culture. Created as a voluntary organization by the nuclear industry in 1999, NSnet has 35 members and is assisted by CRIEPI and NUPEC for its activities relevant to human factors. Given the fact that nuclear facility operators not belonging to WANO had no institutional system available for exchange of experiences and good practices for better safety among themselves, NSnet's activities focus on peer review by member organizations and onsite seminars. Starting April 2000 with visits to three fuel fabricators, NSnet intends to have 23 peer-review visits in 2 yr (Ref. 1). The six-member review team stays on-site for 4 days, during which time they review-using guidelines available from WANO and IAEA-OSART-six areas: organization/management, emergency preparedness, education/training, operation/ maintenance, protection against occupational radiation exposure, and prevention of accidents. A series of on-site seminars is held at members' nuclear facilities, to which NSnet dispatches experts for lectures. NSnet plans to hold such seminars twice per month. Other activities include information-sharing through a newsletter, a Web site (www. nsnet.gr.jp), and others. Although considerable differences exist in the design and the practices in operation/maintenance between power reactors and JCO, utilities can extract lessons from the accident that will be worth consideration for their own facilities in the areas of safety culture, education and training, and interface between design and operation. This thinking prompted the Nuclear Safety Promotion Center at Kashiwazaki-Kariwa NPS, to which the author belonged at that time, to launch the

PA activity by using nuclear power plant safety demonstration and analysis

International Nuclear Information System (INIS)

Tsuchiya, Mitsuo; Kamimae, Rie

1999-01-01

INS/NUPEC presents one of Public acceptance (PA) methods for nuclear power in Japan, 'PA activity by using Nuclear Power Plant Safety Demonstration and Analysis', by using one of videos which is explained and analyzed accident events (Loss of Coolant Accident). Safety regulations of The National Government are strictly implemented in licensing at each of basic design and detailed design. To support safety regulation activities conducted by the National Government, INS/NLTPEC continuously implement Safety demonstration and analysis. With safety demonstration and analysis, made by assuming some abnormal conditions, what impacts could be produced by the assumed conditions are forecast based on specific design data on a given nuclear power plants. When analysis results compared with relevant decision criteria, the safety of nuclear power plants is confirmed. The decision criteria are designed to help judge if or not safety design of nuclear power plants is properly made. The decision criteria are set in the safety examination guidelines by taking sufficient safety allowance based on the latest technical knowledge obtained from a wide range of tests and safety studies. Safety demonstration and analysis is made by taking the procedure which are summarized in this presentation. In Japan, various PA (Public Acceptance) pamphlets and videos on nuclear energy have been published. But many of them focused on such topics as necessity or importance of nuclear energy, basic principles of nuclear power generation, etc., and a few described safety evaluation particularly of abnormal and accident events in accordance with the regulatory requirements. In this background, INS/NUPEC has been making efforts to prepare PA pamphlets and videos to explain the safety of nuclear power plants, to be simple and concrete enough, using various analytical computations for abnormal and accident events. In results, PA activity of INS/NUPEC is evaluated highly by the people

Addressing the fundamental issues in reliability evaluation of passive safety of AP1000 for a comparison with active safety of PWR

International Nuclear Information System (INIS)

Hashim Muhammad; Yoshikawa, Hidekazu; Yang Ming

2013-01-01

Passive safety systems adopted in advanced Pressurized Water Reactor (PWR), such as AP1000 and EPR, should attain higher reliability than the existing active safety systems of the conventional PWR. The objective of this study is to discuss the fundamental issues relating to the reliability evaluation of AP1000 passive safety systems for a comparison with the active safety systems of conventional PWR, based on several aspects. First, comparisons between conventional PWR and AP1000 are made from the both aspects of safety design and cost reduction. The main differences between these PWR plants exist in the configurations of safety systems: AP1000 employs the passive safety system while reducing the number of active systems. Second, the safety of AP1000 is discussed from the aspect of severe accident prevention in the event of large break loss of coolant accidents (LOCA). Third, detailed fundamental issues on reliability evaluation of AP1000 passive safety systems are discussed qualitatively by using single loop models of safety systems of both PWRs plants. Lastly, methodology to conduct quantitative estimation of dynamic reliability for AP1000 passive safety systems in LOCA condition is discussed, in order to evaluate the reliability of AP1000 in future by a success-path-based reliability analysis method (i.e., GO-FLOW). (author)

A review of the nuclear safety activities in Italy

International Nuclear Information System (INIS)

Merelli, A.

1989-01-01

A review of research programs carried out in Italy in the field of nuclear reactor safety was done in 1986, in the frame of the activities of the Commission of the European Communities, the International Energy Agency and the Nuclear Energy Agency of the Organization for Economic Cooperation and Development. The report contains information on these programs, as well as information on the organization of safety research in Italy and the evolution of safety research programs

IAEA activity related to safety of nuclear desalination

International Nuclear Information System (INIS)

Gasparini, M.

2000-01-01

The nuclear plants for desalination to be built in the future will have to meet the standards of safety required for the best nuclear power plants currently in operation or being designed. The current safety approach, based on the achievement of the fundamental safety functions and defence in depth strategy, has been shown to be a sound foundation for the safety and protection of public health, and gives the plant the capability of dealing with a large variety of sequences, even beyond the design basis. The Department of Nuclear Safety of the IAEA is involved in many activities, the most important of which are to establish safety standards, and to provide various safety services and technical knowledge in many Technical Co-operation assistance projects. The department is also involved in other safety areas, notably in the field of future reactors. The IAEA is carrying out a project on the safety of new generation reactors, including those used for desalination, with the objective of fostering an exchange of information on safety approaches, promoting harmonization among Member States and contributing towards the development and revision of safety standards and guidelines for nuclear power plant design. The safety, regulatory and environmental concerns in nuclear powered desalination are those related directly to nuclear power plants, with due consideration given to the coupling process. The protection of product water against radioactive contamination must be ensured. An effective infrastructure, including appropriate training, a legal framework and regulatory regime, is a prerequisite to considering use of nuclear power for desalination plants, also in those countries with limited industrial infrastructures and little experience in nuclear technology or safety. (author)

Activities on safety for the cross-cutting issue of research reactors in the IAEA

International Nuclear Information System (INIS)

Perrotta, J.A.; Boado Magan, H.J.

2003-01-01

IAEA activities in the field of research reactor safety are included in the programme of the Division of Nuclear Installations Safety and implemented by the Engineering Safety Section through its Research Reactor Safety Unit. Following the objectives of the Division, the results of the IAEA missions and the recommendations from International Advisory Groups, the IAEA has conducted in recent years a certain number of activities aiming to enhance the safety of research reactors. The following activities are discussed in this paper: (a) the new Requirements for the Safety of Research Reactors, main features and differences with previous standards (SS-35-S1 and SS-35-S2) and the grading approach for implementation; (b) new documents being developed (safety guides, safety reports and TECDOCs); (c) activities related to the Incident Reporting System for Research Reactor (IRSRR); (d) the new features implemented for the (Integrated Safety Assessment of Research Reactors) INSARR missions; (e) the Code of Conduct on the Safety of Research Reactors developed, following the General Conference Resolution GC(45)/RES/10; and (f) the survey on the safety of research reactors conducted in the year 2002 and the results obtained. (author)

System analysis of vehicle active safety problem

Science.gov (United States)

Buznikov, S. E.

2018-02-01

The problem of the road transport safety affects the vital interests of the most of the population and is characterized by a global level of significance. The system analysis of problem of creation of competitive active vehicle safety systems is presented as an interrelated complex of tasks of multi-criterion optimization and dynamic stabilization of the state variables of a controlled object. Solving them requires generation of all possible variants of technical solutions within the software and hardware domains and synthesis of the control, which is close to optimum. For implementing the task of the system analysis the Zwicky “morphological box” method is used. Creation of comprehensive active safety systems involves solution of the problem of preventing typical collisions. For solving it, a structured set of collisions is introduced with its elements being generated also using the Zwicky “morphological box” method. The obstacle speed, the longitudinal acceleration of the controlled object and the unpredictable changes in its movement direction due to certain faults, the road surface condition and the control errors are taken as structure variables that characterize the conditions of collisions. The conditions for preventing typical collisions are presented as inequalities for physical variables that define the state vector of the object and its dynamic limits.

Chemical surety material decontamination and decommissioning of Los Alamos National Laboratory Chemical Surety Material Laboratory area TA-3, building SM-29, room 4009

International Nuclear Information System (INIS)

Moore, T.E.; Smith, J.M.

1994-04-01

From 1982 through 1987, Los Alamos National Laboratory (LANL) performed surety laboratory operations for the U.S. Army Medical Research and Development Command (MRDC). Room 4009 in building SM-29, TA-3, was used as the laboratory for work with the following chemical surety material (CSM) agents: sarin (GB), soman (GD), lewisite (L), and distilled mustard (HD) radio-labelled with H 3 or C 14 . The work was confined to three CSM-certified fume hoods, located in room 4009 (see diagram in Appendix C). The laboratory ceased all active operations during the late 1986 and early 1987 period. From 1987 until 1993 the laboratory was secured and the ventilation system continued to operate. During late 1992, the decision was made to utilize this laboratory space for other operations, thus a decision was made to dismantle and reconfigure this room. LANL sub-contracted Battelle Memorial Institute (BMI) to draw upon the CSM experience of the technical staff from the Hazardous Materials Research Facility (HMRF) to assist in developing a decontamination and decommissioning plan. BMI was subcontracted to devise a CSM safety training course, and a sampling and air monitoring plan for CSM material to ensure personnel safety during all disassembly operations. LANL subcontracted Johnson Controls personnel to perform all disassembly operations. Beginning in early 1993 BMI personnel from the HMRF visited the laboratory to develop both the safety plan and the sample and air monitoring plan. Execution of that plan began in September 1993 and was completed in January 1994

Chemical surety material decontamination and decommissioning of Los Alamos National Laboratory Chemical Surety Material Laboratory area TA-3, building SM-29, room 4009

Energy Technology Data Exchange (ETDEWEB)

Moore, T.E.; Smith, J.M.

1994-04-01

From 1982 through 1987, Los Alamos National Laboratory (LANL) performed surety laboratory operations for the U.S. Army Medical Research and Development Command (MRDC). Room 4009 in building SM-29, TA-3, was used as the laboratory for work with the following chemical surety material (CSM) agents: sarin (GB), soman (GD), lewisite (L), and distilled mustard (HD) radio-labelled with H{sup 3} or C{sup 14}. The work was confined to three CSM-certified fume hoods, located in room 4009 (see diagram in Appendix C). The laboratory ceased all active operations during the late 1986 and early 1987 period. From 1987 until 1993 the laboratory was secured and the ventilation system continued to operate. During late 1992, the decision was made to utilize this laboratory space for other operations, thus a decision was made to dismantle and reconfigure this room. LANL sub-contracted Battelle Memorial Institute (BMI) to draw upon the CSM experience of the technical staff from the Hazardous Materials Research Facility (HMRF) to assist in developing a decontamination and decommissioning plan. BMI was subcontracted to devise a CSM safety training course, and a sampling and air monitoring plan for CSM material to ensure personnel safety during all disassembly operations. LANL subcontracted Johnson Controls personnel to perform all disassembly operations. Beginning in early 1993 BMI personnel from the HMRF visited the laboratory to develop both the safety plan and the sample and air monitoring plan. Execution of that plan began in September 1993 and was completed in January 1994.

Safety Culture Improvement Activities of YGN 3 and 4

International Nuclear Information System (INIS)

Cho, Il Hoon

2006-01-01

In nuclear power industry all over the world, we can never overemphasize the importance of nuclear safety. After the Chernobyl accident occurred in 1986, Korean nuclear energy industry had made every effort to enhance nuclear safety culture further. And, as a result of the efforts, Korean government declared the five principles for the nuclear energy safety regulation, which were included in the Nuclear Energy Safety Policy Statement published in 1994. In 2001, through the announcement of Nuclear Safety Charter for the peaceful use of nuclear energy, the Ministry of Science and Technology proclaimed at home and abroad that the protection of citizens and environment by securing nuclear safety should be the highest priority in nuclear energy industry. Occupying almost 40% share of domestic electricity generation, Korea Hydro and Nuclear Power Co. decided 'Safety Top Priority Management' as president's management policy, and clearly presented the safety goal to the personnel. By this, the management can effectively place stress on securing safety, which is our highest priority and the only way to win public confidence toward nuclear energy industry. This is prepared to shortly introduce the activities for improving safety culture in Yonggwang Nuclear Power unit 3 and 4 (YGN 3 and 4)

Interactive effects of relay and circuit breaker aging in a safety-related system

International Nuclear Information System (INIS)

Toman, G.J.; Bacanskas, V.P.; Shook, T.A.; Ladlow, C.C.; Gunther, W.

1987-01-01

This paper provides an overview of the results of a program to evaluate the aging of circuit breakers and relays and the effects of that aging on the function of a safety system used in nuclear power plants. The program was performed under the Nuclear Plant Aging Research (NPAR) Program of the US Nuclear Regulatory Commission under subcontract to Brookhaven National Laboratory. There were two primary aspects to the program. In the first, the aging and failure modes of relays and circuit breakers were determined by evaluating the construction, design, and materials and the failure data related to nuclear power plant service. In the second, the interactions between a safety system and its relays and circuit breakers were evaluated to determine the effects of relay and circuit breaker aging on the function of the safety system. The aging of relays and circuit breakers was assessed through evaluation of failure data bases, discussions with utility personnel, and evaluation of equipment operating and maintenance manuals. The interaction study was based on an analysis of the safety injection system of a pressurized water reactor. The effects of stresses from the system were analyzed for the tendency to cause deterioration of the relays and circuit breakers in the system. Then the effect of the deterioration of relays and circuit breakers on the functional capability of the safety system was evaluated

Study on application of safety checklist in preventive maintenance activities

International Nuclear Information System (INIS)

Shi Jin; Chen Song; Liu Jingquan

2013-01-01

The paper describes the principles and the characteristics of safety checklist as a risk evaluation method. Examples of application of safety checklists to preventive maintenance activities such as criteria comparison and checkup items in place in nuclear power plants are illustrated in details with issues appeared in the checklist establishment. Checklist has a good application in the RCM analysis or in the actual preventive maintenance program for Chashma Nuclear Power Plant indicated by concrete instances. In the light of safety checklist which is used to sustain preventive maintenance as a simple and applicable risk analysis approach, we can get deep knowledge of risks of nuclear power plant to perfect preventive maintenance activities. (authors)

Road identification for its-integrated systems of automotive active safety

Directory of Open Access Journals (Sweden)

V. Ivanov

2005-04-01

Full Text Available The paper discusses several aspects of active safety control for automotive application. Particular emphasis is placed on the fuzzy logic determination of friction properties of a tyre-road contact. An example of vehicle control systems equipped with off-board sensors of road roughness, temperature, moisture and rain intensity demonstrates the implementation of this approach. The paper proposes conceptual solutions for preventive active safety control applied to vehicles which are integrated in an intelligent transportation system.

Review of nuclear regulatory activities associated with safety culture and the management of safety in the United Kingdom

International Nuclear Information System (INIS)

Woodhouse, P.A.

1995-01-01

This paper describes some of the key regulatory activities which have taken place in the United Kingdom in recent years in the areas of safety culture and management of safety. It explains how the UK's nuclear licensing regime, regulated and enforced by the Nuclear Installations Inspectorate, (NII), provides the framework for a viable safety management system and identifies a management of safety model which a NII Task Force has developed. It finally identifies further work which is being undertaken by the NII. (author). 4 refs, 2 figs

IAEA activities on safety aspects of NPP ageing

International Nuclear Information System (INIS)

Pachner, J.

1998-01-01

A review of IAEA activities concerned with safety aspects of nuclear power plants ageing is given for the period from 1995 to 1998 with the prospects till year 2000. Coordinated Research programs were conducted on Management Ageing of Concrete Containment Buildings; Management of Ageing of In-Containment I and C cables. TECDOCs were published on Assessment and Management of Ageing of Major NPP Components Important for Safety of CANDU, PWR and BWR NPPs. Technical Committee Meetings and Interregional training courses concerned with the same subjects were held

Development of the safety evaluation system in the respects of organizational factors and workers' consciousness. Pt. 4. Application of the system for contract companies

International Nuclear Information System (INIS)

Hasegawa, Naoko; Hirose, Ayako; Hayase, Kenichi; Tsuge, Tadafumi; Sasou, Kunihide; Takano, Kenichi

2003-01-01

The purpose of our study is to develop a safety evaluation system which clarifies the safety level of an organization. As a basic method of evaluation using a questionnaire had been established, now that the generalization is needed for the system. Hence, this paper is intended to consider the applicability of the system for contract companies. Subjects were workers who belonged to contract companies engaging in the maintenance of power plants in regular inspections. The following results were obtained: 1) The Comprehensive Safety Index (CSI) taking into account individual and organizational factors was identified using the principal component analysis. 2) The validity of CSI was confirmed with significant correlations between the CSI score and the rate of accidents. 3) Careful consideration should be provided for individual factors especially when evaluating the safety level of subcontract companies. 4) It seemed necessary to take into account the influence of parent companies and occupational hazards level. 5) The comparison among different industries should be avoided because of the difference in organizational structures and subjects of attention for keeping safety. (author)

Perspective on Secure Development Activities and Features of Safety I and C Systems

International Nuclear Information System (INIS)

Kang, Youngdoo; Yu, Yeong Jin; Kim, Hyungtae; Kwon, Yong il; Park, Yeunsoo; Choo, Jaeyul; Son, Jun Young; Jeong, Choong Heui

2015-01-01

The Enforcement Decree of the Act on Physical Protection and Radiological Emergency (ED-APPRE) was revised December 2013 to include security requirements on computer systems at nuclear facilities to protect those systems against malicious cyber-attacks. It means Cyber-Security-related measures, controls and activities of safety I and C systems against cyber-attacks shall meet the requirements of ED-APPRE. Still regulation upon inadvertent access or non-malicious modifications to the safety I and C systems is covered under the Nuclear Safety Act. The objective of this paper is to propose KINS' regulatory perspective on secure development and features against non-malicious access or modification of safety I and C systems. Secure development activities and features aim to prevent inadvertent and non-malicious access, and to prevent unwanted action from personnel or connected systems for ensuring reliable operation of safety I and C systems. Secure development activities of safety I and C systems are life cycle activities to ensure unwanted, unneeded and undocumented code is not incorporated into the systems. Secure features shall be developed, verified and qualified throughout the development life cycle

Perspective on Secure Development Activities and Features of Safety I and C Systems

Energy Technology Data Exchange (ETDEWEB)

Kang, Youngdoo; Yu, Yeong Jin; Kim, Hyungtae; Kwon, Yong il; Park, Yeunsoo; Choo, Jaeyul; Son, Jun Young; Jeong, Choong Heui [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2015-05-15

The Enforcement Decree of the Act on Physical Protection and Radiological Emergency (ED-APPRE) was revised December 2013 to include security requirements on computer systems at nuclear facilities to protect those systems against malicious cyber-attacks. It means Cyber-Security-related measures, controls and activities of safety I and C systems against cyber-attacks shall meet the requirements of ED-APPRE. Still regulation upon inadvertent access or non-malicious modifications to the safety I and C systems is covered under the Nuclear Safety Act. The objective of this paper is to propose KINS' regulatory perspective on secure development and features against non-malicious access or modification of safety I and C systems. Secure development activities and features aim to prevent inadvertent and non-malicious access, and to prevent unwanted action from personnel or connected systems for ensuring reliable operation of safety I and C systems. Secure development activities of safety I and C systems are life cycle activities to ensure unwanted, unneeded and undocumented code is not incorporated into the systems. Secure features shall be developed, verified and qualified throughout the development life cycle.

The Evaluation of the Safety Benefits of Combined Passive and On-Board Active Safety Applications

Science.gov (United States)

Page, Yves; Cuny, Sophie; Zangmeister, Tobias; Kreiss, Jens-Peter; Hermitte, Thierry

2009-01-01

One of the objectives of the European TRACE project (TRaffic Accident Causation in Europe, 2006–2008) was to estimate the proportion of injury accidents that could be avoided and/or the proportion of injury accidents where the severity could be mitigated for on-the-market safety applications, if 100 % of the car fleet would be equipped with them. We have selected for evaluation the Electronic Stability Control (ESC) and the Emergency Brake Assist (EBA) applications. As for passive safety systems, recent cars are designed to offer overall safety protection. Car structure, load limiters, front airbags, side airbags, knee airbags, pretensioners, padding and non aggressive structures in the door panel, the dashboard, the windshield, the seats, and the head rest also contribute to applying more protection. The whole safety package is very difficult to evaluate separately, one element independently segmented from the others. We decided to consider evaluating the effectivenessof the whole passive safety package, This package,, for the sake of simplicity, was the number of stars awarded at the Euro NCAP testing. The challenges were to compare the effectiveness of some safety configuration SC I, with the effectiveness of a different safety configuration SC II. A safety configuration is understood as a package of safety functions. Ten comparisons have been carried out such as the evaluation of the safety benefit of a fifth star given that the car has four stars and an EBA. The main outcome of this analysis is that any addition of a passive or active safety function selected in this analysis is producing increased safety benefits. For example, if all cars were five stars fitted with EBA and ESC, instead of four stars without ESC and EBA, injury accidents would be reduced by 47.2% for severe injuries and 69.5% for fatal injuries. PMID:20184838

Workplace activities to promote small attempts for safety. Toward development of safety culture in a nuclear power plant

International Nuclear Information System (INIS)

Fukui, Hirokazu; Sugiman, Toshio

2007-01-01

Activities that could possibly grow into learning activities for developing safety culture were explored by intensive fieldwork in a nuclear power plant depending on Engestroem's activity theory. As a first step to achieve this goal, workers' small attempts that might contribute to nurturing a safety culture were investigated. Eight kinds of activity were observed and interpreted as having the possibility to facilitate small recognition and small practice, i.e., activities including (1) workgroup as community, (2) other workgroups and other departments as community, (3) meeting drawing remarks as mediating artifacts, (4) study session and Off-the-Job-Training as mediating artifact, (5) award as mediating artifact, (6) extended leave as mediating artifact, (7) check sheet as mediating artifact, and (8) skill-transfer system as mediating artifact. (author)

Evaluation of the Potential for the Production of Lignocellulosic Based Ethanol at Existing Corn Ethanol Facilities: Final Subcontract Report, 2 March 2000 - 30 March 2002

Energy Technology Data Exchange (ETDEWEB)

2002-07-01

Subcontract report on opportunities to explore the business potential provided by converting biomass to products such as ethanol. The goals of this study were: (1) To provide the opportunity to explore the business potential provided by converting biomass to products such as ethanol. (2) To take advantage of the grain-processing infrastructure by investigating the co-location of additional biomass conversion facilities at an existing plant site.

Using Active Learning to Identify Health Information Technology Related Patient Safety Events.

Science.gov (United States)

Fong, Allan; Howe, Jessica L; Adams, Katharine T; Ratwani, Raj M

2017-01-18

The widespread adoption of health information technology (HIT) has led to new patient safety hazards that are often difficult to identify. Patient safety event reports, which are self-reported descriptions of safety hazards, provide one view of potential HIT-related safety events. However, identifying HIT-related reports can be challenging as they are often categorized under other more predominate clinical categories. This challenge of identifying HIT-related reports is exacerbated by the increasing number and complexity of reports which pose challenges to human annotators that must manually review reports. In this paper, we apply active learning techniques to support classification of patient safety event reports as HIT-related. We evaluated different strategies and demonstrated a 30% increase in average precision of a confirmatory sampling strategy over a baseline no active learning approach after 10 learning iterations.

Quality Control Activities Related to Mechanical Maintenance of Safety Related Components at Krsko NPP

International Nuclear Information System (INIS)

Djakovic, D.

2016-01-01

For successful, safe and reliable operation of nuclear power plant, maintenance processes have to be systematically controlled and procedures for quality control of maintenance activities shall be established. This is requested by the quality assurance program, which shall provide control over activities affecting the quality of structures, systems, and components, considering their importance to safety. As a part of Quality and Nuclear Oversight Division (QNOD; SKV), the Quality Control Department (QC) provides quality control activities, which are deeply involved in maintenance processes at Krsko NPP, both on safety related and non-safety related (non-nuclear safety) components. QC activities on safety related components have to fulfil all requirements, which will enable the components to perform their intended safety functions. This paper describes quality control activities related to mechanical maintenance of safety related components at Krsko NPP and significant role of the Krsko plant QC Department in three particular maintenance cases connected with safety related components. In these three specific cases, the QC has confirmed its importance in compliance with quality assurance program and presented its significant added value in providing safe and reliable operation of the plant. The first maintenance activity was installation of nozzle check valves in the scope of a modification for improving regulation of spent fuel pit pumps. The QC Department performed receipt inspection of the valves. Using non-destructive examination methods and X-ray spectrometry, it was found out that the valve diffuser was made of improper material, which could cause progressive corrosion of the valve diffuser in borated water and consequently a loss of safety function of the valves followed by long-term consequences. The second one was the receipt inspection of containment ventilation fan coolers. The coolers were claimed and sent back to the supplier because the QC Department

Further activities of safety culture toward nuclear transportation industry

International Nuclear Information System (INIS)

Machida, Y.; Shimakura, D.

2004-01-01

On September 30, 1999, a criticality accident occurred at the uranium processing facility of the JCO Co. Ltd. (hereinafter referred to as ''JCO'') Tokai plant, located in Tokaimura, Ibaraki Prefecture. This was an unprecedented accident in Japan's history of peaceful use of nuclear power, resulting in three workers exposed to severe radiation, two of whom died, and the evacuation and enforced indoor confinement of local residents. Nuclear power suppliers must take personal responsibility for ensuring safety. In this connection, the electric power industry, heavy electric machinery manufacturers, fuel fabricators, and nuclear power research organizations gathered together to establish the Nuclear Safety Network (NSnet) in December 1999, based on the resolve to share and improve the level of the safety culture across the entire nuclear power industry and to assure that such an accident never occurs again. NSnet serves as a link between nuclear power enterprises, research organizations, and other bodies, based on the principles of equality and reciprocity. A variety of activities are pursued, such as diffusing a safety culture, implementing mutual evaluation among members, and exchanging safety-related information. Aiming to share and improve the safety culture throughout the entire nuclear power industry, NSnet thoroughly implements the principle of safety first, while at the same time making efforts to restore trust in nuclear power

Fire Safety Tests for Spherical Resorcinol Formaldehyde Resin: Data Summary Report

Energy Technology Data Exchange (ETDEWEB)

Kim, Dong-Sang; Peterson, Reid A.; Schweiger, Michael J.

2012-07-30

A draft safety evaluation of the scenario for spherical resorcinol-formaldehyde (SRF) resin fire inside the ion exchange column was performed by the Hanford Tank Waste Treatment and Immobilization Plant (WTP) Fire Safety organization. The result of this draft evaluation suggested a potential change of the fire safety classification for the Cesium Ion Exchange Process System (CXP) emergency elution vessels, equipment, and piping, which may be overly bounding based on the fire performance data from the manufacturer of the ion exchange resin selected for use at the WTP. To resolve this question, the fire properties of the SRF resin were measured by Southwest Research Institute (SwRI), following the American Society for Testing and Materials (ASTM) standard procedures, through a subcontract managed by Pacific Northwest National Laboratory (PNNL). For some tests, the ASTM standard procedures were not entirely appropriate or practical for the SRF resin material, so the procedures were modified and deviations from the ASTM standard procedures were noted. This report summarizes the results of fire safety tests performed and reported by SwRI. The efforts by PNNL were limited to summarizing the test results provided by SwRI into one consolidated data report. All as-received SwRI reports are attached to this report in the Appendix. Where applicable, the precision and bias of each test method, as given by each ASTM standard procedure, are included and compared with the SwRI test results of the SRF resin.

