Intranet-based safety documentation in management of major hazards and occupational health and safety.

Science.gov (United States)

Leino, Antti

2002-01-01

In the European Union, Council Directive 96/82/EC requires operators producing, using, or handling significant amounts of dangerous substances to improve their safety management systems in order to better manage the major accident potentials deriving from human error. A new safety management system for the Viikinmäki wastewater treatment plant in Helsinki, Finland, was implemented in this study. The system was designed to comply with both the new safety liabilities and the requirements of OHSAS 18001 (British Standards Institute, 1999). During the implementation phase experiences were gathered from the development processes in this small organisation. The complete documentation was placed in the intranet of the plant. Hyperlinks between documents were created to ensure convenience of use. Documentation was made accessible for all workers from every workstation.

Evolution of Safety Basis Documentation for the Fernald Site

International Nuclear Information System (INIS)

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

2004-01-01

The objective of the Department of Energy's (DOE) Fernald Closure Project (FCP), in suburban Cincinnati, Ohio, is to safely complete the environmental restoration of the Fernald site by 2006. Over 200 out of 220 total structures, at this DOE plant site which processed uranium ore concentrates into high-purity uranium metal products, have been safely demolished, including eight of the nine major production plants. Documented Safety Analyses (DSAs) for these facilities have gone through a process of simplification, from individual operating Safety Analysis Reports (SARs) to a single site-wide Authorization Basis containing nuclear facility Bases for Interim Operations (BIOs) to individual project Auditable Safety Records (ASRs). The final stage in DSA simplification consists of project-specific Integrated Health and Safety Plans (I-HASPs) and Nuclear Health and Safety Plans (N-HASPs) that address all aspects of safety, from the worker in the field to the safety basis requirements preserving the facility/activity hazard categorization. This paper addresses the evolution of Safety Basis Documentation (SBD), as DSAs, from production through site closure

Effective Presentation Media for Passenger Safety I: Comprehension of Briefing Card Pictorials and Pictograms

National Research Council Canada - National Science Library

Corbett, Cynthia L; McLean, Garnet A; Cosper, Donna K

2008-01-01

.... The exact content and presentation media used for safety briefings and cards are the responsibility of the airlines to implement, as long as the required minimum safety information is delivered...

Advanced Photon Source experimental beamline Safety Assessment Document: Addendum to the Advanced Photon Source Accelerator Systems Safety Assessment Document (APS-3.2.2.1.0)

International Nuclear Information System (INIS)

1995-01-01

This Safety Assessment Document (SAD) addresses commissioning and operation of the experimental beamlines at the Advanced Photon Source (APS). Purpose of this document is to identify and describe the hazards associated with commissioning and operation of these beamlines and to document the measures taken to minimize these hazards and mitigate the hazard consequences. The potential hazards associated with the commissioning and operation of the APS facility have been identified and analyzed. Physical and administrative controls mitigate identified hazards. No hazard exists in this facility that has not been previously encountered and successfully mitigated in other accelerator and synchrotron radiation research facilities. This document is an updated version of the APS Preliminary Safety Analysis Report (PSAR). During the review of the PSAR in February 1990, the APS was determined to be a Low Hazard Facility. On June 14, 1993, the Acting Director of the Office of Energy Research endorsed the designation of the APS as a Low Hazard Facility, and this Safety Assessment Document supports that designation

Synthesis of the IRSN report on its analysis of the safety guidance package (DOrS) of the ASTRID reactor project. Safety guidance document for the ASTRID prototype: Referral to the GPR. Opinion related to the safety guidance document of the ASTRID reactor project. ASTRID prototype: Safety guidance document for the ASTRID prototype

International Nuclear Information System (INIS)

Lachaume, Jean-Luc; Niel, Jean-Christophe

2013-01-01

A first document indicates the improvement guidelines for the ASTRID project based on the French experience in the field of sodium-cooled fast neutron reactors, addresses the safety objectives as they are presented for the ASTRID project, discusses how the project includes a regulation and design referential, and how it addresses various aspects of the design approach (ranking and analysis of operation situations, defence in depth, use of probabilistic studies, safety classification and qualification to accidental situations, taking internal and external aggressions into account and taking severe accidents into account at the design level). It comments the guidelines related to the first two barriers, to main safety functions (control of reactivity and of reactor cooling, containment of radioactive and toxic materials), to dismantling, to R and D for safety support. A second document is a letter sent by the ASN to the GPR (permanent group of experts in charge of nuclear reactors) about the safety guidance document for the ASTRID prototype. The third document is the answer and contains comments and recommendations by this group about the content of this document, and therefore addresses the same topics as the first document. The last document defines the framework of the approach to this document

Preparation of safety and regulatory document for BARC Facilities

International Nuclear Information System (INIS)

Prasad, S.S.; Jayarajan, K.

2017-01-01

In India, the necessary codes and safety guidelines for achieving the safety objectives are provided by the Atomic Energy Regulatory Board (AERB), which are in conformity with the principles of radiation protection as formulated by the International Council of Radiation Protection (ICRP) and International Atomic Energy Agency (IAEA). The same is followed by BARC Safety Council (BSC), which is the regulatory body for the BARC facilities. In addition to all types of fuel cycle facilities, BSC regulates safety of many types of conventional facilities. Many such types of facilities and projects are not under the regulatory purview of AERB. Therefore, the Council has also initiated a programme for development and publication of safety documents for installations in BARC in the fields/ topics yet not addressed by IAEA or AERB. This makes the task pioneering, as some of the areas taken up for defining the regulatory requirements are new, where standard regulatory documents are not available

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

Laboratory Safety Manual for Alabama Schools. Bulletin 1975. No. 20.

Science.gov (United States)

Alabama State Dept. of Education, Montgomery.

This document presents the Alabama State Department of Education guidelines for science laboratory safety, equipment, storage, chemical safety, rocket safety, electrical safety, safety with radioisotopes, and safety with biologicals. Also included is a brief bibliography, a teacher's checklist, a listing of laser facts and regulations, and a…

Using Addenda in Documented Safety Analysis Reports

International Nuclear Information System (INIS)

Swanson, D.S.; Thieme, M.A.

2003-01-01

This paper discusses the use of addenda to the Radioactive Waste Management Complex (RWMC) Documented Safety Analysis (DSA) located at the Idaho National Engineering and Environmental Laboratory (INEEL). Addenda were prepared for several systems and processes at the facility that lacked adequate descriptive information and hazard analysis in the DSA. They were also prepared for several new activities involving unreviewed safety questions (USQs). Ten addenda to the RWMC DSA have been prepared since the last annual update

Hanford Site Wide Transportation Safety Document [SEC 1 Thru 3

Energy Technology Data Exchange (ETDEWEB)

MCCALL, D L

2002-06-01

This safety evaluation report (SER) documents the basis for the US Department of Energy (DOE), Richland Operations Office (RL) to approve the Hanford Sitewide Transportation Safety Document (TSD) for onsite Transportation and Packaging (T&P) at Hanford. Hanford contractors, on behalf of DOE-RL, prepared and submitted the Hanford Sitewide Transportation Safety Document, DOE/RL-2001-0036, Revision 0, (DOE/RL 2001), dated October 4, 2001, which is referred to throughout this report as the TSD. In the context of the TSD, Hanford onsite shipments are the activities of moving hazardous materials, substances, and wastes between DOE facilities and over roadways where public access is controlled or restricted and includes intra-area and inter-area movements. The TSD sets forth requirements and standards for onsite shipment of radioactive and hazardous materials and wastes within the confines of the Hanford Site on roadways where public access is restricted by signs, barricades, fences, or other means including road closures and moving convoys controlled by Hanford Site security forces.

Electronic Medical Record Documentation of Driving Safety for Veterans with Diagnosed Dementia.

Science.gov (United States)

Vair, Christina L; King, Paul R; Gass, Julie; Eaker, April; Kusche, Anna; Wray, Laura O

2018-01-01

Many older adults continue to drive following dementia diagnosis, with medical providers increasingly likely to be involved in addressing such safety concerns. This study examined electronic medical record (EMR) documentation of driving safety for veterans with dementia (N = 118) seen in Veterans Affairs primary care and interdisciplinary geriatrics clinics in one geographic region over a 10-year period. Qualitative directed content analysis of retrospective EMR data. Assessment of known risk factors or subjective concerns for unsafe driving were documented in fewer than half of observed cases; specific recommendations for driving safety were evident for a minority of patients, with formal driving evaluation the most frequently documented recommendation by providers. Utilizing data from actual clinical encounters provides a unique snapshot of how driving risk and safety concerns are addressed for veterans with dementia. This information provides a meaningful frame of reference for understanding potential strengths and possible gaps in how this important topic area is being addressed in the course of clinical care. The EMR is an important forum for interprofessional communication, with documentation of driving risk and safety concerns an essential element for continuity of care and ensuring consistency of information delivered to patients and caregivers.

Brief Talk about Lithium-ion Batteries’ Safety and Influencing Factors

Science.gov (United States)

Jin, Cheng

2017-12-01

A brief introduction of the development background, the concept, characteristic and advantages of lithium-ion battery was given. The typical fire accidents about lithium-ion battery in production process, the vehicle with new energy, portable electronic products were summarized. Some important factors for lithium-ion batteries’ safety were emphatically analyzed. Several constructive suggestions on improvement direction were given, meanwhile, we have a nice exception on the future of lithium-ion battery industry.

Effects of perioperative briefing and debriefing on patient safety: a prospective intervention study.

Science.gov (United States)

Leong, Katharina Brigitte Margarethe Siew Lan; Hanskamp-Sebregts, Mirelle; van der Wal, Raymond A; Wolff, Andre P

2017-12-14

This study was carried out to improve patient safety in the operating theatre by the introduction of perioperative briefing and debriefing, which focused on an optimal collaboration between surgical team members. A prospective intervention study with one pretest and two post-test measurements: 1 month before and 4 months and 2.5 years after the implementation of perioperative briefing and debriefing, respectively. Operating theatres of a tertiary care hospital with 875 beds in the Netherlands. All members of five surgical teams participated in the perioperative briefing and debriefing. The implementation of perioperative briefing and debriefing from July 2012 to January 2014. The primary outcome was changes in the team climate, measured by the Team Climate Inventory. Secondary outcomes were the experiences of surgical teams with perioperative briefing and debriefing, measured with a structured questionnaire, and the duration of the briefings, measured by an independent observer. Two and a half years after the introduction of perioperative briefing and debriefing, the team climate increased statistically significant (p≤0.05). Members of the five surgical teams strongly agreed with the positive influence of perioperative briefing and debriefing on clear agreements and reminding one another of the agreements of the day. They perceived a higher efficiency of the surgical programme with more operations starting on time and less unexpectedly long operation time. The perioperative briefing took less than 4 min to conduct. Perioperative briefing and debriefing improved the team climate of surgical teams and the efficiency of their work within the operating theatre with acceptable duration per briefing. Surgical teams with alternating team compositions have the most benefit of briefing and debriefing. © 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

Safety KPIs - Monitoring of safety performance

Directory of Open Access Journals (Sweden)

Andrej Lališ

2014-09-01

Full Text Available This paper aims to provide brief overview of aviation safety development focusing on modern trends represented by implementation of Safety Key Performance Indicators. Even though aviation is perceived as safe means of transport, it is still struggling with its complexity given by long-term growth and robustness which it has reached today. Thus nowadays safety issues are much more complex and harder to handle than ever before. We are more and more concerned about organizational factors and control mechanisms which have potential to further increase level of aviation safety. Within this paper we will not only introduce the concept of Key Performance Indicators in area of aviation safety as an efficient control mechanism, but also analyse available legislation and documentation. Finally we will propose complex set of indicators which could be applied to Czech Air Navigation Service Provider.

Effects of perioperative briefing and debriefing on patient safety: a prospective intervention study.

NARCIS (Netherlands)

Leong, K.B.M.S.L.; Hanskamp-Sebregts, M.E.; Wal, R.A. van der; Wolff, AP

2017-01-01

OBJECTIVES: This study was carried out to improve patient safety in the operating theatre by the introduction of perioperative briefing and debriefing, which focused on an optimal collaboration between surgical team members. DESIGN: A prospective intervention study with one pretest and two post-test

Brief review: sleep health and safety for transportation workers

Directory of Open Access Journals (Sweden)

Quan SF

2015-03-01

Full Text Available Accidents related to sleepiness related fatigue are an important concern in transportation related industries. This brief review outlines the public safety concerns with sleepiness related fatigue in the railroad, aviation and motor vehicle transportation fields. In addition, the common causes of sleepiness related fatigue, and impact on operators and their families are highlighted. It is suggested that in addition to greater recognition and changes in duty hour regulations, there should be a greater emphasis on the education of operators on the importance of sleep and circadian factors in causing fatigue, as well as strategies to mitigate their impact.

Safety principles for nuclear power plants

International Nuclear Information System (INIS)

Vuorinen, A.

1993-01-01

The role and purpose of safety principles for nuclear power plants are discussed. A brief information is presented on safety objectives as given in the INSAG documents. The possible linkage is discussed between the two mentioned elements of nuclear safety and safety culture. Safety culture is a rather new concept and there is more than one interpretation of the definition given by INSAG. The defence in depth is defined by INSAG as a fundamental principle of safety technology of nuclear power. Discussed is the overall strategy for safety measures, and features of nuclear power plants provided by the defence-in-depth concept. (Z.S.) 7 refs

Safety Review Committee - Annual Report 1991-1992

International Nuclear Information System (INIS)

1993-01-01

During the year under review. The Safety Review Committee (SRC) assessed the safety of ANSTO's operations. This was done by site visits, examination of documentation and briefing by ANSTO officers responsible for particular operations, and includes HIFAR and Moata reactors, radioisotope production, packing and dispatch, radioactive waste management practices, occupational health and safety activities and ANSTO's arrangements for public health and safety beyond the site. This report describes the activities and findings of the SRC during the year ending 30 June 1992. 8 figs., ills

Transportation Safety Excellence in Operations Through Improved Transportation Safety Document

International Nuclear Information System (INIS)

Dr. Michael A. Lehto; MAL

2007-01-01

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

Implementing 10 CFR 830 at the FEMP Silos: Nuclear Health and Safety Plans as Documented Safety Analysis

International Nuclear Information System (INIS)

Fisk, Patricia; Rutherford, Lavon

2003-01-01

The objective of the Silos Project at the Fernald Closure Project (FCP) is to safely remediate high-grade uranium ore residues (Silos 1 and 2) and metal oxide residues (Silo 3). The evolution of Documented Safety Analyses (DSAs) for these facilities has reflected the changes in remediation processes. The final stage in silos DSAs is an interpretation of 10 CFR 830 Safe Harbor Requirements that combines a Health and Safety Plan with nuclear safety requirements. This paper will address the development of a Nuclear Health and Safety Plan, or N-HASP

LESSONS LEARNED IN DEVELOPMENT OF THE HANFORD SWOC MASTER DOCUMENTED SAFETY ANALYSIS (MDSA) and IMPLEMENTATION VALIDATION REVIEW (IVR)

International Nuclear Information System (INIS)

MORENO, M.R.

2004-01-01

DOE set clear expectations on a cost-effective approach for achieving compliance with the Nuclear Safety Management requirements (20 CFR 830, Nuclear Safety Rule), which ensured long-term benefit to Hanford, via issuance of a nuclear safety strategy in February 2003. To facilitate implementation of these expectations, tools were developed to streamline and standardize safety analysis and safety document development with the goal of a shorter and more predictable DOE approval cycle. A Hanford Safety Analysis and Risk Assessment Handbook (SARAH) was approved to standardize methodologies for development of safety analyses. A Microsoft Excel spreadsheet (RADIDOSE) was approved for the evaluation of radiological consequences for accident scenarios often postulated at Hanford. Standard safety management program chapters were approved for use as a means of compliance with the programmatic chapters of DOE-STD-3009, ''Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports''. An in-process review was developed between DOE and the Contractor to facilitate DOE approval and provide early course correction. The new Documented Safety Analysis (DSA) developed to address the operations of four facilities within the Solid Waste Operations Complex (SWOC) necessitated development of an Implementation Validation Review (IVR) process. The IVR process encompasses the following objectives: safety basis controls and requirements are adequately incorporated into appropriate facility documents and work instructions, facility personnel are knowledgeable of controls and requirements, and the DSA/TSR controls have been implemented. Based on DOE direction and safety analysis tools, four waste management nuclear facilities were integrated into one safety basis document. With successful completion of implementation of this safety document, lessons-learned from the in-process review, safety analysis tools and IVR process were documented for future action

Review of Policy Documents for Nuclear Safety and Regulation

International Nuclear Information System (INIS)

Kim, Woong Sik; Choi, Kwang Sik; Choi, Young Sung; Kim, Hho Jung; Kim, Ho Ki

2006-01-01

The goal of regulation is to protect public health and safety as well as environment from radiological hazards that may occur as a result of the use of atomic energy. In September 1994, the Korean government issued the Nuclear Safety Policy Statement (NSPS) to establish policy goals of maintaining and achieving high-level of nuclear safety and also help the public understand the national policy and a strong will of the government toward nuclear safety. It declares the importance of establishing safety culture in nuclear community and also specifies five nuclear regulatory principles (Independence, Openness, Clarity, Efficiency and Reliability) and provides the eleven regulatory policy directions. In 2001, the Nuclear Safety Charter was declared to make the highest goal of safety in driving nuclear business clearer; to encourage atomic energy- related institutions and workers to keep in mind the mission and responsibility for assuring safety; to guarantee public confidence in related organizations. The Ministry of Science and Technology (MOST) also issues Yearly Regulatory Policy Directions at the beginning of every year. Recently, the third Atomic Energy Promotion Plan (2007-2011) has been established. It becomes necessary for the relevant organizations to prepare the detailed plans on such areas as nuclear development, safety management, regulation, etc. This paper introduces a multi-level structure of nuclear safety and regulation policy documents in Korea and presents some improvements necessary for better application of the policies

Review of Policy Documents for Nuclear Safety and Regulation

Energy Technology Data Exchange (ETDEWEB)

Kim, Woong Sik; Choi, Kwang Sik; Choi, Young Sung; Kim, Hho Jung; Kim, Ho Ki [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of)

2006-07-01

The goal of regulation is to protect public health and safety as well as environment from radiological hazards that may occur as a result of the use of atomic energy. In September 1994, the Korean government issued the Nuclear Safety Policy Statement (NSPS) to establish policy goals of maintaining and achieving high-level of nuclear safety and also help the public understand the national policy and a strong will of the government toward nuclear safety. It declares the importance of establishing safety culture in nuclear community and also specifies five nuclear regulatory principles (Independence, Openness, Clarity, Efficiency and Reliability) and provides the eleven regulatory policy directions. In 2001, the Nuclear Safety Charter was declared to make the highest goal of safety in driving nuclear business clearer; to encourage atomic energy- related institutions and workers to keep in mind the mission and responsibility for assuring safety; to guarantee public confidence in related organizations. The Ministry of Science and Technology (MOST) also issues Yearly Regulatory Policy Directions at the beginning of every year. Recently, the third Atomic Energy Promotion Plan (2007-2011) has been established. It becomes necessary for the relevant organizations to prepare the detailed plans on such areas as nuclear development, safety management, regulation, etc. This paper introduces a multi-level structure of nuclear safety and regulation policy documents in Korea and presents some improvements necessary for better application of the policies.

33 CFR 96.250 - What documents and reports must a safety management system have?

Science.gov (United States)

2010-07-01

... safety management system have? 96.250 Section 96.250 Navigation and Navigable Waters COAST GUARD, DEPARTMENT OF HOMELAND SECURITY VESSEL OPERATING REGULATIONS RULES FOR THE SAFE OPERATION OF VESSELS AND SAFETY MANAGEMENT SYSTEMS Company and Vessel Safety Management Systems § 96.250 What documents and...

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

International Nuclear Information System (INIS)

Batchelor, K.

1996-03-01

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

CP-50 calibration facility radiological safety assessment document

International Nuclear Information System (INIS)

Chilton, M.W.; Hill, R.L.; Eubank, B.F.

1980-03-01

The CP-50 Calibration Facility Radiological Safety Assessment document, prepared at the request of the Nevada Operations Office of the US Department of Energy to satisfy provisions of ERDA Manual Chapter 0531, presents design features, systems controls, and procedures used in the operation of the calibration facility. Site and facility characteristics and routine and non-routine operations, including hypothetical incidents or accidents are discussed and design factors, source control systems, and radiation monitoring considerations are described

Health Information Technology, Patient Safety, and Professional Nursing Care Documentation in Acute Care Settings.

Science.gov (United States)

Lavin, Mary Ann; Harper, Ellen; Barr, Nancy

2015-04-14

The electronic health record (EHR) is a documentation tool that yields data useful in enhancing patient safety, evaluating care quality, maximizing efficiency, and measuring staffing needs. Although nurses applaud the EHR, they also indicate dissatisfaction with its design and cumbersome electronic processes. This article describes the views of nurses shared by members of the Nursing Practice Committee of the Missouri Nurses Association; it encourages nurses to share their EHR concerns with Information Technology (IT) staff and vendors and to take their place at the table when nursing-related IT decisions are made. In this article, we describe the experiential-reflective reasoning and action model used to understand staff nurses' perspectives, share committee reflections and recommendations for improving both documentation and documentation technology, and conclude by encouraging nurses to develop their documentation and informatics skills. Nursing issues include medication safety, documentation and standards of practice, and EHR efficiency. IT concerns include interoperability, vendors, innovation, nursing voice, education, and collaboration.

ESRS guidelines for software safety reviews. Reference document for the organization and conduct of Engineering Safety Review Services (ESRS) on software important to safety in nuclear power plants

International Nuclear Information System (INIS)

2000-01-01

The IAEA provides safety review services to assist Member States in the application of safety standards and, in particular, to evaluate and facilitate improvements in nuclear power plant safety performance. Complementary to the Operational Safety Review Team (OSART) and the International Regulatory Review Team (IRRT) services are the Engineering Safety Review Services (ESRS), which include reviews of siting, external events and structural safety, design safety, fire safety, ageing management and software safety. Software is of increasing importance to safety in nuclear power plants as the use of computer based equipment and systems, controlled by software, is increasing in new and older plants. Computer based devices are used in both safety related applications (such as process control and monitoring) and safety critical applications (such as reactor protection). Their dependability can only be ensured if a systematic, fully documented and reviewable engineering process is used. The ESRS on software safety are designed to assist a nuclear power plant or a regulatory body of a Member State in the review of documentation relating to the development, application and safety assessment of software embedded in computer based systems important to safety in nuclear power plants. The software safety reviews can be tailored to the specific needs of the requesting organization. Examples of such reviews are: project planning reviews, reviews of specific issues and reviews prior final acceptance. This report gives information on the possible scope of ESRS software safety reviews and guidance on the organization and conduct of the reviews. It is aimed at Member States considering these reviews and IAEA staff and external experts performing the reviews. The ESRS software safety reviews evaluate the degree to which software documents show that the development process and the final product conform to international standards, guidelines and current practices. Recommendations are

IMPLEMENTING CHANGES TO AN APPROVED AND IN-USE DOCUMENTED SAFETY ANALYSIS

International Nuclear Information System (INIS)

KING JP

2008-01-01

The Plutonium Finishing Plant (PFP) has refined a process to ensure a comprehensive and complete DSA/TSR change implementation. Successful Nuclear Facility Safety Basis implementation is essential to avoid creating a Potential Inadequacy in Safety Analysis (PISA) situation, or implementing a facility into a non-compliance that can result in a TSR violation. Once past initial implementation, additional changes to Documented Safety Analysis (DSA) and Technical Safety Requirements (TSRs) are often needed due to needed requirement clarifications, operating experience indicating that Conditions/Required Actions/Surveillance Requirements could be improved, changes in facility conditions, or changes in facility mission etc. An effective change implementation process is essential to ensuring compliance with 10 CFR 830.202(a), 'The contractor responsible for a hazard category 1,2, or 3 DOE nuclear facility must establish and maintain the safety basis for the facility'

Documented Safety Analysis for the B695 Segment

Energy Technology Data Exchange (ETDEWEB)

Laycak, D

2008-09-11

This Documented Safety Analysis (DSA) was prepared for the Lawrence Livermore National Laboratory (LLNL) Building 695 (B695) Segment of the Decontamination and Waste Treatment Facility (DWTF). The report provides comprehensive information on design and operations, including safety programs and safety structures, systems and components to address the potential process-related hazards, natural phenomena, and external hazards that can affect the public, facility workers, and the environment. Consideration is given to all modes of operation, including the potential for both equipment failure and human error. The facilities known collectively as the DWTF are used by LLNL's Radioactive and Hazardous Waste Management (RHWM) Division to store and treat regulated wastes generated at LLNL. RHWM generally processes low-level radioactive waste with no, or extremely low, concentrations of transuranics (e.g., much less than 100 nCi/g). Wastes processed often contain only depleted uranium and beta- and gamma-emitting nuclides, e.g., {sup 90}Sr, {sup 137}Cs, or {sup 3}H. The mission of the B695 Segment centers on container storage, lab-packing, repacking, overpacking, bulking, sampling, waste transfer, and waste treatment. The B695 Segment is used for storage of radioactive waste (including transuranic and low-level), hazardous, nonhazardous, mixed, and other waste. Storage of hazardous and mixed waste in B695 Segment facilities is in compliance with the Resource Conservation and Recovery Act (RCRA). LLNL is operated by the Lawrence Livermore National Security, LLC, for the Department of Energy (DOE). The B695 Segment is operated by the RHWM Division of LLNL. Many operations in the B695 Segment are performed under a Resource Conservation and Recovery Act (RCRA) operation plan, similar to commercial treatment operations with best demonstrated available technologies. The buildings of the B695 Segment were designed and built considering such operations, using proven building

Documented Safety Analysis for the B695 Segment

International Nuclear Information System (INIS)

Laycak, D.

2008-01-01

This Documented Safety Analysis (DSA) was prepared for the Lawrence Livermore National Laboratory (LLNL) Building 695 (B695) Segment of the Decontamination and Waste Treatment Facility (DWTF). The report provides comprehensive information on design and operations, including safety programs and safety structures, systems and components to address the potential process-related hazards, natural phenomena, and external hazards that can affect the public, facility workers, and the environment. Consideration is given to all modes of operation, including the potential for both equipment failure and human error. The facilities known collectively as the DWTF are used by LLNL's Radioactive and Hazardous Waste Management (RHWM) Division to store and treat regulated wastes generated at LLNL. RHWM generally processes low-level radioactive waste with no, or extremely low, concentrations of transuranics (e.g., much less than 100 nCi/g). Wastes processed often contain only depleted uranium and beta- and gamma-emitting nuclides, e.g., 90 Sr, 137 Cs, or 3 H. The mission of the B695 Segment centers on container storage, lab-packing, repacking, overpacking, bulking, sampling, waste transfer, and waste treatment. The B695 Segment is used for storage of radioactive waste (including transuranic and low-level), hazardous, nonhazardous, mixed, and other waste. Storage of hazardous and mixed waste in B695 Segment facilities is in compliance with the Resource Conservation and Recovery Act (RCRA). LLNL is operated by the Lawrence Livermore National Security, LLC, for the Department of Energy (DOE). The B695 Segment is operated by the RHWM Division of LLNL. Many operations in the B695 Segment are performed under a Resource Conservation and Recovery Act (RCRA) operation plan, similar to commercial treatment operations with best demonstrated available technologies. The buildings of the B695 Segment were designed and built considering such operations, using proven building systems, and keeping

USAEC Controls for Nuclear Criticality Safety

Energy Technology Data Exchange (ETDEWEB)

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

1966-05-15

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

Probabilistic safety analysis and radiological protection

International Nuclear Information System (INIS)

Guimaraes, A.C.F.; Goes, A.G.A.

1990-05-01

The author presents a brief description of NUREG-1150 and NUREG-0956, both documents of great importance in the risk area. Based on document's recommendations and following NUREG-1150 similar methodology, a calculation model is proposed in this publication, with the purpose of analyzing the consequences of a severe accident in Angra-I Power Station. The suggested model can be divided in two stages: the first one called front-end considers the power station system safety during the accident, and the second called back-end cares for accident consequences. 9 refs. (B.C.A.)

Status of High Flux Isotope Reactor (HFIR) post-restart safety analysis and documentation upgrades

International Nuclear Information System (INIS)

Cook, D.H.; Radcliff, T.D.; Rothrock, R.B.; Schreiber, R.E.

1990-01-01

The High Flux Isotope Reactor (HFIR), an experimental reactor located at the Oak Ridge National Laboratory (ORNL) and operated for the US Department of Energy by Martin Marietta Energy Systems, was shut down in November, 1986 after the discovery of unexpected neutron embrittlement of the reactor vessel. The reactor was restarted in April, 1989, following an extensive review by DOE and ORNL of the HFIR design, safety, operation, maintenance and management, and the implementation of several upgrades to HFIR safety-related hardware, analyses, documents and procedures. This included establishing new operating conditions to provide added margin against pressure vessel failure, as well as the addition, or upgrading, of specific safety-related hardware. This paper summarizes the status of some of the follow-on (post-restart) activities which are currently in progress, and which will result in a comprehensive set of safety analyses and documentation for the HFIR, comparable with current practice in commercial nuclear power plants. 8 refs

Analysis of compatibility of current Czech initial documentation in the area of technical assurance of nuclear safety with the requirements of the EUR document

International Nuclear Information System (INIS)

Zdebor, J.; Zdebor, R.; Kratochvil, L.

2001-11-01

The publication is structured as follows: Description of existing documentation. General requirements, goals, principles and design principles: Documents being compared; Method of comparison; Results and partial evaluation of comparison of requirements between EUR and Czech regulations (basic goals and safety philosophy; quantitative safety objectives; basic design requirements; extended design requirements; external and internal threats; technical requirements; site conditions); Summary of the comparison of safety requirements. Comparison of requirements for the systems: Requirements for the nuclear reactor unit systems; Barrier systems (fuel system; reactor cooling system; containment system); Remaining systems (control systems; protection systems; coolant makeup and purification system; residual heat removal system; emergency cooling system; power systems); Common technical requirements for systems (technical requirements for systems; internal and external events). (P.A.)

THE FORMATION OF THE CONTOUR OF THE DOCUMENTED AND REAL FLIGHT SAFETY IN THE SYSTEM OF THE INFORMATION PROVISION OF SAFETY OF FLIGHTS

Directory of Open Access Journals (Sweden)

B. I. Bachkalo

2015-01-01

Full Text Available The article discusses the principles and mechanisms of formation of the contour of the real safety of flights and contour of the documented safety, allowing us to obtain information to control fligh safety. The proposed approach can be used in the algorithms of active on-board flight safety management system for the implementation of information support to the crew in flight and automatic control of flight safety.

Planning Document for an NBSR Conversion Safety Analysis Report

Energy Technology Data Exchange (ETDEWEB)

Diamond D. J.; Baek J.; Hanson, A.L.; Cheng, L-Y.; Brown, N.; Cuadra, A.

2013-09-25

The NIST Center for Neutron Research (NCNR) is a reactor-laboratory complex providing the National Institute of Standards and Technology (NIST) and the nation with a world-class facility for the performance of neutron-based research. The heart of this facility is the National Bureau of Standards Reactor (NBSR). The NBSR is a heavy water moderated and cooled reactor operating at 20 MW. It is fueled with high-enriched uranium (HEU) fuel elements. A Global Threat Reduction Initiative (GTRI) program is underway to convert the reactor to low-enriched uranium (LEU) fuel. This program includes the qualification of the proposed fuel, uranium and molybdenum alloy foil clad in an aluminum alloy, and the development of the fabrication techniques. This report is a planning document for the conversion Safety Analysis Report (SAR) that would be submitted to, and approved by, the Nuclear Regulatory Commission (NRC) before the reactor could be converted.This report follows the recommended format and content from the NRC codified in NUREG-1537, “Guidelines for Preparing and Reviewing Applications for the Licensing of Non-power Reactors,” Chapter 18, “Highly Enriched to Low-Enriched Uranium Conversions.” The emphasis herein is on the SAR chapters that require significant changes as a result of conversion, primarily Chapter 4, Reactor Description, and Chapter 13, Safety Analysis. The document provides information on the proposed design for the LEU fuel elements and identifies what information is still missing. This document is intended to assist ongoing fuel development efforts, and to provide a platform for the development of the final conversion SAR. This report contributes directly to the reactor conversion pillar of the GTRI program, but also acts as a boundary condition for the fuel development and fuel fabrication pillars.

Computerising documentation

International Nuclear Information System (INIS)

Anon.

1992-01-01

The nuclear power generation industry is faced with public concern and government pressures over safety, efficiency and risk. Operators throughout the industry are addressing these issues with the aid of a new technology - technical document management systems (TDMS). Used for strategic and tactical advantage, the systems enable users to scan, archive, retrieve, store, edit, distribute worldwide and manage the huge volume of documentation (paper drawings, CAD data and film-based information) generated in building, maintaining and ensuring safety in the UK's power plants. The power generation industry has recognized that the management and modification of operation critical information is vital to the safety and efficiency of its power plants. Regulatory pressure from the Nuclear Installations Inspectorate (NII) to operate within strict safety margins or lose Site Licences has prompted the need for accurate, up-to-data documentation. A document capture and management retrieval system provides a powerful cost-effective solution, giving rapid access to documentation in a tightly controlled environment. The computerisation of documents and plans is discussed in this article. (Author)

Lithuanian Nuclear Safety Advisory Committee - 1993-2003

International Nuclear Information System (INIS)

Medeliene, D.

2003-01-01

Brief overview of the Lithuanian Nuclear Safety Advisory Committee (LNSAC) activities is presented. LNSAC was established in May 1993, main task is to advise the Lithuanian government on industrial and regulatory matters of nuclear safety. One of the most of important tasks was to exert pressure on the Government so that it allocates sufficient funds from the national budget for setting up a national regulatory body. Statements of the members of LNSAC are presented. In the CD minutes of the meetings of the LNSAC in 1993-2003 and official documents regulating Committee activities are included

Documented Safety Analysis for the Waste Storage Facilities

Energy Technology Data Exchange (ETDEWEB)

Laycak, D

2008-06-16

This documented safety analysis (DSA) for the Waste Storage Facilities was developed in accordance with 10 CFR 830, Subpart B, 'Safety Basis Requirements', and utilizes the methodology outlined in DOE-STD-3009-94, Change Notice 3. The Waste Storage Facilities consist of Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area portion of the DWTF complex. These two areas are combined into a single DSA, as their functions as storage for radioactive and hazardous waste are essentially identical. The B695 Segment of DWTF is addressed under a separate DSA. This DSA provides a description of the Waste Storage Facilities and the operations conducted therein; identification of hazards; analyses of the hazards, including inventories, bounding releases, consequences, and conclusions; and programmatic elements that describe the current capacity for safe operations. The mission of the Waste Storage Facilities is to safely handle, store, and treat hazardous waste, transuranic (TRU) waste, low-level waste (LLW), mixed waste, combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL (as well as small amounts from other DOE facilities).

The International Criticality Safety Benchmark Evaluation Project on the Internet

International Nuclear Information System (INIS)

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

2000-01-01

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

Considerations on Applying the Method for Assessing the Level of Safety at Work

Directory of Open Access Journals (Sweden)

Costica Bejinariu

2017-07-01

Full Text Available The application of the method for assessing the level of safety at work starts with a document that contains the cover page, the description of the company (name, location, core business, organizational chart etc., description of the work system, a detailed list of its components, and a brief description of the assessment method. It continues with a Microsoft Excel document, which represents the actual application of the method and, finally, there is another document presenting conclusions, proposals, and prioritizations, which leads to the execution of the Prevention and Protection Plan. The present paper approaches the issue of developing the Microsoft Excel document, an essential part of the method for assessing the level of safety at work. The document is divided into a variable number of worksheets, showing the risk categories of general, specific, and management.

39 CFR 3001.34 - Briefs.

Science.gov (United States)

2010-07-01

..., due regard shall be given to the nature of the proceeding, the complexity and importance of the issues... brief at the same time. In cases where, because of the nature of the issues and the record or the... any other brief, pleading or document. (d) Excerpts from the record. Testimony and exhibits shall not...

ITER final design report, cost review and safety analysis (FDR) and relevant documents

International Nuclear Information System (INIS)

1999-01-01

This volume contains the fourth major milestone report and documents associated with its acceptance, review and approval. This ITER Final Design Report, Cost Review and Safety Analysis was presented to the ITER Council at its 13th meeting in February 1998 and was approved at its extraordinary meeting on 25 June 1998. The contents include an outline of the ITER objectives, the ITER parameters and design overview as well as operating scenarios and plasma performance. Furthermore, design features, safety and environmental characteristics and schedule and cost estimates are given

Documentation for the Waste Reduction Model (WARM)

Science.gov (United States)

This page describes the WARM documentation files and provides links to all documentation files associated with EPA’s Waste Reduction Model (WARM). The page includes a brief summary of the chapters documenting the greenhouse gas emission and energy factors.

Documents preparation and review

International Nuclear Information System (INIS)

1999-01-01

Ignalina Safety Analysis Group takes active role in assisting regulatory body VATESI to prepare various regulatory documents and reviewing safety reports and other documentation presented by Ignalina NPP in the process of licensing of unit 1. The list of main documents prepared and reviewed is presented

Nuclear-power-safety reporting system: feasibility analysis

International Nuclear Information System (INIS)

Finlayson, F.C.; Ims, J.

1983-04-01

The US Nuclear Regulatory Commission (NRC) is evaluating the possibility of instituting a data gathering system for identifying and quantifying the factors that contribute to the occurrence of significant safety problems involving humans in nuclear power plants. This report presents the results of a brief (6 months) study of the feasibility of developing a voluntary, nonpunitive Nuclear Power Safety Reporting System (NPSRS). Reports collected by the system would be used to create a data base for documenting, analyzing and assessing the significance of the incidents. Results of The Aerospace Corporation study are presented in two volumes. This document, Volume I, contains a summary of an assessment of the Aviation Safety Reporting System (ASRS). The FAA-sponsored, NASA-managed ASRS was found to be successful, relatively low in cost, generally acceptable to all facets of the aviation community, and the source of much useful data and valuable reports on human factor problems in the nation's airways. Several significant ASRS features were found to be pertinent and applicable for adoption into a NPSRS

The practical implementation of integrated safety management for nuclear safety analysis and fire hazards analysis documentation

International Nuclear Information System (INIS)

COLLOPY, M.T.

1999-01-01

the integrated safety management system approach for having a uniform and consistent process: a method has been suggested by the U S . Department of Energy at Richland and the Project Hanford Procedures when fire hazard analyses and safety analyses are required. This process provides for a common basis approach in the development of the fire hazard analysis and the safety analysis. This process permits the preparers of both documents to jointly participate in the development of the hazard analysis process. This paper presents this method to implement the integrated safety management approach in the development of the fire hazard analysis and safety analysis that provides consistency of assumptions. consequences, design considerations, and other controls necessarily to protect workers, the public. and the environment

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

Documented Safety Analysis for the Waste Storage Facilities March 2010

Energy Technology Data Exchange (ETDEWEB)

Laycak, D T

2010-03-05

This Documented Safety Analysis (DSA) for the Waste Storage Facilities was developed in accordance with 10 CFR 830, Subpart B, 'Safety Basis Requirements,' and utilizes the methodology outlined in DOE-STD-3009-94, Change Notice 3. The Waste Storage Facilities consist of Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area portion of the DWTF complex. These two areas are combined into a single DSA, as their functions as storage for radioactive and hazardous waste are essentially identical. The B695 Segment of DWTF is addressed under a separate DSA. This DSA provides a description of the Waste Storage Facilities and the operations conducted therein; identification of hazards; analyses of the hazards, including inventories, bounding releases, consequences, and conclusions; and programmatic elements that describe the current capacity for safe operations. The mission of the Waste Storage Facilities is to safely handle, store, and treat hazardous waste, transuranic (TRU) waste, low-level waste (LLW), mixed waste, combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL (as well as small amounts from other DOE facilities).

Selling safety: the use of celebrities in improving awareness of safety in commercial aviation.

Science.gov (United States)

Molesworth, Brett R C; Seneviratne, Dimuth; Burgess, Marion

2016-07-01

The aim of this study was to investigate the influential power of a celebrity to convey key safety messages in commercial aviation using a pre-flight safety briefing video. In addition, the present research sought to examine the effectiveness of subtitles in aiding the recall of these important messages as well as how in-cabin aircraft noise affects recall of this information. A total of 101 participants were randomly divided into four groups (no noise without subtitles, no noise with subtitles, noise without subtitles and noise with subtitles) and following exposure to a pre-recorded pre-flight safety briefing video were tested for recall of key safety messages within that video. Participants who recognised and recalled the name of the celebrity in the safety briefing video recalled significantly more of the messages than participants who did not recognise the celebrity. Subtitles were also found to be effective, however, only in the presence of representative in-cabin aircraft noise. Practitioner Summary: Passenger attention to pre-flight safety briefings on commercial aircraft is poor. Utilising the celebrity status of a famous person may overcome this problem. Results suggest that celebrities do increase the recall of safety-related information.

Hazardous Waste/Mixed Waste Treatment Building Safety Information Document (SID)

International Nuclear Information System (INIS)

Fatell, L.B.; Woolsey, G.B.

1993-01-01

This Safety Information Document (SID) provides a description and analysis of operations for the Hazardous Waste/Mixed Waste Disposal Facility Treatment Building (the Treatment Building). The Treatment Building has been classified as a moderate hazard facility, and the level of analysis performed and the methodology used are based on that classification. Preliminary design of the Treatment Building has identified the need for two separate buildings for waste treatment processes. The term Treatment Building applies to all these facilities. The evaluation of safety for the Treatment Building is accomplished in part by the identification of hazards associated with the facility and the analysis of the facility's response to postulated events involving those hazards. The events are analyzed in terms of the facility features that minimize the causes of such events, the quantitative determination of the consequences, and the ability of the facility to cope with each event should it occur. The SID presents the methodology, assumptions, and results of the systematic evaluation of hazards associated with operation of the Treatment Building. The SID also addresses the spectrum of postulated credible events, involving those hazards, that could occur. Facility features important to safety are identified and discussed in the SID. The SID identifies hazards and reports the analysis of the spectrum of credible postulated events that can result in the following consequences: Personnel exposure to radiation; Radioactive material release to the environment; Personnel exposure to hazardous chemicals; Hazardous chemical release to the environment; Events leading to an onsite/offsite fatality; and Significant damage to government property. The SID addresses the consequences to the onsite and offsite populations resulting from postulated credible events and the safety features in place to control and mitigate the consequences

Hazardous Waste/Mixed Waste Treatment Building Safety Information Document (SID)

Energy Technology Data Exchange (ETDEWEB)

Fatell, L.B.; Woolsey, G.B.

1993-04-15

This Safety Information Document (SID) provides a description and analysis of operations for the Hazardous Waste/Mixed Waste Disposal Facility Treatment Building (the Treatment Building). The Treatment Building has been classified as a moderate hazard facility, and the level of analysis performed and the methodology used are based on that classification. Preliminary design of the Treatment Building has identified the need for two separate buildings for waste treatment processes. The term Treatment Building applies to all these facilities. The evaluation of safety for the Treatment Building is accomplished in part by the identification of hazards associated with the facility and the analysis of the facility`s response to postulated events involving those hazards. The events are analyzed in terms of the facility features that minimize the causes of such events, the quantitative determination of the consequences, and the ability of the facility to cope with each event should it occur. The SID presents the methodology, assumptions, and results of the systematic evaluation of hazards associated with operation of the Treatment Building. The SID also addresses the spectrum of postulated credible events, involving those hazards, that could occur. Facility features important to safety are identified and discussed in the SID. The SID identifies hazards and reports the analysis of the spectrum of credible postulated events that can result in the following consequences: Personnel exposure to radiation; Radioactive material release to the environment; Personnel exposure to hazardous chemicals; Hazardous chemical release to the environment; Events leading to an onsite/offsite fatality; and Significant damage to government property. The SID addresses the consequences to the onsite and offsite populations resulting from postulated credible events and the safety features in place to control and mitigate the consequences.

Area 5 Radioactive Waste Management Site Safety Assessment Document

International Nuclear Information System (INIS)

Horton, K.K.; Kendall, E.W.; Brown, J.J.

1980-02-01

The Area 5 Radioactive Waste Management Safety Assessment Document evaluates site characteristics, facilities and operating practices which contribute to the safe handling and storage/disposal of radioactive wastes at the Nevada Test Site. Physical geography, cultural factors, climate and meteorology, geology, hydrology (with emphasis on radionuclide migration), ecology, natural phenomena, and natural resources are discussed and determined to be suitable for effective containment of radionuclides. Also considered, as a separate section, are facilities and operating practices such as monitoring; storage/disposal criteria; site maintenance, equipment, and support; transportation and waste handling; and others which are adequate for the safe handling and storage/disposal of radioactive wastes. In conclusion, the Area 5 Radioactive Waste Management Site is suitable for radioactive waste handling and storage/disposal for a maximum of twenty more years at the present rate of utilization

Reactor operation safety information document

Energy Technology Data Exchange (ETDEWEB)

1990-01-01

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

Documenting Quality Improvement and Patient Safety Efforts: The Quality Portfolio. A Statement from the Academic Hospitalist Taskforce

OpenAIRE

Taylor, Benjamin B.; Parekh, Vikas; Estrada, Carlos A.; Schleyer, Anneliese; Sharpe, Bradley

2013-01-01

Physicians increasingly investigate, work, and teach to improve the quality of care and safety of care delivery. The Society of General Internal Medicine Academic Hospitalist Task Force sought to develop a practical tool, the quality portfolio, to systematically document quality and safety achievements. The quality portfolio was vetted with internal and external stakeholders including national leaders in academic medicine. The portfolio was refined for implementation to include an outlined fr...

Seismic safety margin research program. Program plan, Revision II

International Nuclear Information System (INIS)

Smith, P.D.; Tokarz, F.J.; Bernreuter, D.L.; Cummings, G.E.; Chou, C.K.; Vagliente, V.N.; Johnson, J.J.; Dong, R.G.

1978-01-01

The document has been prepared pursuant to the second meeting of the Senior Research Review Group of the Seismic Safety Margin Research Program (SSMRP), which was held on June 15, 16, 1978. The major portion of the material contained in the document is descriptions of specific subtasks to be performed on the SSMRP. This is preceded by a brief discussion of the objective of the SSMRP and the approach to be used. Specific subtasks to be performed in Phase I of the SSMRP are as follows: (1) plant/site selection, (2) seismic input, (3) soil structure interaction, (4) structural building response, (5) structural sub-system response, (6) fragility, (7) system analysis, and (8) Phase II task definition

National report of the Slovak Republic. Compiled in terms of the convention on nuclear safety. September 2004

International Nuclear Information System (INIS)

Balaj, J.; Jurina, V.; Kasana, A.

2004-09-01

A brief national safety report of the Slovak Republic in 2004 is presented. A account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD) is presented. These activities are reported under the headings: (1) Introduction; (2) Nuclear installations in Slovakia according to the convention; (3) Legislation and regulation; (4) General safety aspects; (5) Safety of nuclear installations in Slovakia; (6) Annexes: 6.1 List of nuclear installations and technical and economic parameters; 6.2 Some generally binding legal documents concerning nuclear and radiation safety; 6.3 Limits of radioactive discharges; 6.4 Author team. Contents, list of abbreviations used as well as reference index are included

FLAMMABLE GAS TECHNICAL BASIS DOCUMENT

Energy Technology Data Exchange (ETDEWEB)

KRIPPS, L.J.

2005-03-03

This document describes the qualitative evaluation of frequency and consequences for DST and SST representative flammable gas accidents and associated hazardous conditions without controls. The evaluation indicated that safety-significant structures, systems and components (SSCs) and/or technical safety requirements (TSRs) were required to prevent or mitigate flammable gas accidents. Discussion on the resulting control decisions is included. This technical basis document was developed to support WP-13033, Tank Farms Documented Safety Analysis (DSA), and describes the risk binning process for the flammable gas representative accidents and associated represented hazardous conditions. The purpose of the risk binning process is to determine the need for safety-significant structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls for a given representative accident or represented hazardous condition based on an evaluation of the event frequency and consequence.

Guidance and Control Software Project Data - Volume 2: Development Documents

Science.gov (United States)

Hayhurst, Kelly J. (Editor)

2008-01-01

The Guidance and Control Software (GCS) project was the last in a series of software reliability studies conducted at Langley Research Center between 1977 and 1994. The technical results of the GCS project were recorded after the experiment was completed. Some of the support documentation produced as part of the experiment, however, is serving an unexpected role far beyond its original project context. Some of the software used as part of the GCS project was developed to conform to the RTCA/DO-178B software standard, "Software Considerations in Airborne Systems and Equipment Certification," used in the civil aviation industry. That standard requires extensive documentation throughout the software development life cycle, including plans, software requirements, design and source code, verification cases and results, and configuration management and quality control data. The project documentation that includes this information is open for public scrutiny without the legal or safety implications associated with comparable data from an avionics manufacturer. This public availability has afforded an opportunity to use the GCS project documents for DO-178B training. This report provides a brief overview of the GCS project, describes the 4-volume set of documents and the role they are playing in training, and includes the development documents from the GCS project. Volume 2 contains three appendices: A. Guidance and Control Software Development Specification; B. Design Description for the Pluto Implementation of the Guidance and Control Software; and C. Source Code for the Pluto Implementation of the Guidance and Control Software

Development of Onsite Transportation Safety Documents for Nevada Test Site

International Nuclear Information System (INIS)

Frank Hand; Willard Thomas; Frank Sciacca; Manny Negrete; Susan Kelley

2008-01-01

Department of Energy (DOE) Orders require each DOE site to develop onsite transportation safety documents (OTSDs). The Nevada Test Site approach divided all onsite transfers into two groups with each group covered by a standalone OTSD identified as Non-Nuclear and Nuclear. The Non-Nuclear transfers involve all radioactive hazardous material in less than Hazard Category (HC)-3 quantities and all chemically hazardous materials. The Nuclear transfers involve all radioactive material equal to or greater than HC-3 quantities and radioactive material mated with high explosives regardless of quantity. Both OTSDs comply with DOE O 460.1B requirements. The Nuclear OTSD also complies with DOE O 461.1A requirements and includes a DOE-STD-3009 approach to hazard analysis (HA) and accident analysis as needed. All Nuclear OTSD proposed transfers were determined to be non-equivalent and a methodology was developed to determine if 'equivalent safety' to a fully compliant Department of Transportation (DOT) transfer was achieved. For each HA scenario, three hypothetical transfers were evaluated: a DOT-compliant, uncontrolled, and controlled transfer. Equivalent safety is demonstrated when the risk level for each controlled transfer is equal to or less than the corresponding DOT-compliant transfer risk level. In this comparison the typical DOE-STD-3009 risk matrix was modified to reflect transportation requirements. Design basis conditions (DBCs) were developed for each non-equivalent transfer. Initial DBCs were based solely upon the amount of material present. Route-, transfer-, and site-specific conditions were evaluated and the initial DBCs revised as needed. Final DBCs were evaluated for each transfer's packaging and its contents

CERN's new safety policy

CERN Multimedia

2014-01-01

The documents below, published on 29 September 2014 on the HSE website, together replace the document SAPOCO 42 as well as Safety Codes A1, A5, A9, A10, which are no longer in force. As from the publication date of these documents any reference made to the document SAPOCO 42 or to Safety Codes A1, A5, A9 and A10 in contractual documents or CERN rules and regulations shall be deemed to constitute a reference to the corresponding provisions of the documents listed below.   "The CERN Safety Policy" "Safety Regulation SR-SO - Responsibilities and organisational structure in matters of Safety at CERN" "General Safety Instruction GSI-SO-1 - Departmental Safety Officer (DSO)" "General Safety Instruction GSI-SO-2 - Territorial Safety Officer (TSO)" "General Safety Instruction GSI-SO-3 - Safety Linkperson (SLP)" "General Safety Instruction GSI-SO-4 - Large Experiment Group Leader In Matters of Safety (LEXGLI...

National report of the Slovak Republic compiled according to the terms of the convention on nuclear safety

International Nuclear Information System (INIS)

Adamovsky, V.; Betak, A.; Balaj, J.; Bystricka, S.; Grebeciova, J.; Husarcek, J.; Metke, E.; Pospisil, M.; Smrtnik, I.; Turner, M.; Uhrik, P.; Zemanova, D.; Bulla, R.; Filip, A.; Jurina, V.; Sedlak, M.; Tomek, J.; Zimermann, M.

2013-06-01

A brief safety report of the Slovak Republic in 2013 is presented. A account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD) is presented. These activities are reported under the headings: (1) Introduction; (2) Nuclear installations in Slovak Republic in terms of the convention; (3) Legislation and regulation; (4) General safety aspects; (5) Safety of nuclear installations in the Slovak Republic; ((6) Annexes; (6.1) List of nuclear installations and technical and economic indicators; (6.2) Selected generally binding legal regulations and safety guidelines in relation to nuclear and radiation safety; (6.3) List of selected national and international documents applicable to safety of nuclear installations; (6.4) Limits for radioactive discharges; (6.5) IAEA Action Plan on Nuclear Safety; (6.6) Team of authors.

School Survey on Crime and Safety (SSOCS) 2000 Public-Use Data Files, User's Manual, and Detailed Data Documentation. [CD-ROM].

Science.gov (United States)

National Center for Education Statistics (ED), Washington, DC.

This CD-ROM contains the raw, public-use data from the 2000 School Survey on Crime and Safety (SSOCS) along with a User's Manual and Detailed Data Documentation. The data are provided in SAS, SPSS, STATA, and ASCII formats. The User's Manual and the Detailed Data Documentation are provided as .pdf files. (Author)

FLAMMABLE GAS TECHNICAL BASIS DOCUMENT

Energy Technology Data Exchange (ETDEWEB)

KRIPPS, L.J.