Development of a Safety Assessment Information System for the Management of Periodic Safety Assessment Activities

International Nuclear Information System (INIS)

Song, Tae Young

2007-01-01

At present, the 10-year Periodic Safety Review(PSR) has been performing to confirm all the aspects of safety issues for all the operating plants in compliance with domestic nuclear law of article 23, subarticle 3. For each plant, in addition, Probabilistic Safety Assessment(PSA) and Severe Accident Management Guideline(SAMG) are being implemented and revised periodically to reflect the latest safety level according to principle fulfillment of severe accident policy statement. The assessment reports, as one of outcomes from these activities, are submitted into and reviewed by domestic regulatory body. During reviewing (in-office duty) and licensing (regulatory duty) process, a large number of outcomes of which most are the formal technical reports and licensing materials, are inevitably produced. Moreover, repeated review process over the plants can make them accumulated and produce a variety of documents additionally. This circumstance motivates to develop effective tool or system for the management of these reports and related technical documents for the future use in licensing process and for subsequent plant assessments. This paper presents the development status of Safety Assessment Information System(SAIS) which manages safety-related documents of PSR, PSA and SAMG for practical use for experienced engineers in charge of these areas

Development of a Safety Assessment Information System for the Management of Periodic Safety Assessment Activities

Energy Technology Data Exchange (ETDEWEB)

Song, Tae Young [Nuclear Engineering and Technology Institute, Daejeon (Korea, Republic of)

2007-07-01

At present, the 10-year Periodic Safety Review(PSR) has been performing to confirm all the aspects of safety issues for all the operating plants in compliance with domestic nuclear law of article 23, subarticle 3. For each plant, in addition, Probabilistic Safety Assessment(PSA) and Severe Accident Management Guideline(SAMG) are being implemented and revised periodically to reflect the latest safety level according to principle fulfillment of severe accident policy statement. The assessment reports, as one of outcomes from these activities, are submitted into and reviewed by domestic regulatory body. During reviewing (in-office duty) and licensing (regulatory duty) process, a large number of outcomes of which most are the formal technical reports and licensing materials, are inevitably produced. Moreover, repeated review process over the plants can make them accumulated and produce a variety of documents additionally. This circumstance motivates to develop effective tool or system for the management of these reports and related technical documents for the future use in licensing process and for subsequent plant assessments. This paper presents the development status of Safety Assessment Information System(SAIS) which manages safety-related documents of PSR, PSA and SAMG for practical use for experienced engineers in charge of these areas.

Active SMS-based influenza vaccine safety surveillance in Australian children.

Science.gov (United States)

Pillsbury, Alexis; Quinn, Helen; Cashman, Patrick; Leeb, Alan; Macartney, Kristine

2017-12-18

Australia's novel, active surveillance system, AusVaxSafety, monitors the post-market safety of vaccines in near real time. We analysed cumulative surveillance data for children aged 6 months to 4 years who received seasonal influenza vaccine in 2015 and/or 2016 to determine: adverse event following immunisation (AEFI) rates by vaccine brand, age and concomitant vaccine administration. Parent/carer reports of AEFI occurring within 3 days of their child receiving an influenza vaccine in sentinel immunisation clinics were solicited by Short Message Service (SMS) and/or email-based survey. Retrospective data from 2 years were combined to examine specific AEFI rates, particularly fever and medical attendance as a proxy for serious adverse events (SAE), with and without concomitant vaccine administration. As trivalent influenza vaccines (TIV) were funded in Australia's National Immunisation Program (NIP) in 2015 and quadrivalent (QIV) in 2016, respectively, we compared their safety profiles. 7402 children were included. Data were reported weekly through each vaccination season; no safety signals or excess of adverse events were detected. More children who received a concomitant vaccine had fever (7.5% versus 2.8%; p vaccine was associated with the highest increase in AEFI rates among children receiving a specified concomitant vaccine: 30.3% reported an AEFI compared with 7.3% who received an influenza vaccine alone (p safety profiles included low and expected AEFI rates (fever: 4.3% for TIV compared with 3.2% for QIV (p = .015); injection site reaction: 1.9% for TIV compared with 3.0% for QIV (p safety profile between brands. Active participant-reported data provided timely vaccine brand-specific safety information. Our surveillance system has particular utility in monitoring the safety of influenza vaccines, given that they may vary in composition annually. Copyright © 2017 Elsevier Ltd. All rights reserved.

Summary of the Safety Culture Activities in HANARO of KAERI

International Nuclear Information System (INIS)

Lim, In-Cheol; Wu, Jong-Sup; Lee, Kye-Hong

2006-01-01

The definition of safety culture in HANARO takes the IAEA's definition and it is the assembly of characteristics of attitudes in the HANARO center and individuals which establishes that, as an overriding priority, the HANARO safety issues receive the attention warranted by their significance. Since the power operation of HANARO started in 1996, HANARO has been operated for about 11 years and its degree of utilization and the number of experimental facilities have increased. This achievement is partly due to the spread of safety culture to the operators and the reactor users. In this paper, the safety culture activities done by the HANARO center of KAERI are described, and its efforts necessary for an improvement of it are presented

Handling and safety enhancement of race cars using active aerodynamic systems

Science.gov (United States)

Diba, Fereydoon; Barari, Ahmad; Esmailzadeh, Ebrahim

2014-09-01

A methodology is presented in this work that employs the active inverted wings to enhance the road holding by increasing the downward force on the tyres. In the proposed active system, the angles of attack of the vehicle's wings are adjusted by using a real-time controller to increase the road holding and hence improve the vehicle handling. The handling of the race car and safety of the driver are two important concerns in the design of race cars. The handling of a vehicle depends on the dynamic capabilities of the vehicle and also the pneumatic tyres' limitations. The vehicle side-slip angle, as a measure of the vehicle dynamic safety, should be narrowed into an acceptable range. This paper demonstrates that active inverted wings can provide noteworthy dynamic capabilities and enhance the safety features of race cars. Detailed analytical study and formulations of the race car nonlinear model with the airfoils are presented. Computer simulations are carried out to evaluate the performance of the proposed active aerodynamic system.

Quarterly report on the activities in Safety Administration Division. The fourth quarter of 2002

International Nuclear Information System (INIS)

Yamamoto, Junta

2003-11-01

The activities of Safety Administration Division covers many fields in Tokai-Works such as the management of a safety and health, the crisis management and the security, the safeguards of the nuclear materials, the transport of nuclear materials, and the management of a quality assurance. This report is summary of the activities of Safety Administration Division in January to March in 2003. (author)

Quarterly report on the activities in Safety Administration Division. The second quarter of 2003

International Nuclear Information System (INIS)

Yamamoto, Junta

2004-08-01

The activities of Safety Administration Division covers many fields in Tokai-Works such as the management of a safety and health, the crisis management and the security, the safeguards of the nuclear materials, the transport of nuclear materials, and the management of a quality assurance. This report is summary of the activities of Safety Administration Division in July to September in 2003. (author)

Quarterly report on the activities in safety Administration Division. The forth quarter of 2003

International Nuclear Information System (INIS)

Yamamoto, Junta

2005-01-01

The activities of Safety Administration Division covers many fields in Tokai-works such as the management of a safety and health, the crisis management and the security, the safeguards of the nuclear materials, the transport of nuclear materials, and the management of a quality assurance. This report is summary of the activities of Safety Administration Division in January to March in 2004. (author)

Quarterly report on the activities in Safety Administration Division. The first quarter of 2003

International Nuclear Information System (INIS)

Yamamoto, Junta

2004-02-01

The activities of Safety Administration Division covers many fields in Tokai-Works such as the management of a safety and health, the crisis management and the security, the safeguards of the nuclear materials, the transport of nuclear materials, and the management of a quality assurance. This report is summary of the activities of Safety Administration Division in April to June in 2003. (author)

The improvement of near-term CdTe processing and product capabilities and establishment of next-generation CdTe technology. Annual technical progress report, September 1, 1995--August 31, 1996

Energy Technology Data Exchange (ETDEWEB)

Kester, J.; Albright, S. [Golden Photon, Inc., CO (United States)

1997-07-01

The potential of photovoltaics to become a major global business enterprise still lingers outside the limits of industrial capabilities. For the Cadmium Sulfide/Cadmium Telluride (CdS/CdTe) system this potential has continued to focus on improvements in efficiency, stability, and cost reduction. This triad is the primary objective of the present subcontract with NREL entitled {open_quotes}The Improvement of Near-term CdTe Processing and Product Capabilities & Establishment of Next Generation CdTe Technology{close_quotes}. This subcontract represents an intermediate stage of NREL`s plan to assist the growth of the photovoltaic industry in overcoming the scientific and technical barriers to commercialization. This report outlines the progress that has been made during the period of August 1995 through August 1996. The objectives of this subcontract are to improve processing methods, quantify and understand efficiency improvement mechanisms, meet life-testing goals, and address cadmium safety concerns. Task and subtask goals are defined to meet these objectives in specific areas. The approach to fulfilling the subcontract goals is through a balanced plan of process improvement and mechanism identification. These are carried out and continued through monitoring under various long term and accelerated stress conditions. GPI maintains an on-going awareness of all safety related issues, can in particular, those involving cadmium.

Seismic safety programme at NPP Paks. Propositions for coordinated international activity in seismic safety of the WWER-440 V-213

International Nuclear Information System (INIS)

Katona, T.

1995-01-01

This paper presents the Paks NPP seismic safety program, highlighting the specifics of the WWER-440/213 type in operation, and the results of work obtained so far. It covers the following scope: establishment of the seismic safety program (original seismic design, current requirements, principles and structure of the seismic safety program); implementation of the seismic safety program (assessing the seismic hazard of the site, development of the new concept of seismic safety for the NPP, assessing the seismic resistance of the building and the technology); realization of the seismic safety of higher level (technical solutions, drawings, realization); ideas and propositions for coordinated international activity

Further activities of safety culture toward nuclear transportation industry

Energy Technology Data Exchange (ETDEWEB)

Machida, Y.; Shimakura, D. [NSnet, Tokyo (Japan)

2004-07-01

On September 30, 1999, a criticality accident occurred at the uranium processing facility of the JCO Co. Ltd. (hereinafter referred to as ''JCO'') Tokai plant, located in Tokaimura, Ibaraki Prefecture. This was an unprecedented accident in Japan's history of peaceful use of nuclear power, resulting in three workers exposed to severe radiation, two of whom died, and the evacuation and enforced indoor confinement of local residents. Nuclear power suppliers must take personal responsibility for ensuring safety. In this connection, the electric power industry, heavy electric machinery manufacturers, fuel fabricators, and nuclear power research organizations gathered together to establish the Nuclear Safety Network (NSnet) in December 1999, based on the resolve to share and improve the level of the safety culture across the entire nuclear power industry and to assure that such an accident never occurs again. NSnet serves as a link between nuclear power enterprises, research organizations, and other bodies, based on the principles of equality and reciprocity. A variety of activities are pursued, such as diffusing a safety culture, implementing mutual evaluation among members, and exchanging safety-related information. Aiming to share and improve the safety culture throughout the entire nuclear power industry, NSnet thoroughly implements the principle of safety first, while at the same time making efforts to restore trust in nuclear power.

Developing safety culture in nuclear activities. Practical suggestions to assist progress

International Nuclear Information System (INIS)

2000-01-01

The term 'safety culture' was introduced by the International Nuclear Safety Advisory Group (INSAG) in Summary Report on the Post-Accident Review Meeting on the Chernobyl Accident published by the IAEA as Safety Series No. 75-INSAG-1 in 1986, and expanded in Basic Safety Principles for Nuclear Power Plants, Safety Series No. 75-INSAG-3 in 1988. This publication supplements INSAG-4 published in 1991 which includes the definition and concept of safety culture describing practices valuable in establishing and maintaining a sound safety culture in a number of countries. It is intended for those who design, construct, manufacture, operate, maintain or decommission nuclear facilities. It should be practically useful for all those involved in operating nuclear facilities. It will also provide a reference for groups such as regulators who have an interest in developing, improving and evaluating safety culture training and individuals engaged in nuclear activities, and for bodies such as ethics review committees who should take into account safety culture issues for certifying professional excellence in the medical field

Developing safety culture in nuclear activities. Practical suggestions to assist progress

International Nuclear Information System (INIS)

1998-01-01

The term 'safety culture' was introduced by the International Nuclear Safety Advisory Group (INSAG) in Summary Report on the Post-Accident Review Meeting on the Chernobyl Accident published by IAEA as safety Series No. 75-INSAG-1 in 1986, and expanded in Basic Safety principles for Nuclear Power Plants, Safety Series No. 75-INSAG-3 in 1988. This publication supplements INSAG-4 published in 1991 which includes the definition and concept of safety culture describing practices valuable in establishing and maintaining a sound safety culture in a number of countries. It is intended for those who design, construct, manufacture, operate, maintain or decommission nuclear facilities. It should be practically useful for all those involved in operating nuclear facilities. It will also provide a reference for groups such as regulators who have an interest in developing, improving and evaluating safety culture training and individuals engaged in nuclear activities, and for bodies such as ethics review committees who should take into account safety culture issues for certifying professional excellence in the medical field

Does perceived neighborhood walkability and safety mediate the association between education and meeting physical activity guidelines?

Science.gov (United States)

Pratt, Michael; Yin, Shaoman; Soler, Robin; Njai, Rashid; Siegel, Paul Z; Liao, Youlian

2015-04-09

The role of neighborhood walkability and safety in mediating the association between education and physical activity has not been quantified. We used data from the 2010 and 2012 Communities Putting Prevention to Work Behavioral Risk Factor Surveillance System and structural equation modeling to estimate how much of the effect of education level on physical activity was mediated by perceived neighborhood walkability and safety. Neighborhood walkability accounts for 11.3% and neighborhood safety accounts for 6.8% of the effect. A modest proportion of the important association between education and physical activity is mediated by perceived neighborhood walkability and safety, suggesting that interventions focused on enhancing walkability and safety could reduce the disparity in physical activity associated with education level.

Safety and Health Perceptions in Work-related Transport Activities in Ghanaian Industries

Directory of Open Access Journals (Sweden)

Charles Atombo

2017-06-01

Conclusion: OSH culture is not fully complied in industries transport activities. This study, therefore, supports the use of safety seminars and training sessions for industry workers responsible for transport operations for better integration of safety standards.

Status of Safety and Environmental Activities for Inertial Fusion Energy

International Nuclear Information System (INIS)

Latkowski, J.F.; Reyes, S.; Cadwallader, L.C.; Sharpe, J.P.; Marshall, T.D.; Merrill, B.J.; Moore, R.L.; Petti, D.A.; Falquina, R.; Rodriguez, A.; Sanz, J.; Cabellos, O.

2003-01-01

Over the past several years, significant progress has been made in the analysis of safety and environmental (S and E) issues for inertial fusion energy (IFE). Detailed safety assessments have been performed for the baseline power plant concepts, as well as for a conceptual target fabrication facility. Safety analysis results are helping to drive the agenda for experiments. A survey of the S and E characteristics - both radiological and chemical - of candidate target materials has been completed. Accident initiating events have been identified and incorporated into master logic diagrams, which will be essential to the detailed safety analyses that will be needed in the future. Studies of aerosol generation and transport will have important safety implications. A Monte Carlo-based uncertainty analysis procedure has been developed for use in neutron activation calculations. Finally, waste management issues are receiving increased attention and are deserving of further discussion

The safety activities of the ICAO and the IAEA

International Nuclear Information System (INIS)

Franzen, L.F.; Iansiti, E.

1983-01-01

The article presents a comparative analysis of the safety activities of the IAEA and the International Civil Aviation Organization (ICAO), from which possible solutions for the problems faced by the nuclear community are suggested

Safety surveillance of activities on nuclear pressure components in China

International Nuclear Information System (INIS)

Li Ganjie; Li Tianshu; Yan Tianwen

2005-01-01

The nuclear pressure components, which perform the nuclear safety functions, are one of the key physical barriers for nuclear safety. For the national strategy on further development of nuclear power and localization of nuclear pressure components, there still exist some problems in preparedness on the localization. As for the technical basis, what can not be overlooked is the management. Aiming at the current problems, National Nuclear Safety Administration (NNSA) has taken measures to strengthen the propagation and popularization of nuclear safety culture, adjust the review and approval policies for nuclear pressure components qualification license, establish more stringent management requirements, and enhance the surveillance of activities on nuclear pressure equipment. Meanwhile, NNSA has improved the internal management and the regulation efficiency on nuclear pressure components. At the same time, with the development and implementation of 'Rules on the Safety Regulation for Nuclear Safety Important Components' to be promulgated by the State Council of China, NNSA will complete and improve the regulation on nuclear pressure components and other nuclear equipment. (authors)

Safety from Crime and Physical Activity among Older Adults: A Population-Based Study in Brazil

International Nuclear Information System (INIS)

Corseuil, M.W.; Schneider, I.J.C.; Orsi, E.; Hallal, P.C.; Corseuil, H.X.

2012-01-01

Objective. To evaluate the association between safety from crime and physical activity among older adults. Methods. A population-based survey including 1,656 older adults (60+ years) took place in Florianopolis, Brazil, in 2009-2010. Commuting and leisure time physical activity were assessed through the long version of the International Physical Activity Questionnaire. Perception of safety from crime was assessed using the Neighbourhood Environment Walk ability Scale. Results. Perceiving the neighbourhood as safe during the day was related to a 25% increased likelihood of being active in leisure time (95% CI 1.02-1.53); general perception of safety was also associated with a 25% increase in the likelihood of being active in leisure time (95% CI 1.01-1.54). Street lighting was related to higher levels of commuting physical activity (prevalence ratio: 1.89; 95% CI 1.28-2.80). Conclusions. Safety investments are essential for promoting physical activity among older adults in Brazil

Annual report on the activities in Safety Administration Department. Report of the fiscal year 2010

Energy Technology Data Exchange (ETDEWEB)

Aoki, Yoshikazu [Japan Atomic Energy Agency, Nuclear Fuel Cycle Engineering Laboratories, Tokai, Ibaraki (Japan)

2014-01-15

The activities of Safety Administration Department covers many fields in Nuclear Fuel Cycle Engineering Laboratories such as the management of the occupational safety and health, the crisis management, the security, and the management of a quality assurance. This report is the summary of the activities of Safety Administration Department since April, 2010 until March, 2011. (author)

Regulatory activities in the area of fuel safety and performance

International Nuclear Information System (INIS)

Viktorov, A.; Couture, M.

2005-01-01

Generic Action Item 94G02 'Impact of Fuel Bundle Condition on Reactor Safety' in many ways determined the present priorities in regulatory activities related to fuel performance. As one of the closure criteria it required that all licensees establish 'an effective formal and systematic process for integrating fuel design, fuel and channel inspection, laboratory examination, research, operating limits and safety analysis'. To date, such a process has been, to a large extent, put in place by all licensees. To assure that such processes remain operational and effective after the GAI closure, CNSC required, through S-99, to report annually on fuel performance and major activities in the fuel safety area. The scope of reported information has been defined to allow CNSC staff evaluation of key events and trends in fuel performance. To compliment reporting by the industry, CNSC staff has conducted targeted inspections of fuel compliance programs at all sites. Combined together, these activities provide the regulator with the confidence that CANDU fuel is robust and operates with safety margins. The scrutiny, to which fuel performance has been subjected lately, has allowed identification of certain programmatic weaknesses and gaps in the knowledge concerning the fuel behaviour under various conditions. It has become apparent that top-level strategies for assessment of fuel performance may have been inadequate and far from systematic; fuel inspection practices and capabilities have varied significantly from site to site; certain issues were identified but remained unaddressed for significant time; priorities in experimental or design support activities were not assigned consistently. The presentation gives examples of areas where, in the opinion of the CNSC staff, further work is required to support fuel design and safety envelopes. The implementation of new CANFLEX fuel designs is currently being considered by the industry and CNSC staff has been engaged in the review

78 FR 34703 - Pipeline Safety: Information Collection Activities, Revision to Gas Distribution Annual Report

Science.gov (United States)

2013-06-10

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2013-0004] Pipeline Safety: Information Collection Activities, Revision to Gas Distribution Annual Report AGENCY: Pipeline and Hazardous Materials Safety Administration, DOT. ACTION: Notice and request...

Inter-CLI work-group: safety after Fukushima; GT inter-CLI 'surete post Fukushima'

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-11-03

This document contains a whole set of questions asked about nuclear safety and security by a work-group made of members of associations belonging to local information commissions. These questions are asked either to the French State, or to EDF, or to AREVA. They bear on general issues common to La Hague and Flamanville nuclear installations, notably public information, emergency plans, post-accident management, subcontracting, loss of electricity supply, public health, governance, computer hacking, extreme meteorological events. A set of questions concerns the AREVA processing plant in La Hague (warehousing, pools for irradiated fuels, plutonium oxide storage and warehousing, and so on), and another set concerns the Flamanville nuclear power plant (different aspects of the management of a crisis situation). The last set of questions concerns the Manche nuclear waste storage centre

Annual activity report of Ignalina NPP Safety Analysis Group for 1996 year

International Nuclear Information System (INIS)

Ushpuras, E.; Augutis, J.; Bubelis, E.

1997-03-01

The main results of Ignalina NPP Safety Analysis Group (ISAG) investigations for 1996 are presented. ISAG is concentrating its research activities into four areas: the neutrons dynamics modelling, simulation of transient processes during loss of coolant accident, the reactor cooling systems modelling and the probabilistic safety assessment of accident confinement system. Ignalina Safety Analysis Report was prepared on the basis of these results. 37 refs., 9 tabs., 96 figs

Safety update on the use of recombinant activated factor VII in approved indications.

Science.gov (United States)

Neufeld, Ellis J; Négrier, Claude; Arkhammar, Per; Benchikh el Fegoun, Soraya; Simonsen, Mette Duelund; Rosholm, Anders; Seremetis, Stephanie

2015-06-01

This updated safety review summarises the large body of safety data available on the use of recombinant activated factor VII (rFVIIa) in approved indications: haemophilia with inhibitors, congenital factor VII (FVII) deficiency, acquired haemophilia and Glanzmann's thrombasthenia. Accumulated data up to 31 December 2013 from clinical trials as well as post-marketing data (registries, literature reports and spontaneous reports) were included. Overall, rFVIIa has shown a consistently favourable safety profile, with no unexpected safety concerns, in all approved indications. No confirmed cases of neutralising antibodies against rFVIIa have been reported in patients with congenital haemophilia, acquired haemophilia or Glanzmann's thrombasthenia. The favourable safety profile of rFVIIa can be attributed to the recombinant nature of rFVIIa and its localised mechanism of action at the site of vascular injury. Recombinant FVIIa activates factor X directly on the surface of activated platelets, which are present only at the site of injury, meaning that systemic activation of coagulation is avoided and the risk of thrombotic events (TEs) thus reduced. Nonetheless, close monitoring for signs and symptoms of TE is warranted in all patients treated with any pro-haemostatic agent, including rFVIIa, especially the elderly and any other patients with concomitant conditions and/or predisposing risk factors to thrombosis. Copyright © 2015 Elsevier Ltd. All rights reserved.

Safety assessment of discharge chute isolation barrier preparation and installation activities. Revision 3

International Nuclear Information System (INIS)

Meichle, R.H.

1994-01-01

This revision adds a section addressing impacts of dropping surfacing tool and rack cutter on the basin floor, and corrects typographical errors. The safety assessment is made for the activities for the preparation and installation of the discharge chute isolation barriers. The safety assessment includes a hazard assessment and comparisons of potential accidents/events to those addressed by the current safety basis documentation. No significant hazards were identified. An evaluation against the USQ evaluation questions was made and the determination made that the activities do not represent a USQ. Hazard categorization techniques were used to provide a basis for readiness review classifications

A Study of Cyber Security Activities for Development of Safety-related Controller

Energy Technology Data Exchange (ETDEWEB)

Lee, Myeongkyun; Song, Seunghwan; Yoo, Kwanwoo; Yun, Donghwa [Korea Univ., Seoul (Korea, Republic of)

2014-05-15

Nuclear Power Plant Regulatory guide describes the regulatory requirements to implement cyber security activities to ensure that design and operate to respond to cyber threats that exploited to vulnerability of digital-based technologies associated with safety-related digital instrumentation and control systems at nuclear power plants. Cyber security activities coverage is instrumentation and control systems to perform safety functions and digital-based equipment to use development, test, analysis and asset for instrumentation and control systems. Regulatory guidance is required to the cyber security activities that should be performed in each development phase of safety-related controller. Development organization should establish and implement to cyber security plans for responding to cyber threats throughout each lifecycle phase and the result of the cyber security activities should be generated to the documents. In addition, the independent verification and validation organization should perform simulated penetration test for enhancing response capabilities to cyber security threats and development organization should establish and implement response hardening solutions for the cyber security vulnerabilities identified in the simulated penetration test.

A Study of Cyber Security Activities for Development of Safety-related Controller

International Nuclear Information System (INIS)

Lee, Myeongkyun; Song, Seunghwan; Yoo, Kwanwoo; Yun, Donghwa

2014-01-01

Nuclear Power Plant Regulatory guide describes the regulatory requirements to implement cyber security activities to ensure that design and operate to respond to cyber threats that exploited to vulnerability of digital-based technologies associated with safety-related digital instrumentation and control systems at nuclear power plants. Cyber security activities coverage is instrumentation and control systems to perform safety functions and digital-based equipment to use development, test, analysis and asset for instrumentation and control systems. Regulatory guidance is required to the cyber security activities that should be performed in each development phase of safety-related controller. Development organization should establish and implement to cyber security plans for responding to cyber threats throughout each lifecycle phase and the result of the cyber security activities should be generated to the documents. In addition, the independent verification and validation organization should perform simulated penetration test for enhancing response capabilities to cyber security threats and development organization should establish and implement response hardening solutions for the cyber security vulnerabilities identified in the simulated penetration test

Analysis and discussion on reports of additional safety assessment of nuclear installations with respect to the Fukushima accident

International Nuclear Information System (INIS)

Sene, Monique; Sene, Raymond

2011-11-01

This document proposes an analysis of the reports made by the different operators of nuclear installations within the frame of a safety audit of the French nuclear installations with respect to the Fukushima accident. Operators (mainly AREVA, the CEA and EDF) were asked to perform additional safety assessments. In a first part, the conclusions of EDF reports are analysed regarding the seismic risk, the flooding risk, the situation of some specific sites (Fessenheim, Tricastin), other phenomena (rains, winds), loss of electricity supplies and of cooling systems, severe accidents, hydrogen issue, chemical hazards, subcontractors, crisis management. Conclusions of AREVA reports are analysed for the different sites (Tricastin, La Hague, MELOX factory, Romans factory). Conclusions of CEA reports are analysed for the different concerned installations (ATPu, Masurca, Osiris, Phenix, Jules Horowitz reactor). A second part proposes a global analysis of EDF's additional safety assessment reports regarding earthquake, flooding, other extreme natural phenomena, loss of electricity supplies and cooling system, subcontracting conditions, crisis management, and radiation protection organisation. AREVA's and CEA's reports are then analysed in terms of report structure and content, and for the different concerned sites

Personnel Risks in Ensuring Safety of Medical Activity

Directory of Open Access Journals (Sweden)

O. L. Zadvornaya

2017-01-01

Full Text Available Purpose: modern strategies of management of the organization require the formation of special management approaches based on the analysis of the mechanisms and processes of the organization of medical activities related to possible risks in activity of medical personnel. Based on international experience and own research the authors have identified features of a system of management of personnel risk in medical activities, examined approaches showing the sequence and contents of the main practical activities of the formation, maintenance and development of the system of management of personnel risks. Emphasized is the need for further research and implementation of the system of management of personnel risk in health care organizations. Study and assessment of personnel risks affecting the security of medical activities aimed at the development of the system of personnel risk management, development of a system of identification and monitoring of HR risk indicators with a purpose to improve institutional management and increase efficiency of activity of medical organizations. Methods: in the present study, the following methods were used: systemic approach, content analysis, methods of social diagnosis (questionnaires, interviews, comparative analysis, method of expert evaluations, method of statistical processing of information. Results: approaches to predict the occurrence and development of personnel risks have been reviewed and proposed. Conclusions and Relevance: patient safety is a global issue affecting countries at all levels of development. Each year, the WHO identifies a number of systemic and technical aspects and trends in the field of patient safety related to actions of medical workers. Existing imbalances in the staffing of the health system of the Russian Federation increase the probability of potential risks in medical practice. The personnel policy of healthcare of the Russian Federation requires further improvement and

Safety

International Nuclear Information System (INIS)

1998-01-01

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

Comprehensive target populations for current active safety systems using national crash databases.

Science.gov (United States)

Kusano, Kristofer D; Gabler, Hampton C

2014-01-01

The objective of active safety systems is to prevent or mitigate collisions. A critical component in the design of active safety systems is the identification of the target population for a proposed system. The target population for an active safety system is that set of crashes that a proposed system could prevent or mitigate. Target crashes have scenarios in which the sensors and algorithms would likely activate. For example, the rear-end crash scenario, where the front of one vehicle contacts another vehicle traveling in the same direction and in the same lane as the striking vehicle, is one scenario for which forward collision warning (FCW) would be most effective in mitigating or preventing. This article presents a novel set of precrash scenarios based on coded variables from NHTSA's nationally representative crash databases in the United States. Using 4 databases (National Automotive Sampling System-General Estimates System [NASS-GES], NASS Crashworthiness Data System [NASS-CDS], Fatality Analysis Reporting System [FARS], and National Motor Vehicle Crash Causation Survey [NMVCCS]) the scenarios developed in this study can be used to quantify the number of police-reported crashes, seriously injured occupants, and fatalities that are applicable to proposed active safety systems. In this article, we use the precrash scenarios to identify the target populations for FCW, pedestrian crash avoidance systems (PCAS), lane departure warning (LDW), and vehicle-to-vehicle (V2V) or vehicle-to-infrastructure (V2I) systems. Crash scenarios were derived using precrash variables (critical event, accident type, precrash movement) present in all 4 data sources. This study found that these active safety systems could potentially mitigate approximately 1 in 5 of all severity and serious injury crashes in the United States and 26 percent of fatal crashes. Annually, this corresponds to 1.2 million all severity, 14,353 serious injury (MAIS 3+), and 7412 fatal crashes. In addition

Defining safety culture and the nexus between safety goals and safety culture. 1. An Investigation Study on Practical Points of Safety Management

International Nuclear Information System (INIS)

Hasegawa, Naoko; Takano, Kenichi; Hirose, Ayako

2001-01-01

In a report after the Chernobyl accident, the International Atomic Energy Agency indicated the definition and the importance of safety culture and the ideal organizational state where safety culture pervades. However, the report did not mention practical approaches to enhance safety culture. In Japan, although there had been investigations that clarified the consciousness of employees and the organizational climate in the nuclear power and railway industries, organizational factors that clarified the level of organization safety and practical methods that spread safety culture in an organization had not been studied. The Central Research Institute of the Electric Power Industry conducted surveys of organizational culture for the construction, chemical, and manufacturing industries. The aim of our study was to clarify the organizational factors that influence safety in an organization expressed in employee safety consciousness, commitment to safety activities, rate of accidents, etc. If these areas were clarified, the level of organization safety might be evaluated, and practical ways could be suggested to enhance the safety culture. Consequently, a series of investigations was conducted to clarify relationships among organizational climate, employee consciousness, safety management and activities, and rate of accidents. The questionnaire surveys were conducted in 1998-1999. The subjects were (a) managers of the safety management sections in the head offices of the construction, chemical, and manufacturing industries; (b) responsible persons in factories of the chemical and manufacturing industries; and (c) general workers in factories of the chemical and manufacturing industries. The number of collected data was (a) managers in the head office: 48 from the construction industry and 58 from the chemical and manufacturing industries, (b) responsible persons in factories: 567, and (c) general workers: from 29 factories. Items in the questionnaires were selected from

Companies which maintain the nuclear fleet - Information note 2015

International Nuclear Information System (INIS)

2015-01-01

This publication first recalls the reasons for subcontracting the maintenance of French nuclear plants (need of specialised expertise and abilities) even though EDF keeps an industrial and technical control. It describes the framework of these subcontracted activities (a long lasting collaboration, implementation of requirements), and how multi-annual markets are subcontracted to support the development of specialised companies. It outlines to which extent the selection and certification process is rigorous, that subcontractor salaried personnel is to be specifically trained, that radiation protection is performed under the same conditions for everybody. It indicates some specific measures which have been implemented to take subcontractor personnel working conditions into account. The updating of abilities for future activities is discussed. Some key data are provided regarding jobs, contracts, training, medical expenses, and fields of activity of subcontracting companies

On-going and some future safety related activities of the OECD/NEA

International Nuclear Information System (INIS)

Frescura, G.

2001-01-01

The CSNI and CNRA structures and current activities of direct relevance to WWERs are presented. The nuclear regulatory challenges arising from economic deregulation like: direct safety challenges, infrastructure issues, increased pressure on regulatory bodies etc. are given. The OECD/NEA initiatives on assuring nuclear safety competence are mentioned

Regulatory support activities of JNES by thermal-hydraulic and safety analyses

International Nuclear Information System (INIS)

Kasahara, Fumio

2008-01-01

Current status and some related topics on regulatory support activities of Japan Nuclear Energy Safety Organization (JNES) by thermal-hydraulic and safety analyses are reported. The safety of nuclear facilities is secured primarily by plant owners and operators. However, the regulatory body NISA (Nuclear and Industrial Safety Agency) has conducted a strict regulation to confirm the adequacy of the site condition as well as the basic and detailed design. The JNES has been conducting independent analyses from applicants (audit analyses, etc.) by direction of NISA and supporting its review. In addition to the audit analysis, thermal-hydraulic and safety analyses are used in such areas as analytical evaluation for investigation of causes of accidents and troubles, level 2 PSA for risk informed regulation, etc. Recent activities of audit analyses are for the application of Tsuruga 3 and 4 (APWR), the spent fuel storage facility for the establishment, and the LMFBR Monju for the core change. For the trouble event evaluation, the criticality accident analysis of Sika1 was carried out and the evaluation of effectiveness of accident management (AM) measure for Tomari 3 (PWR) and Monju was performed. The analytical codes for these evaluations are continuously revised by reflecting the state-of-art technical information and validated using the information provided by the data from JAEA, OECD project, etc. (author)

Medication safety activities of hospital pharmacists in Ghana; challenges and perceived impact on patient care.

Science.gov (United States)

Acheampong, Franklin; Bruce, Elizabeth; Anto, Berko Panyin

2015-01-01

Pharmacists by their training have the competences and skills to promote safe use of medicines which is an essential component of patient safety. This study explored the perceptions of hospital pharmacists' role in medication safety in Ghana, identified their attendant challenges and ways of enhancing such roles in the future. A self-administered questionnaire was delivered to 200 pharmacists selected conveniently from the 10 regions of Ghana. Questions in the questionnaire were based on a systematic literature review that had catalogued and summarised all the activities of hospital pharmacists related to medication safety. A total of 176 (88% response rate) questionnaires were completed and returned. Almost all pharmacists (97.7%) believed that they were involved in medication safety activities in their daily routine. The frequently performed activities were counselling of out-patient (91.8%), training pharmacy and other clinical students (72.2%), reporting on medication errors (70%), and reconciling medications (69.2%). The mean weekly time spent on the activities ranged from 6.5 to 19.8 hours. Participants who had clinical pharmacy related additional qualifications (χ2 = 37.749; p = 0.049) and worked in tertiary care hospitals (χ2 = 26.6; p = 0.377) undertook more medication safety activities than those without. The cited challenges faced by participants included inadequate time available (62.7%), spending most time in managerial activities (47.3%), lack of formal structures of engagement (43.8%), lack of motivation by superiors (34.9%), and no formal schedule by supervisor (32%). Only 7.7% stated they lack interest in performing those activities. Pharmacists undertake many medication safety activities routinely that they perceive to have impact on patient care outcomes. Restructuring of their managerial roles will contribute to freeing time for pharmacists to engage more in those activities.

Safety activities and human resource development at NCA

International Nuclear Information System (INIS)

Kumanomido, Hironori; Sakurada, Koichi; Yanagisawa, Shigeru; Masuyama, Tadaharu

2015-01-01

Toshiba Nuclear Critical Assembly (NCA) has been safely operated since the first criticality in December 1963. The topics covered in this Yayoi Meeting Report are: (1) the outline of NCA, (2) the safety control situation mainly after the Great East Japan Earthquake in 2011, (3) educational training incorporates the lessons learned in this earthquake, and (4) human resource development during 2008-2015. Regarding safety control, facility maintenance has been conducted systematically according to the maintenance plan from the viewpoint of preventive maintenance. Regarding educational training, two disaster handling training based on the safety regulation and one nuclear emergency drill based on the emergency drill plan for licensee of nuclear energy activity based on the Act of Special Measures Concerning Nuclear Emergency Preparedness every year. Regarding human resource development, development training was given to 358 people including students. This year, training that does not require NCA operation was conducted including gamma-ray spectrum measurement of NCA fuel rod and neutron deceleration property measurement using 252 Cf neutron source. (S.K.)

A generic standard for assessing and managing activities with significant risk to health and safety

International Nuclear Information System (INIS)

Wilde, T.S.; Sandquist, G.M.

2005-01-01

Some operations and activities in industry, business, and government can present an unacceptable risk to health and safety if not performed according to established safety practices and documented procedures. The nuclear industry has extensive experience and commitment to assessing and controlling such risks. This paper provides a generic standard based upon DOE Standard DOE-STD-3007- 93, Nov 1993, Change Notice No. 1, Sep 1998. This generic standard can be used to assess practices and procedures employed by any industrial and government entity to ensure that an acceptable level of safety and control prevail for such operations. When any activity and operation is determined to involve significant risk to health and safety to workers or the public, the organization should adopt and establish an appropriate standard and methodology to ensure that adequate health and safety prevail. This paper uses DOE experience and standards to address activities with recognized potential for impact upon health and safety. Existing and future assessments of health and safety issues can be compared and evaluated against this generic standard for insuring that proper planning, analysis, review, and approval have been made. (authors)

Defining safety culture and the nexus between safety goals and safety culture. 4. Enhancing Safety Culture Through the Establishment of Safety Goals

International Nuclear Information System (INIS)

Tateiwa, Kenji; Miyata, Koichi; Yahagi, Kimitoshi

2001-01-01

Safety culture is the perception of each individual and organization of a nuclear power plant that safety is the first priority, and at Tokyo Electric Power Company (TEPCO), we have been practicing it in everyday activities. On the other hand, with the demand for competitiveness of nuclear power becoming even more intense these days, we need to pursue efficient management while maintaining the safety level at the same time. Below, we discuss how to achieve compatibility between safety culture and efficient management as well as enhance safety culture. Discussion at Tepco: safety culture-nurturing activities such as the following are being implemented: 1. informing the employees of the 'Declaration of Safety Promotion' by handing out brochures and posting it on the intranet home page; 2. publishing safety culture reports covering stories on safety culture of other industry sectors, recent movements on safety culture, etc.; 3. conducting periodic questionnaires to employees to grasp how deeply safety culture is being established; 4. carrying out educational programs to learn from past cases inside and outside the nuclear industry; 5. committing to common ownership of information with the public. The current status of safety culture in Japan sometimes seems to be biased to the quest of ultimate safety; rephrasing it, there have been few discussions regarding the sufficiency of the quantitative safety level in conjunction with the safety culture. Safety culture is one of the most crucial foundations guaranteeing the plant's safety, and for example, the plant safety level evaluated by probabilistic safety assessment (PSA) could be said to be valid only on the ground that a sound and sufficient safety culture exists. Although there is no doubt that the safety culture is a fundamental and important attitude of an individual and organization that keeps safety the first priority, the safety culture in itself should not be considered an obstruction to efforts to implement

Mathematical modelling of active safety system functions as tools for development of driverless vehicles

Science.gov (United States)

Ryazantsev, V.; Mezentsev, N.; Zakharov, A.

2018-02-01

This paper is dedicated to a solution of the issue of synthesis of the vehicle longitudinal dynamics control functions (acceleration and deceleration control) based on the element base of the vehicle active safety system (ESP) - driverless vehicle development tool. This strategy helps to reduce time and complexity of integration of autonomous motion control systems (AMCS) into the vehicle architecture and allows direct control of actuators ensuring the longitudinal dynamics control, as well as reduction of time for calibration works. The “vehicle+wheel+road” longitudinal dynamics control is complicated due to the absence of the required prior information about the control object. Therefore, the control loop becomes an adaptive system, i.e. a self-adjusting monitoring system. Another difficulty is the driver’s perception of the longitudinal dynamics control process in terms of comfort. Traditionally, one doesn’t pay a lot of attention to this issue within active safety systems, and retention of vehicle steerability, controllability and stability in emergency situations are considered to be the quality criteria. This is mainly connected to its operational limits, since it is activated only in critical situations. However, implementation of the longitudinal dynamics control in the AMCS poses another challenge for the developers - providing the driver with comfortable vehicle movement during acceleration and deceleration - while the possible highest safety level in terms of the road grip is provided by the active safety system (ESP). The results of this research are: universal active safety system - AMCS interaction interface; block diagram for the vehicle longitudinal acceleration and deceleration control as one of the active safety system’s integrated functions; ideology of adaptive longitudinal dynamics control, which enables to realize the deceleration and acceleration requested by the AMCS; algorithms synthesised; analytical experiments proving the

Neighbourhood social trust and youth perceptions of safety during daily activities.

Science.gov (United States)

Flynn, Kalen; Richmond, Therese S; Branas, Charles C; Wiebe, Douglas J

2017-10-07

Exposure to adverse neighbourhood conditions can negatively impact adolescent well-being and perceived safety. However, the impact of neighbourhood social trust on perceived safety is largely unknown. We studied 139 adolescent men to investigate how their perceptions of safety varied as a function of social trust levels in the neighbourhoods they traversed; neighbourhoods that were not necessarily their own. Adolescents mapped their minute-by-minute activities over a recent day and rated their perceived safety on a 10-point scale during in-person interviews. Neighbourhood social trust was measured via a citywide random sample survey. Mixed effects regression showed that, compared with their safety perceptions when in areas of low social trust, older adolescents were 73% more likely to feel unsafe when in areas of medium social trust, and 89% more likely to feel unsafe when in areas of high social trust. Inverse relationships between neighbourhood social trust and adolescents' perceived safety highlight the complex interplay between youth, environmental contexts and safety. © Article author(s) (or their employer(s) unless otherwise stated in the text of the article) 2017. All rights reserved. No commercial use is permitted unless otherwise expressly granted.

Overview of the activities of the OECD/NEA/NSC working party on nuclear criticality safety

International Nuclear Information System (INIS)

Nouri, A.; Blomquist, R.; Bradyraap, M.; Briggs, B.; Cousinou, P.; Nomura, Y.; Weber, W.

2003-01-01

The OECD Nuclear Energy Agency (NEA) started dealing with criticality-safety related subjects back in the seventies. In the mid-nineties, several activities related to criticality-safety were grouped together into the Working Party on Nuclear Criticality Safety. This working party has since been operating and reporting to the Nuclear Science Committee. Six expert groups co-ordinate various activities ranging from experimental evaluations to code and data inter-comparisons for the study of static and transient criticality behaviours. The paper describes current activities performed in this framework and the achievements of the various expert groups. (author)

NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security, Issue no. 6, March 2008

International Nuclear Information System (INIS)

2008-03-01

The current issue presents information about the following activities: 1) International Conference on Illicit Nuclear Trafficking which took place in November 2007 in Edinburgh. The principal aim of the conference was to examine the threat and context of illicit nuclear trafficking of radioactive material, specifically, what is being done to combat such trafficking and where more needs to be done. The conference was also to consider how the obligations and commitments of the legally binding and non-binding international instruments could be and are being implemented by various States. 2) INSAG Message on Nuclear Safety Infrastructure in which the INSAG Chairman Richard Meserve addressed nuclear safety in the current context and various issues that warrant special attention. 3) approved for publication the Safety Requirements publication on Safety of Nuclear Fuel Cycle Facilities. 4) The Asian Nuclear Safety Network (ANSN)

Post-Fukushima additional safety assessments: behaviour of French nuclear installations in case of extreme situations and relevance of improvement propositions

International Nuclear Information System (INIS)

2011-01-01

After the Fukushima accident, additional safety assessments (ECS, evaluation complementaire de securite) have been commissioned to assess the resistance of French nuclear installations to extreme scenarios (earthquake, loss of electricity supply, and loss of cooling sources). This report is a synthesis of a more important one. It briefly describes the international context and notices that, in foreign countries, only power reactors are submitted to such additional safety assessments. It describes the approach adopted by the IRSN by considering that severe accidental situation are possible and may have characteristics exceeding the current referential. This approach enables the identification of safety functions which must maintained in these situations, and of some limitations of the current safety referential. The report then discusses the current status of installations, notices that actions are to be performed. It comments the results obtained in terms of installation robustness with respect to risks of earthquake or flooding, or those associated with other external hazards. It comments the analysis performed in case of total loss of cooling sources or of energy supplies in power reactors, in the EPR, and in some other nuclear installations (ILL, CEA's installations, AREVA's laboratories and factories). It finally comments the ability of operators in managing a crisis situation under these conditions, and briefly evokes the subcontracting issue

The Management System for Facilities and Activities. Safety Requirements

International Nuclear Information System (INIS)

2011-01-01

This publication establishes requirements for management systems that integrate safety, health, security, quality assurance and environmental objectives. A successful management system ensures that nuclear safety matters are not dealt with in isolation but are considered within the context of all these objectives. The aim of this publication is to assist Member States in establishing and implementing effective management systems that integrate all aspects of managing nuclear facilities and activities in a coherent manner. It details the planned and systematic actions necessary to provide adequate confidence that all these requirements are satisfied. Contents: 1. Introduction; 2. Management system; 3. Management responsibility; 4. Resource management; 5. Process implementation; 6. Measurement, assessment and improvement.

Two types of a passive safety containment for a near future BWR with active and passive safety systems

International Nuclear Information System (INIS)

Sato, Takashi; Akinaga, Makoto; Kojima, Yoshihiro

2009-01-01

The paper presents two types of a passive safety containment for a near future BWR. They are named Mark S and Mark X containment. One of their common merits is very low peak pressure at severe accidents without venting the containment atmosphere to the environment. The PCV pressure can be moderated within the design pressure. Another merit is the capability to submerge the PCV and the RPV above the core level. The third merit is robustness against external events such as a large commercial airplane crash. Both the containments have a passive cooling core catcher that has radial cooling channels. The Mark S containment is made of reinforced concrete and applicable to a large power BWR up to 1830 MWe. The Mark X containment has the steel secondary containment and can be cooled by natural circulation of outside air. It can accommodate a medium power BWR up to 1380 MWe. In both cases the plants have active and passive safety systems constituting in-depth hybrid safety (IDHS). The IDHS provides not only hardware diversity between active and passive safety systems but also more importantly diversity of the ultimate heat sinks between the atmosphere and the sea water. Although the plant concept discussed in the paper uses well-established technology, plant performance including economy is innovatively and evolutionally improved. Nothing is new in the hardware but everything is new in the performance.

Two types of a passive safety containment for a near future BWR with active and passive safety systems

Energy Technology Data Exchange (ETDEWEB)

Sato, Takashi [Toshiba Corporation, IEC, Gen-SS, 8, Shinsugita-ho, Isogo-ku, Yokohama (Japan)], E-mail: takashi44.sato@glb.toshiba.co.jp; Akinaga, Makoto; Kojima, Yoshihiro [Toshiba Corporation, IEC, Gen-SS, 8, Shinsugita-ho, Isogo-ku, Yokohama (Japan)

2009-09-15

The paper presents two types of a passive safety containment for a near future BWR. They are named Mark S and Mark X containment. One of their common merits is very low peak pressure at severe accidents without venting the containment atmosphere to the environment. The PCV pressure can be moderated within the design pressure. Another merit is the capability to submerge the PCV and the RPV above the core level. The third merit is robustness against external events such as a large commercial airplane crash. Both the containments have a passive cooling core catcher that has radial cooling channels. The Mark S containment is made of reinforced concrete and applicable to a large power BWR up to 1830 MWe. The Mark X containment has the steel secondary containment and can be cooled by natural circulation of outside air. It can accommodate a medium power BWR up to 1380 MWe. In both cases the plants have active and passive safety systems constituting in-depth hybrid safety (IDHS). The IDHS provides not only hardware diversity between active and passive safety systems but also more importantly diversity of the ultimate heat sinks between the atmosphere and the sea water. Although the plant concept discussed in the paper uses well-established technology, plant performance including economy is innovatively and evolutionally improved. Nothing is new in the hardware but everything is new in the performance.

Application of the Management System for Facilities and Activities. Safety Guide

International Nuclear Information System (INIS)

2009-01-01

This publication provides guidance for following the requirements for management systems that integrate safety, health, security, quality assurance and environmental objectives. A successful management system ensures that nuclear safety matters are not dealt with in isolation but are considered within the context of all these objectives. The aim of this publication is to assist Member States to establish and implement effective management systems that coherently integrate all aspects of managing nuclear facilities and activities. Contents: 1. Introduction; 2. Management system; 3. Management responsibility; 4. Resource management; 5. Process implementation; 6. Measurement, assessment and improvement; Appendix I: Transition to an integrated management system; Appendix II: Activities in the document control process; Appendix III: Activities in the procurement process; Appendix IV: Performance of independent assessments; Annex I: Electronic document management system; Annex II: Media for record storage; Annex III: Record retention and storage; Glossary.

Annual activity report of Ignalina NPP Safety Analysis Group for 1995 year

International Nuclear Information System (INIS)

Ushpuras, E.; Augutis, J.; Bubelis, E.

1995-01-01

The main results of Ignalina NPP Safety Analysis Group (ISAG) investigations for 1995 are presented. ISAG is concentrating its research activities into four areas: the neutrons dynamics modelling, simulation of transient processes during loss of coolant accident, the reactor cooling systems modelling and the probabilistic safety assessment of accident confinement system. 18 refs., 9 tabs., 110 figs

The social context moderates the relationships between neighborhood safety and adolescents’ physical activities

Science.gov (United States)

Background. Previous studies of neighborhood safety and physical (in)activity have typically neglected to consider the youth’s peer context as a modifier of these relationships. Objective. Test the independent and interactive effects of perceived neighborhood safety and time spent with friends and p...

Change in neighborhood traffic safety: does it matter in terms of physical activity?

NARCIS (Netherlands)

Jongeneel-Grimen, Birthe; Busschers, Wim; Droomers, Mariël; van Oers, Hans A. M.; Stronks, Karien; Kunst, Anton E.

2013-01-01

There is limited evidence on the causality of previously observed associations between neighborhood traffic safety and physical activity (PA). This study aims to contribute to this evidence by assessing the extent to which changes over time in neighborhood traffic safety were associated with PA.

Evaluating the effectiveness of active vehicle safety systems.

Science.gov (United States)

Jeong, Eunbi; Oh, Cheol

2017-03-01

Advanced vehicle safety systems have been widely introduced in transportation systems and are expected to enhance traffic safety. However, these technologies mainly focus on assisting individual vehicles that are equipped with them, and less effort has been made to identify the effect of vehicular technologies on the traffic stream. This study proposed a methodology to assess the effectiveness of active vehicle safety systems (AVSSs), which represent a promising technology to prevent traffic crashes and mitigate injury severity. The proposed AVSS consists of longitudinal and lateral vehicle control systems, which corresponds to the Level 2 vehicle automation presented by the National Highway Safety Administration (NHTSA). The effectiveness evaluation for the proposed technology was conducted in terms of crash potential reduction and congestion mitigation. A microscopic traffic simulator, VISSIM, was used to simulate freeway traffic stream and collect vehicle-maneuvering data. In addition, an external application program interface, VISSIM's COM-interface, was used to implement the AVSS. A surrogate safety assessment model (SSAM) was used to derive indirect safety measures to evaluate the effectiveness of the AVSS. A 16.7-km freeway stretch between the Nakdong and Seonsan interchanges on Korean freeway 45 was selected for the simulation experiments to evaluate the effectiveness of AVSS. A total of five simulation runs for each evaluation scenario were conducted. For the non-incident conditions, the rear-end and lane-change conflicts were reduced by 78.8% and 17.3%, respectively, under the level of service (LOS) D traffic conditions. In addition, the average delay was reduced by 55.5%. However, the system's effectiveness was weakened in the LOS A-C categories. Under incident traffic conditions, the number of rear-end conflicts was reduced by approximately 9.7%. Vehicle delays were reduced by approximately 43.9% with 100% of market penetration rate (MPR). These results

Recent and current activities of the OECD/NEA Working Group on Fuel Safety (NEA/CSNI). Recent and Current Activities of the Working Group on Fuel Safety (NEA/CSNI)

International Nuclear Information System (INIS)

Petit, Marc

2013-01-01

The Working Group on Fuel Safety (WGFS) is part of the Committee on the Safety of Nuclear Installations (CSNI) of the Nuclear Energy Agency and has the main mission of advancing the current understanding and addressing fuel safety issues. Recent and current activities of the working group have addressed mainly the loss of coolant accident (LOCA), the reactivity initiated accident (RIA), the fuel safety criteria and leaking fuel issues, as well as Fukushima-related fuel topics. In the area of LOCA, the group issued different documents, the most notable being a very comprehensive state of the art report [NEA/CSNI/R (2009)15]. Regarding RIA, some documents were finalised and issued in the recent years, as well as a state of the art report [NEA/CSNI/R (2010)1]. The question of leaking fuel and how it is handled in the reactors is an activity that is just starting. Of particular interest to people developing new fuel concepts is the Nuclear Fuel Safety Criteria Technical Review - Second Edition [NEA/CSNI/R (2012)3]. This document provides a broad overview of the numerous criteria used in the NEA member countries to demonstrate to safe use of fuel in light water reactors. The WGFS has started discussions about fuel related issues raised by the Fukushima accident, in particular, hydrogen production. New concepts have been proposed to solve these issues but it appears that these concepts will need to go through a long qualification process to assess their adequacy for the different situations considered in the evaluation of fuel safety, from normal operation to accident conditions

78 FR 50079 - Information Collection Activities: Safety and Environmental Management Systems (SEMS); Proposed...

Science.gov (United States)

2013-08-16

... DEPARTMENT OF THE INTERIOR Bureau of Safety and Environmental Enforcement [Docket ID BSEE-2013-0005; OMB Control Number 1014-0017: 134E1700D2 EEEE500000 ET1SF0000.DAQ000] Information Collection Activities: Safety and Environmental Management Systems (SEMS); Proposed Collection; Comment Request...

Linking Safety Analysis to Safety Requirements

DEFF Research Database (Denmark)

Hansen, Kirsten Mark

Software for safety critical systems must deal with the hazards identified by safety analysistechniques: Fault trees, event trees,and cause consequence diagrams can be interpreted as safety requirements and used in the design activity. We propose that the safety analysis and the system design use...

Implementation of the safety culture for HANARO Safety Management

International Nuclear Information System (INIS)

Wu, Jongsup; Han, Geeyang; Kim, Iksoo

2008-01-01

Safety is the fundamental principal upon which the management system is based. The IAEA INSAG(International Nuclear Safety Group) states the general aims of the safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams so as to allow them to carry out their tasks safety. The safety culture activities have been implemented and the importance of safety management in nuclear activities for a reactor application and utilization has also been emphasized more than 10 years in HANARO which is a 30 MW multi-purpose research reactor and achieved its first criticality in February 1995. The safety culture activities and implementations have been conducted continuously to enhance its safe operation like the seminars and lectures related to safety matters, participation in international workshops, the development of safety culture indicators, the survey on the attitude of safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of an e-Learning program for safety education. (author)

Source-book of International Activities Related to the Development of Safety Cases for Deep Geological Repositories

International Nuclear Information System (INIS)

2017-01-01

All national radioactive waste management authorities recognise today that a robust safety case is essential in developing disposal facilities for radioactive waste. To improve the robustness of the safety case for the development of a deep geological repository, a wide variety of activities have been carried out by national programs and international organisations over the past years. The Nuclear Energy Agency, since first introducing the modern concept of the 'safety case', has continued to monitor major developments in safety case activities at the international level. This Source-book summarises the activities being undertaken by the Nuclear Energy Agency, the European Commission and the International Atomic Energy Agency concerning the safety case for the operational and post-closure phases of geological repositories for radioactive waste that ranges from low-level to high-level waste and for spent fuel. In doing so, it highlights important differences in focus among the three organisations

48 CFR 970.2303-3 - Contract clauses.

Science.gov (United States)

2010-10-01

... facility, the clause at 48 CFR 970.5223-1, Integration of Environment, Safety and Health into Work Planning..., Renewable Energy Technologies, Occupational Safety and Drug-Free Work Place 970.2303-3 Contract clauses. (a) When work under management and operating contracts and subcontracts thereunder is to be performed at a...

High Volume Manufacturing of Silicon-Film Solar Cells and Modules; Final Subcontract Report, 26 February 2003 - 30 September 2003

Energy Technology Data Exchange (ETDEWEB)

Rand, J. A.; Culik, J. S.

2005-10-01

The objective of the PV Manufacturing R&D subcontract was to continue to improve AstroPower's technology for manufacturing Silicon-Film* wafers, solar cells, and modules to reduce costs, and increase production yield, throughput, and capacity. As part of the effort, new technology such as the continuous back metallization screen-printing system and the laser scribing system were developed and implemented. Existing processes, such as the silicon nitride antireflection coating system and the fire-through process were optimized. Improvements were made to the statistical process control (SPC) systems of the major manufacturing processes: feedstock preparation, wafer growth, surface etch, diffusion, and the antireflection coating process. These process improvements and improved process control have led to an increase of 5% relative power, and nearly 15% relative improvement in mechanical and visual yield.