2005-02-18

This document describes the qualitative evaluation of frequency and consequences for double shell tank (DST) and single shell tank (SST) representative flammable gas accidents and associated hazardous conditions without controls. The evaluation indicated that safety-significant SSCs and/or TSRS were required to prevent or mitigate flammable gas accidents. Discussion on the resulting control decisions is included. This technical basis document was developed to support of the Tank Farms Documented Safety Analysis (DSA) and describes the risk binning process for the flammable gas representative accidents and associated represented hazardous conditions. The purpose of the risk binning process is to determine the need for safety-significant structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls for a given representative accident or represented hazardous condition based on an evaluation of the event frequency and consequence.

A document-driven method for certifying scientific computing software for use in nuclear safety analysis

International Nuclear Information System (INIS)

Smith, W. Spencer; Koothoor, Mimitha

2016-01-01

This paper presents a documentation and development method to facilitate the certification of scientific computing software used in the safety analysis of nuclear facilities. To study the problems faced during quality assurance and certification activities, a case study was performed on legacy software used for thermal analysis of a fuel pin in a nuclear reactor. Although no errors were uncovered in the code, 27 issues of incompleteness and inconsistency were found with the documentation. This work proposes that software documentation follow a rational process, which includes a software requirements specification following a template that is reusable, maintainable, and understandable. To develop the design and implementation, this paper suggests literate programming as an alternative to traditional structured programming. Literate programming allows for documenting of numerical algorithms and code together in what is termed the literate programmer's manual. This manual is developed with explicit traceability to the software requirements specification. The traceability between the theory, numerical algorithms, and implementation facilitates achieving completeness and consistency, as well as simplifies the process of verification and the associated certification

A document-driven method for certifying scientific computing software for use in nuclear safety analysis

Energy Technology Data Exchange (ETDEWEB)

Smith, W. Spencer; Koothoor, Mimitha [Computing and Software Department, McMaster University, Hamilton (Canada)

2016-04-15

This paper presents a documentation and development method to facilitate the certification of scientific computing software used in the safety analysis of nuclear facilities. To study the problems faced during quality assurance and certification activities, a case study was performed on legacy software used for thermal analysis of a fuel pin in a nuclear reactor. Although no errors were uncovered in the code, 27 issues of incompleteness and inconsistency were found with the documentation. This work proposes that software documentation follow a rational process, which includes a software requirements specification following a template that is reusable, maintainable, and understandable. To develop the design and implementation, this paper suggests literate programming as an alternative to traditional structured programming. Literate programming allows for documenting of numerical algorithms and code together in what is termed the literate programmer's manual. This manual is developed with explicit traceability to the software requirements specification. The traceability between the theory, numerical algorithms, and implementation facilitates achieving completeness and consistency, as well as simplifies the process of verification and the associated certification.

Review of SKB's Code Documentation and Testing

International Nuclear Information System (INIS)

Hicks, T.W.

2005-01-01

SKB is in the process of developing the SR-Can safety assessment for a KBS 3 repository. The assessment will be based on quantitative analyses using a range of computational codes aimed at developing an understanding of how the repository system will evolve. Clear and comprehensive code documentation and testing will engender confidence in the results of the safety assessment calculations. This report presents the results of a review undertaken on behalf of SKI aimed at providing an understanding of how codes used in the SR 97 safety assessment and those planned for use in the SR-Can safety assessment have been documented and tested. Having identified the codes us ed by SKB, several codes were selected for review. Consideration was given to codes used directly in SKB's safety assessment calculations as well as to some of the less visible codes that are important in quantifying the different repository barrier safety functions. SKB's documentation and testing of the following codes were reviewed: COMP23 - a near-field radionuclide transport model developed by SKB for use in safety assessment calculations. FARF31 - a far-field radionuclide transport model developed by SKB for use in safety assessment calculations. PROPER - SKB's harness for executing probabilistic radionuclide transport calculations using COMP23 and FARF31. The integrated analytical radionuclide transport model that SKB has developed to run in parallel with COMP23 and FARF31. CONNECTFLOW - a discrete fracture network model/continuum model developed by Serco Assurance (based on the coupling of NAMMU and NAPSAC), which SKB is using to combine hydrogeological modelling on the site and regional scales in place of the HYDRASTAR code. DarcyTools - a discrete fracture network model coupled to a continuum model, recently developed by SKB for hydrogeological modelling, also in place of HYDRASTAR. ABAQUS - a finite element material model developed by ABAQUS, Inc, which is used by SKB to model repository buffer

Lifecycle management for nuclear engineering project documents

International Nuclear Information System (INIS)

Zhang Li; Zhang Ming; Zhang Ling

2010-01-01

The nuclear engineering project documents with great quantity and various types of data, in which the relationships of each document are complex, the edition of document update frequently, are managed difficultly. While the safety of project even the nuclear safety is threatened seriously by the false documents and mistakes. In order to ensure the integrality, veracity and validity of project documents, the lifecycle theory of document is applied to build documents center, record center, structure and database of document lifecycle management system. And the lifecycle management is used to the documents of nuclear engineering projects from the production to pigeonhole, to satisfy the quality requirement of nuclear engineering projects. (authors)

National report of the Slovak Republic. Compiled according to the terms of the convention on nuclear safety, June 2010

International Nuclear Information System (INIS)

Balaj, J.; Homola, J.; Rovny, J.; Metke, E.; Zemanova, D.; Grebeciova, J.; Turner, M.; Pospisil, M.; Bystricka, S.; Jurina, V.; Rovny, I.; Soltes, L.; Husarova, M.; Petrovic, J.; Fazekasova, H.; Zizkova, D.; Vagac, M.; Maudry, J.; Hacaj, A.; Betak, A.; Barbaric, M.

2010-06-01

A brief safety report of the Slovak Republic in 2010 is presented. A account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD) is presented.These activities are reported under the headings: (1) Introduction; (2) Nuclear installations in Slovak Republic in terms of the convention; (3) Legislation and regulation; (4) General safety aspects; (5) Safety of nuclear installations in Slovakia; ((6) Annexes; (6.1) List of nuclear installations and technical and economic indicators; (6.2) Selected generally binding legal regulations and safety guidelines in relation to nuclear and radiation safety; (6.3) List of selected national and international documents applicable to safety of nuclear installations; (6.4) Limits for radioactive discharges; (6.5) Team of authors.

Final Safety Analysis Document for Building 693 Chemical Waste Storage Building at Lawrence Livermore National Laboratory

International Nuclear Information System (INIS)

Salazar, R.J.; Lane, S.

1992-02-01

This Safety Analysis Document (SAD) for the Lawrence Livermore National Laboratory (LLNL) Building 693, Chemical Waste Storage Building (desipated as Building 693 Container Storage Unit in the Laboratory's RCRA Part B permit application), provides the necessary information and analyses to conclude that Building 693 can be operated at low risk without unduly endangering the safety of the building operating personnel or adversely affecting the public or the environment. This Building 693 SAD consists of eight sections and supporting appendices. Section 1 presents a summary of the facility designs and operations and Section 2 summarizes the safety analysis method and results. Section 3 describes the site, the facility desip, operations and management structure. Sections 4 and 5 present the safety analysis and operational safety requirements (OSRs). Section 6 reviews Hazardous Waste Management's (HWM) Quality Assurance (QA) program. Section 7 lists the references and background material used in the preparation of this report Section 8 lists acronyms, abbreviations and symbols. Appendices contain supporting analyses, definitions, and descriptions that are referenced in the body of this report

The Inspector General's report on Nuclear Safety and Radiation Protection 2010

International Nuclear Information System (INIS)

2010-01-01

This document is proposed in French and in English. The author reports, comments and discusses the observations he made during 2010 on different aspects or examples regarding nuclear safety management and radioprotection in the EDF Group, the world's largest nuclear operator with 73 reactors in service: safety management, radioprotection, relationship with the French nuclear safety authority (ASN), skills and training, the implementation and action of an integrated nuclear engineering force, the relationship between safety and business efficiency, actors of the health care sector, the case of the Flamanville EPR reactor, the relationships with contractors, fire hazards, and projects aimed at raising standards. He also addresses observations and information about what is going on in the United Kingdom. He comments a radioprotection incident, the case of an uncontrolled dilution, and a railway accident which occurred in 2006. He gives a brief report of missions in China and in the United States

Applications for electronic documents

International Nuclear Information System (INIS)

Beitel, G.A.

1995-01-01

This paper discusses the application of electronic media to documents, specifically Safety Analysis Reports (SARs), prepared for Environmental Restoration and Waste Management (ER ampersand WM) programs being conducted for the Department of Energy (DOE) at the Idaho National Engineering Laboratory (INEL). Efforts are underway to upgrade our document system using electronic format. To satisfy external requirements (DOE, State, and Federal), ER ampersand WM programs generate a complement of internal requirements documents including a SAR and Technical Safety Requirements along with procedures and training materials. Of interest, is the volume of information and the difficulty in handling it. A recently prepared ER ampersand WM SAR consists of 1,000 pages of text and graphics; supporting references add 10,000 pages. Other programmatic requirements documents consist of an estimated 5,000 pages plus references

Implementation in Russia and the European Union of International Safety Standards of Identity Documents with Biometric Data: Legal Regulation and Perspectives

Directory of Open Access Journals (Sweden)

Alexander Grigoryevich Volevodz

2015-01-01

Full Text Available The article contains the findings of a research into particular aspects of use of identity documents with personal biometric data. It considers the international safety standards of documents with biometric data worked out by the International Civil Aviation Organization (ICAO, pursuant to which those data should be included into machine-readable documents used by their holders for travel to various states. It contains the information on the implementation of these international standards in Russian and European Union law. The author has substantiated a conclusion to the effect that the procedure established in Russia for production and issuance, as well as for use of international, diplomatic and service passports identifying the Russian Federation citizen outside the Russian Federation territory, containing electronic information carriers with personal and biometric personal data, currently conforms to the international safety standards of documents with biometric data. The article surveys the experience of introducing domestic biometric identity documents - electronic passports in various countries of the world, and the problems arising therefrom. It substantiates the advantages and disadvantages of determining a passport of the Russian Federation citizen issued in the form of an identity card with an electronic information carrier, as the main document of the Russian Federation citizen identifying him domestically within the country's territory.

The NUSS safety guides in design and the use of computers

International Nuclear Information System (INIS)

Fischer, J.

1986-01-01

After a brief summary of the NUSS programme, the two design guides are discussed which deal with instrumentation and control circuitry. The potential use of computers is covered differently in these guides because of the historical development and more importantly because of the difference in importance to safety of the I and C systems which are dealt with in these papers. The Agency would consider modifications to the existing guides only when sufficient consensus about the use of computers would warrant a revision of the documents. (author)

Drought Resilience and Water Conservation Technical Brief

Science.gov (United States)

In many areas of the US, the frequency, intensity, and duration of drought events are increasing, this brief highlights EPA drought and conservation activities across the nation and includes links to additional materials and reference documents.

Better Science Through Safety.

Science.gov (United States)

Gerlovich, Jack A.; Downs, Gary E.

Following a brief description of the major components found effective in school safety programs (safety management, education, and services) and data on school accidents in Iowa, this book addresses various aspects of safety related to science instruction, emphasizing that responsibility for safety must be shared by both teacher and students.…

Environmental qualification - walkdowns: The documentation of configuration information for safety related components, equipment and systems

International Nuclear Information System (INIS)

Melmer, J.; Waters, M.

1995-01-01

Environmental Qualification walkdowns are conducted to collect field data to verify/validate/document configurations of safety related equipment and systems. This paper describes the process for conducting walkdowns and the justification for using an electronic format. The following are described: a) Background; b) Preparing, executing and processing walkdowns; c) Hardware/software; d) Impact of a paperless system on walkdown execution, maintenance and work planning; e) Other applications for the technology

Technical basis document for natural event hazards

International Nuclear Information System (INIS)

CARSON, D.M.

2003-01-01

This technical basis document was developed to support the Tank Farms Documented Safety Analysis (DSA), and describes the risk binning process and the technical basis for assigning risk bins for natural event hazards (NEH)-initiated representative accident and associated represented hazardous conditions. The purpose of the risk binning process is to determine the need for safety-significant structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls for a given representative accident or represented hazardous conditions based on an evaluation of the frequency and consequence. Note that the risk binning process is not applied to facility workers, because all facility worker hazardous conditions are considered for safety-significant SSCs and/or TSR-level controls. Determination of the need for safety-class SSCs was performed in accordance with DOE-STD-3009-94, ''Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses'', as described in this report

Passengers' perception of the safety demonstration on board an aircraft

Science.gov (United States)

Ruenruoy, Ratchada

The cabin safety demonstration on board an aircraft is one of the methods to provide safety information for passengers before aircraft takeoff. However, passengers' enthusiasm toward safety demonstrations is normally low. Therefore, the study of passengers' perception toward safety briefings on board an aircraft is important in increasing the safety awareness for the travelling public on commercial aircraft. A survey was distributed to measure the perceptions of Middle Tennessee State University (MTSU) faculty and staff, Aerospace students, and international students who have traveled in the last year. It was generally found that watching the cabin safety demonstration before aircraft takeoff was believed to be important for passengers. However, the attention to the safety demonstration remained low because the safety briefings were not good enough in terms of clear communication, particularly in the recorded audio demonstration and the live safety demonstration methods of briefing.

Hanford surplus facilities hazards identification document

International Nuclear Information System (INIS)

Egge, R.G.

1997-01-01

This document provides general safety information needed by personnel who enter and work in surplus facilities managed by Bechtel Hanford, Inc. The purpose of the document is to enhance access control of surplus facilities, educate personnel on the potential hazards associated with these facilities prior to entry, and ensure that safety precautions are taken while in the facility

Specifications for human factors guiding documents

Energy Technology Data Exchange (ETDEWEB)

Rhodes, W; Szlapetis, I; MacGregor, C [Rhodes and Associates Inc., Toronto, ON (Canada)

1995-04-01

This report specifies the content, function and appearance of three proposed human factors guiding documents to be used by the Atomic Energy Control board and its licensees. These three guiding documents, to be developed at a later date, are: (a) Human Factors Process Guide; (b) Human Factors Activities Guide; and (c) Human Factors Design Integration Guide. The specifications were developed by examining the best documents as identified in a previous contract with the AECB (Review of Human Factors Guidelines and Methods by W. Rhodes, I. Szlapetis et al. 1992), and a brief literature review. The best features and content were selected from existing documents and used to develop specifications for the guiding documents. The developer of the actual guides would use these specifications to produce comprehensive and consolidated documents at a later date. (author). 128 ref., 7 figs.

Specifications for human factors guiding documents

International Nuclear Information System (INIS)

Rhodes, W.; Szlapetis, I.; MacGregor, C.

1995-04-01

This report specifies the content, function and appearance of three proposed human factors guiding documents to be used by the Atomic Energy Control board and its licensees. These three guiding documents, to be developed at a later date, are: (a) Human Factors Process Guide; (b) Human Factors Activities Guide; and (c) Human Factors Design Integration Guide. The specifications were developed by examining the best documents as identified in a previous contract with the AECB (Review of Human Factors Guidelines and Methods by W. Rhodes, I. Szlapetis et al. 1992), and a brief literature review. The best features and content were selected from existing documents and used to develop specifications for the guiding documents. The developer of the actual guides would use these specifications to produce comprehensive and consolidated documents at a later date. (author). 128 ref., 7 figs

Big Data Risk Analysis for Rail Safety?

OpenAIRE

Van Gulijk, Coen; Hughes, Peter; Figueres-Esteban, Miguel; Dacre, Marcus; Harrison, Chris; HUD; RSSB

2015-01-01

Computer scientists believe that the enormous amounts of data in the internet will unchain a management revolution of uncanny proportions. Yet, to date, the potential benefit of this revolution is scantily investigated for safety and risk management. This paper gives a brief overview of a research programme that investigates how the new internet-driven data-revolution could benefit safety and risk management for railway safety in the UK. The paper gives a brief overview the current activities...

Guidance and Control Software Project Data - Volume 1: Planning Documents

Science.gov (United States)

Hayhurst, Kelly J. (Editor)

2008-01-01

The Guidance and Control Software (GCS) project was the last in a series of software reliability studies conducted at Langley Research Center between 1977 and 1994. The technical results of the GCS project were recorded after the experiment was completed. Some of the support documentation produced as part of the experiment, however, is serving an unexpected role far beyond its original project context. Some of the software used as part of the GCS project was developed to conform to the RTCA/DO-178B software standard, "Software Considerations in Airborne Systems and Equipment Certification," used in the civil aviation industry. That standard requires extensive documentation throughout the software development life cycle, including plans, software requirements, design and source code, verification cases and results, and configuration management and quality control data. The project documentation that includes this information is open for public scrutiny without the legal or safety implications associated with comparable data from an avionics manufacturer. This public availability has afforded an opportunity to use the GCS project documents for DO-178B training. This report provides a brief overview of the GCS project, describes the 4-volume set of documents and the role they are playing in training, and includes the planning documents from the GCS project. Volume 1 contains five appendices: A. Plan for Software Aspects of Certification for the Guidance and Control Software Project; B. Software Development Standards for the Guidance and Control Software Project; C. Software Verification Plan for the Guidance and Control Software Project; D. Software Configuration Management Plan for the Guidance and Control Software Project; and E. Software Quality Assurance Activities.

Guidance and Control Software Project Data - Volume 3: Verification Documents

Science.gov (United States)

Hayhurst, Kelly J. (Editor)

2008-01-01

The Guidance and Control Software (GCS) project was the last in a series of software reliability studies conducted at Langley Research Center between 1977 and 1994. The technical results of the GCS project were recorded after the experiment was completed. Some of the support documentation produced as part of the experiment, however, is serving an unexpected role far beyond its original project context. Some of the software used as part of the GCS project was developed to conform to the RTCA/DO-178B software standard, "Software Considerations in Airborne Systems and Equipment Certification," used in the civil aviation industry. That standard requires extensive documentation throughout the software development life cycle, including plans, software requirements, design and source code, verification cases and results, and configuration management and quality control data. The project documentation that includes this information is open for public scrutiny without the legal or safety implications associated with comparable data from an avionics manufacturer. This public availability has afforded an opportunity to use the GCS project documents for DO-178B training. This report provides a brief overview of the GCS project, describes the 4-volume set of documents and the role they are playing in training, and includes the verification documents from the GCS project. Volume 3 contains four appendices: A. Software Verification Cases and Procedures for the Guidance and Control Software Project; B. Software Verification Results for the Pluto Implementation of the Guidance and Control Software; C. Review Records for the Pluto Implementation of the Guidance and Control Software; and D. Test Results Logs for the Pluto Implementation of the Guidance and Control Software.

Canister storage building design basis accident analysis documentation

International Nuclear Information System (INIS)

KOPELIC, S.D.

1999-01-01

This document provides the detailed accident analysis to support HNF-3553, Spent Nuclear Fuel Project Final Safety Analysis Report, Annex A, ''Canister Storage Building Final Safety Analysis Report.'' All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the Canister Storage Building Final Safety Analysis Report

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.

National report of the Slovak Republic. Compiled according to the terms of the convention on nuclear safety. September 2001

International Nuclear Information System (INIS)

Balaj, J.; Bezak, S.; Gies, F.

2001-09-01

A brief national safety report of the Slovak Republic in 2001 is presented. A account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD) is presented. These activities are reported under the headings: (1) Introduction; (2) Nuclear installations in Slovakia accords to the convention definition; (3) Legislation and regulation; (4) General safety aspects; (5) Safety of nuclear installations in Slovakia; ((6) Annexes: (a) List of nuclear installations and technical and economic parameters; (b) 6.2 Some generally binding legal regulations concerning nuclear and radiation safety; (c) 6.3 List of some national and international documents relating to safety of WWER type reactors; 6.4 Limits of radioactive substance discharges; 6.5 Author team. Contents, list of abbreviations used as well as reference index are included

Chinese Road Safety and Driver Behavior Research

OpenAIRE

Wang, Junhua

2015-01-01

The seminar will begin with a brief overview of the Chinese road safety situation, including current safety problems, and then move on to discuss safety research including driver behavior, freeway operational safety, and infrastructure development.

Traceability of Software Safety Requirements in Legacy Safety Critical Systems

Science.gov (United States)

Hill, Janice L.

2007-01-01

How can traceability of software safety requirements be created for legacy safety critical systems? Requirements in safety standards are imposed most times during contract negotiations. On the other hand, there are instances where safety standards are levied on legacy safety critical systems, some of which may be considered for reuse for new applications. Safety standards often specify that software development documentation include process-oriented and technical safety requirements, and also require that system and software safety analyses are performed supporting technical safety requirements implementation. So what can be done if the requisite documents for establishing and maintaining safety requirements traceability are not available?

Canister storage building design basis accident analysis documentation

Energy Technology Data Exchange (ETDEWEB)

KOPELIC, S.D.

1999-02-25

This document provides the detailed accident analysis to support HNF-3553, Spent Nuclear Fuel Project Final Safety Analysis Report, Annex A, ''Canister Storage Building Final Safety Analysis Report.'' All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the Canister Storage Building Final Safety Analysis Report.

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.

IAEA safety fundamentals: the safety of nuclear installations and the defence in depth concept

International Nuclear Information System (INIS)

Aro, I.

2005-01-01

This presentation is a replica of the similar presentation provided by the IAEA Basic Professional Training Course on Nuclear Safety. The presentation utilizes the IAEA Safety Series document No. 110, Safety Fundamentals: the Safety of Nuclear Installations. The objective of the presentation is to provide the basic rationale for actions in provision of nuclear safety. The presentation also provides basis to understand national nuclear safety requirements. There are three Safety Fundamentals documents in the IAEA Safety Series: one for nuclear safety, one for radiation safety and one for waste safety. The IAEA is currently revising its Safety Fundamentals by combining them into one general Safety Fundamentals document. The IAEA Safety Fundamentals are not binding requirements to the Member States. But, a very similar text has been provided in the Convention on Nuclear Safety which is legally binding for the Member State after ratification by the Parliament. This presentation concentrates on nuclear safety. The Safety Fundamentals documents are the 'policy documents' of the IAEA Safety Standards Series. They state the basic objectives, concepts and principles involved in ensuring protection and safety in the development and application of atomic energy for peaceful purposes. They will state - without providing technical details and without going into the application of principles - the rationale for actions necessary in meeting Safety Requirements. Chapter 7 of this presentation describes the basic features of defence in depth concept which is referred to in the Safety Fundamentals document. The defence in depth concept is a key issue in reaching high level of safety specifically at the design stage but as the reader can see the extended concept also refers to the operational stage. The appendix has been taken directly from the IAEA Basic Professional Training Course on Nuclear Safety and applied to the Finnish conditions. The text originates from the references

SAFETY INSTRUCTION AND SAFETY NOTE

CERN Multimedia

TIS Secretariat

2002-01-01

Please note that the SAFETY INSTRUCTION N0 49 (IS 49) and the SAFETY NOTE N0 28 (NS 28) entitled respectively 'AVOIDING CHEMICAL POLLUTION OF WATER' and 'CERN EXHIBITIONS - FIRE PRECAUTIONS' are available on the web at the following urls: http://edms.cern.ch/document/335814 and http://edms.cern.ch/document/335861 Paper copies can also be obtained from the TIS Divisional Secretariat, email: TIS.Secretariat@cern.ch

Safety assessment document for spent fuel handling, packaging, and storage demonstrations at the E-MAD facility on the Nevada Test Site

International Nuclear Information System (INIS)

1985-04-01

The objectives for spent fuel handling and packaging demonstration are to develop the capability to satisfactorily encapsulate typical commercial nuclear reactor spent fuel assemblies and to establish the suitability of interim dry surface and near surface storage concepts. To accomplish these objectives, spent fuel assemblies from a pressurized water reactor have been received, encapsulated in steel canisters, and emplaced in on-site storage facilities and subjected to other tests. As an essential element of these demonstrations, a thorough safety assessment of the demonstration activities conducted at the E-MAD facility has been completed. This document describes the site location and characteristics, the existing E-MAD facility, and the facility modifications and equipment additions made specifically for the demonstrations. The document also summarizes the Quality Assurance Program utilized, and specifies the principal design criteria applicable to the facility modifications, equipment additions, and process operations. Evaluations have been made of the radiological impacts of normal operations, abnormal operations, and postulated accidents. Analyses have been performed to determine the affects on nuclear criticality safety of postulated accidents and credible natural phenomena. The consequences of postulated accidents resulting in fission product gas release have also been estimated. This document identifies the engineered safety features, procedures, and site characteristics that (1) prevent the occurrence of potential accidents or (2) assure that the consequences of postulated accidents are either insignificant or adequately mitigated

General safety considerations

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-09-01

This document presents the full filling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 4 of the document contains some details about the priority to safety, financial and human resources, human factors, quality assurance, safety assessment and verification, radiation protection and emergency preparedness.

General safety considerations

International Nuclear Information System (INIS)

2001-01-01

This document presents the full filling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 4 of the document contains some details about the priority to safety, financial and human resources, human factors, quality assurance, safety assessment and verification, radiation protection and emergency preparedness

General safety considerations

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-09-01

This document presents the full filling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 4 of the document contains some details about the priority to safety, financial and human resources, human factors, quality assurance, safety assessment and verification, radiation protection and emergency preparedness.

General safety considerations

International Nuclear Information System (INIS)

1998-01-01

This document presents the full filling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 4 of the document contains some details about the priority to safety, financial and human resources, human factors, quality assurance, safety assessment and verification, radiation protection and emergency preparedness

Classification of Aeronautics System Health and Safety Documents

Data.gov (United States)

National Aeronautics and Space Administration — Most complex aerospace systems have many text reports on safety, maintenance, and associated issues. The Aviation Safety Reporting System (ASRS) spans several...

Canister Storage Building (CSB) Design Basis Accident Analysis Documentation

International Nuclear Information System (INIS)

CROWE, R.D.; PIEPHO, M.G.

2000-01-01

This document provided the detailed accident analysis to support HNF-3553, Spent Nuclear Fuel Project Final Safety Analysis Report, Annex A, ''Canister Storage Building Final Safety Analysis Report''. All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the Canister Storage Building Final Safety Analysis Report

Canister Storage Building (CSB) Design Basis Accident Analysis Documentation

International Nuclear Information System (INIS)

CROWE, R.D.

1999-01-01

This document provides the detailed accident analysis to support ''HNF-3553, Spent Nuclear Fuel Project Final Safety, Analysis Report, Annex A,'' ''Canister Storage Building Final Safety Analysis Report.'' All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the Canister Storage Building Final Safety Analysis Report

Safety of research reactors - A regulator's perspective

International Nuclear Information System (INIS)

Rahman, M.S.

2001-01-01

Due to historical reasons research reactors have received less regulatory attention in the world than nuclear power plants. This has given rise to several safety issues which, if not addressed immediately, may result in an undesirable situation. However, in Pakistan, research reactors and power reactors have received due attention from the regulatory authority. The Pakistan Research Reactor-1 has been under regulatory surveillance since 1965, the year of its commissioning. The second reactor has also undergone all the safety reviews and checks mandated by the licensing procedures. A brief description of the regulatory framework, the several safety reviews carried out have been briefly described in this paper. Significant activities of the regulatory authority have also been described in verifying the safety of research reactors in Pakistan along with the future activities. The views of the Pakistani regulatory authority on the specific issues identified by the IAEA have been presented along with specific recommendations to the IAEA. We are of the opinion that there are more Member States operating nuclear research reactors than nuclear power plants. Therefore, there should be more emphasis on the research reactor safety, which somehow has not been the case. In several recommendations made to the IAEA on the specific safety issues the emphasis has been, in general, to have a similar documentation and approach for maintaining and verifying operational safety at research reactors as is currently available for nuclear power reactors and may be planned for nuclear fuel cycle facilities. (author)

Appendix C: safety design rationale

International Nuclear Information System (INIS)

Ghose, S.

1985-01-01

A brief discussion of the rationale for safety design of fusion plants is presented in the main text. Further detail safety considerations are presented in this appendix in the form of charts and tables. The author present some of the major safety criteria and other criteria used in blanket selection here

TECHNICAL BASIS DOCUMENT FOR NATURAL EVENT HAZARDS

International Nuclear Information System (INIS)

KRIPPS, L.J.

2006-01-01

This technical basis document was developed to support the documented safety analysis (DSA) and describes the risk binning process and the technical basis for assigning risk bins for natural event hazard (NEH)-initiated accidents. The purpose of the risk binning process is to determine the need for safety-significant structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls for a given representative accident or represented hazardous conditions based on an evaluation of the frequency and consequence. Note that the risk binning process is not applied to facility workers, because all facility worker hazardous conditions are considered for safety-significant SSCs and/or TSR-level controls

A Brief History of the Flathead Tribes.

Science.gov (United States)

Woodcock, Clarence; And Others

A source document, illustrated with many black and white photographs of tribe members and activities, provides a brief history of the American Indian tribes, now called the Flatheads, living on the Flathead Indian Reservation in Montana and describes some of their cultural traditions, particularly their ceremonial dances. The booklet traces the…

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

Criticality safety considerations. Integral Monitored Retrievable Storage (MRS) Facility

International Nuclear Information System (INIS)

1986-09-01

This report summarizes the criticality analysis performed to address criticality safety concerns and to support facility design during the conceptual design phase of the Monitored Retrievable Storage (MRS) Facility. The report addresses the criticality safety concerns, the design features of the facility relative to criticality, and the results of the analysis of both normal operating and hypothetical off-normal conditions. Key references are provided (Appendix C) if additional information is desired by the reader. The MRS Facility design was developed and the related analysis was performed in accordance with the MRS Facility Functional Design Criteria and the Basis for Design. The detailed description and calculations are documented in the Integral MRS Facility Conceptual Design Report. In addition to the summary portion of this report, explanatary notes for various terms, calculation methodology, and design parameters are presented in Appendix A. Appendix B provides a brief glossary of technical terms

Canister Storage Building (CSB) Design Basis Accident Analysis Documentation

Energy Technology Data Exchange (ETDEWEB)

CROWE, R.D.

1999-09-09

This document provides the detailed accident analysis to support ''HNF-3553, Spent Nuclear Fuel Project Final Safety, Analysis Report, Annex A,'' ''Canister Storage Building Final Safety Analysis Report.'' All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the Canister Storage Building Final Safety Analysis Report.

Reactor safety research program. A description of current and planned reactor safety research sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research

International Nuclear Information System (INIS)

1975-06-01

The reactor safety research program, sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, is described in terms of its program objectives, current status, and future plans. Elements of safety research work applicable to water reactors, fast reactors, and gas cooled reactors are presented together with brief descriptions of current and planned test facilities. (U.S.)

AREVA - 2012 Reference document

International Nuclear Information System (INIS)

2013-03-01

After a presentation of the person responsible for this Reference Document, of statutory auditors, and of a summary of financial information, this report address the different risk factors: risk management and coverage, legal risk, industrial and environmental risk, operational risk, risk related to major projects, liquidity and market risk, and other risks (related to political and economic conditions, to Group's structure, and to human resources). The next parts propose information about the issuer, a business overview (markets for nuclear power and renewable energies, customers and suppliers, group's strategy, operations), a brief presentation of the organizational structure, a presentation of properties, plants and equipment (principal sites, environmental issues which may affect these items), analysis and comments on the group's financial position and performance, a presentation of capital resources, a presentation of research and development activities (programs, patents and licenses), a brief description of financial objectives and profit forecasts or estimates, a presentation of administration, management and supervision bodies, a description of the operation of corporate bodies, an overview of personnel, of principal shareholders, and of transactions with related parties, a more detailed presentation of financial information concerning assets, financial positions and financial performance. Addition information regarding share capital is given, as well as an indication of major contracts, third party information, available documents, and information on holdings

Preliminary safety evaluation, based on initial site investigation data. Planning document

International Nuclear Information System (INIS)

Hedin, Allan

2002-12-01

This report is a planning document for the preliminary safety evaluations (PSE) to be carried out at the end of the initial stage of SKBs ongoing site investigations for a deep repository for spent nuclear fuel. The main purposes of the evaluations are to determine whether earlier judgements of the suitability of the candidate area for a deep repository with respect to long-term safety holds up in the light of borehole data and to provide feed-back to continued site investigations and site specific repository design. The preliminary safety evaluations will be carried out by a safety assessment group, based on a site model, being part of a site description, provided by a site modelling group and a repository layout within that model suggested by a repository engineering group. The site model contains the geometric features of the site as well as properties of the host rock. Several alternative interpretations of the site data will likely be suggested. Also the biosphere is included in the site model. A first task for the PSE will be to compare the rock properties described in the site model to previously established criteria for a suitable host rock. This report gives an example of such a comparison. In order to provide more detailed feedback, a number of thermal, hydrological, mechanical and chemical analyses of the site will also be included in the evaluation. The selection of analyses is derived from the set of geosphere and biosphere analyses preliminarily planned for the comprehensive safety assessment named SR-SITE, which will be based on a complete site investigation. The selection is dictated primarily by the expected feedback to continued site investigations and by the availability of data after the PSE. The repository engineering group will consider several safety related factors in suggesting a repository layout: Thermal calculations will be made to determine a minimum distance between canisters avoiding canister surface temperatures above 100 deg C

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.

Management of Documents and Information in BSC Secretariat

International Nuclear Information System (INIS)

Sumathi, E.; Jayarajan, K.

2017-01-01

The regulatory and safety function of BARC facilities is being carried out by BARC Safety Framework with BARC Safety Council as an apex body. Presently, about one hundred safety committees and task forces are functional in the framework. BSC Secretariat (BSCS) provides technical and administrative support to the BARC Safety Framework for the regulatory activities in BARC. Important documents/records related to committee decisions and facilities are maintained in BSCS, through an established documentation and record keeping system. The compliance of regulatory recommendations is verified during regulatory inspections and subsequent submissions made by the facility authority. This supports the effective regulatory decision making of various committees. This article elaborates the maintenance of records and information at BSC

A Generic Software Safety Document Generator

Science.gov (United States)

Denney, Ewen; Venkatesan, Ram Prasad

2004-01-01

Formal certification is based on the idea that a mathematical proof of some property of a piece of software can be regarded as a certificate of correctness which, in principle, can be subjected to external scrutiny. In practice, however, proofs themselves are unlikely to be of much interest to engineers. Nevertheless, it is possible to use the information obtained from a mathematical analysis of software to produce a detailed textual justification of correctness. In this paper, we describe an approach to generating textual explanations from automatically generated proofs of program safety, where the proofs are of compliance with an explicit safety policy that can be varied. Key to this is tracing proof obligations back to the program, and we describe a tool which implements this to certify code auto-generated by AutoBayes and AutoFilter, program synthesis systems under development at the NASA Ames Research Center. Our approach is a step towards combining formal certification with traditional certification methods.

Nuclear criticality safety guide

International Nuclear Information System (INIS)

Pruvost, N.L.; Paxton, H.C.

1996-09-01

This technical reference document cites information related to nuclear criticality safety principles, experience, and practice. The document also provides general guidance for criticality safety personnel and regulators

Nuclear criticality safety guide

Energy Technology Data Exchange (ETDEWEB)

Pruvost, N.L.; Paxton, H.C. [eds.

1996-09-01

This technical reference document cites information related to nuclear criticality safety principles, experience, and practice. The document also provides general guidance for criticality safety personnel and regulators.

Technical basis document for external events

International Nuclear Information System (INIS)

OBERG, B.D.

2003-01-01

This document supports the Tank Farms Documented Safety Analysis and presents the technical basis for the FR-equencies of externally initiated accidents. The consequences of externally initiated events are discussed in other documents that correspond to the accident that was caused by the external event. The external events include aircraft crash, vehicle accident, range fire, and rail accident

Brief draft on surface and subsurface storage of high level and long-lived radioactive wastes. Spent fuels synthesis file

International Nuclear Information System (INIS)

Dumas, C.; Jaecki, P.

2002-01-01

This document makes a synthesis of the results of two brief draft studies performed in 2002 about the surface and subsurface storage of spent fuels. These studies stress on the long duration aspect of the disposal: feasibility of a secular disposal facility, potential risks and safety level of such a facility, estimation of the initial investment and of operation and maintenance costs. The main points of the specifications and the input data are presented first, and then the subsurface and surface draft studies are described. Content: specifications (imposed design principles and options, dry corrosion, input data); subsurface storage (description and design options, thermal dimensioning and ventilation, geotechnical stability of the facility, subsurface water management, dry corrosion, infrastructure durability, safety, monitoring, security and physical protection, technical-economical aspects, case of Mox fuel, case of glass packages); surface storage (description and design options, thermal dimensioning and ventilation, mechanical dimensioning of the facility, dry corrosion, infrastructure durability, safety, monitoring, security and physical protection, technical-economical aspects, case of Mox fuel, case of glass packages); conclusions and perspectives. (J.S.)

Brief description of the Wackersdorf Reprocessing Facility

International Nuclear Information System (INIS)

1986-01-01

The DWK is now planning the construction and operation of a facility for the reprocessing of spent fuel elements and the fabrication of mixed-oxide fuel elements which will initially have an average daily throughput of 2 tons (t) of nuclear fuel. The application required by the Atomic Law was submitted to the Bavarian State Ministry for State Development and Environmental Matters on October 28, 1982. According to Par. 3, Section 1, No. 1 of the Atomic Law Procedural Ordinance such an application for permission in accordance with par. 7 AtL must explicitly be accompanied by a safety report which shall make it possible for third parties to make a judgment whether the impacts associated with the facility and its operation could damage their rights. The safety report is intended to present and explain the concept of the facility, the safety-technological design bases, and the operation of the plant, including its operation and safety systems and the impacts and proposed preventive measures. In addition to the detailed presentations in the safety report, Par. 3 of the Atomic Law Procedural Ordinance also requires a brief description of the plant designed for general public understanding, suitable for the design, which will also explain the expected impacts on the general environment and the surrounding area. Hence the brief description presents and explains the following matters: the site; the technology and state of the art for reprocessing of spent nuclear fuel; the structure and function of the proposed facility; safety provisions of the proposed facility and the management of perturbations in operation; the impacts of the facility and its operation on the environment; measures to be taken for dealing with the radioactive wastes; and provisions for ultimate shut-down of the facility

Safety systems and features of boiling and pressurized water reactors

International Nuclear Information System (INIS)

Khair, H. O. M.

2012-06-01

The safe operation of nuclear power plants (NPP) requires a deep understanding of the functioning of physical processes and systems involved. This study was carried out to present an overview of the features of safety systems of boiling and pressurized water reactors that are available commercially. Brief description of purposes and functions of the various safety systems that are employed in these reactors was discussed and a brief comparison between the safety systems of BWRs and PWRs was made in an effort to emphasize of safety in NPPs.(Author)

Effect of generic issues program on improving safety

International Nuclear Information System (INIS)

Fard, M. R.; Kauffman, J. V.

2010-01-01

The U.S. Nuclear Regulatory Commission (NRC) identifies (by its assessment of plant operation) certain issues involving public health and safety, the common defense and security, or the environment that could affect multiple entities under NRC jurisdiction. The Generic Issues Program (GIP) addresses the resolution of these Generic Issues (GIs). The resolution of these issues may involve new or revised rules, new or revised guidance, or revised interpretation of rules or guidance that affect nuclear power plant licensees, nuclear material certificate holders, or holders of other regulatory approvals. U.S. NRC provides information related to the past and ongoing GIP activities to the general public by the use of three main resources, namely NUREG-0933, 'Resolution of Generic Safety Issues, ' Generic Issues Management Control System (GIMCS), and GIP public web page. GIP information resources provide information such as historical information on resolved GIs, current status of the open GIs, policy documents, program procedures, GIP annual and quarterly reports and the process to contact GIP and propose a GI This paper provides an overview of the GIP and several examples of safety improvements resulting from the resolution of GIs. In addition, the paper provides a brief discussion of a few recent GIs to illustrate how the program functions to improve safety. (authors)

Improving access to skilled attendance at delivery: a policy brief for Uganda.

Science.gov (United States)

Nabudere, Harriet; Asiimwe, Delius; Amandua, Jacinto

2013-04-01

This study describes the process of production, findings for a policy brief on Increasing Access to Skilled Birth Attendance, and subsequent use of the report by policy makers and others from the health sector in Uganda. The methods used to prepare the policy brief use the SUPPORT Tools for evidence-informed health policy making. The problem that this evidence brief addresses was identified through an explicit priority setting process involving policy makers and other stakeholders, further clarification with key informant interviews of relevant policy makers, and review of relevant documents. A working group of national stakeholder representatives and external reviewers commented on and contributed to successive drafts of the report. Research describing the problem, policy options, and implementation considerations was identified by reviewing government documents, routinely collected data, electronic literature searches, contact with key informants, and reviewing the reference lists of relevant documents that were retrieved. The proportion of pregnant women delivering from public and private non-profit facilities was low at 34 percent in 2008/09. The three policy options discussed in the report could be adopted independently or complementary to the other to increase access to skilled care. The Ministry of Health in deliberating to provide intrapartum care at first level health facilities from the second level of care, requested for research evidence to support these decisions. Maternal waiting shelters and working with the private-for-profit sector to facilitate deliveries in health facilities are promising complementary interventions that have been piloted in both the public and private health sector. A combination of strategies is needed to effectively implement the proposed options as discussed further in this article. The policy brief report was used as a background document for two stakeholder dialogue meetings involving members of parliament, policy makers

29 CFR 1905.7 - Form of documents; subscription; copies.

Science.gov (United States)

2010-07-01

... UNDER THE WILLIAMS-STEIGER OCCUPATIONAL SAFETY AND HEALTH ACT OF 1970 General § 1905.7 Form of documents... 29 Labor 5 2010-07-01 2010-07-01 false Form of documents; subscription; copies. 1905.7 Section 1905.7 Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH ADMINISTRATION...

A departmental brief to the Ontario Nuclear Safety Review

International Nuclear Information System (INIS)

1987-09-01

The major nuclear activity in Canada is that associated with the generation of electricity by nuclear power stations. This area is in part subject to federal jurisdiction under the authority of the Atomic Energy Control Board. Environment Canada can play a significant role in influencing decisions regarding environmental aspects of nuclear energy development. The Department believes that the best way to preserve the quality of the environment is to anticipate and prevent problems before they arise. However, even if all precautionary measures were taken in the design and operating procedures of nuclear power stations, accidents can occur and radionuclides and toxic pollutants may escape and disperse into the environment. This brief outlines the rationale for Environment Canada's involvement and role in the nuclear area, and the major programs and activities of the Department with respect to environmental protection and emergency preparedness. The brief also makes recommendations for consideration of environmental protection technologies for nuclear power stations, for improved measurement and modelling capabilities relating to release and dispersion of radionuclides during accident conditions, and for improved communication with the public following a nuclear emergency. Environment Canada recommends that an appropriate environmental review process be undertaken for new or expanded nuclear facilities in Ontario

340 Waste Handling Facility interim safety basis

International Nuclear Information System (INIS)

Bendixsen, R.B.

1995-01-01

This document establishes the interim safety basis (ISB) for the 340 Waste Handling Facility (340 Facility). An ISB is a documented safety basis that provides a justification for the continued operation of the facility until an upgraded final safety analysis report is prepared that complies with US Department of Energy (DOE) Order 5480.23, Nuclear Safety Analysis Reports. The ISB for the 340 Facility documents the current design and operation of the facility. The 340 Facility ISB (ISB-003) is based on a facility walkdown and review of the design and operation of the facility, as described in the existing safety documentation. The safety documents reviewed, to develop ISB-003, include the following: OSD-SW-153-0001, Operating Specification Document for the 340 Waste Handling Facility (WHC 1990); OSR-SW-152-00003, Operating Limits for the 340 Waste Handling Facility (WHC 1989); SD-RE-SAP-013, Safety Analysis Report for Packaging, Railroad Liquid Waste Tank Cars (Mercado 1993); SD-WM-TM-001, Safety Assessment Document for the 340 Waste Handling Facility (Berneski 1994a); SD-WM-SEL-016, 340 Facility Safety Equipment List (Berneski 1992); and 340 Complex Fire Hazard Analysis, Draft (Hughes Assoc. Inc. 1994)

Framework of nuclear safety and safety assessment

International Nuclear Information System (INIS)

Furuta, Kazuo

2007-01-01

Since enormous energy is released by nuclear chain reaction mainly as a form of radiation, a great potential risk accompanies utilization of nuclear energy. Safety has been continuously a critical issue therefore from the very beginning of its development. Though the framework of nuclear safety that has been established at an early developmental stage of nuclear engineering is still valid, more comprehensive approaches are required having experienced several events such as Three Mile Island, Chernobyl, and JCO. This article gives a brief view of the most basic principles how nuclear safety is achieved, which were introduced and sophisticated in nuclear engineering but applicable also to other engineering domains in general. (author)

Documentation: Records and Reports.

Science.gov (United States)

Akers, Michael J

2017-01-01

This article deals with documentation to include the beginning of documentation, the requirements of Good Manufacturing Practice reports and records, and the steps that can be taken to minimize Good Manufacturing Practice documentation problems. It is important to remember that documentation for 503a compounding involves the Formulation Record, Compounding Record, Standard Operating Procedures, Safety Data Sheets, etc. For 503b outsourcing facilities, compliance with Current Good Manufacturing Practices is required, so this article is applicable to them. For 503a pharmacies, one can see the development and modification of Good Manufacturing Practice and even observe changes as they are occurring in 503a documentation requirements and anticipate that changes will probably continue to occur. Copyright© by International Journal of Pharmaceutical Compounding, Inc.

Nuclear power plants documentation system

International Nuclear Information System (INIS)

Schwartz, E.L.

1991-01-01

Since the amount of documents (type and quantity) necessary for the entire design of a NPP is very large, this implies that an overall and detailed identification, filling and retrieval system shall be implemented. This is even more applicable to the FINAL QUALITY DOCUMENTATION of the plant, as stipulated by IAEA Safety Codes and related guides. For such a purpose it was developed a DOCUMENTATION MANUAL, which describes in detail the before mentioned documentation system. Here we present the expected goals and results which we have to reach for Angra 2 and 3 Project. (author)

Preliminary Safety Information Document for the Standard MHTGR. Volume 1, (includes latest Amendments)

Energy Technology Data Exchange (ETDEWEB)

None

1986-01-01

With NRC concurrence, the Licensing Plan for the Standard HTGR describes an application program consistent with 10CFR50, Appendix O to support a US Nuclear Regulatory Commission (NRC) review and design certification of an advanced Standard modular High Temperature Gas-Cooled Reactor (MHTGR) design. Consistent with the NRC's Advanced Reactor Policy, the Plan also outlines a series of preapplication activities which have as an objective the early issuance of an NRC Licensability Statement on the Standard MHTGR conceptual design. This Preliminary Safety Information Document (PSID) has been prepared as one of the submittals to the NRC by the US Department of Energy in support of preapplication activities on the Standard MHTGR. Other submittals to be provided include a Probabilistic Risk Assessment, a Regulatory Technology Development Plan, and an Emergency Planning Bases Report.

Industrial safety, origins and current situation

International Nuclear Information System (INIS)

Gil Sarralbo, J. F.

2011-01-01

Basic Introduction to Industrial Safety, purpose and expected outcome. Concepts and fundamental principles that support it. Brief overview of its evolution over the course of history. The current legal basis in Spain for Industrial Safety. (Author) 4 refs.

Safety of operations in the manufacture of driver fuel for the first charge of the Dragon Reactor and modifications to the safety document for the Dragon Fuel Element Production Building

International Nuclear Information System (INIS)

Beutler, H.; Cross, J.; Flamm, J.

1965-01-01

The manufacture of the zirconium containing 'driver' fuel and fuel elements for the First Charge of the Dragon Reactor Experiment has been completed without incident. This is a report on the safety of operations in the Dragon Fuel Element Production Building during an approximately six month period when the 'driver' fuel was manufactured and 25 elements containing this fuel were assembled and exported to the Reactor Building. The opportunity is taken to bring the Safety Document up-to-date and to report on any significant operational failures of equipment. (author)

RELEASE OF DRIED RADIOACTIVE WASTE MATERIALS TECHNICAL BASIS DOCUMENT

International Nuclear Information System (INIS)

KOZLOWSKI, S.D.

2007-01-01

This technical basis document was developed to support RPP-23429, Preliminary Documented Safety Analysis for the Demonstration Bulk Vitrification System (PDSA) and RPP-23479, Preliminary Documented Safety Analysis for the Contact-Handled Transuranic Mixed (CH-TRUM) Waste Facility. The main document describes the risk binning process and the technical basis for assigning risk bins to the representative accidents involving the release of dried radioactive waste materials from the Demonstration Bulk Vitrification System (DBVS) and to the associated represented hazardous conditions. Appendices D through F provide the technical basis for assigning risk bins to the representative dried waste release accident and associated represented hazardous conditions for the Contact-Handled Transuranic Mixed (CH-TRUM) Waste Packaging Unit (WPU). The risk binning process uses an evaluation of the frequency and consequence of a given representative accident or represented hazardous condition to determine the need for safety structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls. A representative accident or a represented hazardous condition is assigned to a risk bin based on the potential radiological and toxicological consequences to the public and the collocated worker. Note that the risk binning process is not applied to facility workers because credible hazardous conditions with the potential for significant facility worker consequences are considered for safety-significant SSCs and/or TSR-level controls regardless of their estimated frequency. The controls for protection of the facility workers are described in RPP-23429 and RPP-23479. Determination of the need for safety-class SSCs was performed in accordance with DOE-STD-3009-94, Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses, as described below

New set of Chemical Safety rules

CERN Multimedia

HSE Unit

2011-01-01

A new set of four Safety Rules was issued on 28 March 2011: Safety Regulation SR-C ver. 2, Chemical Agents (en); General Safety Instruction GSI-C1, Prevention and Protection Measures (en); General Safety Instruction GSI-C2, Explosive Atmospheres (en); General Safety Instruction GSI-C3, Monitoring of Exposure to Hazardous Chemical Agents in Workplace Atmospheres (en). These documents form part of the CERN Safety Rules and are issued in application of the “Staff Rules and Regulations” and of document SAPOCO 42. These documents set out the minimum requirements for the protection of persons from risks to their occupational safety and health arising, or likely to arise, from the effects of hazardous chemical agents that are present in the workplace or used in any CERN activity. Simultaneously, the HSE Unit has published seven Safety Guidelines and six Safety Forms. These documents are available from the dedicated Web page “Chemical, Cryogenic and Biological Safety&...

Advisory Committee on human radiation experiments. Supplemental Volume 2a, Sources and documentation appendices. Final report

International Nuclear Information System (INIS)

1995-01-01

This large document provides a catalog of the location of large numbers of reports pertaining to the charge of the Presidential Advisory Committee on Human Radiation Research and is arranged as a series of appendices. Titles of the appendices are Appendix A- Records at the Washington National Records Center Reviewed in Whole or Part by DoD Personnel or Advisory Committee Staff; Appendix B- Brief Descriptions of Records Accessions in the Advisory Committee on Human Radiation Experiments (ACHRE) Research Document Collection; Appendix C- Bibliography of Secondary Sources Used by ACHRE; Appendix D- Brief Descriptions of Human Radiation Experiments Identified by ACHRE, and Indexes; Appendix E- Documents Cited in the ACHRE Final Report and other Separately Described Materials from the ACHRE Document Collection; Appendix F- Schedule of Advisory Committee Meetings and Meeting Documentation; and Appendix G- Technology Note

Advisory Committee on human radiation experiments. Supplemental Volume 2a, Sources and documentation appendices. Final report

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-01-01

This large document provides a catalog of the location of large numbers of reports pertaining to the charge of the Presidential Advisory Committee on Human Radiation Research and is arranged as a series of appendices. Titles of the appendices are Appendix A- Records at the Washington National Records Center Reviewed in Whole or Part by DoD Personnel or Advisory Committee Staff; Appendix B- Brief Descriptions of Records Accessions in the Advisory Committee on Human Radiation Experiments (ACHRE) Research Document Collection; Appendix C- Bibliography of Secondary Sources Used by ACHRE; Appendix D- Brief Descriptions of Human Radiation Experiments Identified by ACHRE, and Indexes; Appendix E- Documents Cited in the ACHRE Final Report and other Separately Described Materials from the ACHRE Document Collection; Appendix F- Schedule of Advisory Committee Meetings and Meeting Documentation; and Appendix G- Technology Note.

Annotated bibliography National Environmental Policy Act (NEPA) documents for Sandia National Laboratories

International Nuclear Information System (INIS)

Harris, J.M.

1995-04-01

The following annotated bibliography lists documents prepared by the Department of Energy (DOE), and predecessor agencies, to meet the requirements of the National Environmental Policy Act (NEPA) for activities and facilities at Sandia National Laboratories sites. For each NEPA document summary information and a brief discussion of content is provided. This information may be used to reduce the amount of time or cost associated with NEPA compliance for future Sandia National Laboratories projects. This summary may be used to identify model documents, documents to use as sources of information, or documents from which to tier additional NEPA documents

Annotated bibliography National Environmental Policy Act (NEPA) documents for Sandia National Laboratories

Energy Technology Data Exchange (ETDEWEB)

Harris, J.M.

1995-04-01

The following annotated bibliography lists documents prepared by the Department of Energy (DOE), and predecessor agencies, to meet the requirements of the National Environmental Policy Act (NEPA) for activities and facilities at Sandia National Laboratories sites. For each NEPA document summary information and a brief discussion of content is provided. This information may be used to reduce the amount of time or cost associated with NEPA compliance for future Sandia National Laboratories projects. This summary may be used to identify model documents, documents to use as sources of information, or documents from which to tier additional NEPA documents.

iPad-based patient briefing for radiological examinations-a clinical trial.