Implementation of the safety culture for HANARO safety management

Energy Technology Data Exchange (ETDEWEB)

Wu, Jongsup; Han, Geeyang; Kim, Iksoo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2008-11-15

Safety is the fundamental principal upon which a management system is based. The IAEA INSAG (International Nuclear Safety Group) states the general aims of a safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams, so as to allow them to carry out their tasks safely. The safety culture activities have been implemented and the importance of a safety management in nuclear activities for a reactor application and utilization has also been emphasized for more than 10 years in HANARO which is a 30MW multi-purpose research reactor that achieved its first criticality in February 1995. The safety culture activities and implementations have been conducted continuously to enhance its safe operation such as the seminars and lectures related to safety matters, participation in international workshops and the development of safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of a e-learning program for a safety education purpose.

Implementation of the safety culture for HANARO safety management

International Nuclear Information System (INIS)

Wu, Jongsup; Han, Geeyang; Kim, Iksoo

2008-01-01

Safety is the fundamental principal upon which a management system is based. The IAEA INSAG (International Nuclear Safety Group) states the general aims of a safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams, so as to allow them to carry out their tasks safely. The safety culture activities have been implemented and the importance of a safety management in nuclear activities for a reactor application and utilization has also been emphasized for more than 10 years in HANARO which is a 30MW multi-purpose research reactor that achieved its first criticality in February 1995. The safety culture activities and implementations have been conducted continuously to enhance its safe operation such as the seminars and lectures related to safety matters, participation in international workshops and the development of safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of a e-learning program for a safety education purpose

Fundamental safety principles. Safety fundamentals

International Nuclear Information System (INIS)

2007-01-01

This publication states the fundamental safety objective and ten associated safety principles, and briefly describes their intent and purpose. The fundamental safety objective - to protect people and the environment from harmful effects of ionizing radiation - applies to all circumstances that give rise to radiation risks. The safety principles are applicable, as relevant, throughout the entire lifetime of all facilities and activities - existing and new - utilized for peaceful purposes, and to protective actions to reduce existing radiation risks. They provide the basis for requirements and measures for the protection of people and the environment against radiation risks and for the safety of facilities and activities that give rise to radiation risks, including, in particular, nuclear installations and uses of radiation and radioactive sources, the transport of radioactive material and the management of radioactive waste

Fundamental safety principles. Safety fundamentals

International Nuclear Information System (INIS)

2006-01-01

This publication states the fundamental safety objective and ten associated safety principles, and briefly describes their intent and purpose. The fundamental safety objective - to protect people and the environment from harmful effects of ionizing radiation - applies to all circumstances that give rise to radiation risks. The safety principles are applicable, as relevant, throughout the entire lifetime of all facilities and activities - existing and new - utilized for peaceful purposes, and to protective actions to reduce existing radiation risks. They provide the basis for requirements and measures for the protection of people and the environment against radiation risks and for the safety of facilities and activities that give rise to radiation risks, including, in particular, nuclear installations and uses of radiation and radioactive sources, the transport of radioactive material and the management of radioactive waste

77 FR 22387 - Pipeline Safety: Information Collection Activities, Revision to Gas Transmission and Gathering...

Science.gov (United States)

2012-04-13

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2012-0024] Pipeline Safety: Information Collection Activities, Revision to Gas Transmission and Gathering Pipeline Systems Annual Report, Gas Transmission and Gathering Pipeline Systems Incident Report...

77 FR 58616 - Pipeline Safety: Information Collection Activities, Revision to Gas Transmission and Gathering...

Science.gov (United States)

2012-09-21

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2012-0024] Pipeline Safety: Information Collection Activities, Revision to Gas Transmission and Gathering Pipeline Systems Annual Report, Gas Transmission and Gathering Pipeline Systems Incident Report...

25 Years of Community Activities towards Harmonization of Nuclear Safety Criteria and Requirements - Achievements and Prospects

International Nuclear Information System (INIS)

Lillington, J.N.; Turland, B.D.; Haste, T.J.; Seiler, J.M.; Carretero, A.; Perez, T.; Geutges, A.; Van Hienen, J.F.A.; Jehee, J.N.T.; Sehgal, B.R.; Mattila, L.; Holmstrom, H.; Karwat, H.; Maroti, L.; Toth, I.; Husarcek, J.

2001-10-01

The main objective was to advise the EC on future challenges and opportunities in terms of enhanced co-operation in the area of nuclear safety and harmonization of safety requirements and practices in an enlarged European Union. The activities were divided into 3 sub-tasks as follows: part A, to prepare an analysis, synthesis and assessment of the main achievements from Community activities related to the Resolutions on the technological problems of nuclear safety of 1975 and 1992, with due consideration for related research activities; part B, to prepare an overview of safety philosophies and practices in EU Member States, taking account of their specific national practices in terms of legal framework, type and age of operating nuclear reactors; part C, to provide elements of a strategy for future activities in the frame of the Council Resolutions, with particular attention to the context of enlargement of the EU. (author)

Implementation of the safety culture for HANARO safety management

Energy Technology Data Exchange (ETDEWEB)

Wu, Jong Sup; Han, Gee Yang; Kim, Ik Soo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2008-11-15

Safety is the fundamental principal upon which a management system is based. The IAEA INSAG(International Nuclear Safety Group) states the general aims of a safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams, so as to allow them to carry out their tasks safety. The safety culture activities have been implemented and the importance of a safety management in nuclear activities for a reactor application and utilization has also been emphasized for more than 10 years in HANARO which is a 30 MW multi purpose research reactor that achieved its first criticality in February 1995. The safety culture activities and implementation have been conducted continuously to enhance its safe operation such as the seminars and lectures related to safety matters, participation in international workshops and the development of safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of an e Learning program for a safety education purpose.

Implementation of the safety culture for HANARO safety management

International Nuclear Information System (INIS)

Wu, Jong Sup; Han, Gee Yang; Kim, Ik Soo

2008-01-01

Safety is the fundamental principal upon which a management system is based. The IAEA INSAG(International Nuclear Safety Group) states the general aims of a safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams, so as to allow them to carry out their tasks safety. The safety culture activities have been implemented and the importance of a safety management in nuclear activities for a reactor application and utilization has also been emphasized for more than 10 years in HANARO which is a 30 MW multi purpose research reactor that achieved its first criticality in February 1995. The safety culture activities and implementation have been conducted continuously to enhance its safe operation such as the seminars and lectures related to safety matters, participation in international workshops and the development of safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of an e Learning program for a safety education purpose

Regulatory activities in reactor safety

International Nuclear Information System (INIS)

Salvatore, J.E.L.

1987-01-01

The safety phylosophy in designs and operation of nuclear power plants and, the steps for evaluating the safety and quality assurance, in the licensing procedure are described. The CNEN organization structure and the licensing procedure for nuclear power plants in Brazil are presented. (M.C.K.) [pt

Instructional games and activities for criticality safety training

International Nuclear Information System (INIS)

Bullard, B.; McBride, J.

1993-01-01

During the past several years, the Training and Management Systems Division (TMSD) staff of Oak Ridge Institute for Science and Education (ORISE) has designed and developed nuclear criticality safety (NCS) training programs that focus on high trainee involvement through the use of instructional games and activities. This paper discusses the instructional game, initial considerations for developing games, advantages and limitations of games, and how games may be used in developing and implementing NCS training. It also provides examples of the various instructional games and activities used in separate courses designed for Martin Marietta Energy Systems (MMES's) supervisors and U.S. Nuclear Regulatory Commission (NRC) fuel facility inspectors

Spesialisasi Kegiatan Produksi dan Kemitraan Subkontrak pada Klaster Batik Kota Pekalongan

Directory of Open Access Journals (Sweden)

Aulia Dwi Zulhida

2016-08-01

Full Text Available Pekalongan City is known as the batik city. Thus it has the city branding as "Pekalongan World's City of Batik." This branding is a result of people’s daily activity related to batik. Pekalongan has 860 batik industries in 2013 and have the specialization in the production activities and subcontracting partnerships. Most of the batik industries do not do the production process entirely by themselves, but by joining to the other industries with a particular specialization. This study aims to determine the specialization of production activities and subcontracting partnership in Pekalongan batik cluster. The results of this study show that there is a majority of ‘batik cap’ industries that is equal to 82% of the total industries in Pekalongan. The specializations consist of making the batik, convection, and making of the canting. These specializations are geographically grouped into a center due to the endowment factors such as labors, land, and infrastructures. Specialization of production activities also leads to partnership subcontracting in the batik cluster, which is known by a factor of specialty subcontracting. The subcontracting partnership gives negative and positive impacts, such as the reliance between the subcontractor and the principal, efficiency of production factors, and cost efficiency.

Perceived neighborhood safety related to physical activity but not recreational screen-based sedentary behavior in adolescents.

Science.gov (United States)

Lenhart, Clare M; Wiemken, Andrew; Hanlon, Alexandra; Perkett, Mackenzie; Patterson, Freda

2017-09-18

A growing proportion of adolescents have poor cardiovascular health behaviors, including low levels of physical activity and high levels of sedentary behavior, thus increasing the likelihood of poor heart health in later years. This study tested the hypothesis that low perceived neighborhood safety would be associated with low levels of physical activity and high levels of recreational sedentary behavior in high-school students. Using cross-sectional, weighted data from the 2015 Pennsylvania (USA) State and Philadelphia city Youth Risk Behavior Survey, multivariable logistic regression modeling was used to examine the association between perceived neighborhood safety, and physical activity levels and recreational screen-based sedentary behavior time respectively, while controlling for potential confounders. After adjustment for other significant correlates of physical activity, students with low perceived neighborhood safety had a 21% reduced odds of being physically active on 5 or more days of the last week as compared to those who felt safe (p = 0.044). Perceived safety was not related to sedentary behavior; but sports team participation emerged as a strong correlate of low screen-based sedentary behavior (OR = 0.73, p = .002). These data add to a growing body of work demonstrating the importance of perceived safety with physical activity levels in youth. Sports team participation may be a viable target to reduce screen-based sedentary time.

Perceived neighborhood safety related to physical activity but not recreational screen-based sedentary behavior in adolescents

Directory of Open Access Journals (Sweden)

Clare M. Lenhart

2017-09-01

Full Text Available Abstract Background A growing proportion of adolescents have poor cardiovascular health behaviors, including low levels of physical activity and high levels of sedentary behavior, thus increasing the likelihood of poor heart health in later years. This study tested the hypothesis that low perceived neighborhood safety would be associated with low levels of physical activity and high levels of recreational sedentary behavior in high-school students. Methods Using cross-sectional, weighted data from the 2015 Pennsylvania (USA State and Philadelphia city Youth Risk Behavior Survey, multivariable logistic regression modeling was used to examine the association between perceived neighborhood safety, and physical activity levels and recreational screen-based sedentary behavior time respectively, while controlling for potential confounders. Results After adjustment for other significant correlates of physical activity, students with low perceived neighborhood safety had a 21% reduced odds of being physically active on 5 or more days of the last week as compared to those who felt safe (p = 0.044. Perceived safety was not related to sedentary behavior; but sports team participation emerged as a strong correlate of low screen-based sedentary behavior (OR = 0.73, p = .002. Conclusion These data add to a growing body of work demonstrating the importance of perceived safety with physical activity levels in youth. Sports team participation may be a viable target to reduce screen-based sedentary time.

75 FR 4904 - Railroad Safety Advisory Committee (RSAC); Working Group Activity Update

Science.gov (United States)

2010-01-29

... amend regulations protecting persons who work on, under, or between rolling equipment; and persons...-7257] Railroad Safety Advisory Committee (RSAC); Working Group Activity Update AGENCY: Federal Railroad... Committee (RSAC) Working Group Activities. SUMMARY: The FRA is updating its announcement of RSAC's Working...

Active and intelligent packaging: The indication of quality and safety.

Science.gov (United States)

Janjarasskul, Theeranun; Suppakul, Panuwat

2018-03-24

The food industry has been under growing pressure to feed an exponentially increasing world population and challenged to meet rigorous food safety law and regulation. The plethora of media consumption has provoked consumer demand for safe, sustainable, organic, and wholesome products with "clean" labels. The application of active and intelligent packaging has been commercially adopted by food and pharmaceutical industries as a solution for the future for extending shelf life and simplifying production processes; facilitating complex distribution logistics; reducing, if not eliminating the need for preservatives in food formulations; enabling restricted food packaging applications; providing convenience, improving quality, variety and marketing features; as well as providing essential information to ensure consumer safety. This chapter reviews innovations of active and intelligent packaging which advance packaging technology through both scavenging and releasing systems for shelf life extension, and through diagnostic and identification systems for communicating quality, tracking and brand protection.

Considering lessons learned about safety culture and their reflection to activity. After Fukushima Daiichi Nuclear Power Plant accident experience

International Nuclear Information System (INIS)

Obu, Etsuji; Hamada, Jun; Fukano, Takuya

2011-01-01

Fukushima Daiichi Nuclear Power Plant accident forced neighboring residents to evacuate for a long time and gave Public anxieties greatly and significant effects to social activities in Japan. Public trust of nuclear power was lost by not preventing the accident and future of nuclear power became reconsidered, which nuclear industry people regretted deeply. Japan Nuclear Technology Institute (JANTI) had conducted activities enhancing safety culture in nuclear industry. It would be necessary to consider improvements of accident prevention and mitigation measures after evaluating the accident in a viewpoint of 'safety culture'. Based on published information and knowledge accumulated by activities of JANTI, the accident was examined taking account of greatness of nuclear accident and its effects from the side of safety culture. Lessons learned about safety culture were pointed out as; (1) reconfirmation of specialty of nuclear technology. (2) reinforcement of questioning and learning attitudes and (3) improvement of evaluation capability of nuclear safety and safety assurance against external event. These were reflected in activities such as; (1) reconsideration of safety culture assessment, (2) strengthening further support to improve safety culture consciousness and (3) improvement of peer review activity. (T. Tanaka)

Annual activity report of Ignalina NPP Safety Analysis Group for the year 1997

International Nuclear Information System (INIS)

Ushpuras, E.; Augutis, J.; Bubelis, E.; Kaliatka, A

1998-01-01

The main results of Ignalina NPP Safety Analysis Group (ISAG) investigations for the year 1997 are presented. ISAG is concentrating its research activities into four areas: the neutrons dynamics modelling, simulation of transient processes during loss of coolant accident, the reactor cooling systems modelling and the probabilistic safety assessment of accident confinement system

Kozloduy nuclear power plant. Units 1-4. Status of safety assessment activities. Rev. 2

International Nuclear Information System (INIS)

1999-01-01

This paper presents the results of the status of safety assessment activities carried out by the Kozloduy Nuclear Power Plant (KNPP) in order to evaluate the current status of the safety of its reactor units 1-4. The steam supply system of this units is based of the reactor WWER-440/ B-230, which is a PWR of Russian design developed according to the safety standards in force in USSR in late 60-s. Now a days 10 reactor units of this type are in operation in four NPPs. Despite of efforts of the different plants to implement safety improvements measures during first 10-15 years of operation of this type of reactor its major safety problems were not eliminated and were a subject of international concern. The systematic evaluation of the deficiencies of the original design of this type of reactors have been initiated by IAEA in the beginning of 1990 and brought to developing a comprehensive list of safety problems which required urgent implementation of safety measures in all plants. To solve this problems in 1991 KNPP initiated implementation of so called 'short term' safety improvement program, developed with the help of WANO under agreement with Bulgarian Nuclear Safety Authority (BNSA) and consortium RISKAUDIT. The program was based on a stage approach and was foreseen to be implemented by tree stages in very tight time schedule in order to achieve significant and rapid improvements of the level of safety in operation of the units. The Short Tenn Program was implemented between the years 1991 and 1997 thanks of the strong safety commitment of NEK and KNPP staff and the broad international cooperation and financial support. Important part of resources were supplied under PHARE program of CEC, EBRD grant agreement and EDF support. The plant current safety level analysis has been performed using IAEA analytical methodology according to 50-SG-O12 standard 'Periodic safety review of operational nuclear power plants'. The approach and criteria for acceptable safety level

IAEA activities in preparation of reglamentary documents on nuclear power plant safety

International Nuclear Information System (INIS)

Konstantinov, L.V.

1976-01-01

The activities of the IAEA in the field of working out practical rules and recommendations ensuring the nuclear power plant safety are discussed. The practical rules will establish the aims and the minimum of requirements, that must be carried out to ensure the necessary safety of systems, components and equipment of the nuclear power plant throughout the whole period of its exploitation. Described is the procedure of the document preparation, consisting of the collection of documents, edited in different countries, the integration of documents by the IAEA Secretariat, the consideratiom of documents by the Group of senior advisers, the preparation of the draft document, the additional wort at the document in accordaqce with the remarks of the IAEA member-countries, the edition and dissemination of documents. The necessity for the active participation of the CMEA member-countries in the development and discussion of documents concerning the nuclear power plant safety is stated [ru

Management services

International Nuclear Information System (INIS)

Adkins, S.K.; Alford, D.R.; Barnette, A.B.

1979-01-01

The Management Services Section provides coordinated professional administrative services to the Fusion Energy Division (FED), allowing the work of technical professionals to be more fully concentrated in their areas of specialty. Services are provided in general administration, personnel, financial management, communications (including text and graphics generation), management information, library, safety, quality assurance, and nonprogrammatic engineering services. Highlights of the past year included adoption of the Procurement Module in the FED Management Information System (MIS) for use by the entire Laboratory, completion of the Personnel Module of the MIS, greatly increased personnel recruiting activity, and increased industrial subcontracting activity

[Fundamental role of the workers' representative in preventive safety activity].

Science.gov (United States)

Ossicini, A; Bindi, L; Casale, M C

2003-01-01

With the arrival of Legislative Decree 626/94 which brought into Italian law the EU directives on workers' health and safety at the workplace, our country has also introduced rules that make a break with the past in this area, with the creation of new professional roles. The workers' safety representative takes on a fundamentally important role in the management of prevention, safety and health for workers in their place of employment in accordance with article 19. In fact, before the introduction of this Legislative Decree, the "protection" of workers' health was essentially based on rules and regulations the application of which was left to the exclusive and direct responsibility of the relationship between the employer and doctor, leaving out any participation by the worker. Whereas in the past workers could only be considered the final receivers of instructions about the security measures to apply, with Law 626 the workers themselves became active participants in the assessment of risks at work and consequently in the implementing of all the safety and hygiene measures contributing to the reduction of risk levels. The new regulations now in force assign important tasks to the workers' safety representative; all tasks and responsibilities associated with that role are examined and discussed, especially those relating to rights to information and training, consultation and participation in the process of designing and promoting safety measures. The job of workers' representative today takes on a fundamentally important meaning and role in a self-regulating system of work safety, where he or she has a proper area responsibility, so becoming a reference point for the workers generally.

Incentive issues in the South African construction industry ...

African Journals Online (AJOL)

2003: 728; Beer et al., 2004: 42). The common types of ... technical/performance, and safety (Bower et al., 2002: 33; Bubshait,. 2003: 67; Lahdenpera .... contractors, poor management, poor attitudes within subcontracting organisations, and ...

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

A semi annual report on the activities in safety administration division. Report of the second half of 2004

International Nuclear Information System (INIS)

Yamamoto, Junta

2005-07-01

The activities of Safety Administration Division covers many fields in Tokai-Works such as the management of a safety and health, the crisis management and the security, and the management of a quality assurance. This report is summary of the activities of Safety Administration Division in October, 2004 to March, 2005. (author)

In vitro Activity and Safety Assessment of New Synthesized Thiazolo ...

African Journals Online (AJOL)

Purpose: To synthesis a series of novel thiazolo pyrimidine derivatives and evaluate them in vitro for their safety and anthelmintic activity against E. multilocularis metacestodes using BALB/c mice. Methods: A new series of substituted amino thiazole, hydrazinothiazole and thiazolo pyrimidine derivatives (2-6) were ...

Role of in-house safety analysis and research activities in regulatory decision making

International Nuclear Information System (INIS)

Pradhan, Santosh K.; Nagrale, Dhanesh B.; Gaikwad, Avinash J.

2015-01-01

Achievement of an acceptable level of nuclear safety is an essential requirement for the peaceful utilization of nuclear energy. The success of Global Nuclear Safety Regime is built upon a foundation of research. Such research has been sponsored by Governments and industry and has led to improved designs, safer and more reliable plant operation, and improvements in operating plant efficiency. A key element of this research has been the nuclear safety research performed or sponsored by regulatory organizations. In part, it has been the safety research performed or sponsored by regulatory organizations that has contributed to improved safety and has laid the foundation for activities such as risk-informed regulation, plant life extension, improved plant performance (e.g. power uprates) and new plant designs. The regulatory research program is meant to improve the regulatory authority’s knowledge where uncertainty exists, where safety margins are not well-characterized, and where regulatory decisions need to be confirmed in existing or new designs and technologies. The regulatory body get research initiated either in-house or by the licensee or through technical support organizations (TSOs). Research and analysis carried out within the regulatory body is of immense value in this context. This could be in the form of analysis of safety significant events, analysis of severe accidents, review of operating experience, independent checks of critical designs and even review of operator responses under different situations towards arriving at modifications to training programmes and licensing procedures for operating personnel. A latent benefit of regulatory research carried out by the regulators themselves is that it improves their technical competence considerably which in turn leads to high quality safety reviews and improved regulation in general. The aim of the present paper is to provide an overview of role of regulatory research and the in-house regulatory safety

Mesoscale Modeling of Kinetic Phase Behaviors in Mg-B-H (Subcontract Report)

Energy Technology Data Exchange (ETDEWEB)

Yu, H. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Thornton, K. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Wood, B. C. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2017-10-13

Storage of hydrogen on board vehicles is one of the critical enabling technologies for creating hydrogenfueled transportation systems that can reduce oil dependency and mitigate the long-term effects of fossil fuels on climate change. Stakeholders in developing hydrogen infrastructure are currently focused on highpressure storage at 350 bar and 700 bar, in part because no viable solid-phase storage material has emerged. Nevertheless, solid-state materials, including high-density hydrides, remain of interest because of their unique potential to meet all DOE targets and deliver hydrogen at lower pressures and higher on-board densities. A successful solution would significantly reduce costs and ensure the economic viability of a U.S. hydrogen infrastructure. The Mg(BH₄)₂-MgB₂ system represents a highly promising solution because of its reasonable reaction enthalpy, high intrinsic capacity, and demonstrated reversibility, yet suffers from poor reaction kinetics. This subcontract aims to deliver a phase-field model for the kinetics of the evolution of the relevant phases within the Mg-B-H system during hydrogenation and dehydrogenation. This model will be used within a broader theory, synthesis, and characterization framework to study the properties of geometry-selected nanoparticles of pristine and doped MgB₂/Mg(BH₄)₂ with two aims: (1) understand the intrinsic limitations in (de)hydrogenation; (2) devise strategies for improving thermodynamics and kinetics through nanostructuring.

NREL Photovoltaic Program FY 1995 annual report

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-06-01

This report summarizes the in-house and subcontracted R&D activities from Oct. 1994 through Sept. 1995; their objectives are to conduct basic, applied, and engineering research, manage subcontracted R&D projects, perform research complementary to subcontracted work, develop and maintain state-of-the-art measurement and device capabilities, develop PV manufacturing technology and modules, transfer results to industry, and evolve viable partnerships for PV systems and market development. The research activities are grouped into 5 sections: crystalline Si and advanced devices, thin-film PV, PV manufacturing, PV module and system performance and engineering, and PV applications and market development.

Current Activities on Nuclear Safety Culture in Korea. How to meet the challenges for Safety and Safety Culture?

Energy Technology Data Exchange (ETDEWEB)

Oh, Chaewoon [International Policy Department Policy and Standard Division, Korea Institute of Nuclear Safety, 19 Gusung-Dong Yuseong-Ku, 305-338 DAEJEON (Korea, Republic of)

2008-07-01

'Statement of Nuclear Safety Policy' declared by the Korean Government elucidates adherence to the principle of 'priority to safety'. The 3. Comprehensive Nuclear Energy Promotion Plan (2007-2011) more specifically addressed the necessity to develop and apply 'safety culture evaluation criteria' and to strengthen safety management of concerned organizations in an autonomous way. Putting these policies as a backdrop, Korean Government has taken diverse safety culture initiatives and has encouraged the relevant organizations to develop safety culture practices of their own accord. Accordingly, KHNP, the operating organization in Korea, developed a 'safety culture performance indicator', which has been used to evaluate safety mind of employees and the evaluation results have been continuously reflected in operational management and training programs. Furthermore, KHNP inserted 'nuclear safety culture subject' into every course of more than two week length, and provided employees with special lectures on safety culture. KINS, the regulatory organization, developed indicators for the safety culture evaluation based on the IAEA Guidelines. Also, KINS has hosted an annual Nuclear Safety Technology Information Meeting to share information between regulatory organizations and industries. Furthermore, KINS provided a nuclear safety culture class to the new employees and they are given a chance to participate in performance of a role-reversal socio-drama. Additionally, KINS developed a safety culture training program, published training materials and conducted a 'Nuclear Safety Culture Basic Course' in October 2007, 4 times of which are planed this year. In conclusion, from Government to relevant organizations, 'nuclear safety culture' concept is embraced as important and has been put into practice on a variety of forms. Specifically, 'education and training' is a starting line and sharing

Evaluation of the safety culture in the regulatory activity in Camaguey province

International Nuclear Information System (INIS)

Naranjo Lopez, A.M.; Barreras Caballero, A.; Damera Martinez, A.

1999-01-01

Previous studied accomplished in the country have permitted to evaluate the activity of the regulatory body in nuclear safety matter in part of the national territory. These studies did not encompass the Camaguey province. In the work are shown the results of the study in this part of the territory, accomplished as of the survey elaborated by the National Nuclear Safety Center using guides it ASCOT and other documents of the IAEA

ITER safety

International Nuclear Information System (INIS)

Raeder, J.; Piet, S.; Buende, R.

1991-01-01

As part of the series of publications by the IAEA that summarize the results of the Conceptual Design Activities for the ITER project, this document describes the ITER safety analyses. It contains an assessment of normal operation effluents, accident scenarios, plasma chamber safety, tritium system safety, magnet system safety, external loss of coolant and coolant flow problems, and a waste management assessment, while it describes the implementation of the safety approach for ITER. The document ends with a list of major conclusions, a set of topical remarks on technical safety issues, and recommendations for the Engineering Design Activities, safety considerations for siting ITER, and recommendations with regard to the safety issues for the R and D for ITER. Refs, figs and tabs

Safety in numbers: does perceived safety mediate associations between the neighborhood social environment and physical activity among women living in disadvantaged neighborhoods?

Science.gov (United States)

Timperio, Anna; Veitch, Jenny; Carver, Alison

2015-05-01

The aim of this study is to examine associations between the neighborhood social environment and leisure-time physical activity (LTPA)(1) and walking among women, and whether these associations are mediated by perceived personal safety. Women (n = 3784) living in disadvantaged urban and rural neighborhoods within Victoria, Australia completed a self-administered survey on five social environment variables (neighborhood crime, neighborhood violence, seeing others walking and exercising in the neighborhood, social trust/cohesion), perceived personal safety, and their physical activity in 2007/8. Linear regression analyses examined associations between social environment variables and LTPA and walking. Potential mediating pathways were assessed using the product-of-coefficients test. Moderated mediation by urban/rural residence was examined. Each social environment variable was positively associated with engaging in at least 150 min/week of LTPA (OR = 1.16 to 1.56). Only two social environment variables, seeing others walking (OR = 1.45) and exercising (OR = 1.31), were associated with ≥ 150 min/week of walking. Perceived personal safety mediated all associations. Stronger mediation was found in urban areas for crime, violence and social trust/cohesion. The neighborhood social environment is an important influence on physical activity among women living in disadvantaged areas. Feelings of personal safety should not be included in composite or aggregate scores relating to the social environment. Copyright © 2015 Elsevier Inc. All rights reserved.

INPO Perspectives and Activities to Enhance Supplier Human Performance and Safety Culture

International Nuclear Information System (INIS)

Duncan, R. J.