Science.gov (United States)

Schlechtweg, Philipp M; Hammon, Matthias; Giese, David; Heberlein, Christian; Uder, Michael; Schwab, Siegfried A

2014-08-01

To analyze if an iPad-based patient briefing can serve as a digital alternative to conventional documentations prior to radiological examinations. One hundred one patients referred for routine MRI were randomized into two groups, who underwent iPad-based and classic written briefing in opposite order. For each briefing completion time, completeness and correctness were noted. Patient's knowledge about the content of either briefing modality was subsequently tested. The influence of patient-related factors on the performance of the electronic briefing (EB) was analyzed. Finally, the patient's subjective impression of the EB was assessed. The mean durations were 4.4 ± 2.2 min for EB and 1.7 ± 1.3 min for the classic briefing (p iPad briefings were returned entirely filled out, whereas 11 % of the classic forms were returned with missing data. No significant differences in memorization of the briefing's information were objectified. There was a positive correlation between the duration of EB and age (r = 0.53; p iPads transfers the information for the patients equally well compared to the classic written approach. Although iPad briefing took patients longer to perform, the majority would prefer it to written consent briefings in the future. Nevertheless, measures have to be undertaken to improve the overall acceptance and performance.

Cold Vacuum Drying Facility Design Basis Accident Analysis Documentation

International Nuclear Information System (INIS)

PIEPHO, M.G.

1999-01-01

This document provides the detailed accident analysis to support HNF-3553, Annex B, Spent Nuclear Fuel Project Final Safety Analysis Report, ''Cold Vacuum Drying Facility Final Safety Analysis Report (FSAR).'' All assumptions, parameters and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the FSAR

Executive-style briefings on selected repository design issues

International Nuclear Information System (INIS)

1978-01-01

This document is a collection of executive-style briefings on selected repository design issues. Most of the briefings discuss differences between the US repository design bases presented in US Working Draft on Repository Physical Descriptions in a Salt Formation, prepared in support of INFCE discussions of May 1978 and the FRG-Netherlands design bases, presented in Design Study of a Radioactive Waste Repository to be Mined in a Medium-Size Salt Dome by Hamstra and Velzeboer, Netherlands Energy Research Foundation, January 1978. Advantages and disadvantages of the two sets of design bases are discussed, and the impacts of adopting either of these bases on the other's programs and positions are identified

Mixing of incompatible materials in waste tanks technical basis document

International Nuclear Information System (INIS)

SANDGREN, K.R.

2003-01-01

This technical basis document was developed to support the Tank Farms Documented Safety Analysis (DSA) and describes the risk binning process, the technical basis for assigning risk bins, and the controls selected for the mixing of incompatible materials representative accident and associated represented hazardous conditions. The purpose of the risk binning process is to determine the need for safety-significant structures, systems, and components (SSCs) and/or technical safety requirement (TSR)-level controls for a given representative accident or represented hazardous conditions based on an evaluation of the FR-equency and consequence. Note that the risk binning process is not applied to facility workers, because all facility worker hazardous conditions are considered for safety-significant SSCs and/or TSR level controls. Determination of the need for safety-class SSCs was performed in accordance with DOE-STD-3009-94, ''Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses'', as described in this report

Safety evaluation report of the Waste Isolation Pilot Plant safety analysis report: Contact-handled transuranic waste disposal operations

International Nuclear Information System (INIS)

1997-02-01

DOE 5480.23, Nuclear Safety Analysis Reports, requires that the US Department of Energy conduct an independent, defensible, review in order to approve a Safety Analysis Report (SAR). That review and the SAR approval basis is documented in this formal Safety Evaluation Report (SER). This SER documents the DOE's review of the Waste Isolation Pilot Plant SAR and provides the Carlsbad Area Office Manager, the WIPP SAR approval authority, with the basis for approving the safety document. It concludes that the safety basis documented in the WIPP SAR is comprehensive, correct, and commensurate with hazards associated with planned waste disposal operations

A brief overview of Ignalina NPP safety issues

International Nuclear Information System (INIS)

Almenas, K.; Ushpuras, E.

1998-01-01

A description of the safety of Ignalina NPP in a very popular form is presented. Answers to the most frequently recurring questions concerning the Ignalina NPP are provided based on recently completed international studies. Questions are like these: can a similar accident to the one that occurred in Chernobyl take place at Ignalina NPP, does the Ignalina NPP have a containment, what are the probabilities and potential consequences of accidents, etc. The brochure contains a short description of Ignalina NPP safety improvement programs

49 CFR 591.6 - Documents accompanying declarations.

Science.gov (United States)

2010-10-01

... SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) IMPORTATION OF VEHICLES AND EQUIPMENT SUBJECT TO FEDERAL SAFETY, BUMPER AND THEFT PREVENTION STANDARDS § 591.6 Documents accompanying... be accompanied by a statement substantiating that the vehicle was not manufactured for use on the...

Guidance and Control Software Project Data - Volume 4: Configuration Management and Quality Assurance Documents

Science.gov (United States)

Hayhurst, Kelly J. (Editor)

2008-01-01

The Guidance and Control Software (GCS) project was the last in a series of software reliability studies conducted at Langley Research Center between 1977 and 1994. The technical results of the GCS project were recorded after the experiment was completed. Some of the support documentation produced as part of the experiment, however, is serving an unexpected role far beyond its original project context. Some of the software used as part of the GCS project was developed to conform to the RTCA/DO-178B software standard, "Software Considerations in Airborne Systems and Equipment Certification," used in the civil aviation industry. That standard requires extensive documentation throughout the software development life cycle, including plans, software requirements, design and source code, verification cases and results, and configuration management and quality control data. The project documentation that includes this information is open for public scrutiny without the legal or safety implications associated with comparable data from an avionics manufacturer. This public availability has afforded an opportunity to use the GCS project documents for DO-178B training. This report provides a brief overview of the GCS project, describes the 4-volume set of documents and the role they are playing in training, and includes configuration management and quality assurance documents from the GCS project. Volume 4 contains six appendices: A. Software Accomplishment Summary for the Guidance and Control Software Project; B. Software Configuration Index for the Guidance and Control Software Project; C. Configuration Management Records for the Guidance and Control Software Project; D. Software Quality Assurance Records for the Guidance and Control Software Project; E. Problem Report for the Pluto Implementation of the Guidance and Control Software Project; and F. Support Documentation Change Reports for the Guidance and Control Software Project.

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

Information Brief on Green Power Marketing, 2nd Edition

Energy Technology Data Exchange (ETDEWEB)

Sweezey, B.; Houston, A.

1998-02-01

This document is the second in a series of information briefs on green power marketing activity in the United States. It includes descriptions of utility green pricing programs, green power marketing activity, retail access legislation and pilot programs, and other data and information supporting the development of green power markets.

Guide for the realization of Design Base Documents (DBD)

International Nuclear Information System (INIS)

Roca Mallofre, G. la

2010-01-01

Guide for improving the consistency and quality content of the Design Base Documents. It's a short description of how to carry out and complete these Documents but focusing on those aspects that can be more confusing and harder to interpret. This guide aims to clarify the term Design Base distinguishing between production and safety, and it focuses on safety Design Base Documents and their values and references. It also emphasizes the difference between the support system and the interface system when there is a functional connection between different systems.

Management of safety and safety culture at the NPPs of Ukraine

International Nuclear Information System (INIS)

Koltakov, Vladimir

2002-01-01

The report contains general aspects of safety and safety culture. The brief description of operational characteristics and basic indexes of atomic power plants at the Ukraine are represented. The information referring to structure of NPPs of Operation organization license-holder, safety responsibility of both Regulatory and Utility Bodies also is given. The main part of the report include seven sections: 1. Practical application of safety management models; 2. erspective on the relationship between safety management and safety culture; 3. The role of leadership in achieving high standards of safety; 4. Current and future challengers that impact on safety culture and safety management (e.g. the impact of competition, changing, economic and political circumstances, workforce demographics, etc.); 5. Key lessons learned from major events; 6. Practical applications of safety culture concepts (e.g. learning organizations, training staff communications, etc.); 7. dvance in human performance. Some of the main pending safety and safety culture problems that are necessary to achieve in the near future are mentioned

Nuclear safety legislation and supervision in China

International Nuclear Information System (INIS)

Zhang Shiguan

1991-02-01

The cause for the urgent need of nuclear safety legislation and supervision in China is firstly described, and then a brief introduction to the basic principle and guideline of nuclear safety is presented. Finally the elaboration on the establishment of nuclear safety regulatory system, the enactment of a series of regulations and safety guides, and the implementation of licencing, nuclear safety supervision and research for ensuring the safety of nuclear energy, since the founding of the National Nuclear Safety Administration, are introduced

Government Research and Development Summaries: Nuclear, Te, Ti Project Briefs. Monthly report

International Nuclear Information System (INIS)

1988-01-01

Nuclear, Te, Ti Project Briefs describe the status of all RandD programs submitted to the Power Information Center by the government sponsors in energy conversion from fission, fusion, and radioisotope power sources and other thermal systems that use thermionic systems. These briefs also follow related investigations of plasma dynamics. The document is not to be reproduced, in whole or in part, for dissemination outside your own organization nor may it be reproduced for advertising or sales promotion purposes

Community Documentation Centre on Industrial Risk. Bulletin no. 8

International Nuclear Information System (INIS)

Masera, M.; Rasmussen, K.

1993-01-01

The Directorate-General for Environment, Nuclear Safety and Civil Protection of the Commission of the European Communities is responsible for the effective and harmonized implementation of the Directive 82/501/EEC on the major-accident hazards of certain industrial activities. To this end, the Commission, in collaboration with the Committee of Competent Authorities responsible for the implementation of this Directive in the twelve Member States, carries out a whole range of activities. One of the most essential areas for action identified was the need for a systematic diffusion of information concerning the practical implementation of the Directive in the Member States, including the technical rules and guidelines applied, the safety practices and the lessons learnt from major accidents. Therefore, the Commission decided to set up a Community Documentation Centre on Industrial Risks (CDCIR). This Documentation Centre is run by the European Commission, Joint Research Centre, Institute for Systems Engineering and Informatics (ISEI), at Ispra, Italy, among its support activities on the implementation of the Directive. The Documentation Centre will collect, classify and review technical rules, guidelines and documents concerning the requirements of the Directive, as well as the safety of industrial installations produced by governments, administrative, scientific or technical bodies, national or international organizations and industrial or professional associations. Documents on major accidents in the form of reports, videotapes will also be collected and reviewed. The Centre is accessible to interested visitors, documents which are not covered by copyright and are not restricted can be obtained from the Documentation Centre on request. Periodical volumes which will feature the inventory, including abstracts, of the collected material will be published and made available to all interested parties. The Centre will also publish documents devoted to compare existing

Community Documentation Centre on Industrial Risk. Bulletin no. 4

International Nuclear Information System (INIS)

Gow, H.B.F.

1991-01-01

The Directorate-General for Environment, Nuclear Safety and Civil Protection of the Commission of the European Communities is responsible for the effective and harmonized implementation of the Directive 82/501/EEC on the major-accident hazards of certain industrial activities. To this end, the Commission, in collaboration with the Committee of Competent Authorities responsible for the implementation of this Directive in the twelve Member States, carries out a whole range of activities. One of the most essential areas for action identified was the need for a systematic diffusion of information concerning the practical implementation of the Directive in the Member States, including the technical rules and guidelines applied, the safety practices and the lessons learnt from major accidents. Therefore, the Commission decided to set up a Community Documentation Centre on Industrial Risks (CDCIR). This Documentation Centre is run by the European Commission, Joint Research Centre, Institute for Systems Engineering and Informatics (ISEI), at Ispra, Italy, among its support activities on the implementation of the Directive. The Documentation Centre will collect, classify and review technical rules, guidelines and documents concerning the requirements of the Directive, as well as the safety of industrial installations produced by governments, administrative, scientific or technical bodies, national or international organizations and industrial or professional associations. Documents on major accidents in the form of reports, videotapes will also be collected and reviewed. The Centre is accessible to interested visitors, documents which are not covered by copyright and are not restricted can be obtained from the Documentation Centre on request. Periodical volumes which will feature the inventory, including abstracts, of the collected material will be published and made available to all interested parties. The Centre will also publish documents devoted to compare existing

Community Documentation Centre on Industrial Risk. Bulletin no. 10

International Nuclear Information System (INIS)

Perschke, A.; Kirchsteiger, C.

1996-01-01

The Directorate-General for Environment, Nuclear Safety and Civil Protection of the Commission of the European Communities is responsible for the effective and harmonized implementation of the Directive 82/501/EEC on the major-accident hazards of certain industrial activities. To this end, the Commission, in collaboration with the Committee of Competent Authorities responsible for the implementation of this Directive in the twelve Member States, carries out a whole range of activities. One of the most essential areas for action identified was the need for a systematic diffusion of information concerning the practical implementation of the Directive in the Member States, including the technical rules and guidelines applied, the safety practices and the lessons learnt from major accidents. Therefore, the Commission decided to set up a Community Documentation Centre on Industrial Risks (CDCIR). This Documentation Centre is run by the European Commission, Joint Research Centre, Institute for Systems Engineering and Informatics (ISEI), at Ispra, Italy, among its support activities on the implementation of the Directive. The Documentation Centre will collect, classify and review technical rules, guidelines and documents concerning the requirements of the Directive, as well as the safety of industrial installations produced by governments, administrative, scientific or technical bodies, national or international organizations and industrial or professional associations. Documents on major accidents in the form of reports, videotapes will also be collected and reviewed. The Centre is accessible to interested visitors, documents which are not covered by copyright and are not restricted can be obtained from the Documentation Centre on request. Periodical volumes which will feature the inventory, including abstracts, of the collected material will be published and made available to all interested parties. The Centre will also publish documents devoted to compare existing

Community Documentation Centre on Industrial Risk. Bulletin no. 5

International Nuclear Information System (INIS)

Gow, H.B.F.

1991-11-01

The Directorate-General for Environment, Nuclear Safety and Civil Protection of the Commission of the European Communities is responsible for the effective and harmonized implementation of the Directive 82/501/EEC on the major-accident hazards of certain industrial activities. To this end, the Commission, in collaboration with the Committee of Competent Authorities responsible for the implementation of this Directive in the twelve Member States, carries out a whole range of activities. One of the most essential areas for action identified was the need for a systematic diffusion of information concerning the practical implementation of the Directive in the Member States, including the technical rules and guidelines applied, the safety practices and the lessons learnt from major accidents. Therefore, the Commission decided to set up a Community Documentation Centre on Industrial Risks (CDCIR). This Documentation Centre is run by the European Commission, Joint Research Centre, Institute for Systems Engineering and Informatics (ISEI), at Ispra, Italy, among its support activities on the implementation of the Directive. The Documentation Centre will collect, classify and review technical rules, guidelines and documents concerning the requirements of the Directive, as well as the safety of industrial installations produced by governments, administrative, scientific or technical bodies, national or international organizations and industrial or professional associations. Documents on major accidents in the form of reports, videotapes will also be collected and reviewed. The Centre is accessible to interested visitors, documents which are not covered by copyright and are not restricted can be obtained from the Documentation Centre on request. Periodical volumes which will feature the inventory, including abstracts, of the collected material will be published and made available to all interested parties. The Centre will also publish documents devoted to compare existing

Community Documentation Centre on Industrial Risk. Bulletin no. 7

International Nuclear Information System (INIS)

Gow, H.B.F.; Carditello, I.

1993-04-01

The Directorate-General for Environment, Nuclear Safety and Civil Protection of the Commission of the European Communities is responsible for the effective and harmonized implementation of the Directive 82/501/EEC on the major-accident hazards of certain industrial activities. To this end, the Commission, in collaboration with the Committee of Competent Authorities responsible for the implementation of this Directive in the twelve Member States, carries out a whole range of activities. One of the most essential areas for action identified was the need for a systematic diffusion of information concerning the practical implementation of the Directive in the Member States, including the technical rules and guidelines applied, the safety practices and the lessons learnt from major accidents. Therefore, the Commission decided to set up a Community Documentation Centre on Industrial Risks (CDCIR). This Documentation Centre is run by the European Commission, Joint Research Centre, Institute for Systems Engineering and Informatics (ISEI), at Ispra, Italy, among its support activities on the implementation of the Directive. The Documentation Centre will collect, classify and review technical rules, guidelines and documents concerning the requirements of the Directive, as well as the safety of industrial installations produced by governments, administrative, scientific or technical bodies, national or international organizations and industrial or professional associations. Documents on major accidents in the form of reports, videotapes will also be collected and reviewed. The Centre is accessible to interested visitors, documents which are not covered by copyright and are not restricted can be obtained from the Documentation Centre on request. Periodical volumes which will feature the inventory, including abstracts, of the collected material will be published and made available to all interested parties. The Centre will also publish documents devoted to compare existing

Community Documentation Centre on Industrial Risk. Bulletin no. 9

International Nuclear Information System (INIS)

Perschke, A.

1995-01-01

The Directorate-General for Environment, Nuclear Safety and Civil Protection of the Commission of the European Communities is responsible for the effective and harmonized implementation of the Directive 82/501/EEC on the major-accident hazards of certain industrial activities. To this end, the Commission, in collaboration with the Committee of Competent Authorities responsible for the implementation of this Directive in the twelve Member States, carries out a whole range of activities. One of the most essential areas for action identified was the need for a systematic diffusion of information concerning the practical implementation of the Directive in the Member States, including the technical rules and guidelines applied, the safety practices and the lessons learnt from major accidents. Therefore, the Commission decided to set up a Community Documentation Centre on Industrial Risks (CDCIR). This Documentation Centre is run by the European Commission, Joint Research Centre, Institute for Systems Engineering and Informatics (ISEI), at Ispra, Italy, among its support activities on the implementation of the Directive. The Documentation Centre will collect, classify and review technical rules, guidelines and documents concerning the requirements of the Directive, as well as the safety of industrial installations produced by governments, administrative, scientific or technical bodies, national or international organizations and industrial or professional associations. Documents on major accidents in the form of reports, videotapes will also be collected and reviewed. The Centre is accessible to interested visitors, documents which are not covered by copyright and are not restricted can be obtained from the Documentation Centre on request. Periodical volumes which will feature the inventory, including abstracts, of the collected material will be published and made available to all interested parties. The Centre will also publish documents devoted to compare existing

Community Documentation Centre on Industrial Risk. Bulletin no. 6

International Nuclear Information System (INIS)

Gow, H.B.F.

1992-06-01

The Directorate-General for Environment, Nuclear Safety and Civil Protection of the Commission of the European Communities is responsible for the effective and harmonized implementation of the Directive 82/501/EEC on the major-accident hazards of certain industrial activities. To this end, the Commission, in collaboration with the Committee of Competent Authorities responsible for the implementation of this Directive in the twelve Member States, carries out a whole range of activities. One of the most essential areas for action identified was the need for a systematic diffusion of information concerning the practical implementation of the Directive in the Member States, including the technical rules and guidelines applied, the safety practices and the lessons learnt from major accidents. Therefore, the Commission decided to set up a Community Documentation Centre on Industrial Risks (CDCIR). This Documentation Centre is run by the European Commission, Joint Research Centre, Institute for Systems Engineering and Informatics (ISEI), at Ispra, Italy, among its support activities on the implementation of the Directive. The Documentation Centre will collect, classify and review technical rules, guidelines and documents concerning the requirements of the Directive, as well as the safety of industrial installations produced by governments, administrative, scientific or technical bodies, national or international organizations and industrial or professional associations. Documents on major accidents in the form of reports, videotapes will also be collected and reviewed. The Centre is accessible to interested visitors, documents which are not covered by copyright and are not restricted can be obtained from the Documentation Centre on request. Periodical volumes which will feature the inventory, including abstracts, of the collected material will be published and made available to all interested parties. The Centre will also publish documents devoted to compare existing

Community Documentation Centre on Industrial Risk. Bulletin no. 11

International Nuclear Information System (INIS)

Perschke, A.; Kirchsteiger, C.; Carnevali, C.

1997-01-01

The Directorate-General for Environment, Nuclear Safety and Civil Protection of the Commission of the European Communities is responsible for the effective and harmonized implementation of the Directive 82/501/EEC on the major-accident hazards of certain industrial activities. To this end, the Commission, in collaboration with the Committee of Competent Authorities responsible for the implementation of this Directive in the twelve Member States, carries out a whole range of activities. One of the most essential areas for action identified was the need for a systematic diffusion of information concerning the practical implementation of the Directive in the Member States, including the technical rules and guidelines applied, the safety practices and the lessons learnt from major accidents. Therefore, the Commission decided to set up a Community Documentation Centre on Industrial Risks (CDCIR). This Documentation Centre is run by the European Commission, Joint Research Centre, Institute for Systems Engineering and Informatics (ISEI), at Ispra, Italy, among its support activities on the implementation of the Directive. The Documentation Centre will collect, classify and review technical rules, guidelines and documents concerning the requirements of the Directive, as well as the safety of industrial installations produced by governments, administrative, scientific or technical bodies, national or international organizations and industrial or professional associations. Documents on major accidents in the form of reports, videotapes will also be collected and reviewed. The Centre is accessible to interested visitors, documents which are not covered by copyright and are not restricted can be obtained from the Documentation Centre on request. Periodical volumes which will feature the inventory, including abstracts, of the collected material will be published and made available to all interested parties. The Centre will also publish documents devoted to compare existing

A new era of safety at CERN

CERN Multimedia

CERN Bulletin

2014-01-01

CERN is modernising its safety policy and organisational structure in matters of Safety with the introduction of new reference documents that have come into force on 29 September. These texts adapt the Organization’s safety policy to take account of how the Laboratory has evolved and to include best practice in Safety matters.   Safety is a priority at CERN, so it’s no coincidence that the Organization’s anniversary has been chosen as the time to launch a modernised approach to its Safety policy and how Safety matters are organised. On the day of CERN’s 60th anniversary, the SAPOCO 42 document, which covered both policy and organisational aspects, was replaced by a more concise general policy statement. The organisational structure and responsibilities in matters of Safety are now set out in a Safety Regulation, that is supplemented by subsidiary documents. Together these documents will replace the corresponding parts of the former SAPOCO 42 as well as Saf...

ISAM newsletter. No. 3

International Nuclear Information System (INIS)

Torres, Carlos

1998-11-01

This issue of the ISAM newsletter informs on the past and forthcoming ISAM Co-ordinating Group meetings and highlights working group and safety case activities. The document briefs on the particular safety cases: Vault safety case; Radon-type facility safety case; and Borehole safety case. The document highlights also the ISAM Virtual Workspace which provides the opportunity through the World Wide Web for ISAM participants to share information and to work together on the Safety Cases and Working Group Activities. A list of ISAM documents is provided

Cold Vacuum Drying (CVD) Facility Design Basis Accident Analysis Documentation

Energy Technology Data Exchange (ETDEWEB)

PIEPHO, M.G.

1999-10-20

This document provides the detailed accident analysis to support HNF-3553, Annex B, Spent Nuclear Fuel Project Final Safety Analysis Report, ''Cold Vacuum Drying Facility Final Safety Analysis Report (FSAR).'' All assumptions, parameters and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the FSAR.

Regulatory guidance document

International Nuclear Information System (INIS)

1994-05-01

The Office of Civilian Radioactive Waste Management (OCRWM) Program Management System Manual requires preparation of the OCRWM Regulatory Guidance Document (RGD) that addresses licensing, environmental compliance, and safety and health compliance. The document provides: regulatory compliance policy; guidance to OCRWM organizational elements to ensure a consistent approach when complying with regulatory requirements; strategies to achieve policy objectives; organizational responsibilities for regulatory compliance; guidance with regard to Program compliance oversight; and guidance on the contents of a project-level Regulatory Compliance Plan. The scope of the RGD includes site suitability evaluation, licensing, environmental compliance, and safety and health compliance, in accordance with the direction provided by Section 4.6.3 of the PMS Manual. Site suitability evaluation and regulatory compliance during site characterization are significant activities, particularly with regard to the YW MSA. OCRWM's evaluation of whether the Yucca Mountain site is suitable for repository development must precede its submittal of a license application to the Nuclear Regulatory Commission (NRC). Accordingly, site suitability evaluation is discussed in Chapter 4, and the general statements of policy regarding site suitability evaluation are discussed in Section 2.1. Although much of the data and analyses may initially be similar, the licensing process is discussed separately in Chapter 5. Environmental compliance is discussed in Chapter 6. Safety and Health compliance is discussed in Chapter 7

GATEWAY Report Brief: SSL Demonstration: Long-Term Evaluation of Indoor Field Performance

Energy Technology Data Exchange (ETDEWEB)

None, None

2017-02-28

Report brief summarizing a GATEWAY program evaluation of the long-term performance characteristics (chromaticity change, maintained illuminance, and operations and maintenance) of LED lighting systems in four field installations previously documented in separate DOE GATEWAY reports.

Engineering design guidelines for nuclear criticality safety

International Nuclear Information System (INIS)

Waltz, W.R.

1988-08-01

This document provides general engineering design guidelines specific to nuclear criticality safety for a facility where the potential for a criticality accident exists. The guide is applicable to the design of new SRP/SRL facilities and to major modifications Of existing facilities. The document is intended an: A guide for persons actively engaged in the design process. A resource document for persons charged with design review for adequacy relative to criticality safety. A resource document for facility operating personnel. The guide defines six basic criticality safety design objectives and provides information to assist in accomplishing each objective. The guide in intended to supplement the design requirements relating to criticality safety contained in applicable Department of Energy (DOE) documents. The scope of the guide is limited to engineering design guidelines associated with criticality safety and does not include other areas of the design process, such as: criticality safety analytical methods and modeling, nor requirements for control of the design process

49 CFR 237.155 - Documents and records.

Science.gov (United States)

2010-10-01

..., DEPARTMENT OF TRANSPORTATION BRIDGE SAFETY STANDARDS Documentation, Records, and Audits of Bridge Management Programs § 237.155 Documents and records. Each track owner required to implement a bridge management... protected by a security system that incorporates a user identity and password, or a comparable method, to...

LMFBR: safety aspects

International Nuclear Information System (INIS)

Natta, M.

1990-01-01

This presentation of LMFBR safety is limited at Super Phenix reactor. After a brief description of the reactor, some details on safety systems, in normal or accidental conditions, are given. The main functions studied are: chain reaction trip, residual power evacuation, reactor containment. In heavy accident the behaviour of Super Phenix is studied which its particular characteristics and the possibilities of operators reactions. The probability of appearance and the maximum consequences of heavy accidents are given [fr

Fluor Daniel Hanford contract standards/requirements identification document

Energy Technology Data Exchange (ETDEWEB)

Bennett, G.L.

1997-04-24

This document, the Standards/Requirements Identification Document (S/RID) for the Fluor Daniel Hanford Contract, represents the necessary and sufficient requirements to provide an adequate level of protection of the worker, public health and safety, and the environment.

Fluor Daniel Hanford company standards requirements identification document

International Nuclear Information System (INIS)

Bennett, G.L.

1997-01-01

This document, the Standards/Requirements Identification Document (S/RID) for the Fluor Daniel Hanford Contract, represents the necessary and sufficient requirements to provide an adequate level of protection of the worker, public health and safety, and the environment

Bibliography and documents issued list through fiscal year 1982

International Nuclear Information System (INIS)

1982-12-01

This document is a bibliography of the published reports, papers, and documents of the Basalt Waste Isolation Project (BWIP) that have been publicly released during fiscal years 1978 to 1982. A brief history of the National Waste Terminal Storage Program and the BWIP is included to provide the reader with the scope of activities involved in the technical endeavor to identify a potential geologic repository site for the permanent isolation of radioactive wastes. The bibliography is organized by scientific discipline and in chronological order. An author index is provided after the bibliography

Safety first. Status reports on the IAEA's safety standards

International Nuclear Information System (INIS)

Webb, G.; Karbassioun, A.; Linsley, G.; Rawl, R.