2016-01-01

Within their own organizations, utilities have made significant improvements in human performance and safety culture, supported by a strong community of practice through INPO and WANO. In recent years, utilities have been making increasing use of suppliers for design, construction, inspection and maintenance services in support of their NPPs. Many of these suppliers do not have the benefit of being members of a community of practice when it comes to human performance and safety culture. To help the supplier community make improvements similar to what the utilities have achieved, INPO has recently expanded its Supplier Participant program to address the issue of human performance and safety culture in the supplier community. The intent of this paper will be to share the INPO’s perspectives and activities in helping suppliers of services and products to NPPs enhance their human performance and safety culture. (author)

Key regulatory and safety issues emerging NEA activities. Lessons Learned from Fukushima Dai-ichi NPS Accident - Key Regulatory and Safety Issues

International Nuclear Information System (INIS)

Nakoski, John

2013-01-01

A presentation was provided on the key safety and regulatory issues and an update of activities undertaken by the NEA and its members in response to the accident at the Fukushima Daiichi nuclear power stations (NPS) on 11 March 2011. An overview of the accident sequence and the consequences was provided that identified the safety functions that were lost (electrical power, core cooling, and primary containment) that lead to units 1, 2, and 3 being in severe accident conditions with large off-site releases. Key areas identified for which activities of the NEA and member countries are in progress include accident management; defence-in-depth; crisis communication; initiating events; operating experience; deterministic and probabilistic assessments; regulatory infrastructure; radiological protection and public health; and decontamination and recovery. For each of these areas, a brief description of the on-going and planned NEA activities was provided within the three standing technical committees of the NEA with safety and regulatory mandates (the Committee on Nuclear Regulatory Activities - CNRA, the Committee on the Safety of Nuclear Installations - CSNI, and the Committee on Radiation Protection and Public Health - CRPPH). On-going activities of CNRA include a review of enhancement being made to the regulatory aspects for the oversight of on-site accident management strategies and processes in light of the lessons learned from the accident; providing guidance to regulators on crisis communication; and supporting the peer review of the safety assessments of risk-significant research reactor facilities in light of the accident. Within the scope of the CSNI mandate, activities are being undertaken to better understand accident progression; characteristics of new fuel designs; and a benchmarking study of fast-running software for estimating source term under severe accident conditions to support protective measure recommendations. CSNI also has ongoing work in human

Maintenance, a global approach

International Nuclear Information System (INIS)

Calmejane, P.

2001-01-01

Maintenance is an important economic activity, it can represent up to 40% of operating costs in some fabrication units. The opening of energy markets to competition has led main operators to center their activities on their basis business and to sub-contract subsidiary activities. Subcontracting with strong engagements from the sub-contractor about results, time allowed and costs is now currently applied in nuclear industry. (A.C.)

75 FR 25282 - Office of the Director, Office of Biotechnology Activities; Notice of a Safety Symposium

Science.gov (United States)

2010-05-07

..., Office of Biotechnology Activities; Notice of a Safety Symposium There will be a safety symposium...: Challenges in Clinical Trial Design with Novel Receptors'' on June 15, 2010 at the Rockville Hotel and... that can maximize both anti-tumor effect and safety. An agenda will be posted to OBA's Web site closer...

Safety of evolutionary and innovative nuclear reactors: IAEA activities and world efforts

International Nuclear Information System (INIS)

Saito, T.; Gasparini, M.

2004-01-01

'Defence in Depth' approach constitutes the basis of the IAEA safety standards for nuclear power plants. Lessons learned from the current generation of reactors suggest that, for the next generation of reactor designs, the Defence in Depth philosophy should be retained, and that its implementation should be guided by the probabilistic insights. Recent developments in the area of general safety requirements based on Defence in Depth approach are examined and summarized. Global efforts to harmonize safety requirements for evolutionary nuclear power plants have involved many countries and organizations such as IAEA, US EPRI and European Utility EUR Organization. In recent years, developments of innovative nuclear power plants are also being discussed. The IAEA is currently developing a safety approach specifically for innovative nuclear reactors. This approach will eventually lead to a proposal of safety requirements for innovative reactors. Such activities related to safety requirements of evolutionary and innovative reactors are introduced. Various evolutionary and innovative reactor designs are reported in the world. The safety design features of evolutionary large LWRs, innovative LWRs, Modular High Temperature Gas Reactors and Small Liquid Metal Cooled LMRs are also introduced. Enhanced safety features proposed in such reactors are discussed and summarized according to the levels of Defence in Depth. For future nuclear plants, international cooperation and harmonization, especially in the area of safety, appear to be inevitable. Based on the past experience with many member states, the IAEA believes itself to be the uniquely positioned international organization to play this key role. (authors)

Safety Justification and Safety Case for Safety-critical Software in Digital Reactor Protection System

International Nuclear Information System (INIS)

Kwon, Kee-Choon; Lee, Jang-Soo; Jee, Eunkyoung

2016-01-01

Nuclear safety-critical software is under strict regulatory requirements and these regulatory requirements are essential for ensuring the safety of nuclear power plants. The verification & validation (V and V) and hazard analysis of the safety-critical software are required to follow regulatory requirements through the entire software life cycle. In order to obtain a license from the regulatory body through the development and validation of safety-critical software, it is essential to meet the standards which are required by the regulatory body throughout the software development process. Generally, large amounts of documents, which demonstrate safety justification including standard compliance, V and V, hazard analysis, and vulnerability assessment activities, are submitted to the regulatory body during the licensing process. It is not easy to accurately read and evaluate the whole documentation for the development activities, implementation technology, and validation activities. The safety case methodology has been kwon a promising approach to evaluate the level and depth of the development and validation results. A safety case is a structured argument, supported by a body of evidence that provides a compelling, comprehensible, and valid case that a system is safe for a given application in a given operating environment. It is suggested to evaluate the level and depth of the results of development and validation by applying safety case methodology to achieve software safety demonstration. A lot of documents provided as evidence are connected to claim that corresponds to the topic for safety demonstration. We demonstrated a case study in which more systematic safety demonstration for the target system software is performed via safety case construction than simply listing the documents

Safety Justification and Safety Case for Safety-critical Software in Digital Reactor Protection System

Energy Technology Data Exchange (ETDEWEB)

Kwon, Kee-Choon; Lee, Jang-Soo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Jee, Eunkyoung [KAIST, Daejeon (Korea, Republic of)

2016-10-15

Nuclear safety-critical software is under strict regulatory requirements and these regulatory requirements are essential for ensuring the safety of nuclear power plants. The verification & validation (V and V) and hazard analysis of the safety-critical software are required to follow regulatory requirements through the entire software life cycle. In order to obtain a license from the regulatory body through the development and validation of safety-critical software, it is essential to meet the standards which are required by the regulatory body throughout the software development process. Generally, large amounts of documents, which demonstrate safety justification including standard compliance, V and V, hazard analysis, and vulnerability assessment activities, are submitted to the regulatory body during the licensing process. It is not easy to accurately read and evaluate the whole documentation for the development activities, implementation technology, and validation activities. The safety case methodology has been kwon a promising approach to evaluate the level and depth of the development and validation results. A safety case is a structured argument, supported by a body of evidence that provides a compelling, comprehensible, and valid case that a system is safe for a given application in a given operating environment. It is suggested to evaluate the level and depth of the results of development and validation by applying safety case methodology to achieve software safety demonstration. A lot of documents provided as evidence are connected to claim that corresponds to the topic for safety demonstration. We demonstrated a case study in which more systematic safety demonstration for the target system software is performed via safety case construction than simply listing the documents.

Safety goals and safety culture opening plenary. 2. Safety Regulation Implemented by Gosatomnadzor of Russia

International Nuclear Information System (INIS)

Gutsalov, A.T.; Bukrinsky, A.M.

2001-01-01

This paper describes principles and approaches used by Gosatomnadzor of Russia in establishing safety goals. The link between safety goals and safety culture is demonstrated. The paper also contains information on nuclear regulatory activities in Russia. Regulatory documents of Gosatomnadzor of Russia do not provide precise definitions of safety goals as IAEA documents INSAG-3 or INSAG-12 do. However, overall activities of Gosatomnadzor of Russia are directed to the achievement of these safety goals, as Gosatomnadzor of Russia is a federal executive authority responsible for the regulation of nuclear and radiation safety in accordance with the Russian Federal Law 'On the Use of Nuclear Energy'. Thus, in the Statement of the Policy of the Russian Regulatory Authority, enacted in 1992, it was established that the overall activities of Gosatomnadzor of Russia are directed to the achievement of the main goal. This goal is to establish conditions that ensure that personnel, the public, and the environment are protected from unacceptable radiation and nonproliferation of nuclear materials. The practical application of such a method as given by the publication of Statements of Policy of Gosatomnadzor of Russia may be considered as a safety culture element. 'General Provisions of NPP Safety Ensuring' (OPB-88/ 97) is a regulatory document of the highest level in the hierarchy of regulatory documents of Gosatomnadzor of Russia. It establishes quantitative values of safety goals as do the foregoing IAEA documents. Thus, this regulatory document sets up the following: 1. The estimated total probability of severe accidents should not exceed 10 5 /reactor.yr. 2. The estimated probability of the worst possible radioactive release to the environment specified in the standards should not exceed 10 -7 /reactor.yr in the case of severe beyond-design-basis accidents. 3. The probability of a reactor vessel failure should not exceed 10 -7 /reactor.yr. The foregoing values are somehow

Concepts and techniques: Active electronics and computers in safety-critical accelerator operation

International Nuclear Information System (INIS)

Frankel, R.S.

1995-01-01

The Relativistic Heavy Ion Collider (RHIC) under construction at Brookhaven National Laboratory, requires an extensive Access Control System to protect personnel from Radiation, Oxygen Deficiency and Electrical hazards. In addition, the complicated nature of operation of the Collider as part of a complex of other Accelerators necessitates the use of active electronic measurement circuitry to ensure compliance with established Operational Safety Limits. Solutions were devised which permit the use of modern computer and interconnections technology for Safety-Critical applications, while preserving and enhancing, tried and proven protection methods. In addition a set of Guidelines, regarding required performance for Accelerator Safety Systems and a Handbook of design criteria and rules were developed to assist future system designers and to provide a framework for internal review and regulation

Concepts and techniques: Active electronics and computers in safety-critical accelerator operation

Energy Technology Data Exchange (ETDEWEB)

Frankel, R.S.

1995-12-31

The Relativistic Heavy Ion Collider (RHIC) under construction at Brookhaven National Laboratory, requires an extensive Access Control System to protect personnel from Radiation, Oxygen Deficiency and Electrical hazards. In addition, the complicated nature of operation of the Collider as part of a complex of other Accelerators necessitates the use of active electronic measurement circuitry to ensure compliance with established Operational Safety Limits. Solutions were devised which permit the use of modern computer and interconnections technology for Safety-Critical applications, while preserving and enhancing, tried and proven protection methods. In addition a set of Guidelines, regarding required performance for Accelerator Safety Systems and a Handbook of design criteria and rules were developed to assist future system designers and to provide a framework for internal review and regulation.

International cooperation in the safety and environmental assessment for the ITER engineering design activities

International Nuclear Information System (INIS)

Gordon, C.; Baker, D.J.; Bartels, H-W.

1998-01-01

The ITER Project includes design and assessment activities to ensure the safety and environmental attractiveness of ITER and demonstrate that it can be sited in any of the sponsoring Parties with a minimum of site-specific redesign. This paper highlights some of the efforts to develop an international consensus approach for ITER safety design and assessment, including: development of general safety and environmental design criteria; development of quantitative dose-release assessment criteria; development of a radiation protection program; waste characterization; and development of safety analysis guidelines. The high level of interaction, cooperation and collaboration between the Joint Central Team and the Home Teams, and between the safety team and designers, and the spirit of consensus that has guided them have resulted in a safe design for ITER and a safety design and assessment that can meet the needs of the potential host countries. (author)

Nuclear Safety Regulations

International Nuclear Information System (INIS)

Novosel, N.; Prah, M.

2008-01-01

Beside new Ordinance on the control of nuclear material and special equipment ('Official Gazette' No. 15/08), from 2006 State Office for Nuclear Safety (SONS) adopted Ordinance on performing nuclear activities ('Official Gazette' No. 74/06) and Ordinance on special requirements which expert organizations must fulfil in order to perform certain activities in the field of nuclear safety ('Official Gazette' No. 74/06), based on Nuclear Safety Act ('Official Gazette' No. 173/03). The Ordinance on performing nuclear activities regulates the procedure of notification of the intent to perform nuclear activities, submitting the application for the issue of a licence to perform nuclear activities, and the procedure for issuing decisions on granting a licence to perform a nuclear activity. The Ordinance also regulates the content of the forms for notification of the intent to perform nuclear activities, as well as of the application for the issue of a licence to perform the nuclear activity and the method of keeping the register of nuclear activities. According to the Nuclear Safety Act, nuclear activities are the production, processing, use, storage, disposal, transport, import, export, possession or other handling of nuclear material or specified equipment. The Ordinance on special requirements which expert organizations must fulfil in order to perform certain activities in the field of nuclear safety regulates these mentioned conditions, whereas compliance is established by a decision passed by the SONS. Special requirements which expert organizations must fulfil in order to perform certain activities in the field of nuclear safety are organizational, technical, technological conditions and established system of quality assurance. In 2007, State Office for Nuclear Safety finalized the text of new Ordinance on conditions for nuclear safety and protection with regard to the siting, design, construction, use and decommissioning of a facility in which a nuclear activity is

Parental safety concerns--a barrier to sport and physical activity in children?

Science.gov (United States)

Boufous, Soufiane; Finch, Caroline; Bauman, Adrian

2004-10-01

To examine the extent to which parents and carers perceive injury and safety risks as serious enough to prevent or discourage their children, aged 5-12 years, from participating in sports/physical activity and to identify factors that influence these perceptions. An analysis of the 2001 New South Wales Child Health Survey. More than one-quarter of parents/ carers of active children aged 5-12 years reported discouraging or preventing children from playing a particular sport (34.7% for boys and 16.6% for girls) because of injury and safety concerns. In boys, the most frequently discouraged sport was rugby league (23.2%), followed by rugby union (7.5%) and Australian rules football (2.8%). Among girls, the most frequently discouraged activities were rollerblading (2.7%), rugby league (2.3%) and soccer (2.1%). Multivariate analysis shows that factors independently associated with parents' decision to prevent/discourage their child from engaging in sport/physical activity include their child's age and gender, language spoken at home, presence of disability, and the respondent's relation to the child. Efforts need to be made to modify some sports/ activities, such as football codes, in order to minimise injury and to ensure that children continue enjoying their favourite activity well into adulthood. Guidelines designed to promote physical activity among children and young adolescents need to take into account parental concerns regarding the associated risk of injury.

Results of activities of the State Office for Nuclear Safety in state supervision of nuclear safety of nuclear facilities and radiation protection in 2003

International Nuclear Information System (INIS)

Kovar, P.

2004-01-01

The report summarises results of activities of the State Office for Nuclear Safety (SUJB) in the supervision of nuclear safety and radiation protection in the Czech Republic. The first part of the report evaluates nuclear safety of nuclear installations and contains information concerning the results of supervision of radiation protection in 2003 in the Czech Republic. The second part of the report describes new responsibilities of the SUJB in the domain of nuclear, chemical, bacteriological (biological) and toxin weapons ban. (author)

Survey and evaluation of inherent safety characteristics and passive safety systems for use in probabilistic safety analyses

International Nuclear Information System (INIS)

Wetzel, N.; Scharfe, A.

1998-01-01

The present report examines the possibilities and limits of a probabilistic safety analysis to evaluate passive safety systems and inherent safety characteristics. The inherent safety characteristics are based on physical principles, that together with the safety system lead to no damage. A probabilistic evaluation of the inherent safety characteristic is not made. An inventory of passive safety systems of accomplished nuclear power plant types in the Federal Republic of Germany was drawn up. The evaluation of the passive safety system in the analysis of the accomplished nuclear power plant types was examined. The analysis showed that the passive manner of working was always assumed to be successful. A probabilistic evaluation was not performed. The unavailability of the passive safety system was determined by the failure of active components which are necessary in order to activate the passive safety system. To evaluate the passive safety features in new concepts of nuclear power plants the AP600 from Westinghouse, the SBWR from General Electric and the SWR 600 from Siemens, were selected. Under these three reactor concepts, the SWR 600 is specially attractive because the safety features need no energy sources and instrumentation in this concept. First approaches for the assessment of the reliability of passively operating systems are summarized. Generally it can be established that the core melt frequency for the passive concepts AP600 and SBWR is advantageous in comparison to the probabilistic objectives from the European Pressurized Water Reactor (EPR). Under the passive concepts is the SWR 600 particularly interesting. In this concept the passive systems need no energy sources and instrumentation, and has active operational systems and active safety equipment. Siemens argues that with this concept the frequency of a core melt will be two orders of magnitude lower than for the conventional reactors. (orig.) [de

Priming patient safety: A middle-range theory of safety goal priming via safety culture communication.

Science.gov (United States)

Groves, Patricia S; Bunch, Jacinda L

2018-05-18

The aim of this paper is discussion of a new middle-range theory of patient safety goal priming via safety culture communication. Bedside nurses are key to safe care, but there is little theory about how organizations can influence nursing behavior through safety culture to improve patient safety outcomes. We theorize patient safety goal priming via safety culture communication may support organizations in this endeavor. According to this theory, hospital safety culture communication activates a previously held patient safety goal and increases the perceived value of actions nurses can take to achieve that goal. Nurses subsequently prioritize and are motivated to perform tasks and risk assessment related to achieving patient safety. These efforts continue until nurses mitigate or ameliorate identified risks and hazards during the patient care encounter. Critically, this process requires nurses to have a previously held safety goal associated with a repertoire of appropriate actions. This theory suggests undergraduate educators should foster an outcomes focus emphasizing the connections between nursing interventions and safety outcomes, hospitals should strategically structure patient safety primes into communicative activities, and organizations should support professional development including new skills and the latest evidence supporting nursing practice for patient safety. © 2018 John Wiley & Sons Ltd.

IAEA activities related to safety indicators, time frames and reference scenarios

International Nuclear Information System (INIS)

Batandjieva, B.; Hioki, K.; Metcalf, P.

2002-01-01

The fundamental principles for the safe management of radioactive waste have been agreed internationally and form the basis for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management that entered into force in June 2001. Protection of human health and the environment and safety of facilities (including radioactive waste disposal facilities) are widely recognised principles to be followed and demonstrated in post-closure safety assessment of waste repositories. Dose and risk are at present internationally agreed safety criteria, used for judging the acceptability of such facilities. However, there have been a number of activities initiated and co-ordinated by the International Atomic Energy Agency (IAEA) which have provided an international forum for discussion and consensus building on the use safety indicators which are complementary to dose and risk. The Agency has been working on the definition of other safety indicators, such as flux, time, environmental concentration, etc.; the desired characteristics, and use of these indicators in different time frames. The IAEA has focused on safety indicators related to geological disposal, exploring their role in the development of a safety case, evaluating the advantages and disadvantages of using other safety indicators and how they complement the dose and risk indicators. The use of these indicators have been discussed also from regulatory perspective, mainly in terms of achieving reasonable assurance and confidence in safety assessments for waste repositories and decision making in the presence of uncertainty in the context of disposal of long-lived waste. Considerable effort has also been expended by the Agency on the development and application of principles for defining critical groups and biospheres for deep geological repositories. One of the important and successful IAEA programmes in this field is the Biosphere Modelling and Assessment (BIOMASS) project

Application of the Management System for Facilities and Activities. Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2016-01-01

This publication provides guidance for following the requirements for management systems that integrate safety, health, security, quality assurance and environmental objectives. A successful management system ensures that nuclear safety matters are not dealt with in isolation but are considered within the context of all these objectives. The aim of this publication is to assist Member States to establish and implement effective management systems that coherently integrate all aspects of managing nuclear facilities and activities.

Research study about the establishment of safety culture. Effects of organizational factors in construction industry's safety indices

International Nuclear Information System (INIS)

Kojima, Mitsuhiro; Hirose, Humiko; Takano, Kenichi; Hasegawa, Naoko

1999-01-01

To find the relationships between safety related activities (such as safety patrol' or '4s/5s activities') and accidents rate in the workplace, questionnaires were sent to 965 construction companies and 120 answers were returned. In this questionnaire, safety activities, safety regulations and safety policies of the companies were asked and organizational climates, company policies, philosophies and the number of accidents in workplace were also asked. There seems some relationships between accidents rate and safety activities, safety regulations and safety policies in the companies, but the deviations between estimate values and observed values are so great that it seems impossible to estimate the accidents rate in the working place from the safety activities, safety regulations and safety policies of the companies. On the other hand, some characteristics of safety activities and organizational climates in the construction industry were identified using multi variants analysis. More detailed researches using sophisticated questionnaire will be conducted in the construction industry and petrochemical industry and relationships between the accidents rate and the safety activities will be compared between different industries. (author)

76 FR 40092 - Department Regulatory Agenda; Semiannual Summary

Science.gov (United States)

2011-07-07

... result in more effective public participation. This publication in the Federal Register does not impose... associated with subcontracting with Small Business, Small Disadvantaged Business, and Women-Owned Small... Water Efficiency, Renewable Energy Technologies, Occupational Safety, and Drug-Free Workplace Section...

Department of Transportation Agency Semiannual Regulatory Agenda

Science.gov (United States)

2010-12-20

... result in more effective public participation. This publication in the Federal Register does not impose... contracting issues associated with subcontracting with Small Business, Small Disadvantaged Business, and Women... and Water Efficiency, Renewable Energy Technologies, Occupational Safety, and Drug-Free Workplace...

Development of active rear steer actuator. Development of four wheel steer actuator for active safety; Active rear steer actuator no kaihatsu. Yobo anzen ni muketa 4WS actuator no kaihatsu

Energy Technology Data Exchange (ETDEWEB)

Yamanaka, T [Aisin Seiki Co. Ltd., Aichi (Japan)

1997-10-01

Recently, ecology, energy saving and safety have become important issues. And Active Safety is spotlighted in vehicle control area. Many researches and developments on four wheel steer system have been done to improve vehicle stability. We have developed the Active Rear Steer system with electromechanical Actuator, which is mass-productive, compact, and high response and durable. 10 figs., 5 tabs.

A Novel Control Algorithm for Integration of Active and Passive Vehicle Safety Systems in Frontal Collisions

Directory of Open Access Journals (Sweden)

Daniel Wallner

2010-10-01

Full Text Available The present paper investigates an approach to integrate active and passive safety systems of passenger cars. Worldwide, the introduction of Integrated Safety Systems and Advanced Driver Assistance Systems (ADAS is considered to continue the today

Development and Testing of a Nutrition, Food Safety, and Physical Activity Checklist for EFNEP and FSNE Adult Programs

Science.gov (United States)

Bradford, Traliece; Serrano, Elena L.; Cox, Ruby H.; Lambur, Michael

2010-01-01

Objective: To develop and assess reliability and validity of the Nutrition, Food Safety, and Physical Activity Checklist to measure nutrition, food safety, and physical activity practices among adult Expanded Food and Nutrition Education Program (EFNEP) and Food Stamp Nutrition Education program (FSNE) participants. Methods: Test-retest…

The safety of high activity long life nuclear waste

International Nuclear Information System (INIS)

Devillers, Ch.

1998-01-01

The article concerns the deep geological storage for managing high activity long life nuclear waste. He puts forward a context giving a structure to the discussions of those involved concerning an assessment of the safety of a deep geological deposit project. Three main aspects are put forward. The risks for future generations and the time scales to be considered: briefly, the deposit needs to satisfy two functions for protecting man and the environment, namely firstly isolating high activity radionuclides from the biosphere during the time required for their radioactive decay (about ten thousands years), and secondly delay and dilute long life radionuclides without any a priori time limit so as to reduce their effects in the biosphere to extremely low levels. The risks are linked to possible failures of the containment barriers whose causes need to be analysed and be provided against by suitable provisions concerning their design. The definition of these design provisions requires an in depth examination of uncertain elements. The main causes of uncertainty are listed according to the scale of time in question, that is O-10,000 years, 10,000-100,000 years and beyond 100,000 years, stressing the importance of selecting a stable geological site and more generally a solid concept that is not very sensitive in uncertainties. Beyond 100,000 years the extent of uncertainties no longer makes it possible to make realistic predictions. It is thus necessary to consider the alternative scenarios concerning geological and climatic changes and the corresponding increasing risks of radionuclides. The risks in question may be relativized by realizing that on this time scale, the residual activities of soluble and insoluble alpha and beta emitters are comparable to those of a storage centre located on the surface at the end of the monitoring period. Finally, the article considers the approach put forward concerning the safety of a deep geological storage advocated by the French

49 CFR 23.47 - What is the base for a recipient's goal for concessions other than car rentals?

Science.gov (United States)

2010-10-01

... Transportation PARTICIPATION OF DISADVANTAGED BUSINESS ENTERPRISE IN AIRPORT CONCESSIONS Goals, Good Faith... rental operations. (c) The dollar amount of a management contract or subcontract with a non-ACDBE and the gross receipts of business activities to which a management or subcontract with a non-ACDBE pertains are...

Nuclear Data Activities in Support of the DOE Nuclear Criticality Safety Program

International Nuclear Information System (INIS)

Westfall, R.M.; McKnight, R.D.

2005-01-01

The DOE Nuclear Criticality Safety Program (NCSP) provides the technical infrastructure maintenance for those technologies applied in the evaluation and performance of safe fissionable-material operations in the DOE complex. These technologies include an Analytical Methods element for neutron transport as well as the development of sensitivity/uncertainty methods, the performance of Critical Experiments, evaluation and qualification of experiments as Benchmarks, and a comprehensive Nuclear Data program coordinated by the NCSP Nuclear Data Advisory Group (NDAG).The NDAG gathers and evaluates differential and integral nuclear data, identifies deficiencies, and recommends priorities on meeting DOE criticality safety needs to the NCSP Criticality Safety Support Group (CSSG). Then the NDAG identifies the required resources and unique capabilities for meeting these needs, not only for performing measurements but also for data evaluation with nuclear model codes as well as for data processing for criticality safety applications. The NDAG coordinates effort with the leadership of the National Nuclear Data Center, the Cross Section Evaluation Working Group (CSEWG), and the Working Party on International Evaluation Cooperation (WPEC) of the OECD/NEA Nuclear Science Committee. The overall objective is to expedite the issuance of new data and methods to the DOE criticality safety user. This paper describes these activities in detail, with examples based upon special studies being performed in support of criticality safety for a variety of DOE operations

Does Perceived Neighborhood Walkability and Safety Mediate the Association Between Education and Meeting Physical Activity Guidelines?

OpenAIRE

Pratt, Michael; Yin, Shaoman; Soler, Robin; Njai, Rashid; Siegel, Paul Z.; Liao, Youlian

2015-01-01

The role of neighborhood walkability and safety in mediating the association between education and physical activity has not been quantified. We used data from the 2010 and 2012 Communities Putting Prevention to Work Behavioral Risk Factor Surveillance System and structural equation modeling to estimate how much of the effect of education level on physical activity was mediated by perceived neighborhood walkability and safety. Neighborhood walkability accounts for 11.3% and neighborhood safet...

NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security. Issue no. 4, June 2007

International Nuclear Information System (INIS)

2007-04-01

This newsletter contains information on the Centre for Advanced Safety Assessment Tools (CASAT), the new strategy for the recovery of radioactive sources, the Technical Support Organization Conference and a message form the Director of the Division of Nuclear Installation Safety. To improve the efficiency of safety assessment methods, ensure transparency in their validation and application and establish an excellent knowledge base and training programmes, the IAEA's Centre for Advanced Safety Assessment Tools (CASAT) has therefore been formed. The Centre addresses the need for continuous technical support mechanisms for safety assessment methods. It provides support to Member States to enhance their safety assessment capabilities for present and future generations of nuclear systems, with a special focus on countries with a developing nuclear technology and nuclear safety infrastructure. It serves as a consolidated repository of relevant safety analysis knowledge, provides for focused training including advanced analytical simulations, and supports collaboration on safety assessment projects among Member States. The resources provided through CASAT include codes, models, databases, verification and validation information, analytical procedures and guides. The main purpose of the recently established Radioactive Source Technical Coordination Group (RSTCG) is to facilitate the technical coordination of activities of the IAEA related to the control and management of radioactive sources through the development of common approaches in technical matters and to advise the management of the relevant Divisions. It is the task of the RSTCG to provide the programme managers of the participating divisions/sections with a common opinion/advice on technical issues related to the control and management of radioactive sources. The RSTCG members obtain, inter alia from programme managers, information on all relevant project proposals, and share relevant materials in due time to

Radiation safety in radioluminous paint workshop handling tritium activated paint

International Nuclear Information System (INIS)

Gaur, P.K.; Venkateswaran, T.V.

1986-01-01

This paper discusses the safety features related to a workshop when tritium activated luminous paint is handled by workmen. Salient features of the workshop and the methods employed for monitoring the radiation levels are briefly outlined and results are discussed. The importance of proper ventilation of the workplace and precautions to be taken in the storage of painted articles are highlighted. (author). 1 table, 3 figs

AREVA General Inspectorate Annual Report 2013 - Status of safety in nuclear facilities

International Nuclear Information System (INIS)

Oursel, Luc; Riou, Jean

2014-06-01

discipline. As in the previous year, the quality of relationship with the French nuclear safety regulator (ASN) and the management of the criticality risk were identified as areas for vigilance, as well as safety skills and resources, and sufficient managerial presence in the field. Other highlights of 2013 were the simplification of the group's legal structure, the continued roll-out of the new INB order, and the close attention paid to the conditions for implementing subcontracted work. Content: 1 - Context; 2 - Lessons learned from inspections; 3 - Radiological monitoring of personnel; 4 - Environmental monitoring; 5 - Operating experience from events; 6 - Crosscutting processes: Safety management, Safety of facilities, Operational safety; 7 - Areas for improvement and outlook; 8 - Glossary

75 FR 42818 - Agency Information Collection; Activity Under OMB Review; Collection of Safety Culture Data for...

Science.gov (United States)

2010-07-22

... Collection; Activity Under OMB Review; Collection of Safety Culture Data for Program Evaluation AGENCY... . SUPPLEMENTARY INFORMATION: Title: Collection of Safety Culture Data for Program Evaluation. Type of Request... data on the nation's transportation system is an important component of BTS' responsibility to the...

NREL photovoltaic program FY 1997 annual report

Energy Technology Data Exchange (ETDEWEB)

McConnell, R.D.; Hansen, A.; Smoller, S.

1998-06-01

This report summarizes the in-house and subcontracted research and development (R and D) activities under the NREL PV Program from October 1, 1996, through September 30, 1997 (FY 1997). The NREL PV Program is part of the US Department of Energy`s (DOE`s) National Photovoltaics Program, as described in the DOE National Photovoltaics Program Plan for 1996--2000. The FY 1997 budget authority for carrying out the NREL PV Program was $39.3 million in operating funds and $0.4 million in capital equipment funds. Subcontract activities represent a major part of the NREL PV Program, with $21.8 million (55% of PV funds) going to some 84 subcontractors. Cost sharing by industry added almost $8.8 million to the subcontract R and D activities with industry.

Fundamental Safety Principles

International Nuclear Information System (INIS)

Abdelmalik, W.E.Y.

2011-01-01

This work presents a summary of the IAEA Safety Standards Series publication No. SF-1 entitled F UDAMENTAL Safety PRINCIPLES p ublished on 2006. This publication states the fundamental safety objective and ten associated safety principles, and briefly describes their intent and purposes. Safety measures and security measures have in common the aim of protecting human life and health and the environment. These safety principles are: 1) Responsibility for safety, 2) Role of the government, 3) Leadership and management for safety, 4) Justification of facilities and activities, 5) Optimization of protection, 6) Limitation of risks to individuals, 7) Protection of present and future generations, 8) Prevention of accidents, 9)Emergency preparedness and response and 10) Protective action to reduce existing or unregulated radiation risks. The safety principles concern the security of facilities and activities to the extent that they apply to measures that contribute to both safety and security. Safety measures and security measures must be designed and implemented in an integrated manner so that security measures do not compromise safety and safety measures do not compromise security.

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

MEMS sensor technologies for human centred applications in healthcare, physical activities, safety and environmental sensing: a review on research activities in Italy.

Science.gov (United States)

Ciuti, Gastone; Ricotti, Leonardo; Menciassi, Arianna; Dario, Paolo

2015-03-17

Over the past few decades the increased level of public awareness concerning healthcare, physical activities, safety and environmental sensing has created an emerging need for smart sensor technologies and monitoring devices able to sense, classify, and provide feedbacks to users' health status and physical activities, as well as to evaluate environmental and safety conditions in a pervasive, accurate and reliable fashion. Monitoring and precisely quantifying users' physical activity with inertial measurement unit-based devices, for instance, has also proven to be important in health management of patients affected by chronic diseases, e.g., Parkinson's disease, many of which are becoming highly prevalent in Italy and in the Western world. This review paper will focus on MEMS sensor technologies developed in Italy in the last three years describing research achievements for healthcare and physical activity, safety and environmental sensing, in addition to smart systems integration. Innovative and smart integrated solutions for sensing devices, pursued and implemented in Italian research centres, will be highlighted, together with specific applications of such technologies. Finally, the paper will depict the future perspective of sensor technologies and corresponding exploitation opportunities, again with a specific focus on Italy.

MEMS Sensor Technologies for Human Centred Applications in Healthcare, Physical Activities, Safety and Environmental Sensing: A Review on Research Activities in Italy

Directory of Open Access Journals (Sweden)

Gastone Ciuti

2015-03-01

Full Text Available Over the past few decades the increased level of public awareness concerning healthcare, physical activities, safety and environmental sensing has created an emerging need for smart sensor technologies and monitoring devices able to sense, classify, and provide feedbacks to users’ health status and physical activities, as well as to evaluate environmental and safety conditions in a pervasive, accurate and reliable fashion. Monitoring and precisely quantifying users’ physical activity with inertial measurement unit-based devices, for instance, has also proven to be important in health management of patients affected by chronic diseases, e.g., Parkinson’s disease, many of which are becoming highly prevalent in Italy and in the Western world. This review paper will focus on MEMS sensor technologies developed in Italy in the last three years describing research achievements for healthcare and physical activity, safety and environmental sensing, in addition to smart systems integration. Innovative and smart integrated solutions for sensing devices, pursued and implemented in Italian research centres, will be highlighted, together with specific applications of such technologies. Finally, the paper will depict the future perspective of sensor technologies and corresponding exploitation opportunities, again with a specific focus on Italy.

Current activities and future trends in reliability analysis and probabilistic safety assessment in Hungary

International Nuclear Information System (INIS)

Hollo, E.; Toth, J.

1986-01-01

In Hungary reliability analysis (RA) and probabilistic safety assessment (PSA) of nuclear power plants was initiated 3 years ago. First, computer codes for automatic fault tree analysis (CAT, PREP) and numerical evaluation (REMO, KITT1,2) were adapted. Two main case studies - detailed availability/reliability calculation of diesel sets and analysis of safety systems influencing event sequences induced by large LOCA - were performed. Input failure data were taken from publications, a need for failure and reliability data bank was revealed. Current and future activities involves: setup of national data bank for WWER-440 units; full-scope level-I PSA of PAKS NPP in Hungary; operational safety assessment of particular problems at PAKS NPP. In the present article the state of RA and PSA activities in Hungary, as well as the main objectives of ongoing work are described. A need for international cooperation (for unified data collection of WWER-440 units) and for IAEA support (within Interregional Program INT/9/063) is emphasized. (author)

Safety basis for selected activities in single-shell tanks with flammable gas concerns. Revision 1

International Nuclear Information System (INIS)

Schlosser, R.L.

1996-01-01

This is full revision to Revision 0 of this report. The purpose of this report is to provide a summary of analyses done to support activities performed for single-shell tanks. These activities are encompassed by the flammable gas Unreviewed Safety Question (USQ). The basic controls required to perform these activities involve the identification, elimination and/or control of ignition sources and monitoring for flammable gases. Controls are implemented through the Interim Safety Basis (ISB), IOSRs, and OSDs. Since this report only provides a historical compendium of issues and activities, it is not to be used as a basis to perform USQ screenings and evaluations. Furthermore, these analyses and others in process will be used as the basis for developing the Flammable Gas Topical Report for the ISB Upgrade

Status of food safety management activities in fresh produce companies in the European Union and beyond

NARCIS (Netherlands)

Kirezieva, K.; Luning, P.A.; Jacxsens, L.; Uyttendaele, M.

2015-01-01

An increase in food safety incidences linked to fresh produce has been reported in recent years. Imports from the transitional economies have often been blamed for these incidences. However, limited information is available about the status of food safety management activities in companies in

Quarterly report on the activities in safety administration division. The third quarter of 2002. Document on present state of affairs

International Nuclear Information System (INIS)

Ishibashi, Takashi

2003-06-01

The activities of Safety Administration Division covers many fields in Tokai-Works such as the management of a labor safety health, the crisis management and the security, the safeguards of the nuclear materials, the transport of nuclear materials, and the management of a quality assurance. This report is summary of the activities of Safety Administration Division in October to December in 2002. (author)

La sous-traitance au Brésil : un phénomène à la fois ancien et nouveau Subcontracting in Brazil: a phenomenon both new and old La subcontratación en Brasil : un fenómeno antiguo y nuevo a la vez

Directory of Open Access Journals (Sweden)

Graça Druck

2009-05-01

Full Text Available L’objectif de l’article est de discuter la sous-traitance aujourd’hui au Brésil. Nous discutons dans l’article le processus de flexibilisation et de précarisation du travail au Brésil, en prenant comme objet d’étude la sous-traitance, en tant qu’une des principales politiques de gestion et d’organisation du travail dans le cadre de la restructuration productive. Nous présentons une synthèse du processus de sous-traitance observé ces dernières années dans le pays, sous ses anciennes et nouvelles modalités, et nous analysons les résultats empiriques récents sur la sous-traitance dans des entreprises industrielles à haut risque pour l’environnement et la santé des travailleurs, dans la Région Métropolitaine de Salvador/Bahia/Brésil, de même que nous indiquons les principales de formes de résistance et de contre-pouvoirs construits contre la précarisation du travail et la sous-traitance.The purpose of the article is to discuss current subcontracting in Brazil. Our study subject « subcontracting as one of the main work management and organization policies in the framework of productive restructurings » used to discuss the work flexilibization and precarization process in Brazil. We present a synthesis of the subcontracting process observed in recent years in this country, under its old and new conditions, and we analyze the recent empirical results on subcontracting in industrial enterprises at high risk to the environment and workers’ health, in the metropolitan region of Salvador/Bahia, Brazil. We also identify the main forms of resistance and the counterbalances developed against work precarization and subcontracting.El objetivo de este artículo es discutir la tercerización en el Brasil contemporáneo. Se discute el proceso de flexibilización y de precarización del trabajo en Brasil, tomando como objeto de estudio la subcontratación como una de las principales políticas de gestión y de organizaci

Unreviewed safety question evaluation of 100K East and 100K West in-basin fuel characterization program activities

International Nuclear Information System (INIS)

Alwardt, L.D.

1995-01-01

The purpose of this report is to provide the basis for answers to an Unreviewed Safety Question (USQ) safety evaluation of the 105K East (KE) and 105K West (KW) in-basin activities associated with the fuel characterization program as described in the characterization shipping plan. The significant activities that are common to both 105 KE and 105 KW basins are the movement of canisters from their main basin storage locations (or potentially from the 105 KE Tech View Pit if a dump table is available) to the south loadout pit transfer channel, hydrogen generation testing in the single element fuel container, loading the single element fuel container into the shipping cask, loading of the shipping cask onto a flat-bed trailer, return of the test fuel elements or element pieces from the 327 facility, placement of the fuel elements back into Mark 2 canisters, and placement of the canisters in the main storage basin. Decapping of canisters in the south loadout pit transfer channel and re-encapsulation of canisters are activities specific to the 105 KW basin. The scope of this safety evaluation includes only those characterization fuel shipment activities performed in the 105 KE and 105 KW fuel storage basin structures up to installation of the overpack. The packaging safety evaluation report governs the shipment of the fuel elements. The K Basins Plant Review Committee has determined that the in-basin activities associated with the fuel characterization program fuel shipments are bounded by the current safety envelop and do not constitute an unreviewed safety question. This determination is documented on Attachment 1

IAEA Safety Standards on Management Systems and Safety Culture

International Nuclear Information System (INIS)

Persson, Kerstin Dahlgren

2007-01-01

The IAEA has developed a new set of Safety Standard for applying an integrated Management System for facilities and activities. The objective of the new Safety Standards is to define requirements and provide guidance for establishing, implementing, assessing and continually improving a Management System that integrates safety, health, environmental, security, quality and economic related elements to ensure that safety is properly taken into account in all the activities of an organization. With an integrated approach to management system it is also necessary to include the aspect of culture, where the organizational culture and safety culture is seen as crucial elements of the successful implementation of this management system and the attainment of all the goals and particularly the safety goals of the organization. The IAEA has developed a set of service aimed at assisting it's Member States in establishing. Implementing, assessing and continually improving an integrated management system. (author)

77 FR 15453 - Pipeline Safety: Information Collection Activities

Science.gov (United States)

2012-03-15

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No... information collection titled, ``Gas Pipeline Safety Program Certification and Hazardous Liquid Pipeline... collection request that PHMSA will be submitting to OMB for renewal titled, ``Gas Pipeline Safety Program...

Managing preventive occupational health and safety activities in Danish enterprises during a period of financial crisis

DEFF Research Database (Denmark)

Andersen, Hans H. K.; Bach, Elsa

2017-01-01

The onset of the financial crisis in 2008 has put pressure on enterprises that in turn have downsized and reorganized. Research has shown that economic recession has an effect on psychological and behavioral health that is attributed to working environment problems. The objective of this study is...... focus on the management of preventive workplace health and safety activities in enterprises during a period of economic recession....... is to unravel whether the onset of a general economic recession has had an impact on companies’ and public institutions’ preventive occupational health and safety activities. Hypotheses of the role of pro-cyclical and countercyclical effects are presented. This study is based on a survey of enterprise...... preventive occupational health safety activities. The baseline for the survey was established, in 2006 before the onset of the recession, with a follow up in 2011. Findings are discussed that support both the pro-cyclical and the countercyclical hypotheses. It is concluded that there is a need for a special...

Experiences in the promotion of the safety culture in radiological activities in Cuba

International Nuclear Information System (INIS)

Ferro, Ruben; Guillen, Alba; Ilizastigui, Fidel

2001-01-01

During the last decade, the need to promote and achieve high safety culture levels has been one of the priorities in the nuclear sector around the world, although it has been focused basically on nuclear power. Nevertheless, it is an important and current topic for any risk related activity, since it results in a greater involvement and commitment of managers and personnel to safety, thereby reducing the so called 'organizational failures', one of the most frequent contributors to several of the major industrial disasters in the recent years. The International Atomic Energy Agency (IAEA) has also pointed that out and in some of its recent publications and meetings has recognized the need for extending this concept to the area of radioactive source. In Cuba, the Regulatory Body has been working in this direction during several years, promoting national research and studies in this field, issuing documents and organizing events and other activities. With this it is expected to introduce new work methods and practices to be applied by management and personnel involved in the use of radioactive sources, reflecting a higher safety culture level. This paper summarizes the experience of Cuban Regulatory Body in this field. (author)

New Nuclear Safety Regulations

International Nuclear Information System (INIS)

Novosel, N.; Prah, M.; Cizmek, A.

2008-01-01

Beside new Ordinance on the control of nuclear material and special equipment (Official Gazette No. 15/08), from 2006 State Office for Nuclear Safety (SONS) adopted Ordinance on performing nuclear activities (Official Gazette No. 74/06) and Ordinance on special conditions for individual activities to be performed by expert organizations which perform activities in the area of nuclear safety (Official Gazette No. 74/06), based on Nuclear Safety Act (Official Gazette No. 173/03). The Ordinance on performing nuclear activities regulates the procedure of announcing the intention to perform nuclear activity, submitting an application for the issue of a license to perform nuclear activity, and the procedure for adoption a decision on issuing a nuclear activity license. The Ordinance also regulates the contents of the application form for the announcement of the intention to perform nuclear activity, as well as of the application for the issue of a nuclear activity license and the method of keeping a nuclear activity register. The Ordinance on special conditions for individual activities to be performed by expert organizations which perform activities in the area of nuclear safety regulates these mentioned conditions, whereas compliance is established by a decision passed by the SONS. Special conditions for individual activities to be performed by expert organizations which perform activities in the area of nuclear safety are organizational, technical, technological conditions and established system of quality assurance. In 2007, SONS finalized the text of new Ordinance on nuclear safety and protection conditions for location, design, construction, operation and decommissioning of facility in which nuclear activity is performed. This Ordinance regulates nuclear safety and protection conditions for location, design, construction, operation and decommissioning of facility in which nuclear activity is performed. This Ordinance defines facilities in which nuclear activity is

75 FR 51525 - Railroad Safety Advisory Committee (RSAC); Working Group Activity Update

Science.gov (United States)

2010-08-20

.... The Working Group continues to work on after arrival orders, and at the September 25-26, 2008, meeting... protecting persons who work on, under, or between rolling equipment and persons applying, removing or.... 63] Railroad Safety Advisory Committee (RSAC); Working Group Activity Update AGENCY: Federal Railroad...

Activities of Nuclear Regulatory Authority and safety of nuclear facilities in the Slovak Republic in 1993

International Nuclear Information System (INIS)

1994-04-01

A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (NRA SR) in 1993 is presented. These activities are reported under the headings: (1) Introduction; (2) Regulatory activities at nuclear power plants units in operation; (2.1) Nuclear power plant SEP-EBO V-1; (4) Selected operation events and safety assessment in NPP SEP-EBO V-1; (2.2) Safety assessment of NPP SEP-EBO V-2; (3) Results of regulatory activities at the decommissioning of NPP A-1; (4) Regulatory activities at units under construction SEP-EMO - NPP Mochovce; (5) Further regulatory activities. (5.1) Preparation of designated personnel; (5.2) Inspection and accountancy of nuclear material; (5.3) Security provisions; (5.4) Accounted items and double use items; (5.5) Problem of radioactive wastes; (6.1) International co-operation activities of NRA; (6.2) Emergency planning; (6.3) International activities for quality enhancement of national supervision; (7) Conclusion [sk

Active and passive vehicle safety at Volkswagen accident research

Energy Technology Data Exchange (ETDEWEB)

Jungmichel, M.; Stanzel, M.; Zobel, R. [Volkswagen AG, Wolfsburg (Germany)

2001-07-01

Accident Analysis is an efficient means of improving vehicle passive safety and is used frequently and intensively. However, reliable data on accident causation is much more difficult to obtain. In most cases, one or more of the persons involved in an accident will face litigation and therefore are reluctant to provide the information that is essential to researchers. In addition, antilock brakes in almost every current vehicle have caused certain characteristic evidence, i.e. skid marks, to appear much less frequently than before. However, this evidence provides valuable information for assessing the reaction of the driver and his attempt to avoid the accident. In order to implement strategies of accident avoidance, accident causation must first be fully understood. Therefore, one of the assignments of the Volkswagen Accident Research Unit is to interpret global statistics, as well as to study single cases in order to come up with strategies for collision avoidance or mitigation. Currently, our primary concern is focused on active vehicle safety by researching vehicle behavior in the pre-crash phase. (orig.)

Training to Support Standardization and Improvement of Safety I and C Related Verification and Validation Activities

Energy Technology Data Exchange (ETDEWEB)

Ammon, G.; Schoenfelder, C.

2014-07-01

In recent years AREVA has conducted several measures to enhance the effectiveness of safety I and C related verification and validation activities within nuclear power plant (NPP) new build as well as modernization projects, thereby further strengthening its commitment to achieving the highest level of safety in nuclear facilities. (Author)

Safety upgrading activities against tsunami, earthquake, and severe accident at Hamaoka NPPs

International Nuclear Information System (INIS)

Watanabe, Tetsuya; Wakunaga, Takao; Ishida, Takahisa

2013-01-01

As the lessons learned by the Fukushima Daiichi NPPs accident, Chubu Electric Power carried out the Emergency Safety Measures at Hamaoka NPPs immediately, and announced the plan for tsunami countermeasures including the construction of 18m-height tsunami protection wall in July 2011. Furthermore, the company announced the additional severe accident and tsunami countermeasures, and etc. in December 2012 and in April 2013, such as the installation of Filtered Containment Venting System and increasing the height of the tsunami protection wall from 18m to 22m. In this paper, we present major safety upgrading activities against tsunami, earthquake and severe accident at Hamaoka NPPs. (author)

Reactor safety activities at the Centro de Desenvolvimento da Tecnologia Nuclear (CDTN)-Nuclebras

International Nuclear Information System (INIS)

Pinheiro, R.B.

1986-08-01

This report presents the major activities developed at NUCLEBRAS in the area of Reactor Safety. The Thermohydraulics and Reactor Safety program consists of activities in the analytical and experimental area. The more recent activities under way in the analytical area are presented together with some results. They are mainly related to the development and assessment of advanced computer codes to be used in the analysis of the behavior of the plant during operational transients and postulated accidents and in thermohydraulic core design. In the experimental area, the main accomplishments and activities under way are reported they refer to steady state CHF tests in a 9-rod bundle and rewetting experiments in a tubular test section. In particular, the status of the design development of a new facility for Separate Effects LOCA tests (DTL-ES) is described. Concerning the Components Testing program, the basic characteristics of a valve test facility (CTC) are described and the present status of its construction is reported. Reference is also made to existing installations and a summary of tests already performed for Angra-2 components qualification is presented. (Author) [pt

SAFETY ANALYSIS APPROACH TO TANK 241-SY-101 REMEDIATION ACTIVITIES

International Nuclear Information System (INIS)

RYAN, G.W.

2000-01-01

, supplemental controls to ensure safety during remediation operations and activities were developed and approved at the Contractor level with DOE cognizance through their participation as an integral part of the Project Team. This approach was selected as the most expedient to meet the aggressive project schedule and changing tank conditions. This project has been successful in meeting established goals because of the effectiveness of an integrated project team that included Nuclear Safety and Licensing at the start, the integral involvement of DOE during each phase of the project, and the ability of the Contractor to develop, approve, and implement the supplemental controls necessary to safely perform operations and activities

Energies and media nr 27. Conditions for the nuclear sector. Incidents this summer in France, Belgium and Germany

International Nuclear Information System (INIS)

2008-10-01

After some comments on recent events in the nuclear sector (agreement between India and the USA, new programs in different countries, activity of French companies abroad), this issue comments the worrying accumulation of incidents which occurred in several French nuclear installations in France (notably on the Tricastin site). It comments the actions of the French nuclear safety authority (ASN), the incident classification, delays in public information, problems faced on fuel assemblies, the issue of subcontracting. Incidents which occurred in Belgium (leakage of radioactive iodine) and Germany (water in an ancient salt and potash mine) are also commented

Regulatory Oversight of Safety Culture in Finland: A Systemic Approach to Safety

International Nuclear Information System (INIS)

Oedewald, P.; Väisäsvaara, J.

2016-01-01

In Finland the Radiation and Nuclear Safety Authority STUK specifies detailed regulatory requirements for good safety culture. Both the requirements and the practical safety culture oversight activities reflect a systemic approach to safety: the interconnections between the technical, human and organizational factors receive special attention. The conference paper aims to show how the oversight of safety culture can be integrated into everyday oversight activities. The paper also emphasises that the scope of the safety culture oversight is not specific safety culture activities of the licencees, but rather the overall functioning of the licence holder or the new build project organization from safety point of view. The regulatory approach towards human and organizational factors and safety culture has evolved throughout the years of nuclear energy production in Finland. Especially the recent new build projects have highlighted the need to systematically pay attention to the non-technical aspects of safety as it has become obvious how the HOF issues can affect the design processes and quality of construction work. Current regulatory guides include a set of safety culture related requirements. The requirements are binding to the licence holders and they set both generic and specific demands on the licencee to understand, monitor and to develop safety culture of their own organization but also that of their supplier network. The requirements set for the licence holders has facilitated the need to develop the regulator’s safety culture oversight practices towards a proactive and systemic approach.

SAFETY

CERN Multimedia

Niels Dupont

2013-01-01

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

Supporting Fernald Site Closure with Integrated Health and Safety Plans as Documented Safety Analyses

International Nuclear Information System (INIS)

Kohler, S.; Brown, T.; Fisk, P.; Krach, F.; Klein, B.

2004-01-01

At the Fernald Closure Project (FCP) near Cincinnati, Ohio, environmental restoration activities are supported by Documented Safety Analyses (DSAs) that combine the required project-specific Health and Safety Plans, Safety Basis Requirements (SBRs), and Process Requirements (PRs) into single Integrated Health and Safety Plans (I-HASPs). These integrated DSAs employ Integrated Safety Management methodology in support of simplified restoration and remediation activities that, so far, have resulted in the decontamination and demolition (D and D) of over 200 structures, including eight major nuclear production plants. There is one of twelve nuclear facilities still remaining (Silos containing uranium ore residues) with its own safety basis documentation. This paper presents the status of the FCP's safety basis documentation program, illustrating that all of the former nuclear facilities and activities have now replaced. Basis of Interim Operations (BIOs) with I-HASPs as their safety basis during the closure process

Introduction of the activity of the radiation safety for KOMAC

Energy Technology Data Exchange (ETDEWEB)

Min, Yi Sub; Park, Sung Kyun; Park, Jeong Min; Cho, Yong Sub [KAERI, Daejeon (Korea, Republic of)

2016-05-15

The 100 MeV linear proton accelerator as well as the various types of the ion accelerator have been operated and developed in KOMAC. These accelerators are classified as a radiation generator by the nuclear law of Korea. The operation of these accelerators included in the KOMAC site should be approved by Nuclear Safety and Security Committee (NSSC). This paper introduces the activity in terms of the radiation safety for these accelerator operations and their future plan. The model of the ion beam accelerator for analysis installed in KOMAC is a 5SDH-2, produced by National Electrostatics Corporation. This ion beam accelerator, devolved from Korea Institute of Geoscience and Mineral Resources (KIGAM), consists of two ion source, accelerating tanks and four beamlines. Ions in the ion beam accelerator are accelerated using a tandem method, that is, ions accelerated have been drawn out by the negative ions from the ion source and then changed into positive ions in the acceleration tube intermediate.

Active gated imaging for automotive safety applications

Science.gov (United States)

Grauer, Yoav; Sonn, Ezri

2015-03-01

The paper presents the Active Gated Imaging System (AGIS), in relation to the automotive field. AGIS is based on a fast gated-camera equipped with a unique Gated-CMOS sensor, and a pulsed Illuminator, synchronized in the time domain to record images of a certain range of interest which are then processed by computer vision real-time algorithms. In recent years we have learned the system parameters which are most beneficial to night-time driving in terms of; field of view, illumination profile, resolution and processing power. AGIS provides also day-time imaging with additional capabilities, which enhances computer vision safety applications. AGIS provides an excellent candidate for camera-based Advanced Driver Assistance Systems (ADAS) and the path for autonomous driving, in the future, based on its outstanding low/high light-level, harsh weather conditions capabilities and 3D potential growth capabilities.

Additional safety assessment of the INB 29. After the Fukushima Daiichi accident

International Nuclear Information System (INIS)

2012-01-01

A first part presents various general characteristics of the base nuclear installation (INB) number 29 (CIS bio International): main buildings, used materials, venting systems, electric supplies, control and command system, radiation protection measures. A second part identifies the cliff-edge effects and critical structures and equipment. The next parts address the seismic risk (installation sizing, margin assessment, robustness to fires possibly initiated by an earthquake), the flooding risk (installation sizing with respect to different flooding risks of different origins, margin assessment, active liquid waste tanks), other extreme natural phenomena (related to flooding, earthquake/flooding combination), the loss of electric supplies, thermal releases (loss of cyclotron cooling, releases related to source warehousing), the organization of severe accident management, the influence of other installations on crisis management, and subcontracting practices

Benchmarking promotion and deployment activities regarding intelligent vehicle safety systems in the EU

NARCIS (Netherlands)

Kievit, M. de; Malone, K.M.; Zwijnenberg, H.; Arem, B. van

2008-01-01

This paper presents the results of a Benchmarking study performed in the European Union on Awareness and Promotion & Deployment activities related to Intelligent Vehicle Safety (IVS) systems (1). The study, commissioned by the European Commission under the Intelligent Car Initiative (a i2010

The Agency's technical co-operation activities in 1992

International Nuclear Information System (INIS)

1993-08-01

This report on the International Atomic Energy Agency's Technical Co-operation Activities in 1992 contains an overview of the general issues involved, including both in-house and external developments, resources and delivery, and evaluation of programs; an overview by field of activity and by division within the Agency; an overview by geographic area, distinguishing (i) Africa, (ii) Asia and the Pacific, (iii) Latin America, (iv) and the Middle East and Europe; an overview by component (i.e., experts, equipment, fellowships, training courses, sub-contracts and miscellaneous); and an overview by fund technical assistance and co-operation fund, extrabudgetary resources, United Nations Development Program (UNDP), assistance in kind. It also contains a profile on technical co-operation activities in Latin America. Projects concluded during 1992 are listed together with a description of their achievements. It concludes with implementation summaries. 10 figs, 9 tabs

Nuclear safety in Slovak Republic. Status of safety improvements

International Nuclear Information System (INIS)

Toth, A.