1998-01-01

Documents in the IAEA's Safety Standards Series known as RASS (Radiation Safety Standards) are produced to develop an internally consistent set of regulatory-style publications that reflects an international consensus on the principles of radiation protection and safety and their application through regulation. In this article are briefly presented the Agency's programmes on Nuclear Safety Standards (NUSS), Radioactive Waste Safety Standards (RADWASS), and Safe Transport of Radioactive Materials

General safety orientations of the Jules Horowitz Reactor Project (JHRP)

International Nuclear Information System (INIS)

Tremodeux, P.; Fiorini, G.L.

2000-01-01

After a brief reminder of the JHR purpose, the document outlines the General Safety related Orientations/Recommendations used for the design and the safety assessment of the facility. As far as the JHR design is new, the safety philosophy adopted for this reactor will be as consistent as possible with that recommended for future (power...) reactors. The general recommendations developed in the paper are: the general nuclear safety approach for the design, operation and analysis with, in particular, the adoption of the Defence In Depth principle; the general safety objectives in terms of radiological consequences; the use of Probabilistic Safety Studies; quality assurance. The 'Defence in Depth' concept using amongst others the 'Barrier' principle remains the basis of the JHR safety. 'Defence In Depth' is applied both to design and operation. Its adequacy is checked during the safety assessment and the paper gives the technical recommendations that should allow the designer to implement this concept into the final design. Built mainly for experimental irradiation the JHR facilities will be handled according to conventional or new operation rules which could put materials under stress and entail handling errors. Specific recommendations are defined to take into account the corresponding peculiarities; they are discussed in the paper. The safety design of the JHR takes into account the experience accumulated through the CEA experimental irradiation programmes, which represents several dozen reactor years; the consultation of CEA reactor facilities operators is ongoing. The corresponding feedback is shortly described. Recommendations related to maintenance and associated operation are indicated as well as those regarding the human factor. Details are given on the JHR safety practical implementation through the CEA/DRN Safety approach. Details of the corresponding Safety Objectives are also discussed. Finally the designer position on the role of probabilistic safety

K West integrated water treatment system subproject safety analysis document

International Nuclear Information System (INIS)

SEMMENS, L.S.

1999-01-01

This Accident Analysis evaluates unmitigated accident scenarios, and identifies Safety Significant and Safety Class structures, systems, and components for the K West Integrated Water Treatment System

K West integrated water treatment system subproject safety analysis document

Energy Technology Data Exchange (ETDEWEB)

SEMMENS, L.S.

1999-02-24

This Accident Analysis evaluates unmitigated accident scenarios, and identifies Safety Significant and Safety Class structures, systems, and components for the K West Integrated Water Treatment System.

Tools for plant safety engineer

International Nuclear Information System (INIS)

Fabic, S.

1996-01-01

This paper contains: - review of tools for monitoring plant safety equipment reliability and readiness, before and accident (performance indicators for monitoring the risk and reliability performance and for determining when degraded performance alert levels are achieved) - brief reviews of tools for use during an accident: Emergency Operating Procedures (EOPs), Emergency Response Data System (ERDS), Reactor Safety Assessment System (RSAS), Computerized Accident Management Support

Nuclear criticality safety department training implementation

International Nuclear Information System (INIS)

Carroll, K.J.; Taylor, R.G.; Worley, C.A.

1996-01-01

The Nuclear Criticality Safety Department (NCSD) is committed to developing and maintaining a staff of qualified personnel to meet the current and anticipated needs in Nuclear Criticality Safety (NCS) at the Oak Ridge Y-12 Plant. The NCSD Qualification Program is described in Y/DD-694, Qualification Program, Nuclear Criticality Safety Department This document provides a listing of the roles and responsibilities of NCSD personnel with respect to training and details of the Training Management System (TMS) programs, Mentoring Checklists and Checksheets, as well as other documentation utilized to implement the program. This document supersedes Y/DD-696, Revision 2, dated 3/27/96, Training Implementation, Nuclear Criticality Safety Department. There are no backfit requirements associated with revisions to this document

Berkeley Lab - Materials Sciences Division

Science.gov (United States)

culture and policies at MSD MSD0010: Integrated Safety Management: Principles and Case Studies Calendar ? Click Here! Resources for MSD Safety MSD Safety MSD's Integrated Safety Management Plan [PDF] Safety for MSD classes on Integrated Safety Management MSD0015 Handout - Waste Briefing Document [PDF] Waste

Cold Vacuum Drying facility design basis accident analysis documentation

International Nuclear Information System (INIS)

CROWE, R.D.

2000-01-01

This document provides the detailed accident analysis to support HNF-3553, Annex B, Spent Nuclear Fuel Project Final Safety Analysis Report (FSAR), ''Cold Vacuum Drying Facility Final Safety Analysis Report.'' All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the FSAR. The calculations in this document address the design basis accidents (DBAs) selected for analysis in HNF-3553, ''Spent Nuclear Fuel Project Final Safety Analysis Report'', Annex B, ''Cold Vacuum Drying Facility Final Safety Analysis Report.'' The objective is to determine the quantity of radioactive particulate available for release at any point during processing at the Cold Vacuum Drying Facility (CVDF) and to use that quantity to determine the amount of radioactive material released during the DBAs. The radioactive material released is used to determine dose consequences to receptors at four locations, and the dose consequences are compared with the appropriate evaluation guidelines and release limits to ascertain the need for preventive and mitigative controls

Cold Vacuum Drying facility design basis accident analysis documentation

Energy Technology Data Exchange (ETDEWEB)

CROWE, R.D.

2000-08-08

This document provides the detailed accident analysis to support HNF-3553, Annex B, Spent Nuclear Fuel Project Final Safety Analysis Report (FSAR), ''Cold Vacuum Drying Facility Final Safety Analysis Report.'' All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the FSAR. The calculations in this document address the design basis accidents (DBAs) selected for analysis in HNF-3553, ''Spent Nuclear Fuel Project Final Safety Analysis Report'', Annex B, ''Cold Vacuum Drying Facility Final Safety Analysis Report.'' The objective is to determine the quantity of radioactive particulate available for release at any point during processing at the Cold Vacuum Drying Facility (CVDF) and to use that quantity to determine the amount of radioactive material released during the DBAs. The radioactive material released is used to determine dose consequences to receptors at four locations, and the dose consequences are compared with the appropriate evaluation guidelines and release limits to ascertain the need for preventive and mitigative controls.

Technical documentation challenges in aviation maintenance : a proceedings report.

Science.gov (United States)

2012-11-01

The 2012 Technical Documentation workshop addressed both problems and solutions associated with technical : documentation for maintenance. These issues are known to cause errors, rework, maintenance delays, other : safety hazards, and FAA administrat...

HANFORD SAFETY ANALYSIS & RISK ASSESSMENT HANDBOOK (SARAH)

Energy Technology Data Exchange (ETDEWEB)

EVANS, C B

2004-12-21

The purpose of the Hanford Safety Analysis and Risk Assessment Handbook (SARAH) is to support the development of safety basis documentation for Hazard Category 2 and 3 (HC-2 and 3) U.S. Department of Energy (DOE) nuclear facilities to meet the requirements of 10 CFR 830, ''Nuclear Safety Management''. Subpart B, ''Safety Basis Requirements.'' Consistent with DOE-STD-3009-94, Change Notice 2, ''Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses'' (STD-3009), and DOE-STD-3011-2002, ''Guidance for Preparation of Basis for Interim Operation (BIO) Documents'' (STD-3011), the Hanford SARAH describes methodology for performing a safety analysis leading to development of a Documented Safety Analysis (DSA) and derivation of Technical Safety Requirements (TSR), and provides the information necessary to ensure a consistently rigorous approach that meets DOE expectations. The DSA and TSR documents, together with the DOE-issued Safety Evaluation Report (SER), are the basic components of facility safety basis documentation. For HC-2 or 3 nuclear facilities in long-term surveillance and maintenance (S&M), for decommissioning activities, where source term has been eliminated to the point that only low-level, residual fixed contamination is present, or for environmental remediation activities outside of a facility structure, DOE-STD-1120-98, ''Integration of Environment, Safety, and Health into Facility Disposition Activities'' (STD-1120), may serve as the basis for the DSA. HC-2 and 3 environmental remediation sites also are subject to the hazard analysis methodologies of this standard.

Nuclear safety in France

International Nuclear Information System (INIS)

Tanguy, P.

1979-01-01

A brief description of the main safety aspects of the French nuclear energy programme and of the general safety organization is followed by a discussion on the current thinking in CEA on some important safety issues. As far as methodology is concerned, the use of probabilistic analysis in the licensing procedure is being extensively developed. Reactor safety research is aimed at a better knowledge of the safety margins involved in the present designs of both PWRs and LMFBRs. A greater emphasis should be put during the next years in the safety of the nuclear fuel cycle installations, including waste disposals. Finally, it is suggested that further international cooperation in the field of nuclear safety should be developed in order to insure for all countries the very high safety level which has been achieved up till now. (author)

The IAEA safety standards for radiation, waste and nuclear safety

International Nuclear Information System (INIS)

Gonzalez, Abel J.

1997-01-01

This paper presents a brief description of the standards for radiation, waste and nuclear safety established by the International Atomic Energy Agency (IAEA). It provides a historical overview of their development and also summarizes the standards' current preparation and review process. The final paragraphs offer an outlook on future developments. (author)

Model review and evaluation for application in DOE safety basis documentation of chemical accidents - modeling guidance for atmospheric dispersion and consequence assessment

Energy Technology Data Exchange (ETDEWEB)

Lazaro, M. A. [Argonne National Lab. (ANL), Argonne, IL (United States); Woodarad, K. [Argonne National Lab. (ANL), Argonne, IL (United States); Hanna, S. R. [Argonne National Lab. (ANL), Argonne, IL (United States); Hesse, D. J. [Argonne National Lab. (ANL), Argonne, IL (United States); Huang, J. -C. [Argonne National Lab. (ANL), Argonne, IL (United States); Lewis, J. [Argonne National Lab. (ANL), Argonne, IL (United States); Mazzola, C. A. [Argonne National Lab. (ANL), Argonne, IL (United States)

1997-09-01

The U.S. Department of Energy (DOE), through its Defense Programs (DP), Office of Engineering and Operations Suppon, established the Accident Phenomenology and Consequence (AP AC) Methodology Evaluation Program to identify and evaluate methodologies and computer codes to support accident phenomenological and consequence calculations for both radiological and nonradiological materials at DOE facilities and to identify development needs. The program is also intended to define and recommend "best or good engineering/safety analysis practices" to be followed in preparing ''design or beyond design basis" assessments to be included in DOE nuclear and nonnuclear facility safety documents. The AP AC effort is intended to provide scientifically sound and more consistent analytical approaches, by identifying model selection procedures and application methodologies, in order to enhance safety analysis activities throughout the DOE complex.

Tank farms criticality safety manual

International Nuclear Information System (INIS)

FORT, L.A.

2003-01-01

This document defines the Tank Farms Contractor (TFC) criticality safety program, as required by Title 10 Code of Federal Regulations (CFR-), Subpart 830.204(b)(6), ''Documented Safety Analysis'' (10 CFR- 830.204 (b)(6)), and US Department of Energy (DOE) 0 420.1A, Facility Safety, Section 4.3, ''Criticality Safety.'' In addition, this document contains certain best management practices, adopted by TFC management based on successful Hanford Site facility practices. Requirements in this manual are based on the contractor requirements document (CRD) found in Attachment 2 of DOE 0 420.1A, Section 4.3, ''Nuclear Criticality Safety,'' and the cited revisions of applicable standards published jointly by the American National Standards Institute (ANSI) and the American Nuclear Society (ANS) as listed in Appendix A. As an informational device, requirements directly imposed by the CRD or ANSI/ANS Standards are shown in boldface. Requirements developed as best management practices through experience and maintained consistent with Hanford Site practice are shown in italics. Recommendations and explanatory material are provided in plain type

Light-water reactor safety analysis codes

International Nuclear Information System (INIS)

Jackson, J.F.; Ransom, V.H.; Ybarrondo, L.J.; Liles, D.R.

1980-01-01

A brief review of the evolution of light-water reactor safety analysis codes is presented. Included is a summary comparison of the technical capabilities of major system codes. Three recent codes are described in more detail to serve as examples of currently used techniques. Example comparisons between calculated results using these codes and experimental data are given. Finally, a brief evaluation of current code capability and future development trends is presented

Hanford surplus facilities hazards identification document. Revision 2

International Nuclear Information System (INIS)

Egge, R.G.

1996-02-01

This document provides general safety information needed by personnel who enter and work in surplus facilities managed by Bechtel Hanford, Inc. (BHI). The purpose of the document is to enhance access control of surplus facilities, educate personnel on the potential hazards associated with these facilities prior to entry, and ensure that safety precautions are taken while in the facility. Questions concerning the currency of this information should be directed to the building administrator (as listed in BHI-FS-01, Field Support Administration, Section 1.1, ''Access Control for ERC Surplus Facilities'')

Construction safety program for the National Ignition Facility Appendix A: Safety Requirements

International Nuclear Information System (INIS)

Cerruti, S.J.

1997-01-01

These rules apply to all LLNL employees, non-LLNL employees (including contract labor, supplemental labor, vendors, personnel matrixed/assigned from other National Laboratories, participating guests, visitors and students) and construction contractors/subcontractors. The General Safety and Health rules shall be used by management to promote accident prevention through indoctrination, safety and health training and on-the-job application. As a condition for contracts award, all contractors and subcontractors and their employees must certify on Form S ampersand H A-1 that they have read and understand, or have been briefed and understand, the National Ignition Facility OCIP Project General Safety Rules

Construction safety program for the National Ignition Facility Appendix A: Safety Requirements

Energy Technology Data Exchange (ETDEWEB)

Cerruti, S.J.

1997-01-14

These rules apply to all LLNL employees, non-LLNL employees (including contract labor, supplemental labor, vendors, personnel matrixed/assigned from other National Laboratories, participating guests, visitors and students) and construction contractors/subcontractors. The General Safety and Health rules shall be used by management to promote accident prevention through indoctrination, safety and health training and on-the-job application. As a condition for contracts award, all contractors and subcontractors and their employees must certify on Form S & H A-1 that they have read and understand, or have been briefed and understand, the National Ignition Facility OCIP Project General Safety Rules.

Oak Ridge National Laboratory Environmenal, Safety, and Health Management Plan

International Nuclear Information System (INIS)

1991-12-01

The 1990 Tiger Team Appraisal of Oak Ridge National Laboratory (ORNL) revealed that neither Martin Marietta Energy Systems, Inc. (Energy Systems) nor ORNL had a strategic plan for Environmental, Safety, and Health (ES ampersand H) activities. There were no detailed plans describing ORNL's mission, objectives, and strategies for ES ampersand H activities. A number of plans do exist that cover various aspects of ES ampersand H. Their scope ranges from multiyear program plans to annual audit schedules to compliance plans to action plans from specific audits. However, there is not a single document that identifies the plans and the objectives they are to address. This document describes the strategic plan for ORNL and provides the linkage among existing plans. It gives a brief description of the organization and management of ES ampersand H activities at ORNL. The plan identifies the general strategies to be taken by ORNL, using the overall guidance from Energy Systems in its corporate ES ampersand H Strategic Plan. It also identifies more detailed plans for implementation of these strategies, where appropriate

Safety at Work : Research Methodology

NARCIS (Netherlands)

Beurden, van K. (Karin); Boer, de J. (Johannes); Brinks, G. (Ger); Goering-Zaburnenko, T. (Tatiana); Houten, van Y. (Ynze); Teeuw, W. (Wouter)

2012-01-01

In this document, we provide the methodological background for the Safety atWork project. This document combines several project deliverables as defined inthe overall project plan: validation techniques and methods (D5.1.1), performanceindicators for safety at work (D5.1.2), personal protection

International consensus on safety principles

International Nuclear Information System (INIS)

Warnecke, E.

1993-01-01

The International Atomic Energy Agency (IAEA) has been regularly requested by its Member States to provide evidence that radioactive waste can be managed safely and to help demonstrate a harmonization of approach at the international level by providing safety documents. In response, IAEA established a special series of safety documents devoted to radioactive waste management. These documents will be elaborated within the Radioactive Waste Safety Standards (RADWASS) programme [1,2] which covers all aspects of radioactive waste management. The RADWASS programme develops a series of international consensus documents on all parts of the safe management of radioactive waste, including disposal. The purpose of the RADWASS programme is to (i) document existing international consensus in the approaches and methodologies for safe radioactive waste management, (ii) create a mechanism to establish consensus where it does not exist and (iii) provide Member States with a comprehensive series of internationally agreed upon documents to complement national standards and criteria. This paper describes the RADWASS programme, and covers the structure, implementation plans and status of documents under preparation

Alcator C-MOD final safety analysis

International Nuclear Information System (INIS)

Fiore, C.L.

1989-06-01

This document is designed to address the safety issues involved with the Alcator C-Mod project. This report will begin with a brief description of the experimental objectives which will be followed by information concerning the site. The Alcator C-Mod experiment is a pulsed fusion experiment in which a plasma formed from small amounts of hydrogen or deuterium gas is confined in a magnetic field for short periods (∼1 s). No radioactive fuels or fissile materials are used in the device, so that no criticality hazard exists and no credible nuclear accident can occur. During deuterium operation, the production of a small number of neutrons from a short pulse could result in a small amount of short- and intermediate-lived radioactive isotopes being produced inside the experimental cell. This report will demonstrate that this does not pose an additional hazard to the general population. The health and safety hazards resulting from Alcator C-Mod occur to the workers on the experiment, each of which is described in its own chapter with the steps taken to minimize the risk to employees. These hazards include fire, chemicals and cryogenics, air quality, electrical, electromagnetic radiation, ionizing radiation, and mechanical and natural phenomena. None of these hazards is unique to the facility, and methods of protection from them are well defined and are discussed in the chapter which describes each hazard. The quality assurance program, critical to ensuring the safety aspects of the program, will also be described

HANFORD SAFETY ANALYSIS and RISK ASSESSMENT HANDBOOK (SARAH)

International Nuclear Information System (INIS)

EVANS, C.B.

2004-01-01

The purpose of the Hanford Safety Analysis and Risk Assessment Handbook (SARAH) is to support the development of safety basis documentation for Hazard Category 2 and 3 (HC-2 and 3) U.S. Department of Energy (DOE) nuclear facilities to meet the requirements of 10 CFR 830, ''Nuclear Safety Management''. Subpart B, ''Safety Basis Requirements.'' Consistent with DOE-STD-3009-94, Change Notice 2, ''Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses'' (STD-3009), and DOE-STD-3011-2002, ''Guidance for Preparation of Basis for Interim Operation (BIO) Documents'' (STD-3011), the Hanford SARAH describes methodology for performing a safety analysis leading to development of a Documented Safety Analysis (DSA) and derivation of Technical Safety Requirements (TSR), and provides the information necessary to ensure a consistently rigorous approach that meets DOE expectations. The DSA and TSR documents, together with the DOE-issued Safety Evaluation Report (SER), are the basic components of facility safety basis documentation. For HC-2 or 3 nuclear facilities in long-term surveillance and maintenance (S and M), for decommissioning activities, where source term has been eliminated to the point that only low-level, residual fixed contamination is present, or for environmental remediation activities outside of a facility structure, DOE-STD-1120-98, ''Integration of Environment, Safety, and Health into Facility Disposition Activities'' (STD-1120), may serve as the basis for the DSA. HC-2 and 3 environmental remediation sites also are subject to the hazard analysis methodologies of this standard

Development of NUMO safety case for geological disposal

International Nuclear Information System (INIS)

Suzuki, Satoru; Deguchi, Akira

2016-01-01

NUMO has developed a generic safety ease based on the latest knowledge to show the feasibility and safety of geological disposal in Japan. The NUMO safety case has been developed to provide a basic structure for subsequent safety cases that would be applied to any selected site, emphasising practical approaches and methodology, which will be applicable for the conditions/constraints during an actual siting process. This paper will provide a brief overview of the NUMO safety case. (author)

Safety

International Nuclear Information System (INIS)

2001-01-01

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

Grasping at Straws: Comments on the Alberta Pipeline Safety Review

Directory of Open Access Journals (Sweden)

Jennifer Winter

2013-09-01

Full Text Available The release last month of the Alberta Pipeline Safety Review was meant to be a symbol of the province’s renewed commitment to environmental responsibility as it aims for new export markets. The report’s authors, Group 10 Engineering, submitted 17 recommendations covering public safety and pipeline incidents, pipeline integrity management and pipeline safety near bodies of water — and many of them run the gamut from the obvious to the unhelpful to the contradictory. That the energy regulator ought to be staffed to do its job should go without saying; in fact, staffing levels were never identified as an issue. The recommendation that record retention and transfer requirements be defined for mergers and acquisitions, sales and takeovers is moot. There is no reason a purchasing party would not want all relevant documents, and no real way to enforce transparency if the seller opts to withhold information. Harmonizing regulations between provinces could reduce companies’ cost of doing business, but could also prove challenging if different jurisdictions use performance-based regulations — which is what the Review recommended Alberta consider. This very brief paper pries apart the Review’s flaws and recommends that the province go back to the drawing board. Safety is a serious issue; a genuine statistical review linking pipeline characteristics to failures and risk-mitigation activities would be a better alternative by far.

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

Energy Technology Data Exchange (ETDEWEB)

MORRIS, K.L.

1999-06-29

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

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

International Nuclear Information System (INIS)

Morris, K.L.

1999-01-01

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

Towards the european strategy for particle physics : The briefing book

NARCIS (Netherlands)

Akesson, T.; Aleksan, R.; Allanach, B.; Bertolucci, S.; Blondel, A.; Butterworth, J.; Cavalli-Sforza, M.; Cervera, A.; de Naurois, M.; Desch, K.; Egede, U.; Heuer, R.; Hoecker, A.; Huber, P.; Jungmann, K.; Linde, F.; Lombardi, A.; Mangano, M.; Mezzetto, M.; Onderwater, G.; Palanque-Delabrouille, N.; Peach, K.; Polosa, A.; Rondio, E.; Webber, B.; Weiglein, G.; Womersley, J.

This document was prepared as part of the briefing material for the Workshop of the CERN Council Strategy Group, held in DESY Zeuthen from 2nd to 6th May 2006. It gives an overview of the physics issues and of the technological challenges that will shape the future of the field, and incorporates

Nuclear safety review for the year 2001

International Nuclear Information System (INIS)

2002-07-01

The Nuclear Safety Review for the Year 2001 reports on worldwide efforts to strengthen nuclear and radiation safety, including radioactive waste safety. It is in three parts. Part 1 describes those events in 2001 that have, or may have, significance for nuclear, radiation and waste safety worldwide. It includes developments such as new initiatives in international cooperation, events of safety significance and events that may be indicative of trends in safety. Part 2 describes some of the IAEA's efforts to strengthen international co-operation in nuclear, radiation and waste safety during 2001. It covers legally binding international agreements, non-binding safety standards, and provisions for the application of safety standards. This is done in a very brief manner, because these issues are addressed in more detail in the Agency's Annual Report for 2001. Part 3 presents a brief look ahead to some issues that are likely to be prominent in the coming year(s). The topics covered were selected by the IAEA Secretariat on the basis of trends observed in recent years, account being taken of planned or expected future developments. A draft of the Nuclear Safety Review for the Year 2001 was presented to the March 2002 session of IAEA's Board of Governors. This final version has been prepared taking account of the discussion in the Board. In some places, information has been added to describe developments early in 2002 that were considered pertinent to the discussion of events during 2001

Integrated Management System, Configuration and Document Control for Research Reactors

International Nuclear Information System (INIS)

Steynberg, B.J.; Bruyn, J.F. du

2017-01-01

An integrated management system is a single management framework establishing all the processes necessary for the organisation to address all its goals and objectives. Very often only quality, environment and health & safety goals are included when referred to an integrated management system. However, within the research reactor environment such system should include goals pertinent to economic, environmental, health, operational, quality, safeguards, safety, security, and social considerations. One of the important objectives of an integrated management is to create the environment for a healthy safety culture. Configuration management is a disciplined process that involves both management and technical direction to establish and document the design requirements and the physical configuration of the research reactor and to ensure that they remain consistent with each other and the documentation. Configuration is the combination of the physical, functional, and operational characteristics of the structures, systems, and components (SSCs) or parts of the research reactor, operation, or activity. The basic objectives and general principles of configuration management are the same for all research reactors. The objectives of configuration management are to: a) Establish consistency among design requirements, physical configuration, and documentation (including analyses, drawings, and procedures) for the research reactor; b) Maintain this consistency throughout the life of the research reactor, particularly as changes are being made; and c) Retain confidence in the safety of the research reactor. The key elements needed to manage the configuration of research reactors are design requirements, work control, change control, document control, and configuration management assessments. The objective of document control is to ensure that only the most recently approved versions of documents are used in the process of operating, maintaining, and modifying the research reactor

Guidelines for the review research reactor safety. Reference document for IAEA Integrated Safety Assessment of Research Reactors (INSARR)

International Nuclear Information System (INIS)

1997-01-01

In 1992, the IAEA published new safety standards for research reactors as part of the set of publications considered by its Research Reactor Safety Programme (RRSP). This set also includes publications giving guidance for all safety aspects related to the lifetime of a research reactor. In addition, the IAEA has also revised the Safety Standards for radiation protection. Consequently, it was considered advisable to revise the Integrated Safety Assessment of Research Reactors (INSARR) procedures to incorporate the new requirements and guidance as well as to extend the scope of the safety reviews to currently operating research reactors. The present report is the result of this revision. The purpose of this report is to give guidance on the preparation, execution, reporting and follow-up of safety review mission to research reactors as conducted by the IAEA under its INSARR missions safety service. However, it will also be of assistance to operators and regulators in conducting: (a) ad hoc safety assessments of research reactors to address individual issues such as ageing or safety culture; and (b) other types of safety reviews such as internal and peer reviews and regulatory inspections

EADL: Evaluated Atomic Data Library of the Lawrence Livermore National Laboratory, USA. Summary documentation

International Nuclear Information System (INIS)

Lemmel, H.D.; Perkins, S.T.; Cullen, D.E.; Chen, M.H.; Hubbell, J.H.; Rathkopf, J.; Scofield, J.

1994-01-01

A brief summary documentation of the LLNL Evaluated Atomic Data Library EADL is given. The data library is available from the IAEA Nuclear Data Section on magnetic tape, costfree, upon request. (author)

Organizational Behavior: A Brief Overview and Safety Orientation.