1999-01-01

Status of the safety improvements at Bohunice V-1 units concerning WWER-440/V-230 design upgrading were as follows: supplementing of steam generator super-emergency feed water system; higher capacity of emergency core cooling system; supplementing of automatic links between primary and secondary circuit systems; higher level of secondary system automation. The goal of the modernization program for Bohunice V-1 units WWER-440/V-230 was to increase nuclear safety to the level of the proposals and IAEA recommendations and to reach probability goals of the reactor concerning active zone damage, leak of radioactive materials, failures of safety systems and damage shields. Upgrading program for Mochovce NPP - WWER-440/V-213 is concerned with improving the integrity of the reactor pressure vessel, steam generators 'leak before break' methods applied for the NPP, instrumentation and control of safety systems, diagnostic systems, replacement of in-core monitoring system, emergency analyses, pressurizers safety relief valves, hydrogen removal system, seismic evaluations, non-destructive testing, fire protection. Implementation of quality assurance has a special role in improvement of operational safety activities as well as safety management and safety culture, radiation protection, decommissioning and waste management and training. The Year 2000 problem is mentioned as well

Report for spreading culture of medical radiation safety in Korea: Mainly the activities of the Korean alliance for radiation safety and culture in medicine (KARSM)

International Nuclear Information System (INIS)

Yoon, Yong Su; Kim, Jung Min; Kim, Ji Hyun; Choi, In Seok; Sung, Dong Wook; Do, Kyung Hyun; Jung, Seung Eun; Kim, Hyung Soo

2013-01-01

There are many concerns about radiation exposure in Korea after Fukushima Nuclear Plant Accident on 2011 in Japan. As some isotope materials are detected in Korea, people get worried about the radioactive material. In addition, the mass media create an air of anxiety that jump on the people’s fear instead of scientific approach. Therefore, for curbing this flow, health, medical institute from the world provide a variety of information about medical radiation safety and hold the campaign which can give people the image that medical radiation is safe. At this, the Korean Food and Drug Administration(KFDA) suggested that make the alliance of medical radiation safety and culture on August, 2011. Seven societies and institutions related medical radiation started to research and advertise the culture of medical radiation safety in Korea. In this report, mainly introduce the activities of the Korean Alliance for Radiation Safety and Culture in Medicine(KARSM) for spreading culture of medical radiation safety from 2011 to 2012

Report for spreading culture of medical radiation safety in Korea: Mainly the activities of the Korean alliance for radiation safety and culture in medicine (KARSM)

Energy Technology Data Exchange (ETDEWEB)

Yoon, Yong Su; Kim, Jung Min; Kim, Ji Hyun; Choi, In Seok [Dept. of Radiologic Science, Korea University, Seoul (Korea, Republic of); Sung, Dong Wook [Dept. of Radiology, Kyunghee University Hospital, Seoul (Korea, Republic of); Do, Kyung Hyun [Dept. of Radiology, University of Ulsan College of Medicine, Asan Medical Center, Seoul (Korea, Republic of); Jung, Seung Eun [Dept. of Radiology, College of Medicine, The Catholic University of Korea, Seoul (Korea, Republic of); Kim, Hyung Soo [Dept. of Radiation Safety, National Institute of Food and Drug Safety Evaluation, Korea Food and Drug Administration, Seoul (Korea, Republic of)

2013-09-15

There are many concerns about radiation exposure in Korea after Fukushima Nuclear Plant Accident on 2011 in Japan. As some isotope materials are detected in Korea, people get worried about the radioactive material. In addition, the mass media create an air of anxiety that jump on the people’s fear instead of scientific approach. Therefore, for curbing this flow, health, medical institute from the world provide a variety of information about medical radiation safety and hold the campaign which can give people the image that medical radiation is safe. At this, the Korean Food and Drug Administration(KFDA) suggested that make the alliance of medical radiation safety and culture on August, 2011. Seven societies and institutions related medical radiation started to research and advertise the culture of medical radiation safety in Korea. In this report, mainly introduce the activities of the Korean Alliance for Radiation Safety and Culture in Medicine(KARSM) for spreading culture of medical radiation safety from 2011 to 2012.

Safety objectives for nuclear activities in Canada

International Nuclear Information System (INIS)

1982-04-01

This report by the Advisory Committee on Nuclear Safety presents a concise statement of the basic safety objectives which the Committee considers underlie, or should underlie, the regulations and the licensing and compliance practices of the Atomic Energy Control Board. The report also includes a number of general criteria for achieving these objectives

DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 1 of 2: Technical standard

International Nuclear Information System (INIS)

1998-05-01

This Department of Energy (DOE) technical standard (referred to as the Standard) provides guidance for integrating and enhancing worker, public, and environmental protection during facility disposition activities. It provides environment, safety, and health (ES and H) guidance to supplement the project management requirements and associated guidelines contained within DOE O 430.1A, Life-Cycle Asset Management (LCAM), and amplified within the corresponding implementation guides. In addition, the Standard is designed to support an Integrated Safety Management System (ISMS), consistent with the guiding principles and core functions contained in DOE P 450.4, Safety Management System Policy, and discussed in DOE G 450.4-1, Integrated Safety Management System Guide. The ISMS guiding principles represent the fundamental policies that guide the safe accomplishment of work and include: (1) line management responsibility for safety; (2) clear roles and responsibilities; (3) competence commensurate with responsibilities; (4) balanced priorities; (5) identification of safety standards and requirements; (6) hazard controls tailored to work being performed; and (7) operations authorization. This Standard specifically addresses the implementation of the above ISMS principles four through seven, as applied to facility disposition activities

Nuclear Power and Safety Division activity

International Nuclear Information System (INIS)

Pazdera, F.

1991-01-01

History of the Division is briefly described. Present research is centered on reliability analyses and thermal hydraulic analyses of transients and accidents. Some results of the safety analyses have been applied at nuclear power plants. A characterization is presented of computer codes for analyzing the behavior of fuel in normal and accident conditions. Research activities in the field of water chemistry and corrosion are oriented to the corrosion process at high temperatures and high pressures, and the related mass and radioactivity transfer; the effect of some chemical processes on primary coolant circuit materials; optimization of PWR filtration systems; and the development of the requisite monitoring instrumentation. A computerized operator support system has been developed, and at present it is tested at the Dukovany nuclear power plant. A program of nuclear fuel cycle strategy and economy has been worked out for nuclear fuel performance evaluation. Various options for better fuel exploitation, alternatives for advanced fuelling, and fuel cycle costs are assessed, and out-of-reactor fuel cycle options are compared. (M.D.). 7 refs., 32 refs

FLUOR HANFORD SAFETY MANAGEMENT PROGRAMS

Energy Technology Data Exchange (ETDEWEB)

GARVIN, L. J.; JENSEN, M. A.

2004-04-13

This document summarizes safety management programs used within the scope of the ''Project Hanford Management Contract''. The document has been developed to meet the format and content requirements of DOE-STD-3009-94, ''Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses''. This document provides summary descriptions of Fluor Hanford safety management programs, which Fluor Hanford nuclear facilities may reference and incorporate into their safety basis when producing facility- or activity-specific documented safety analyses (DSA). Facility- or activity-specific DSAs will identify any variances to the safety management programs described in this document and any specific attributes of these safety management programs that are important for controlling potentially hazardous conditions. In addition, facility- or activity-specific DSAs may identify unique additions to the safety management programs that are needed to control potentially hazardous conditions.

EC-sponsored research activities on innovative passive safety systems

International Nuclear Information System (INIS)

Bermejo, J.M.; Goethem, G. van

2000-01-01

On April 26th 1994, the European Union (EU) adopted via a Council Decision a EURATOM Multiannual Programme for community activities in the field of Nuclear Fission Safety (NFS) Research for the period 1994 to 1998. An area of work having, as an objective, to 'explore innovative approaches' to improve the safety of future and existing reactors, was introduced in this programme. Most of the projects selected in this area, which have been grouped under a common cluster known as 'INNO', are currently being carried out on a 'cost-shared' basis, i.e. contribution of the European Commission is up to 50% of the total cost. At present, the 'INNO' cluster is composed of 10 projects in which 25 different organisations, representing research centres, universities, regulators, utilities and vendors from 7 EU member states and Switzerland, are involved. These projects are proving to be an efficient means to gain the necessary phenomenological knowledge and to solve the challenging problems, many times of generic nature, posed among others by the characteristically small driving forces of the systems studied and by the lack of really prototypical test facilities. (author)

National program for the fostering and development of safety culture in the nuclear activities in Cuba

International Nuclear Information System (INIS)

Ferro Fernandez, R.; Guillen Campos, A.

2002-01-01

Since its appearance, as a result of the investigations of the accident in the Chernobyl Nuclear Power Plant, the term Safety Culture has been considered a key element to achieve a high level of safety in the nuclear installations, becoming a basic safety principle, internationally. The Cuban regulatory authority understood from very early the importance of the promotion and development of attitudes and characteristics in the organizations and personnel involved in the nuclear sector, reflecting a high Safety Culture, in order to propitiate a higher involvement of all employees in safety, contributing this way to the prevention of accidents in the nuclear facilities. Although the Cuban Nuclear Program was significantly reduced in the 90's, the regulatory authority has continued working in this direction and assimilated all the international experience for its application in its strategies for the development of a Safety Culture in the nuclear activities in the country. The present work summarizes the Cuban experience in the establishment of a National Program for the fostering and development of a Safety Culture. (author)

Safety-Related Improvisation in Led Outdoor Activities: An Exploratory Investigation into Its Occurrence and Influencing Factors

Science.gov (United States)

Trotter, Margaret J.; Salmon, Paul M.; Lenné, Michael G.

2014-01-01

The dynamic nature of led outdoor activities means that, despite activity providers' best efforts, activity leaders can be exposed to unanticipated situations for which no procedures exist. Improvisation, the spontaneous, real-time conception and execution of a novel response, has been identified as a potential means of maintaining safety in…

Safety Teams: An Approach to Engage Students in Laboratory Safety

Science.gov (United States)

Alaimo, Peter J.; Langenhan, Joseph M.; Tanner, Martha J.; Ferrenberg, Scott M.

2010-01-01

We developed and implemented a yearlong safety program into our organic chemistry lab courses that aims to enhance student attitudes toward safety and to ensure students learn to recognize, demonstrate, and assess safe laboratory practices. This active, collaborative program involves the use of student "safety teams" and includes…

Underground Pumped Hydroelectric Storage (UPHS). Program report, April 1-September 30, 1979. ANL Activity No. 49964

Energy Technology Data Exchange (ETDEWEB)

Blomquist, C.A.; Frigo, A.A.; Tam, S.W.; Clinch, J.M.

1979-10-01

The Argonne National Laboratory Underground Pumped Hydroelectric Storage activities for the second half of FY 1979 are described. Activities include program management and support, subcontract work, and systems studies. Information is given on the preliminary design, hydraulic performance, and cost of high-head, 350-MW capacity, single- and two-stage reversible, Francis-type pump turbines. Similar information is also presented on 350- and 500-MW capacity, multistage, unregulated, reversible, pump turbines. An assessment of the application potential of controlled-flow rate pumps and pump turbines is included. The effects of the charge/discharge ratio of a pumped stoage plant is also discussed.

Safety- and risk analysis activities in other areas than the nuclear industry

International Nuclear Information System (INIS)

Kozine, I.; Duijm, N.J.; Lauridsen, K.

2000-12-01

The report gives an overview of the legislation within the European Union in the field of major industrial hazards and gives examples of decision criteria applied in a number of European countries when judging the acceptability of an activity. Furthermore, the report mentions a few methods used in the analysis of the safety of chemical installations. (au)

Annual activity report of Ignalina NPP Safety Analysis Group for 1994 year

International Nuclear Information System (INIS)

Ushpuras, E.; Kaliatka, A.; Chesna, B.; Dundulis, G.

1995-01-01

The main results of Ignalina NPP Safety Analysis Group (ISAG) investigations for 1994 are presented. ISAG is concentrated its research activities into 3 areas: the neutrons dynamics modeling, simulation of transient processes during loss of coolant accident and calculation of reactor building structure's streses and other mechanical properties in the case of accident. 6 refs., 13 tabs., 69 figs

Toxicity of Biologically Active Peptides and Future Safety Aspects: An Update.

Science.gov (United States)

Khan, Fazlullah; Niaz, Kamal; Abdollahi, Mohammad

2018-02-18

Peptides are fragments of proteins with significant biological activities. These peptides are encoded in the protein sequence. Initially, such peptides are inactive in their parental form, unless proteolytic enzymes are released. These peptides then exhibit various functions and play a therapeutic role in the body. Besides the therapeutic and physiological activities of peptides, the main purpose of this study was to highlight the safety aspects of peptides. We performed an organized search of available literature using PubMed, Google Scholar, Medline, EMBASE, Reaxys and Scopus databases. All the relevant citations including research and review articles about the toxicity of biologically active peptides were evaluated and gathered in this study. Biological peptides are widely used in the daily routine ranging from food production to the cosmetics industry and also they have a beneficial role in the treatment and prevention of different diseases. These peptides are manufactured by both chemical and biotechnological techniques, which show negligible toxicity, however, some naturally occurring peptides and enzymes may induce high toxicity. Depending upon the demand and expected use in the food or pharmaceutical industry, we need different approaches to acertain the safety of these peptides preferentially through in silico methods. Intestinal wall disruption, erythrocytes and lymphocytes toxicity, free radical production, enzymopathic and immunopathic tissue damage and cytotoxicity due to the consumption of peptides are the main problems in the biological system that lead to various complicated disorders. Therefore, before considering biologically active peptides for food production and for therapeutic purpose, it is first necessary to evaluate the immunogenicity and toxicities of peptides. Copyright© Bentham Science Publishers; For any queries, please email at epub@benthamscience.org.

Analysis of the reliability of the active injection safety systems of Angra I

International Nuclear Information System (INIS)

Frutuoso e Melo, P.F.F.

1981-01-01

The reliability of the active emergency core cooling systems of Angra I nuclear power plant is evaluated. The fault tree analysis is employed. The unavailability of the above cited systems, is calculated. A parametric sensitivity analysis has been performed, due to the existing scattering in the failure and repair rate data of these system's components. The minimal cut sets were determined and, as a final step, a reliability importance analysis has been performed. This final step has required the development of a computer program. The methodology and data from the 'Reactor Safety Study' (Wash-1400) (in which the reliability of safety systems of a tipical PWR plant is calculated), is employed. The unavailability values for the safety systems analysed are too low, thus showing that in most cases the systems analysed are available to mitigate the effects of a loss-of-coolant accident. (Author) [pt

Review of occupational safety and health activities in Southern Africa funded under the DANIDA/ILO framework agreement on technical cooperation

DEFF Research Database (Denmark)

Hasle, Peter; Jørgensen, Claus

2003-01-01

A review of occupational safety and health activities in Southern Africa (SADC region) which have been funded under the DANIDA/ILO framework agreement on technical cooperation.......A review of occupational safety and health activities in Southern Africa (SADC region) which have been funded under the DANIDA/ILO framework agreement on technical cooperation....

Leadership and Management for Safety. General Safety Requirements

International Nuclear Information System (INIS)

2016-01-01

This Safety Requirements publication establishes requirements that support Principle 3 of the Fundamental Safety Principles in relation to establishing, sustaining and continuously improving leadership and management for safety and an integrated management system. It emphasizes that leadership for safety, management for safety, an effective management system and a systemic approach (i.e. an approach in which interactions between technical, human and organizational factors are duly considered) are all essential to the specification and application of adequate safety measures and to the fostering of a strong safety culture. Leadership and an effective management system will integrate safety, health, environmental, security, quality, human-and-organizational factor, societal and economic elements. The management system will ensure the fostering of a strong safety culture, regular assessment of performance and the application of lessons from experience. The publication is intended for use by regulatory bodies, operating organizations (registrants and licensees) and other organizations concerned with facilities and activities that give rise to radiation risks

General safety guidelines for looking for a low mass activity-long life waste storage site

International Nuclear Information System (INIS)

2008-01-01

The objective of this document is to define general guidelines which must be followed during the stages of search for a site and stages of design of a storage facility for low activity-long life radioactive wastes, in order to ensure its safety after closure. After having specified the considered wastes, geological shapes, and situations, this document defines the fundamental objective and the associated criteria (protection against chemical risk, radioprotection). It presents the design aspects related to safety (safety principles and functions, waste packages, public works engineering, geological environment, storage concepts). The last part deals with the safety demonstration after site closure which includes the control of some components, the assessment of disturbances in the storage facility or due to its presence, the taking of uncertainty and sensitivity studies into account, the influence of natural events

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

International Nuclear Information System (INIS)

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

2005-01-01

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

Nuclear safety regulations

International Nuclear Information System (INIS)

1998-01-01

The Departmental Rules and The Safety Guides were issued by the NNSA in 1998. The NNSA performed the activities of propagation and implementation of nuclear safety regulations at QTNPP in order to improve the nuclear safety culture of operating organization and construct and contract organizations

Decommissioning: Regulatory activities and identification of key organizational and human factors safety issues

International Nuclear Information System (INIS)

Durbin, N.E.; Melber, B.D.; Lekberg, A.

2001-12-01

In the late 1990's the Swedish government decided to shut down Unit 1 of the Barsebaeck nuclear power plant. This report documents some of the efforts made by the Swedish Nuclear Power Inspectorate (SKI) to address human factors and organizational issues in nuclear safety during decommissioning of a nuclear facility. This report gives a brief review of the background to the decommissioning of Barsebaeck 1 and points out key safety issues that can arise during decommissioning. The main regulatory activities that were undertaken were requirements that the plant provide special safety reports on decommissioning focusing on first, the operation of both units until closure of Unit 1 and second, the operation of Unit 2 when Unit 1 was closed. In addition, SKI identified areas that might be affected by decommissioning and called these areas out for special attention. With regard to these areas of special attention, SKI required that the plant provide monthly reports on changing and emerging issues as well as self-assessments of the areas to be addressed in the special safety reports. Ten key safety issues were identified and evaluated with regard to different stages of decommissioning and with regard to the actions taken by Barsebaeck. Some key conclusions from SKI's experience in regulating a decommissioning nuclear power plant conclude the report

Expansion of passive safety function

International Nuclear Information System (INIS)

Inai, Nobuhiko; Nei, Hiromichi; Kumada, Toshiaki.

1995-01-01

Expansion of the use of passive safety functions is proposed. Two notions are presented. One is that, in the design of passive safety nuclear reactors where aversion of active components is stressed, some active components are purposely introduced, by which a system is built in such a way that it behaves in an apparently passive manner. The second notion is that, instead of using a passive safety function alone, a passive safety function is combined with some active components, relating the passivity in the safety function with enhanced controllability in normal operation. The nondormant system which the authors propose is one example of the first notion. This is a system in which a standby safety system is a portion of the normal operation system. An interpretation of the nondormant system via synergetics is made. As an example of the second notion, a PIUS density lock aided with active components is proposed and is discussed

Regulatory inspection activities related to inspection planning, plant maintenance and assessment of safety. Proceedings of an international workshop

International Nuclear Information System (INIS)

Van Binnebeek, J.J.; Aubrey, Richard; Grandame, Melvyn; Aro, Ilari; Balloffet, Yves; Klonk, Hartmut; Manzella, Pietro; Koizumi, Hiroyoshi; Bouvrie, E.C. des; Forsberg, Staffan; Lang, Hans-Guenter; Mehew, Robert; Warren, Thomas; Woodhouse, Paul; Gallo, Robert M.; Campbell, Rob; )

1997-01-01

The NEA Committee on Nuclear Regulatory Activities (CNRA) believes that an essential factor in ensuring the safety of nuclear installations is the continuing exchange and analysis of technical information and data. To facilitate this exchange the Committee has established Working Groups and Groups of Experts in specialised topics. CNRA believes that safety inspections are a major element in the regulatory authority's efforts to ensure the safe operation of nuclear facilities. Considering the importance of these issues, the Committee has established a special Working Group on Inspection Practices (WGIP). The purpose of WGIP, is to facilitate the exchange of information and experience related to regulatory safety inspections between CNRA Member countries. This was the 3. international workshop held by the WGIP on regulatory inspection activities. The focus of this workshop was on 3 main topics; Inspection Planning, Plant Maintenance and Assessment of Safety. This document presents the proceedings from the workshop, including: workshop programme, results and conclusions, papers and presentations and the list of participants. The main purpose of the Workshop is to provide a forum of exchange of information on the regulatory inspection activities

Regulatory inspection activities related to inspection planning, plant maintenance and assessment of safety. Proceedings of an international workshop

Energy Technology Data Exchange (ETDEWEB)

Van Binnebeek, J. J. [AIB-Vincotte Nuclear - AVN, Avenue du Roi, 157, B-1060 Brussels (Belgium); Aubrey, Richard; Grandame, Melvyn [Atomic Energy Control Board - AECB, P.O. Box 1046, Station B, 280 Slater Street, Ottawa, Ontario K1P 5S9 (Canada); Aro, Ilari [Finnish Centre for Radiation and Nuclear Safety - STUK, P.O. Box 14, FIN-00881 Helsinki (Finland); Balloffet, Yves [DRIRE Rhone Alpes, 146, rue Pierre Corneille, 69426 Lyon CEDEX 03 (France); Klonk, Hartmut [Bundesamt fuer Strahlenschutz - BfS, Federal Office for Radiation Protection, Postbox 10 01 49, 38201 Salzgitter 1 (Germany); Manzella, Pietro [A.N.P.A., Via V. Brancati, 48, 1-00144 Roma EUR (Italy); Koizumi, Hiroyoshi [Tech. Stan. Dept. - JAPEIC, Shin-Toranomon Bldg., 1-5-11, Akasaka, Minato-ku, Tokyo 107 (Japan); Bouvrie, E.C. des [Ministry of Social Affairs and Employment, Nuclear Safety Dept. KFD, P.O. Box 90804, 2509 LV The Hague (Netherlands); Forsberg, Staffan [Swedish Nuclear Power Inspectorate - SKI, Klarabergsviadukten 90, S-10658 Stockholm (Sweden); Lang, Hans-Guenter [Section Plant Coordination and Inspection, Swiss Federal Nuclear Safety Inspectorate - HSK, CH-5232 Villigen-HSK (Switzerland); Mehew, Robert; Warren, Thomas; Woodhouse, Paul [Health and Safety Executive - NII, St. Peter' s House, Balliol Road, Bootle, Merseyside L20 3LZ (United Kingdom); Gallo, Robert M. [Special Inspection Branch, US Nuclear Regulatory Commission - US NRC, Mail Stop 0-9A1, Washington, DC 20555 (United States); Campbell, Rob [International Atomic Energy Agency - IAEA, P.O. Box 100, A-1400 Vienna (International Atomic Energy Agency (IAEA))

1997-07-01

The NEA Committee on Nuclear Regulatory Activities (CNRA) believes that an essential factor in ensuring the safety of nuclear installations is the continuing exchange and analysis of technical information and data. To facilitate this exchange the Committee has established Working Groups and Groups of Experts in specialised topics. CNRA believes that safety inspections are a major element in the regulatory authority's efforts to ensure the safe operation of nuclear facilities. Considering the importance of these issues, the Committee has established a special Working Group on Inspection Practices (WGIP). The purpose of WGIP, is to facilitate the exchange of information and experience related to regulatory safety inspections between CNRA Member countries. This was the 3. international workshop held by the WGIP on regulatory inspection activities. The focus of this workshop was on 3 main topics; Inspection Planning, Plant Maintenance and Assessment of Safety. This document presents the proceedings from the workshop, including: workshop programme, results and conclusions, papers and presentations and the list of participants. The main purpose of the Workshop is to provide a forum of exchange of information on the regulatory inspection activities.

Assessing Patient Activation among High-Need, High-Cost Patients in Urban Safety Net Care Settings.

Science.gov (United States)

Napoles, Tessa M; Burke, Nancy J; Shim, Janet K; Davis, Elizabeth; Moskowitz, David; Yen, Irene H

2017-12-01

We sought to examine the literature using the Patient Activation Measure (PAM) or the Patient Enablement Instrument (PEI) with high-need, high-cost (HNHC) patients receiving care in urban safety net settings. Urban safety net care management programs serve low-income, racially/ethnically diverse patients living with multiple chronic conditions. Although many care management programs track patient progress with the PAM or the PEI, it is not clear whether the PAM or the PEI is an effective and appropriate tool for HNHC patients receiving care in urban safety net settings in the United States. We searched PubMed, EMBASE, Web of Science, and PsycINFO for articles published between 2004 and 2015 that used the PAM and between 1998 and 2015 that used the PEI. The search was limited to English-language articles conducted in the United States and published in peer-reviewed journals. To assess the utility of the PAM and the PEI in urban safety net care settings, we defined a HNHC patient sample as racially/ethnically diverse, low socioeconomic status (SES), and multimorbid. One hundred fourteen articles used the PAM. All articles using the PEI were conducted outside the U.S. and therefore were excluded. Nine PAM studies (8%) included participants similar to those receiving care in urban safety net settings, three of which were longitudinal. Two of the three longitudinal studies reported positive changes following interventions. Our results indicate that research on patient activation is not commonly conducted on racially and ethnically diverse, low SES, and multimorbid patients; therefore, there are few opportunities to assess the appropriateness of the PAM in such populations. Investigators expressed concerns with the potential unreliability and inappropriate nature of the PAM on multimorbid, older, and low-literacy patients. Thus, the PAM may not be able to accurately assess patient progress among HNHC patients receiving care in urban safety net settings. Assessing

Activity of the Atomic Energy Society of Japan for compiling the consensus standard on nuclear criticality safety control

International Nuclear Information System (INIS)

Yamane, Yoshihiro; Matsumoto, Tadakuni

2003-01-01

Activity of the Atomic Energy Society of Japan for compiling the consensus standard on nuclear criticality safety control is presented. The standard recommends an enhancement of nuclear criticality safety throughout a life cycle of facility in terms of a concept of 'barriers against criticality'. (author)

Use of the Home Safety Self-Assessment Tool (HSSAT) within Community Health Education to Improve Home Safety.

Science.gov (United States)

Horowitz, Beverly P; Almonte, Tiffany; Vasil, Andrea

2016-10-01

This exploratory research examined the benefits of a health education program utilizing the Home Safety Self-Assessment Tool (HSSAT) to increase perceived knowledge of home safety, recognition of unsafe activities, ability to safely perform activities, and develop home safety plans of 47 older adults. Focus groups in two senior centers explored social workers' perspectives on use of the HSSAT in community practice. Results for the health education program found significant differences between reported knowledge of home safety (p = .02), ability to recognize unsafe activities (p = .01), safely perform activities (p = .04), and develop a safety plan (p = .002). Social workers identified home safety as a major concern and the HSSAT a promising assessment tool. Research has implications for reducing environmental fall risks.

Taking ownership of safety. What are the active ingredients of safety coaching and how do they impact safety outcomes in critical offshore working environments?

Science.gov (United States)

Krauesslar, Victoria; Avery, Rachel E; Passmore, Jonathan

2015-01-01

Safety coaching interventions have become a common feature in the safety critical offshore working environments of the North Sea. Whilst the beneficial impact of coaching as an organizational tool has been evidenced, there remains a question specifically over the use of safety coaching and its impact on behavioural change and producing safe working practices. A series of 24 semi-structured interviews were conducted with three groups of experts in the offshore industry: safety coaches, offshore managers and HSE directors. Using a thematic analysis approach, several significant themes were identified across the three expert groups including connecting with and creating safety ownership in the individual, personal significance and humanisation, ingraining safety and assessing and measuring a safety coach's competence. Results suggest clear utility of safety coaching when applied by safety coaches with appropriate coach training and understanding of safety issues in an offshore environment. The current work has found that the use of safety coaching in the safety critical offshore oil and gas industry is a powerful tool in managing and promoting a culture of safety and care.