Science.gov (United States)

Waller, Mary J

2015-12-01

Organizational Behavior (OB) is a discipline of social science that seeks explanations for human behavior in organizations. OB draws on core disciplines such as psychology, sociology, anthropology, economics, communication, and law to create and investigate multilevel explanations of why people engage in particular behaviors, and which behaviors under which circumstances lead to better outcomes in organizations. Created using an applied or pragmatic lens and tested with a wide range of both quantitative and qualitative methodologies, most OB theories and research have direct implications for managers and for other organizational participants. Not surprisingly, one focal area of OB research concerns safety in organizations, and a growing body of safety-oriented literature in OB is based on data collected during simulation training across a variety of organizations such as hospitals, airlines, nuclear power plants, and other high reliability organizations. Copyright © 2015 Mosby, Inc. All rights reserved.

Engineering and Safety Partnership Enhances Safety of the Space Shuttle Program (SSP)

Science.gov (United States)

Duarte, Alberto

2007-01-01

Project Management must use the risk assessment documents (RADs) as tools to support their decision making process. Therefore, these documents have to be initiated, developed, and evolved parallel to the life of the project. Technical preparation and safety compliance of these documents require a great deal of resources. Updating these documents after-the-fact not only requires substantial increase in resources - Project Cost -, but this task is also not useful and perhaps an unnecessary expense. Hazard Reports (HRs), Failure Modes and Effects Analysis (FMEAs), Critical Item Lists (CILs), Risk Management process are, among others, within this category. A positive action resulting from a strong partnership between interested parties is one way to get these documents and related processes and requirements, released and updated in useful time. The Space Shuttle Program (SSP) at the Marshall Space Flight Center has implemented a process which is having positive results and gaining acceptance within the Agency. A hybrid Panel, with equal interest and responsibilities for the two larger organizations, Safety and Engineering, is the focal point of this process. Called the Marshall Safety and Engineering Review Panel (MSERP), its charter (Space Shuttle Program Directive 110 F, April 15, 2005), and its Operating Control Plan emphasizes the technical and safety responsibilities over the program risk documents: HRs; FMEA/CILs; Engineering Changes; anomalies/problem resolutions and corrective action implementations, and trend analysis. The MSERP has undertaken its responsibilities with objectivity, assertiveness, dedication, has operated with focus, and has shown significant results and promising perspectives. The MSERP has been deeply involved in propulsion systems and integration, real time technical issues and other relevant reviews, since its conception. These activities have transformed the propulsion MSERP in a truly participative and value added panel, making a

Safety culture in transport

International Nuclear Information System (INIS)

Decobert, V.

1998-01-01

'Safety culture' is a wording that appeared first in 1986, during the evaluation of what happened during the Tchernobyl accident. Safety culture is defined in the IAEA 75-INSAG-4 document as the characteristics and attitude which, in organizations and in men behaviours, make that questions related to safety of nuclear power plants benefits, in priority, of the attention that they need in function of their importance. The INSAG-4 document identifies three different elements necessary to the development of the safety culture: commitment of the policy makers, commitment of the managers of the industry, and commitment of individuals. This paper gives examples to show how safety culture is existing in the way Transnucleaire performs the activities in the field of transport of nuclear materials. (author)

Brief Classroom Training Sessions for Workplace Readiness: Are They Effective?

Science.gov (United States)

Palesy, Debra

2017-01-01

Classroom training sessions for new home care workers (HCWs) are often brief and ad hoc, varying in format and content. Yet the application of this training may be central to worker and client safety. A qualitative approach was adopted for this inquiry, comprising two separate but related practical studies. In the first, exploratory study,…

The effects of ionizing radiation and review of the Young-Woollard document

International Nuclear Information System (INIS)

Marko, A.M.; Myers, D.K.

1983-04-01

A review of a document entitled 'The Health Dangers of Uranium Mining and Jurisdictional Questions' has been prepared. E.R. Young and R.F. Woollard submitted, in 1980, this document to the British Columbia Royal Commission of Inquiry, Health and Environmental Protection - Uranium Mining (INIS-mf--7757). When we reviewed the document it became clear that the views concerning effects of low-level radiation including alpha irradiation do not have scientific consensus. For this reason we have included a brief summary of conclusions produced by various international and national bodies on the effects of radiation on humans

Concept document of the repository-based software engineering program: A constructive appraisal

Science.gov (United States)

1992-01-01

A constructive appraisal of the Concept Document of the Repository-Based Software Engineering Program is provided. The Concept Document is designed to provide an overview of the Repository-Based Software Engineering (RBSE) Program. The Document should be brief and provide the context for reading subsequent requirements and product specifications. That is, all requirements to be developed should be traceable to the Concept Document. Applied Expertise's analysis of the Document was directed toward assuring that: (1) the Executive Summary provides a clear, concise, and comprehensive overview of the Concept (rewrite as necessary); (2) the sections of the Document make best use of the NASA 'Data Item Description' for concept documents; (3) the information contained in the Document provides a foundation for subsequent requirements; and (4) the document adequately: identifies the problem being addressed; articulates RBSE's specific role; specifies the unique aspects of the program; and identifies the nature and extent of the program's users.

14 CFR Appendix B of Part 415 - Safety Review Document Outline

Science.gov (United States)

2010-01-01

... Performance Graphs 2.0Launch Operator Organization (§ 415.111) 2.1Launch Operator Organization (§ 415.111 and... Plan 4.3.1Flight Safety Personnel 4.3.2Flight Safety Rules 4.3.3Flight Safety System Summary and... Instrumentation Plan 6.2Configuration Management and Control Plan 6.3Frequency Management Plan 6.4Flight...

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

Proposals for the Radioactive Substances (Basic Safety Standards) (England and Wales) Regulations 2000 and the Radioactive Substances (Basic Safety Standards) (England and Wales) Direction 2000. Consultative document

International Nuclear Information System (INIS)

2000-01-01

This document contains proposals for changes to the Radioactive Substances Act 1993 (RSA 93) and proposals for a Direction to be given to the Environment Agency in order to implement aspects of the European Directive 96/29/Euratom concerned with the control of radioactive waste. The Directive lays down basic safety standards for the protection of the health of workers and the general public against the dangers arising from ionising radiation. With the Government pledged to making government more accessible and responsive, an important feature of this approach is effective consultation with all interested organisations. This leads to more realistic and robust proposals, which is particularly important when dealing with proposed legislation. In March this year, the Government published a consultation paper 'The Radioactive Substances Act 1993: Implementing the Revised Basic Safety Standards Directive Euratom 96/29.' This sought comments on the basic principles for change - including the setting of levels of radioactivity below which radioactive material should be considered outside the framework of regulatory control. This document forms the second stage of the consultation process with the aim of gathering views on the proposed legal instruments to implement the Directive. This document: explains the background to the proposed regulations (paragraphs 8-13); summarises the results of the consultation on principles (paragraphs 14-24); describes the proposed changes (paragraphs 25-36); includes draft Regulations (paragraphs 27-29); includes a draft Direction to the Environment Agency (paragraphs 30-36); describes the next steps (paragraphs 37-39); includes a draft Regulatory Impact Assessment (paragraphs 40-41). In general, the devolved administrations in Scotland, Wales and Northern Ireland have assumed responsibility for environmental issues and hence management of radioactive waste policies and legislation affecting their respective countries. However, this

Electronic document management at Sizewell B

International Nuclear Information System (INIS)

Rippon, Simon.

1996-01-01

Sizewell ''B'', Britain's first PWR, officially opened on March 25 1996, will now rely for its document management on a sophisticated computer-based system. One of the largest single engineering projects ever to be commissioned on one site in Britain, Sizewell ''B'' accommodates more than 300,000 documents, including over 200,000 drawings. The electronic document management system will provide a number of important benefits, including a more direct method of maintaining the station's Configuration Management and hence maintaining high safety standards; improved turnaround in plant modification proposals (PMP); significant time and cost savings in managing vital records; and increased productivity. (Author)

Topical session proceedings of the 5. IGSC meeting on: observations regarding the safety case in recent safety assessment studies

International Nuclear Information System (INIS)

Hooper, Alan J.; Voinis, Sylvie; Van Luik, Abraham E.

2004-01-01

Within the NEA, the IGSC (Integration Group for the Safety Case) has, as an essential role, to develop common views on such key aspects of the safety case. Therefore, since the inauguration of the IGSC in 2000, four meetings were organised with topical sessions to explore various of these key aspects. This is a report on the fifth such topical session, held as part of the 5. plenary meeting of the IGSC. The session was attended by 36 participants, representing waste management organisations and regulatory authorities from 16 NEA member countries, the IAEA and the European Commission. The purpose of this topical session was to provide support to the finalising of the IGSC safety case brochure by getting a description of the safety case content of the IAEA Draft Safety Requirements document and by getting an overview of progress that could be observed from national organisations on developing their cases for system safety and/or developing the required methodologies. The objective was that the IGSC safety case brochure should be supportive of the IAEA/NEA document, and be reflective of the experience of the IGSC member programmes and organisations. The topical session was mainly aimed at exchanging information on: - The safety case related content of the proposed IAEA/NEA document (currently titled: 'IAEA Safety Standards Series, Geological Disposal of Radioactive Waste, Draft Safety Requirements (DS-154)'). - National programmes where safety assessments have recently been completed, e.g. ONDRAF/NIRAS, Nagra and Andra. - Feedback from international peer reviews, e.g. the Andra Dossier 2001 Argile, the Belgian SAFIR 2 report, the SR 97 report and the US-DOE Yucca Mountain TSPA. - The evolution of some national assessment methods and approaches e.g. SKB and Nagra. - The content of the draft IGSC safety case brochure entitled: 'The Nature and Purpose of the Post-closure Safety Case in Geological Disposal'. This document presents the various

Role of systems safety in maintaining affordable safety in the 1980's

International Nuclear Information System (INIS)

Hollister, H.; Trauth, C.A. Jr.

1979-01-01

Historically, the Department of Energy and its predecessors have used and supported the development of systems safety programs, practices, and principles, finding them by and large adequate, effective, and managerially efficient. Today, attempts are bing made to resolve increasingly complex environmental, safety, and health problems by turning to increasingly complex and detailed regulation as the primary governmental answer. It is increasingly doubtful that such an approach will provide management of these issues and problems that is either effective or efficient. Challenge is issued to those in systems safety to develop and apply systems safety principles and practices more broadly to total operational systems and not just to hardware and to environmental and health protection and not just to safety, so that the total universe of environmental, safety, and health can be managed effectively and efficiently with encouragement of innovation and creativity, using a relatively brief and concise, but adequate, regulatory base

Fiscal year 1999 waste information requirements document

International Nuclear Information System (INIS)

Adams, M.R.

1998-01-01

The Waste Information Requirements Document (WIRD) has the following purposes: To describe the overall drivers that require characterization information and to document their source; To define how characterization is going to satisfy the drivers, close issues, and measure and report progress; and To describe deliverables and acceptance criteria for characterization. Characterization information is required to maintain regulatory compliance, perform operations and maintenance, resolve safety issues, and prepare for disposal of waste. Commitments addressing these requirements are derived from the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement; the Recommendation 93-5 Implementation Plan (DOE-RL 1996a) to the Defense Nuclear Facilities Safety Board (DNFSB); and other requirement sources listed in Section 2.0. The Waste Information Requirements Document replaces the tank waste analysis plans and the tank characterization plan previously required by the Tri-Party Agreement, Milestone M-44-01 and M-44-02 series

Setting clear expectations for safety basis development

International Nuclear Information System (INIS)

MORENO, M.R.

2003-01-01

DOE-RL has set clear expectations for a cost-effective approach for achieving compliance with the Nuclear Safety Management requirements (10 CFR 830, Nuclear Safety Rule) which will ensure long-term benefit to Hanford. To facilitate implementation of these expectations, tools were developed to streamline and standardize safety analysis and safety document development resulting in a shorter and more predictable DOE approval cycle. A Hanford Safety Analysis and Risk Assessment Handbook (SARAH) was issued to standardized methodologies for development of safety analyses. A Microsoft Excel spreadsheet (RADIDOSE) was issued for the evaluation of radiological consequences for accident scenarios often postulated for Hanford. A standard Site Documented Safety Analysis (DSA) detailing the safety management programs was issued for use as a means of compliance with a majority of 3009 Standard chapters. An in-process review was developed between DOE and the Contractor to facilitate DOE approval and provide early course correction. As a result of setting expectations and providing safety analysis tools, the four Hanford Site waste management nuclear facilities were able to integrate into one Master Waste Management Documented Safety Analysis (WM-DSA)

Safety in nuclear power systems

International Nuclear Information System (INIS)

Myers, L.C.

1987-05-01

This paper discusses the issue of safety in complex energy systems and provides brief accounts of some of the most serious reactor accidents that have occurred to date. Details are also provided of Ontario Hydro's problems with Unit 2 at Pickering

Improved safety at CERN

CERN Multimedia

2006-01-01

As announced in Weekly Bulletin No. 43/2006, a new approach to the implementation of Safety at CERN has been decided, which required taking some managerial decisions. The guidelines of the new approach are described in the document 'New approach to Safety implementation at CERN', which also summarizes the main managerial decisions I have taken to strengthen compliance with the CERN Safety policy and Rules. To this end I have also reviewed the mandates of the Safety Commission and the Safety Policy Committee (SAPOCO). Some details of the document 'Safety Policy at CERN' (also known as SAPOCO42) have been modified accordingly; its essential principles, unchanged, remain the basis for the safety policy of the Organisation. I would also like to inform you that I have appointed Dr M. Bona as the new Head of the Safety Commission until 31.12.2008, and that I will proceed soon to the appointment of the members of the new Safety Policy Committee. All members of the personnel are deemed to have taken note of the d...

Integrating Occupational Health and Safety into TAFE Courses: Curriculum Topics.

Science.gov (United States)

Hall, Bob; Mageean, Pauline

This guide is designed to help technical and further education (TAFE) curriculum writers in Australia integrate safety education into vocational education courses. It provides a general overview of occupational health and safety from the perspective of TAFE trade training and a brief summary of the major health and safety issues that might be…

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

Safety culture and the 5 steps to safer surgery: an intervention study.

Science.gov (United States)

Hill, M R; Roberts, M J; Alderson, M L; Gale, T C E

2015-06-01

Improvements in safety culture have been postulated as one of the mechanisms underlying the association between the introduction of the World Health Organisation (WHO) Surgical Safety Checklist with perioperative briefings and debriefings, and enhanced patient outcomes. The 5 Steps to Safer Surgery (5SSS) incorporates pre-list briefings, the three steps of the WHO Surgical Safety Checklist (SSC) and post-list debriefings in one framework. We aimed to identify any changes in safety culture associated with the introduction of the 5SSS in orthopaedic operating theatres. We assessed the safety culture in the elective orthopaedic theatres of a large UK teaching hospital before and after introduction of the 5SSS using a modified version of the Safety Attitude Questionnaire - Operating Room (SAQ-OR). Primary outcome measures were pre-post intervention changes in the six safety culture domains of the SAQ-OR. We also analysed changes in responses to two items regarding perioperative briefings. The SAQ-OR survey response rate was 80% (60/75) at baseline and 74% (53/72) one yr later. There were significant improvements in both the reported frequency (Pculture domain scores (Working Conditions, Perceptions of Management, Job Satisfaction, Safety Climate and Teamwork Climate) of the SAQ-OR (Pculture of elective orthopaedic operating theatres. © The Author 2015. Published by Oxford University Press on behalf of the British Journal of Anaesthesia. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

X-ray safety in Ontario

International Nuclear Information System (INIS)

1980-03-01

In July 1979 the Ontario Advisory Committee on Radiology was formed to develop a comprehensive strategy for x-ray safety in the province. At its hearings the committee recieved submissions from groups representing physicians, dentists, chiropractors, radiological technicians, physiotherapists, podiatrists, and consumers, among others; these briefs are included as appendices to the report. The report surveys the historical background and the current situation in Ontario, and makes recommendations for an organized safety program. (L.L.)

Safety and Toxicology of Cannabinoids

OpenAIRE

Sachs, Jane; McGlade, Erin; Yurgelun-Todd, Deborah

2015-01-01

There is extensive research on the safety, toxicology, potency, and therapeutic potential of cannabis. However, uncertainty remains facilitating continued debate on medical and recreational cannabis policies at the state and federal levels. This review will include a brief description of cannabinoids and the endocannabinoid system; a summary of the acute and long-term effects of cannabis; and a discussion of the therapeutic potential of cannabis. The conclusions about safety and efficacy will...

The methodological seminar “Psychological Safety in Transport”

Directory of Open Access Journals (Sweden)

Sviridenko I.N.

2018-03-01

Full Text Available This paper provides a short brief overview of the methodological seminar “Psychological Safety in Transport” organized in Yekaterinburg on the 17th November 2017. This seminar consisted of the plenary session and four workshops focused on analyzing most important issues of Human Factor of Road Safety.

Safety Review related to Commercial Grade Digital Equipment in Safety System

International Nuclear Information System (INIS)

Yu, Yeongjin; Park, Hyunshin; Yu, Yeongjin; Lee, Jaeheung

2013-01-01

The upgrades or replacement of I and C systems on safety system typically involve digital equipment developed in accordance with non-nuclear standards. However, the use of commercial grade digital equipment could include the vulnerability for software common-mode failure, electromagnetic interference and unanticipated problems. Although guidelines and standards for dedication methods of commercial grade digital equipment are provided, there are some difficulties to apply the methods to commercial grade digital equipment for safety system. This paper focuses on regulatory guidelines and relevant documents for commercial grade digital equipment and presents safety review experiences related to commercial grade digital equipment in safety system. This paper focuses on KINS regulatory guides and relevant documents for dedication of commercial grade digital equipment and presents safety review experiences related to commercial grade digital equipment in safety system. Dedication including critical characteristics is required to use the commercial grade digital equipment on safety system in accordance with KEPIC ENB 6370 and EPRI TR-106439. The dedication process should be controlled in a configuration management process. Appropriate methods, criteria and evaluation result should be provided to verify acceptability of the commercial digital equipment used for safety function

Nuclear safety review for the year 2000

International Nuclear Information System (INIS)

2001-06-01

The nuclear safety review for the year 2000 reports on worldwide efforts to strengthen nuclear and radiation safety, including radioactive waste safety. It is in three parts: Part 1 describes those events in 2000 that have, or may have, significance for nuclear, radiation and waste safety worldwide. It includes developments such as new initiatives in international cooperation, events of safety significance and events that may be indicative of trends in safety; Part 2 describes some of the IAEA efforts to strengthen international co-operation in nuclear, radiation and waste safety during 2000. It covers legally binding international agreements, non-binding safety standards, and provisions for the application of safety standards. This is done in a very brief manner, because these issues are addressed in more detail in the Agency's Annual Report for 2000; Part 3 presents a brief look ahead to some issues that are likely to be prominent in the coming year(s). The topics covered were selected by the IAEA Secretariat on the basis of trends observed in recent years, account being taken of planned or expected future developments. A draft of the Nuclear Safety Review for the Year 2000 was presented to the March 2001 session of the IAEA Board of Governors. This final version has been prepared taking account of the discussion in the Board. In some places, information has been added to describe developments early in 2001 that were considered pertinent to the discussion of events during 2000. In such cases, a note containing the more recent information has been provided in the form of a footnote

GSFC Safety and Mission Assurance Organization

Science.gov (United States)

Kelly, Michael P.

2010-01-01

This viewgraph presentation reviews NASA Goddard Space Flight Center's approach to safety and mission assurance. The contents include: 1) NASA GSFC Background; 2) Safety and Mission Assurance Directorate; 3) The Role of SMA-D and the Technical Authority; 4) GSFC Mission assurance Requirements; 5) GSFC Systems Review Office (SRO); 6) GSFC Supply Chain Management Program; and 7) GSFC ISO9001/AS9100 Status Brief.

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

The Problem with Briefs, in Brief

Science.gov (United States)

Conaway, Carrie L.

2013-01-01

Policy briefs written by academics--the kind typically published in "Education Finance and Policy"--should be a crucial source of information for policy makers. Yet too frequently these briefs fail to garner the consideration they deserve. Their authors are too focused on the potential objections of their fellow academics, who are…

Project brief of pre-contract in project management

International Nuclear Information System (INIS)

Mohd Jamil Hashim; Mohd Azmi Sidid Omar; Abdul Rahman Norazumin; Zakaria Dris; Abdul Murad Abu Bakar; Alwi Othman

2010-01-01

Project brief is a comprehensive document used in translating the user needs and requirement for the project implementation. This document is important for the designer as a main guidance towards establishing project details. Research shown that problem usually arises from not well-defined scope and needs by the user. With lack of information the designer tend to assume and interprets wrong translation. Other issues arise from project management are time, cost, budgetary, lack of communication and establishing quality management. Some ideas of improvement were gain by doing cross reference with JKR quality system management, workshop and brainstorming. It shows that an improvement of data collection system has to be integrating with some basic format details, drawings and declaration forms to be established. (author)

Reviewing industrial safety in nuclear power plants

International Nuclear Information System (INIS)

1990-02-01

This document contains guidance and reference materials for Operational Safety Review Team (OSART) experts, in addition to the OSART Guidelines (TECDOC-449), for use in the review of industrial safety activities at nuclear power plants. It sets out objectives for an excellent industrial safety programme, and suggests investigations which should be made in evaluating industrial safety programmes. The attributes of an excellent industrial safety programme are listed as examples for comparison. Practical hints for reviewing industrial safety are discussed, so that the necessary information can be obtained effectively through a review of documents and records, discussions with counterparts, and field observations. There are several annexes. These deal with major features of industrial safety programmes such as safety committees, reporting and investigation systems and first aid and medical facilities. They include some examples which are considered commendable. The document should be taken into account not only when reviewing management, organization and administration but also in the review of related areas, such as maintenance and operations, so that all aspects of industrial safety in an operating nuclear power plant are covered

Content accessibility of Web documents: Overview of concepts and needed standards

DEFF Research Database (Denmark)

Alapetite, A.

2006-01-01

The concept of Web accessibility refers to a combined set of measures, namely, how easily and how efficiently different types of users may make use of a given service. While some recommendations for accessibility are focusing on people with variousspecific disabilities, this document seeks...... to broaden the scope to any type of user and any type of use case. The document provides an introduction to some required concepts and technical standards for designing accessible Web sites. A brief review of thelegal requirements in a few countries for Web accessibility complements the recommendations...

Reload core safety verification

International Nuclear Information System (INIS)

Svetlik, M.; Minarcin, M.

2003-01-01

This paper presents a brief look at the process of reload core safety evaluation and verification in Slovak Republic. It gives an overview of experimental verification of selected nuclear parameters in the course of physics testing during reactor start-up. The comparison of IAEA recommendations and testing procedures at Slovak and European nuclear power plants of similar design is included. An introduction of two level criteria for evaluation of tests represents an effort to formulate the relation between safety evaluation and measured values (Authors)

Ferrocyanide Safety Program rationale for removing six tanks from the safety watch list

International Nuclear Information System (INIS)

Borsheim, G.L.

1993-09-01

This report documents an in-depth study of single-shell tanks containing ferrocyanide wastes. Topics include: safety assessments, tank histories, supportive documentation about interim stabilization and planned remedial activities

Safety assessment requirements for onsite transfers of radioactive material

International Nuclear Information System (INIS)

Opperman, E.K.; Jackson, E.J.; Eggers, A.G.

1992-05-01

This document contains the requirements for developing a safety assessment document for an onsite package containing radioactive material. It also provides format and content guidance to establish uniformity in the safety assessment documentation and to ensure completeness of the information provided

Effects of a Brief Video Intervention on White University Students' Racial Attitudes

Science.gov (United States)

Soble, Jason R.; Spanierman, Lisa B.; Liao, Hsin-Ya

2011-01-01

The authors investigated the effects of a brief video intervention on the racial attitudes of White university students. One hundred thirty-eight self-identified White students were randomly assigned to either an experimental condition in which they viewed a video documenting the pervasiveness of institutional racism and White privilege in the…

CNEA's quality system documentation

International Nuclear Information System (INIS)

Mazzini, M.M.; Garonis, O.H.

1998-01-01

Full text: To obtain an effective and coherent documentation system suitable for CNEA's Quality Management Program, we decided to organize the CNEA's quality documentation with : a- Level 1. Quality manual. b- Level 2. Procedures. c-Level 3. Qualities plans. d- Level 4: Instructions. e- Level 5. Records and other documents. The objective of this work is to present a standardization of the documentation of the CNEA's quality system of facilities, laboratories, services, and R and D activities. Considering the diversity of criteria and formats for elaboration the documentation by different departments, and since ultimately each of them generally includes the same quality management policy, we proposed the elaboration of a system in order to improve the documentation, avoiding unnecessary time wasting and costs. This will aloud each sector to focus on their specific documentation. The quality manuals of the atomic centers fulfill the rule 3.6.1 of the Nuclear Regulatory Authority, and the Safety Series 50-C/SG-Q of the International Atomic Energy Agency. They are designed by groups of competent and highly trained people of different departments. The normative procedures are elaborated with the same methodology as the quality manuals. The quality plans which describe the organizational structure of working group and the appropriate documentation, will asses the quality manuals of facilities, laboratories, services, and research and development activities of atomic centers. The responsibilities for approval of the normative documentation are assigned to the management in charge of the administration of economic and human resources in order to fulfill the institutional objectives. Another improvement aimed to eliminate unnecessary invaluable processes is the inclusion of all quality system's normative documentation in the CNEA intranet. (author) [es

Safe Transport of Radioactive Material, International Regulations and its Supporting Documents

International Nuclear Information System (INIS)

El-Shinawy, R.M.K.

2005-01-01

Safe transport of radioactive material regulations issued by IAEA since 1961, provide standards for insuring a high level of safety of people,transport workers, property and environment against radiation, contamination and criticality hazards as well as thermal effects associated with the transport of the radioactive wastes and material. The history ,development, philosophy and scope of these international regulations were mentioned as well as the different supporting documents to the regulations for safe transport of radioactive material were identified.The first supporting document , namely TS - G-1.1 ( ST-2) ,Advisory material is also issued by the IAEA.It contains both the advisory and explanatory materials previously published in safety series No 7 and 37 and therefore TS-G-1.1 (ST-2) will supersede safety series No 7 and 37. The second supporting document namely TS-G-1.2 (ST-3), planning and preparing for emergency response to transport accidents involving radioactive material ,which will supersede safety series No 87. In addition to quality assurance (SS=113), compliance assurance (SS=112), the training manual and other

Safe Transport of Radioactive Material, International Regulations and its Supporting Documents

Energy Technology Data Exchange (ETDEWEB)

El-Shinawy, R M.K. [Radiation Protection Dept., NRC, Atomic Energy Authority, Cairo (Egypt)

2005-04-01

Safe transport of radioactive material regulations issued by IAEA since 1961, provide standards for insuring a high level of safety of people,transport workers, property and environment against radiation, contamination and criticality hazards as well as thermal effects associated with the transport of the radioactive wastes and material. The history ,development, philosophy and scope of these international regulations were mentioned as well as the different supporting documents to the regulations for safe transport of radioactive material were identified.The first supporting document , namely TS - G-1.1 ( ST-2) ,Advisory material is also issued by the IAEA.It contains both the advisory and explanatory materials previously published in safety series No 7 and 37 and therefore TS-G-1.1 (ST-2) will supersede safety series No 7 and 37. The second supporting document namely TS-G-1.2 (ST-3), planning and preparing for emergency response to transport accidents involving radioactive material ,which will supersede safety series No 87. In addition to quality assurance (SS=113), compliance assurance (SS=112), the training manual and other.