Safety Basis Report

International Nuclear Information System (INIS)

R.J. Garrett

2002-01-01

As part of the internal Integrated Safety Management Assessment verification process, it was determined that there was a lack of documentation that summarizes the safety basis of the current Yucca Mountain Project (YMP) site characterization activities. It was noted that a safety basis would make it possible to establish a technically justifiable graded approach to the implementation of the requirements identified in the Standards/Requirements Identification Document. The Standards/Requirements Identification Documents commit a facility to compliance with specific requirements and, together with the hazard baseline documentation, provide a technical basis for ensuring that the public and workers are protected. This Safety Basis Report has been developed to establish and document the safety basis of the current site characterization activities, establish and document the hazard baseline, and provide the technical basis for identifying structures, systems, and components (SSCs) that perform functions necessary to protect the public, the worker, and the environment from hazards unique to the YMP site characterization activities. This technical basis for identifying SSCs serves as a grading process for the implementation of programs such as Conduct of Operations (DOE Order 5480.19) and the Suspect/Counterfeit Items Program. In addition, this report provides a consolidated summary of the hazards analyses processes developed to support the design, construction, and operation of the YMP site characterization facilities and, therefore, provides a tool for evaluating the safety impacts of changes to the design and operation of the YMP site characterization activities

Safety Basis Report

Energy Technology Data Exchange (ETDEWEB)

R.J. Garrett

2002-01-14

As part of the internal Integrated Safety Management Assessment verification process, it was determined that there was a lack of documentation that summarizes the safety basis of the current Yucca Mountain Project (YMP) site characterization activities. It was noted that a safety basis would make it possible to establish a technically justifiable graded approach to the implementation of the requirements identified in the Standards/Requirements Identification Document. The Standards/Requirements Identification Documents commit a facility to compliance with specific requirements and, together with the hazard baseline documentation, provide a technical basis for ensuring that the public and workers are protected. This Safety Basis Report has been developed to establish and document the safety basis of the current site characterization activities, establish and document the hazard baseline, and provide the technical basis for identifying structures, systems, and components (SSCs) that perform functions necessary to protect the public, the worker, and the environment from hazards unique to the YMP site characterization activities. This technical basis for identifying SSCs serves as a grading process for the implementation of programs such as Conduct of Operations (DOE Order 5480.19) and the Suspect/Counterfeit Items Program. In addition, this report provides a consolidated summary of the hazards analyses processes developed to support the design, construction, and operation of the YMP site characterization facilities and, therefore, provides a tool for evaluating the safety impacts of changes to the design and operation of the YMP site characterization activities.

Efficacy and safety of superficial chemical peeling in treatment of active acne vulgaris.

Science.gov (United States)

Al-Talib, Hassanain; Al-Khateeb, Alyaa; Hameed, Ayad; Murugaiah, Chandrika

2017-01-01

Acne vulgaris is an extremely common condition affecting the pilosebaceous unit of the skin and characterized by presence of comedones, papules, pustules, nodules, cysts, which might result in permanent scars. Acne vulgaris commonly involve adolescents and young age groups. Active acne vulgaris is usually associated with several complications like hyper or hypopigmentation, scar formation and skin disfigurement. Previous studies have targeted the efficiency and safety of local and systemic agents in the treatment of active acne vulgaris. Superficial chemical peeling is a skin-wounding procedure which might cause some potentially undesirable adverse events. This study was conducted to review the efficacy and safety of superficial chemical peeling in the treatment of active acne vulgaris. It is a structured review of an earlier seven articles meeting the inclusion and exclusion criteria. The clinical assessments were based on pretreatment and post-treatment comparisons and the role of superficial chemical peeling in reduction of papules, pustules and comedones in active acne vulgaris. This study showed that almost all patients tolerated well the chemical peeling procedures despite a mild discomfort, burning, irritation and erythema have been reported; also the incidence of major adverse events was very low and easily manageable. In conclusion, chemical peeling with glycolic acid is a well-tolerated and safe treatment modality in active acne vulgaris while salicylic acid peels is a more convenient for treatment of darker skin patients and it showed significant and earlier improvement than glycolic acid.

Indicators of safety culture - selection and utilization of leading safety performance indicators

Energy Technology Data Exchange (ETDEWEB)

Reiman, Teemu; Pietikaeinen, Elina (VTT, Technical Research Centre of Finland (Finland))

2010-03-15

Safety indicators play a role in providing information on organizational performance, motivating people to work on safety and increasing organizational potential for safety. The aim of this report is to provide an overview on leading safety indicators in the domain of nuclear safety. The report explains the distinction between lead and lag indicators and proposes a framework of three types of safety performance indicators - feedback, monitor and drive indicators. Finally the report provides guidance for nuclear energy organizations for selecting and interpreting safety indicators. It proposes the use of safety culture as a leading safety performance indicator and offers an example list of potential indicators in all three categories. The report concludes that monitor and drive indicators are so called lead indicators. Drive indicators are chosen priority areas of organizational safety activity. They are based on the underlying safety model and potential safety activities and safety policy derived from it. Drive indicators influence control measures that manage the socio technical system; change, maintain, reinforce, or reduce something. Monitor indicators provide a view on the dynamics of the system in question; the activities taking place, abilities, skills and motivation of the personnel, routines and practices - the organizational potential for safety. They also monitor the efficacy of the control measures that are used to manage the socio technical system. Typically the safety performance indicators that are used are lagging (feedback) indicators that measure the outcomes of the socio technical system. Besides feedback indicators, organizations should also acknowledge the important role of monitor and drive indicators in managing safety. The selection and use of safety performance indicators is always based on an understanding (a model) of the socio technical system and safety. The safety model defines what risks are perceived. It is important that the safety

Indicators of safety culture - selection and utilization of leading safety performance indicators

International Nuclear Information System (INIS)

Reiman, Teemu; Pietikaeinen, Elina

2010-03-01

Safety indicators play a role in providing information on organizational performance, motivating people to work on safety and increasing organizational potential for safety. The aim of this report is to provide an overview on leading safety indicators in the domain of nuclear safety. The report explains the distinction between lead and lag indicators and proposes a framework of three types of safety performance indicators - feedback, monitor and drive indicators. Finally the report provides guidance for nuclear energy organizations for selecting and interpreting safety indicators. It proposes the use of safety culture as a leading safety performance indicator and offers an example list of potential indicators in all three categories. The report concludes that monitor and drive indicators are so called lead indicators. Drive indicators are chosen priority areas of organizational safety activity. They are based on the underlying safety model and potential safety activities and safety policy derived from it. Drive indicators influence control measures that manage the socio technical system; change, maintain, reinforce, or reduce something. Monitor indicators provide a view on the dynamics of the system in question; the activities taking place, abilities, skills and motivation of the personnel, routines and practices - the organizational potential for safety. They also monitor the efficacy of the control measures that are used to manage the socio technical system. Typically the safety performance indicators that are used are lagging (feedback) indicators that measure the outcomes of the socio technical system. Besides feedback indicators, organizations should also acknowledge the important role of monitor and drive indicators in managing safety. The selection and use of safety performance indicators is always based on an understanding (a model) of the socio technical system and safety. The safety model defines what risks are perceived. It is important that the safety

BARC safety framework

International Nuclear Information System (INIS)

Jayarajan, K.; Taly, Y.K.

2017-01-01

BARC has a large number facilities and a large number of employees. It has a variety of activities, carried out in different parts of India. All activities related nuclear fuel cycle are carried out in BARC. In addition, BARC has many non-nuclear facilities and projects. Therefore, regulation of BARC facilities is a challenging task. BSC was constituted in the year 2000 to address the challenges of regulating safety of the projects, plants and facilities of BARC. It has a comprehensive regulatory framework, which makes use of the expertise of more than one thousand experts of BARC for safety and regulatory activities. BSC has completed hundred meetings and issued regulatory consents to many projects, facilities and activities. During the last 17 years, BSC has constituted 44 committees in three tiers, which had conducted more than 2000 meetings to support safety and regulatory activities of BSC

Study on safety classifications of software used in nuclear power plants and distinct applications of verification and validation activities in each class

International Nuclear Information System (INIS)

Kim, B. R.; Oh, S. H.; Hwang, H. S.; Kim, D. I.

2000-01-01

This paper describes the safety classification regarding instrumentation and control (I and C) systems and their software used in nuclear power plants, provides regulatory positions for software important to safety, and proposes verification and validation (V and V) activities applied differently in software classes which are important elements in ensuring software quality assurance. In other word, the I and C systems important to safety are classified into IC-1, IC-2, IC-3, and Non-IC and their software are classified into safety-critical, safety-related, and non-safety software. Based upon these safety classifications, the extent of software V and V activities in each class is differentiated each other. In addition, the paper presents that the software for use in I and C systems important to safety is divided into newly-developed and previously-developed software in terms of design and implementation, and provides the regulatory positions on each type of software

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

International Nuclear Information System (INIS)

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

2016-01-01

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

High committee for nuclear safety transparency and information. Annual activity report. June 2008 - December 2009

International Nuclear Information System (INIS)

2010-01-01

This document is the first activity report of the High committee for nuclear safety transparency and information (HCTISN), created on June 18, 2008. The HCTISN is a French authority of information, dialogue and debate about the risks linked with nuclear activities and about their impacts on public health, on the environment and on nuclear safety. The committee has the ability to express his opinion and recommendations about any question on the above topics and to propose any measure aiming at warranting or improving the transparency in the nuclear domain. This activity report offers a synthetic overview of the actions already undertaken: the plutonium imports from UK, the contamination incident at the Socatri facility (a Areva-Eurodif daughter company located at the Tricastin site), and the dismantling strategy of basic nuclear facilities. It presents the composition, organization, missions and means of the Committee, the different working groups and the follow-up of the different recommendations emitted so far by the Committee. (J.S.)

76 FR 45904 - Pipeline Safety: Information Collection Activities

Science.gov (United States)

2011-08-01

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No... at U.S. Department of Transportation, Pipeline and Hazardous Materials Safety Administration, 1200...: On Occasion. Title: Record Keeping for Natural Gas Pipeline Operators. OMB Control Number: 2137-0049...

75 FR 13807 - Pipeline Safety: Information Collection Activities

Science.gov (United States)

2010-03-23

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No... of Transportation, Pipeline and Hazardous Materials Safety Administration, 1200 New Jersey Avenue, SE...: Updates to Pipeline and Liquefied Natural Gas Reporting Requirements (One Rule). The Notice of Proposed...

Safety and Radiation Protection at Nuclear Power Plants in France in 2015. IRSN's position - Mission Report 2016

International Nuclear Information System (INIS)

2017-01-01

particularly the case for forgetting to wear a dosimeter with 22 events in 2015, as opposed to 17 events in 2014 and 11 events in 2013. Finally, as in 2014, deviations associated with access and stay in controlled area decreased significantly, although they still represent the largest number of events. The implementation by EDF of operational action plans seems to have a positive effect. Expertise on specific issues in 2015: In its report, IRSN also presents its main conclusions on specific issues that were the subject of an assessment in 2015:Guidelines of the periodic review associated with the fourth ten-yearly reactor safety reviews for the 900 MWe reactors; - The optimization of the radiation protection of workers in EDF plants, and particularly the adequacy and sufficiency of organizational arrangements; - The control by EDF of the risks associated with the subcontracted maintenance activities

Development of a Generic Environmental Safety Case for the Disposal of Higher Activity Wastes in the UK

International Nuclear Information System (INIS)

Bailey, Lucy; Hicks, Tim

2016-01-01

The UK generic ESC demonstrates safe disposal of higher activity wastes, by providing: • A demonstration of how environmental safety can be achieved by a variety of disposal concepts based on systems of multiple engineered and natural barriers, providing multiple safety functions; • An understanding of expected barrier performance and how conditions in a disposal system will evolve, based on research findings presented in RWM’s knowledge base; • An approach to safety assessment based on multiple lines of reasoning, involving both qualitative and quantitative analysis; • Complementary insight modelling and total system modelling used to develop understanding of how different components of the engineered and natural barrier system contribute to safety

Waste isolation safety assessment program. Task 4. Third contractor information meeting

International Nuclear Information System (INIS)

1980-06-01

The Contractor Information Meeting (October 14 to 17, 1979) was part of the FY-1979 effort of Task 4 of the Waste Isolation Safety Assessment Program (WISAP): Sorption/Desorption Analysis. The objectives of this task are to: evaluate sorption/desorption measurement methods and develop a standardized measurement procedure; produce a generic data bank of nuclide-geologic interactions using a wide variety of geologic media and groundwaters; perform statistical analysis and synthesis of these data; perform validation studies to compare short-term laboratory studies to long-term in situ behavior; develop a fundamental understanding of sorption/desorption processes; produce x-ray and gamma-emitting isotopes suitable for the study of actinides at tracer concentrations; disseminate resulting information to the international technical community; and provide input data support for repository safety assessment. Conference participants included those subcontracted to WISAP Task 4, representatives and independent subcontractors to the Office of Nuclear Waste Isolation, representatives from other waste disposal programs, and experts in the area of waste/geologic media interaction. Since the meeting, WISAP has been divided into two programs: Assessment of Effectiveness of Geologic Isolation Systems (AEGIS) (modeling efforts) and Waste/Rock Interactions Technology (WRIT) (experimental work). The WRIT program encompasses the work conducted under Task 4. This report contains the information presented at the Task 4, Third Contractor Information Meeting. Technical Reports from the subcontractors, as well as Pacific Northwest Laboratory (PNL), are provided along with transcripts of the question-and-answer sessions. The agenda and abstracts of the presentations are also included. Appendix A is a list of the participants. Appendix B gives an overview of the WRIT program and details the WRIT work breakdown structure for 1980

Waste isolation safety assessment program. Task 4. Third contractor information meeting

Energy Technology Data Exchange (ETDEWEB)

1980-06-01

The Contractor Information Meeting (October 14 to 17, 1979) was part of the FY-1979 effort of Task 4 of the Waste Isolation Safety Assessment Program (WISAP): Sorption/Desorption Analysis. The objectives of this task are to: evaluate sorption/desorption measurement methods and develop a standardized measurement procedure; produce a generic data bank of nuclide-geologic interactions using a wide variety of geologic media and groundwaters; perform statistical analysis and synthesis of these data; perform validation studies to compare short-term laboratory studies to long-term in situ behavior; develop a fundamental understanding of sorption/desorption processes; produce x-ray and gamma-emitting isotopes suitable for the study of actinides at tracer concentrations; disseminate resulting information to the international technical community; and provide input data support for repository safety assessment. Conference participants included those subcontracted to WISAP Task 4, representatives and independent subcontractors to the Office of Nuclear Waste Isolation, representatives from other waste disposal programs, and experts in the area of waste/geologic media interaction. Since the meeting, WISAP has been divided into two programs: Assessment of Effectiveness of Geologic Isolation Systems (AEGIS) (modeling efforts) and Waste/Rock Interactions Technology (WRIT) (experimental work). The WRIT program encompasses the work conducted under Task 4. This report contains the information presented at the Task 4, Third Contractor Information Meeting. Technical Reports from the subcontractors, as well as Pacific Northwest Laboratory (PNL), are provided along with transcripts of the question-and-answer sessions. The agenda and abstracts of the presentations are also included. Appendix A is a list of the participants. Appendix B gives an overview of the WRIT program and details the WRIT work breakdown structure for 1980.

Simplifying documentation while approaching site closure: integrated health and safety plans as documented safety analysis

International Nuclear Information System (INIS)

Brown, Tulanda

2003-01-01

At the Fernald Closure Project (FCP) near Cincinnati, Ohio, environmental restoration activities are supported by Documented Safety Analyses (DSAs) that combine the required project-specific Health and Safety Plans, Safety Basis Requirements (SBRs), and Process Requirements (PRs) into single Integrated Health and Safety Plans (I-HASPs). By isolating any remediation activities that deal with Enriched Restricted Materials, the SBRs and PRs assure that the hazard categories of former nuclear facilities undergoing remediation remain less than Nuclear. These integrated DSAs employ Integrated Safety Management methodology in support of simplified restoration and remediation activities that, so far, have resulted in the decontamination and demolition (D and D) of over 150 structures, including six major nuclear production plants. This paper presents the FCP method for maintaining safety basis documentation, using the D and D I-HASP as an example

Benchmarking Promotion and Deployment Activities Regarding Intelligent Vehicle Safety Systems in the European Union

NARCIS (Netherlands)

de Kievit, M.; Malone, K.M.; Zwijnenberg, H.; van Arem, B.

2008-01-01

This paper presents the results of a Benchmarking study performed in the European Union on Awareness and Promotion & Deployment activities related to Intelligent Vehicle Safety (IVS) systems (1). The study, commissioned by the European Commission under the Intelligent Car Initiative (a i2010

White paper on nuclear safety in 2005

International Nuclear Information System (INIS)

2006-04-01

The white paper consists of four parts. The first part described the outline of international discussions on safety culture and activities promoted by utilities and regulatory bodies in Japan. The second part explained the main activities of the Nuclear Safety Commission of Japan and nuclear regulatory authorities on nuclear safety regulation. The third part introduced various activities for ensuring overall nuclear safety in Japan, such as safety regulation systems for nuclear facilities, disaster measures at nuclear facilities, progress in nuclear research, nuclear safety regulation by risk-informed utilization, environmental radiation surveys, international cooperation on nuclear safety. The forth part contained various materials and data related to the Nuclear Safety Commission of Japan. (J.P.N.)

75 FR 73160 - Pipeline Safety: Information Collection Activities

Science.gov (United States)

2010-11-29

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No...-Related Conditions on Gas, Hazardous Liquid, and Carbon Dioxide Pipelines and Liquefied Natural Gas... Pipelines and Liquefied Natural Gas Facilities.'' The Pipeline Safety Laws (49 U.S.C. 60132) require each...

IAEA Safety Standards

International Nuclear Information System (INIS)

2016-09-01

The IAEA Safety Standards Series comprises publications of a regulatory nature covering nuclear safety, radiation protection, radioactive waste management, the transport of radioactive material, the safety of nuclear fuel cycle facilities and management systems. These publications are issued under the terms of Article III of the IAEA’s Statute, which authorizes the IAEA to establish “standards of safety for protection of health and minimization of danger to life and property”. Safety standards are categorized into: • Safety Fundamentals, stating the basic objective, concepts and principles of safety; • Safety Requirements, establishing the requirements that must be fulfilled to ensure safety; and • Safety Guides, recommending measures for complying with these requirements for safety. For numbering purposes, the IAEA Safety Standards Series is subdivided into General Safety Requirements and General Safety Guides (GSR and GSG), which are applicable to all types of facilities and activities, and Specific Safety Requirements and Specific Safety Guides (SSR and SSG), which are for application in particular thematic areas. This booklet lists all current IAEA Safety Standards, including those forthcoming

75 FR 64348 - BOEMRE Information Collection Activity: 1010-0182, Increased Safety Measures for Energy...

Science.gov (United States)

2010-10-19

... No. BOEM-2010-0052] BOEMRE Information Collection Activity: 1010-0182, Increased Safety Measures for... the likelihood of blowouts, loss of well control, fires, spillages, physical obstruction to other... subsequent oil spill in the Gulf of Mexico. These events highlight the importance of ensuring safe operations...

Integration of Active and Passive Safety Technologies--A Method to Study and Estimate Field Capability.

Science.gov (United States)

Hu, Jingwen; Flannagan, Carol A; Bao, Shan; McCoy, Robert W; Siasoco, Kevin M; Barbat, Saeed

2015-11-01

The objective of this study is to develop a method that uses a combination of field data analysis, naturalistic driving data analysis, and computational simulations to explore the potential injury reduction capabilities of integrating passive and active safety systems in frontal impact conditions. For the purposes of this study, the active safety system is actually a driver assist (DA) feature that has the potential to reduce delta-V prior to a crash, in frontal or other crash scenarios. A field data analysis was first conducted to estimate the delta-V distribution change based on an assumption of 20% crash avoidance resulting from a pre-crash braking DA feature. Analysis of changes in driver head location during 470 hard braking events in a naturalistic driving study found that drivers' head positions were mostly in the center position before the braking onset, while the percentage of time drivers leaning forward or backward increased significantly after the braking onset. Parametric studies with a total of 4800 MADYMO simulations showed that both delta-V and occupant pre-crash posture had pronounced effects on occupant injury risks and on the optimal restraint designs. By combining the results for the delta-V and head position distribution changes, a weighted average of injury risk reduction of 17% and 48% was predicted by the 50th percentile Anthropomorphic Test Device (ATD) model and human body model, respectively, with the assumption that the restraint system can adapt to the specific delta-V and pre-crash posture. This study demonstrated the potential for further reducing occupant injury risk in frontal crashes by the integration of a passive safety system with a DA feature. Future analyses considering more vehicle models, various crash conditions, and variations of occupant characteristics, such as age, gender, weight, and height, are necessary to further investigate the potential capability of integrating passive and DA or active safety systems.

The IAEA's activities in safeguarding nuclear materials and in developing internationally acceptable safety codes and guides for nuclear power plants

International Nuclear Information System (INIS)

Rometsch, Rudolf; Specter, Herschel

1977-01-01

Promoting the peaceful use of nuclear energy and aiming at the international sharing of its benefits are objectives that guide the activities of the Agency. But this promotional work is carried out on condition that security and safety are provided for. All Agency assistance involving nuclear facilities will be subjected to standards of safety or other standards, which are proposed by a State the Agency finds essentially equivalent. Safeguards are always applied on the basis of agreement. States party to NPT are obligated to negotiate and conclude with the Agency agreements which cover all their peaceful nuclear activities. Safeguards agreements concluded outside NPT are applied to specific supplies of facilities, equipment and material. To assist countries in laying down their nuclear safety regulations the Agency's program for the developing of codesof practice and safety guides for nuclear power plants draws up guidelines for governmental organizations, siting, design, operation and quality assurance. Codes are the fundamental documents laying down the objectives of each field of nuclear safety

Safety design

International Nuclear Information System (INIS)

Kunitomi, Kazuhiko; Shiozawa, Shusaku

2004-01-01

JAERI established the safety design philosophy of the HTTR based on that of current reactors such as LWR in Japan, considering inherent safety features of the HTTR. The strategy of defense in depth was implemented so that the safety engineering functions such as control of reactivity, removal of residual heat and confinement of fission products shall be well performed to ensure safety. However, unlike the LWR, the inherent design features of the high-temperature gas-cooled reactor (HTGR) enables the HTTR meet stringent regulatory criteria without much dependence on active safety systems. On the other hand, the safety in an accident typical to the HTGR such as the depressurization accident initiated by a primary pipe rupture shall be ensured. The safety design philosophy of the HTTR considers these unique features appropriately and is expected to be the basis for future Japanese HTGRs. This paper describes the safety design philosophy and safety evaluation procedure of the HTTR especially focusing on unique considerations to the HTTR. Also, experiences obtained from an HTTR safety review and R and D needs for establishing the safety philosophy for the future HTGRs are reported

Guide for understanding and evaluation of safety culture

International Nuclear Information System (INIS)

2008-01-01

This report was the guide of understanding and evaluation of safety culture. Operator's activities for enhancement of safety culture in nuclear installations became an object of safety regulation in the management system. Evaluation of operator's activities (including top management's involvement) to prevent degradation of safety culture and organization climate in daily works needed understanding of safety culture and diversity of operator's activities. This guide was prepared to check indications of degradation of safety culture and organization climate in operator's activities in daily works and encourage operator's activities to enhance safety culture improvement and good practice. Comprehensive evaluation of operator's activities to prevent degradation of safety culture and organization climate would be performed from the standpoints of 14 safety culture elements such as top management commitment, clear plan and implementation of upper manager, measures to avoid wrong decision making, questioning attitude, reporting culture, good communications, accountability and openness, compliance, learning system, activities to prevent accidents or incidents beforehand, self-assessment or third party evaluation, work management, change management and attitudes/motivation. Element-wise examples and targets for evaluation were attached with evaluation check tables. (T. Tanaka)

The value of safety and safety as a value

NARCIS (Netherlands)

Ratilainen, H.; Salminen, S.; Zwetsloot, G.I.J.M.; Perttula, P.; Starren, A.; Steijn, W.; Pahkin, K.; Drupsteen, L.; Puro, V.; Räsänen, T.; Aaltonen, M.; Berkers, F.; Kalakoski, V.

2016-01-01

The research presented in this document analyzes how safety values are defined and used in practice, in particular by managers, and how they affect employers’ and employees’ decisions and behaviour at work. The work comprises three complementary activities: a literature review on the value of safety

SAFETY ALERT: Electrical insulation defect on safety helmets

CERN Multimedia

HSE Unit

2013-01-01

Contrarily to the information provided until 31 May 2013, some “Euro Protection” safety helmets do not respect any of the requirements for electrical insulation.   This alert concerns the safety helmets identified under the following SCEM numbers: 50.43.30.050.4 white 50.43.30.060.2 yellow 50.43.30.070.0 blue This amounts up to several hundreds of helmets on the CERN site. People who need to wear an electrically insulated safety helmet for their activities, must from now on acquire a duly insulated item to be found on the CERN store under the following SCEM numbers: 50.43.30.210.6: Petzl Vertex ST Helmet (without vent) 50.43.30.300.1: IDRA Helmet with a visor for electrical work As for the people who do not need to wear an electrically insulated helmet for their activities, they can continue working with the aforementioned helmets. For your information, please take note of the maximum use limit of each helmet: “Euro Protection” Safety Helme...

Regulatory review of safety cases and safety assessments for near surface

International Nuclear Information System (INIS)

Nys, V.

2003-01-01

The activities of the ASAM Regulatory Review Working Group are presented. Regulatory review of the safety assessment is made. It includes the regulatory review of post-closure safety assessment; safety case development and confidence building. The ISAM methodology is reviewed and SA system description is presented. Recommendations on the review process management are given

Field studies of safety security rescue technologies through training and response activities

Science.gov (United States)

Murphy, Robin R.; Stover, Sam

2006-05-01

This paper describes the field-oriented philosophy of the Institute for Safety Security Rescue Technology (iSSRT) and summarizes the activities and lessons learned during calendar year 2005 of its two centers: the Center for Robot-Assisted Search and Rescue and the NSF Safety Security Rescue industry/university cooperative research center. In 2005, iSSRT participated in four responses (La Conchita, CA, Mudslides, Hurricane Dennis, Hurricane Katrina, Hurricane Wilma) and conducted three field experiments (NJTF-1, Camp Hurricane, Richmond, MO). The lessons learned covered mobility, operator control units, wireless communications, and general reliability. The work has collectively identified six emerging issues for future work. Based on these studies, a 10-hour, 1 continuing education unit credit course on rescue robotics has been created and is available. Rescue robots and sensors are available for loan upon request.

Qualification of safety-critical software for digital reactor safety system in nuclear power plants

International Nuclear Information System (INIS)

Kwon, Kee-Choon; Park, Gee-Yong; Kim, Jang-Yeol; Lee, Jang-Soo

2013-01-01

This paper describes the software qualification activities for the safety-critical software of the digital reactor safety system in nuclear power plants. The main activities of the software qualification processes are the preparation of software planning documentations, verification and validation (V and V) of the software requirements specifications (SRS), software design specifications (SDS) and codes, and the testing of the integrated software and integrated system. Moreover, the software safety analysis and software configuration management are involved in the software qualification processes. The V and V procedure for SRS and SDS contains a technical evaluation, licensing suitability evaluation, inspection and traceability analysis, formal verification, software safety analysis, and an evaluation of the software configuration management. The V and V processes for the code are a traceability analysis, source code inspection, test case and test procedure generation. Testing is the major V and V activity of the software integration and system integration phases. The software safety analysis employs a hazard operability method and software fault tree analysis. The software configuration management in each software life cycle is performed by the use of a nuclear software configuration management tool. Through these activities, we can achieve the functionality, performance, reliability, and safety that are the major V and V objectives of the safety-critical software in nuclear power plants. (author)

Work on fusion technology at Studsvik during 1978

International Nuclear Information System (INIS)

Pauli, R.; Espefaelt, R.; Lorenzen, J.

1978-02-01

Studsvik is associated with the EUR-ATOM fusion research program and work within fusion technology is carried out regarding reactor control, conceptual design, safety and environmental impact; radiation damage. In addition research by subcontracts is done in atomic physics data at Lund university and in surface physics at Research Institute of Physics, Stockholm university. (author)

Fusion safety status report

International Nuclear Information System (INIS)

1986-10-01

This report includes information on a) tritium handling and safety; b) activation product generation and release; c) lithium safety; d) superconducting magnet safety; e) operational safety and shielding; f) environmental impact; g) recycling, decommissioning and waste management; and h) accident analysis. Recommendations for high priority research and development are presented, as well as the current status in each area

Nuclear power safety economics

International Nuclear Information System (INIS)

Legasov, V.A.; Demin, V.F.; Shevelev, Ya.V.

1984-01-01

The existing conceptual and methodical basis for the decision-making process insuring safety of the nuclear power and other (industrial and non-industrial) human activities is critically analyzed. Necessity of development a generalized economic safety analysis method (GESAM) is shown. Its purpose is justifying safety measures. Problems of GESAM development are considered including the problem of costing human risk. A number of suggestions on solving them are given. Using the discounting procedure in the assessment of risk or detriment caused by harmful impact on human health is substantiated. Examples of analyzing some safety systems in the nuclear power and other spheres of human activity are given