Safety; Avertissement

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

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

Software Safety Risk in Legacy Safety-Critical Computer Systems

Science.gov (United States)

Hill, Janice L.; Baggs, Rhoda

2007-01-01

Safety Standards contain technical and process-oriented safety requirements. Technical requirements are those such as "must work" and "must not work" functions in the system. Process-Oriented requirements are software engineering and safety management process requirements. Address the system perspective and some cover just software in the system > NASA-STD-8719.13B Software Safety Standard is the current standard of interest. NASA programs/projects will have their own set of safety requirements derived from the standard. Safety Cases: a) Documented demonstration that a system complies with the specified safety requirements. b) Evidence is gathered on the integrity of the system and put forward as an argued case. [Gardener (ed.)] c) Problems occur when trying to meet safety standards, and thus make retrospective safety cases, in legacy safety-critical computer systems.

Campaign To Reduce Child Poverty. Progress Report [and] Policy Briefs 1-5.

Science.gov (United States)

New Mexico Advocates for Children & Families, Albuquerque.

This document is comprised of a progress report and five policy briefs related to the New Mexico Advocates for Children and Families' Campaign To Reduce Child Poverty. This multi-year initiative educates the public and policymakers about child poverty and promotes public policy changes that would reduce poverty. The progress report presents…

Document status for 1 and 2 Kozloduy NPP decommissioning activities -Phase 'Final Shutdown'

International Nuclear Information System (INIS)

Vangev, A.; Boyadjiev, Z.

1997-01-01

Decommissioning process (D and D) is the final phase of each nuclear reactor life cycle. The first nuclear reactor generation has reached his expiration life date. Decommissioning working documentation had not been taken into account at the project and construction stage. The decommissioning activities, planning and legislation has to develop along their operation. Most of developed nuclear energetic countries have gathered good experience and have create their own decommissioning strategy. This report represents in brief an overview of different country's approaches and the Kozloduy NPP decommissioning activity intention in near future and reviews the D and D working document status for 1 and 2 Kozloduy NPP Units decommissioning. Kozloduy NPP D and D task to the moment is to plan the first stage of the decommissioning process - 'The Final Shutdown' and to prepare the working documents for the phase execution. The Final Shutdown of Kozloduy NPP - 1 is the termination of operation of the Units 1 and 2 and the electricity production cessation after their useful life exhaust. In accordance with the legal legislation in Bulgaria only the normal planned termination of operation on units 1 and 2 should be prescribed. The project results concern the initial condition of the equipment and systems, their preparation and sequence for defueling, decontamination and dismantling. A plan for activities' organization for D and D and Complex Characterization of the Site under consideration will contain the following documents: 1. Time-schedule for the sequence of activities during the stages of the Final Shutdown and Safe Enclosure preparation. Technical project for organization of work related to Final Shutdown; 2. Complex Characterization Programme for a condition investigation of the Units 1 and 2 equipment and systems. 3. Technical project for design modifications and dismantling of equipment and systems which violate the radiation and nuclear safety during the Final Shutdown

Measures to strengthen international co-operation in nuclear, radiation and transport safety and waste management. Nuclear safety review for the year 2003

International Nuclear Information System (INIS)

2004-01-01

The Nuclear Safety Review for the Year 2003 presents an overview of the current issues and trends in nuclear, radiation, transport and radioactive waste safety during 2003. As in 2002 the overview is supported by more detailed Notes by the Secretariat: Safety Related Events and Issues Worldwide during 2003 (document 2004/Note 6), The Agency's Safety Standards: Activities during 2003 (document 2004/Note 7) and Providing for the Application of the Safety Standards (document 2004/Note 8). In January 2003, the Agency implemented an organization change and developed an integrated approach to reflect a broader assignment of nuclear safety and nuclear security and to better exploit synergy between them. The Office of Physical Protection and Material Security renamed to Office of Nuclear Security was transferred from the Department of Safeguards to the Department of Nuclear Safety, which became the Department of Nuclear Safety and Security to reflect the change. This Review provides information primarily on nuclear safety, and nuclear security will be addressed in a separate report

Safety assessment of research reactors and preparation of the safety analysis report

International Nuclear Information System (INIS)

1994-01-01

This Safety Guide presents guidelines, approved by international consensus, for the preparation, review and assessment of safety documentation for research reactors such as the Safety Analysis Report. While the Guide is most applicable to research reactors in the design and construction stage, it is also recommended for use during relicensing or reassessment of existing reactors

Nuclear Criticality Safety Department Qualification Program

International Nuclear Information System (INIS)

Carroll, K.J.; Taylor, R.G.; Worley, C.A.

1996-01-01

The Nuclear Criticality Safety Department (NCSD) is committed to developing and maintaining a staff of highly qualified personnel to meet the current and anticipated needs in Nuclear Criticality Safety (NCS) at the Oak Ridge Y-12 Plant. This document defines the Qualification Program to address the NCSD technical and managerial qualification as required by the Y-1 2 Training Implementation Matrix (TIM). This Qualification Program is in compliance with DOE Order 5480.20A and applicable Lockheed Martin Energy Systems, Inc. (LMES) and Y-1 2 Plant procedures. It is implemented through a combination of WES plant-wide training courses and professional nuclear criticality safety training provided within the department. This document supersedes Y/DD-694, Revision 2, 2/27/96, Qualification Program, Nuclear Criticality Safety Department There are no backfit requirements associated with revisions to this document

Overview of the fundamental safety principles

International Nuclear Information System (INIS)

Chishinga, Milton Mulenga

2015-02-01

The primary objective of this work was to provide an overview of the International Atomic Energy (IAEA) document; 'Fundamental Safety principles, SF.1'. The document outlines ten (10) fundamental principles which provide the basis for an effective the radiation protection framework. The document is the topmost in the hierarchy of the IAEA Safety Standards Series. These principles are the foundation of the nuclear safety put stringent obligations on Parties under the Convention on Nuclear Safety. The fundamental safety objective is to protect people and the environment from harmful effects of ionizing radiation. The fundamental Safety objective of protecting people individually and collectively and the environment has to be achieved without unduly limiting the operation of facilities or the conduct of activities that give rise to risks. The thematic areas covered are; responsibility for safety, role of government, leadership and management for safety, justification of facilities and activities, optimization of protection, limitation of risks to individuals, protection of present and future generations, prevention of accidents, emergency preparedness and response and protective actions to reduce existing or unregulated radiation risks. Appropriate recommendations have been provided for effective application of the principles by Governments, Regulatory Bodies and Operating Organizations of facilities and Nuclear Installations the give rise to radiation risks. (au)

B plant standards/requirements identification document (S/RID)

Energy Technology Data Exchange (ETDEWEB)

Maddox, B.S., Westinghouse Hanford

1996-07-29

This Standards/Requirements Identification Document (S/RID) set forth the Environmental Safety and Health (ES{ampersand}H) standards/requirements for the B Plant. This S/RID is applicable to the appropriate life cycle phases of design, construction,operation, and preparation for decommissioning. These standards/requirements are adequate to ensure the protection of the health and safety of workers, the public, and the environment.

The IAEA safety standards

International Nuclear Information System (INIS)

Karbassioun, Ahmad

1995-01-01

During the development of the NUSS standards, wide consultation was carried out with all the Member States to obtain a consensus and the programme was supervised by a Senior Advisory Group consisting of senior safety experts from 13 countries. This group of senior regulators later became what is now known as the Nuclear Safety Standards Advisory Group (NUSSAG) and comprises of senior regulatory experts from 16 countries. The standards that were developed comprise of four types of documents: safety fundamentals; codes of practice; safety guides; and safety practices. The safety fundamentals set out the basic objectives, concepts and principles for nuclear safety in nuclear power plants. The codes of practice, are of a legislative nature, and establish the general objectives that must be fulfilled to ensure adequate nuclear power plant safety. They cover five areas: governmental organization; siting, design, operation and quality assurance. The safety guides, administrative in character, recommend procedures and acceptable technical solutions to implement the codes and guides by presenting further details gained from Member States, on the application and interpretation of individual concepts in the NUSS codes and guides. In total in the NUSS series there is currently one Fundamentals document, five Codes of Practice and fifty-six Safety Guides

Clinical decision support improves quality of telephone triage documentation--an analysis of triage documentation before and after computerized clinical decision support.

Science.gov (United States)

North, Frederick; Richards, Debra D; Bremseth, Kimberly A; Lee, Mary R; Cox, Debra L; Varkey, Prathibha; Stroebel, Robert J

2014-03-20

Clinical decision support (CDS) has been shown to be effective in improving medical safety and quality but there is little information on how telephone triage benefits from CDS. The aim of our study was to compare triage documentation quality associated with the use of a clinical decision support tool, ExpertRN©. We examined 50 triage documents before and after a CDS tool was used in nursing triage. To control for the effects of CDS training we had an additional control group of triage documents created by nurses who were trained in the CDS tool, but who did not use it in selected notes. The CDS intervention cohort of triage notes was compared to both the pre-CDS notes and the CDS trained (but not using CDS) cohort. Cohorts were compared using the documentation standards of the American Academy of Ambulatory Care Nursing (AAACN). We also compared triage note content (documentation of associated positive and negative features relating to the symptoms, self-care instructions, and warning signs to watch for), and documentation defects pertinent to triage safety. Three of five AAACN documentation standards were significantly improved with CDS. There was a mean of 36.7 symptom features documented in triage notes for the CDS group but only 10.7 symptom features in the pre-CDS cohort (p < 0.0001) and 10.2 for the cohort that was CDS-trained but not using CDS (p < 0.0001). The difference between the mean of 10.2 symptom features documented in the pre-CDS and the mean of 10.7 symptom features documented in the CDS-trained but not using was not statistically significant (p = 0.68). CDS significantly improves triage note documentation quality. CDS-aided triage notes had significantly more information about symptoms, warning signs and self-care. The changes in triage documentation appeared to be the result of the CDS alone and not due to any CDS training that came with the CDS intervention. Although this study shows that CDS can improve documentation, further study is needed

Levels of safety satisfactory for commercialization of the breeder

International Nuclear Information System (INIS)

Ferguson, R.L.

1979-01-01

A brief discussion is presented of the Department of Energy's LMFBR safety program and the safety levels which DOE believes would be satisfactory for the commercialization of the breeder are indicated. Some observations are offered on the Three Mile Island accident and some of its implications are discussed for the LMFBR program

First Steps to Endangered Language Documentation: The Kalasha Language, a Case Study

Science.gov (United States)

Mela-Athanasopoulou, Elizabeth

2011-01-01

The present paper based on extensive fieldwork D conducted on Kalasha, an endangered language spoken in the three small valleys in Chitral District of Northwestern Pakistan, exposes a spontaneous dialogue-based elicitation of linguistic material used for the description and documentation of the language. After a brief display of the basic typology…

Seismic qualification of non-safety class equipment whose failure would damage safety class equipment

International Nuclear Information System (INIS)

LaSalle, F.R.

1991-01-01

Both Code of Federal Regulations, Title 10, Part 50, and US Department of Energy Order 6340.1A have requirements to assess the interaction of non-safety and safety class structures and equipment during a seismic event to maintain the safety function. At the Hanford Site, a cost effective program has been developed to perform the evaluation of non-safety class equipment. Seismic qualification is performed by analysis, test, or upgrading of the equipment to ensure the integrity of safety class structures and equipment. This paper gives a brief overview and synopsis that address design analysis guidelines including applied loading, damping values, component anchorage, allowable loads, and stresses. Test qualification of equipment and walkdown acceptance criteria for heating ampersand ventilation (H ampersand V) ducting, conduit, cable tray, missile zone of influence, as well as energy criteria are presented

Monitored Retrievable Storage System Requirements Document

International Nuclear Information System (INIS)

1994-03-01

This Monitored Retrievable Storage System Requirements Document (MRS-SRD) describes the functions to be performed and technical requirements for a Monitored Retrievable Storage (MRS) facility subelement and the On-Site Transfer and Storage (OSTS) subelement. The MRS facility subelement provides for temporary storage, at a Civilian Radioactive Waste Management System (CRWMS) operated site, of spent nuclear fuel (SNF) contained in an NRC-approved Multi-Purpose Canister (MPC) storage mode, or other NRC-approved storage modes. The OSTS subelement provides for transfer and storage, at Purchaser sites, of spent nuclear fuel (SNF) contained in MPCs. Both the MRS facility subelement and the OSTS subelement are in support of the CRWMS. The purpose of the MRS-SRD is to define the top-level requirements for the development of the MRS facility and the OSTS. These requirements include design, operation, and decommissioning requirements to the extent they impact on the physical development of the MRS facility and the OSTS. The document also presents an overall description of the MRS facility and the OSTS, their functions (derived by extending the functional analysis documented by the Physical System Requirements (PSR) Store Waste Document), their segments, and the requirements allocated to the segments. In addition, the top-level interface requirements of the MRS facility and the OSTS are included. As such, the MRS-SRD provides the technical baseline for the MRS Safety Analysis Report (SAR) design and the OSTS Safety Analysis Report design

High level waste storage tanks 242-A evaporator standards/requirement identification document

International Nuclear Information System (INIS)

Biebesheimer, E.

1996-01-01

This document, the Standards/Requirements Identification Document (S/RIDS) for the subject facility, represents the necessary and sufficient requirements to provide an adequate level of protection of the worker, public health and safety, and the environment. It lists those source documents from which requirements were extracted, and those requirements documents considered, but from which no requirements where taken. Documents considered as source documents included State and Federal Regulations, DOE Orders, and DOE Standards

Food irradiation: Its role in food safety

International Nuclear Information System (INIS)

Qureshi, R.U.

1985-01-01

This document provides a brief overview of the process of food irradiation and describes the potential for food irradiation in the Asia-Pacific region. The advantages in controlling food-borne diseases and in promoting trade are discussed. 4 tabs

[Patient safety in home care - A review of international recommendations].

Science.gov (United States)

Czakert, Judith; Lehmann, Yvonne; Ewers, Michael

2018-06-08

In recent years there has been a growing trend towards nursing care at home in general as well as towards intensive home care being provided by specialized home care services in Germany. However, resulting challenges for patient safety have rarely been considered. Against this background we aimed to explore whether international recommendations for patient safety in home care in general and in intensive home care in particular already exist and how they can stimulate further practice development in Germany. A review of online English documents containing recommendations for patient safety in intensive home care was conducted. Available documents were analyzed and compared in terms of their form and content. Overall, a small number of relevant documents could be identified. None of these documents exclusively refer to the intensive home care sector. Despite their differences, however, the analysis of four selected documents showed similarities, e. g., regarding specific topics of patient safety (communication, involvement of patients and their relatives, risk assessment, medication management, qualification). Furthermore, strengths and weaknesses of the documents became apparent: e. g., an explicit understanding of patient safety, a literature-based introduction to safety topics or an adaptation of the recommendations to the specific features of home care were occasionally lacking. This document analysis provides interesting input to the formal and content-related development of specific recommendations and to practice development in Germany to improve patient safety in home care. Copyright © 2018. Published by Elsevier GmbH.

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.

The safety of pressurized water reactors

International Nuclear Information System (INIS)

Panossian, J.; Tanguy, P.

1991-01-01

In this paper we present a review of the status of the safety level of modern pressurized water reactors, that is to say those that meet the safety criteria accepted today by the international nuclear community. We will mainly rely on the operating experience and the Probabilistic Safety Assessments concerning French reactors. We will not back over the basic safety concepts of these reactors, which are well known. We begin with a brief review of some of the lessons learned from the two main accidents discussed in the present meeting. Three Mile Island and Chernobyl, without entering into details presented in previous papers. The presentation ends with a rather lengthy conclusion, aimed more at those not directly involved in the technical details of nuclear safety matters

FMCSA safety program effectiveness measurement : Roadside Intervention Effectiveness Model FY 2012, [analysis brief].

Science.gov (United States)

2016-02-01

Roadside Inspection and Traffic Enforcement are two of : the Federal Motor Carrier Safety Administrations : (FMCSAs) key safety programs. The Roadside : Inspection Program consists of roadside inspections : performed by qualified safety inspect...

Melter Disposal Strategic Planning Document

Energy Technology Data Exchange (ETDEWEB)

BURBANK, D.A.

2000-09-25

This document describes the proposed strategy for disposal of spent and failed melters from the tank waste treatment plant to be built by the Office of River Protection at the Hanford site in Washington. It describes program management activities, disposal and transportation systems, leachate management, permitting, and safety authorization basis approvals needed to execute the strategy.

29 CFR 1921.17 - Service; copies of documents and pleadings.

Science.gov (United States)

2010-07-01

... 29 Labor 7 2010-07-01 2010-07-01 false Service; copies of documents and pleadings. 1921.17 Section 1921.17 Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH ADMINISTRATION... LONGSHOREMEN'S AND HARBOR WORKERS' COMPENSATION ACT Miscellaneous § 1921.17 Service; copies of documents and...

FMCSA safety program effectiveness measurement : roadside intervention effectiveness model FY 2011 : [analysis brief].

Science.gov (United States)

2015-06-01

Roadside Inspection and Traffic Enforcement are two of the Federal Motor Carrier Safety Administrations (FMCSAs) key safety programs. The Roadside Inspection program consists of roadside inspections performed by qualified safety inspectors. The...

System Design and the Safety Basis

International Nuclear Information System (INIS)

Ellingson, Darrel

2008-01-01

The objective of this paper is to present the Bechtel Jacobs Company, LLC (BJC) Lessons Learned for system design as it relates to safety basis documentation. BJC has had to reconcile incomplete or outdated system description information with current facility safety basis for a number of situations in recent months. This paper has relevance in multiple topical areas including documented safety analysis, decontamination and decommissioning (D and D), safety basis (SB) implementation, safety and design integration, potential inadequacy of the safety analysis (PISA), technical safety requirements (TSR), and unreviewed safety questions. BJC learned that nuclear safety compliance relies on adequate and well documented system design information. A number of PIS As and TSR violations occurred due to inadequate or erroneous system design information. As a corrective action, BJC assessed the occurrences caused by systems design-safety basis interface problems. Safety systems reviewed included the Molten Salt Reactor Experiment (MSRE) Fluorination System, K-1065 fire alarm system, and the K-25 Radiation Criticality Accident Alarm System. The conclusion was that an inadequate knowledge of system design could result in continuous non-compliance issues relating to nuclear safety. This was especially true with older facilities that lacked current as-built drawings coupled with the loss of 'historical knowledge' as personnel retired or moved on in their careers. Walkdown of systems and the updating of drawings are imperative for nuclear safety compliance. System design integration with safety basis has relevance in the Department of Energy (DOE) complex. This paper presents the BJC Lessons Learned in this area. It will be of benefit to DOE contractors that manage and operate an aging population of nuclear facilities

High-level waste tank farm set point document

International Nuclear Information System (INIS)

Anthony, J.A. III.

1995-01-01

Setpoints for nuclear safety-related instrumentation are required for actions determined by the design authorization basis. Minimum requirements need to be established for assuring that setpoints are established and held within specified limits. This document establishes the controlling methodology for changing setpoints of all classifications. The instrumentation under consideration involve the transfer, storage, and volume reduction of radioactive liquid waste in the F- and H-Area High-Level Radioactive Waste Tank Farms. The setpoint document will encompass the PROCESS AREA listed in the Safety Analysis Report (SAR) (DPSTSA-200-10 Sup 18) which includes the diversion box HDB-8 facility. In addition to the PROCESS AREAS listed in the SAR, Building 299-H and the Effluent Transfer Facility (ETF) are also included in the scope

High-level waste tank farm set point document

Energy Technology Data Exchange (ETDEWEB)

Anthony, J.A. III

1995-01-15

Setpoints for nuclear safety-related instrumentation are required for actions determined by the design authorization basis. Minimum requirements need to be established for assuring that setpoints are established and held within specified limits. This document establishes the controlling methodology for changing setpoints of all classifications. The instrumentation under consideration involve the transfer, storage, and volume reduction of radioactive liquid waste in the F- and H-Area High-Level Radioactive Waste Tank Farms. The setpoint document will encompass the PROCESS AREA listed in the Safety Analysis Report (SAR) (DPSTSA-200-10 Sup 18) which includes the diversion box HDB-8 facility. In addition to the PROCESS AREAS listed in the SAR, Building 299-H and the Effluent Transfer Facility (ETF) are also included in the scope.

Continuous Improvement in Online Education: Documenting Teaching Effectiveness in the Online Environment through Observations

Science.gov (United States)

Purcell, Jennifer W.; Scott, Heather I.; Mixson-Brookshire, Deborah

2017-01-01

Teaching observations are commonly used among educators to document and improve teaching effectiveness. Unfortunately, the necessary protocols and supporting infrastructure are not consistently available for faculty who teach online. This paper presents a brief literature review and reflective narratives of educators representing online education…

Fire safety assessment of tunnel structures

DEFF Research Database (Denmark)

Gkoumas, Konstantinos; Giuliani, Luisa; Petrini, Francesco

2011-01-01

.g. structural and non structural, organizational, human behavior). This is even more truth for the fire safety design of such structures. Fire safety in tunnels is challenging because of the particular environment, bearing in mind also that a fire can occur in different phases of the tunnel’s lifecycle. Plans...... for upgrading fire safety provisions and tunnel management are also important for existing tunnels. In this study, following a brief introduction of issues regarding the above mentioned aspects, the structural performance of a steel rib for a tunnel infrastructure subject to fire is assessed by means...

Methodology briefing students in the safety on physical education in the gym

Directory of Open Access Journals (Sweden)

N. N. Mukhamediarov

2014-01-01

Full Text Available Purpose : to determine the effective components of the methodology of coaching students on safety on physical education in the gym. Material : in the experiment involved 90 students aged 17-18 years. Results : the method of forming responsible attitude to the basics of safety during physical training in the gym. Developed special funds: lectures, seminars, analysis of articles, diagnostic interviews, questionnaires, analysis of log data of attendance, log injuries. The criteria of formation responsible attitude to physical training. The results of the implementation methodology. Conclusions : proposed method recommend to instruct students on safety. Use the means of forming a responsible attitude to safety during physical training in the gym that will help reduce injuries and improve quality of the physical training at the university.

Management services, quality assurance, and safety

International Nuclear Information System (INIS)

Anon.

1987-01-01

Broad technical and administrative support for the programmatic research and development activities of the Fusion Energy Division is provided by the Management Services Section and by the division's quality assurance (QA) and safety programs. Support is provided through effective communication with division programmatic staff and through the coordination of resources from disciplines outside the division. The QA activity in the division emphasizes the development and documentation of a QA program that conforms to national standards, the review and approval of engineering documents, supplier surveillance, identification and documentation of nonconforming items, audits, and QA assessments/plans. The division's safety activities include a formal safety program, emergency planning activities, and environmental protection services. Efforts devoted to the removal of hazardous wastes from division facilities were expanded during 1986

Briefs for Parents in Ready-To-Copy Form: English and Spanish. 1993 Compilation.

Science.gov (United States)

Howley, Craig; Cahape, Pat

This document contains English and Spanish versions of six one-page reports for parents. Each brief provides background, suggestions, and sources of further information on educational and child-rearing topics of common interest to parents. Titles are: "The Best and Worst of Times: Support Groups Help" ("Los tiempos mejores y peores: Los grupos…

Analysis of the prevailing standard and technical documents for their applicability under conditions of the 'Ukrytie' operation and technical proposals relating to the elaboration of new ones concerning fire safety

International Nuclear Information System (INIS)

Nazarenko, B.S.; Emets, V.G.

1998-01-01

An analysis of the prevailing laws and standards and technical documents (STD) to ensure safe operation of nuclear power installations, with requirements of nuclear, radiation and fire safety taken into account, has been performed. Proposals on application of some items of prevailing STD under conditions of the 'Ukrytie' operation are presented. Also given are technical proposals on correction of the prevailing operational standard documents and elaboration of special STD

A brief scenario about the ''space pollution'' around the Earth

International Nuclear Information System (INIS)

Brito, T P; Celestino, C C; Moraes, R V

2013-01-01

In this work is presented a brief review about the main events generating of space debris around the Earth, occurred up to the present day. How the clouds of debris ''polluted'' the neighborhood of orbits in which the bodies were initially allocated is here analyzed. The implications of the growth of space debris existing on space missions as well as safety rules to control sources of debris are discussed

76 FR 5537 - Electronic On-Board Recorders and Hours of Service Supporting Documents

Science.gov (United States)

2011-02-01

... supporting documents influence driver operational safety rather than vehicular and mechanical safety... generate greater traffic congestion than a crash involving a CMV transporting other cargoes. Although these...

Safety Design Criteria of Indian Sodium Cooled Fast Reactors

International Nuclear Information System (INIS)

Pillai, P.; Chellapandi, P.; Chetal, S.C.; Vasudeva Rao, P.R.

2013-01-01

• Important feedback has been gained through the design and safety review of PFBR. • The safety criteria document prepared by AERB and IGCAR would provide important input to prepare the dedicated document for the Sodium cooled Fast Reactors at the national and international level. • A common approach with regard to safety, among countries pursuing fast reactor program, is desirable. • Sharing knowledge and experimental facilities on collaborative basis. • Evolution of strong safety criteria – fundamental to assure safety

Incident factor as a learning aspect to enhance safety culture in the experimental fuel element installation of PTBN - BATAN

International Nuclear Information System (INIS)

Heri Hardiyanti; Agus Sartono; Bambang Herutomo; AS Latief

2013-01-01

The safety of a nuclear facility depends not only on the fulfillment of all technical requirements, but also on the role of non-technical aspects. The primary causation of incidents or accidents in a nuclear facility is human error which is non-technical. Therefore, in order to enhance safety, efforts from the technical aspects are as important as efforts to deal with the human factor which can be done through the application of safety culture in the facility. Incidents that took place in the Experimental Fuel Element Installation (EFEI) of PTBN - BATAN from 2011 to 2012 were caused by aging instruments and human error. In order to prevent accidents and to enhance safety, non-technical efforts that were done in the EFEI were, interalia, the obligations on all personnel to attend the pre-lab briefing, to prepare a work proposal, to compose a HIRADC (hazard identification, risk assessment, and determining control) document, to utilize self protection devices, to perform a routine maintenance, and to practice safe behavior. All personnel were involved in all those efforts. Safety is the first priority and can always be improved in the facility. A strong commitment of and cooperation between the top management and the staff are needed. (author)

Nuclear Safety

Energy Technology Data Exchange (ETDEWEB)

Silver, E G [ed.

1989-01-01

This document is a review journal that covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

Instruments for documentation of music therapy sessions

DEFF Research Database (Denmark)

Ridder, Hanne Mette Ochsner

It is an important part of the clinical music therapy work to document the daily sessions. For the clinician it is necessary to have a brief overview of each session in order to assess the methods and the process, and not least to be able to give clear reports of these issues to other health care...... professionals at staff meetings, conferences, etc. For music therapists with many clients there is not time enough during a working day to provide comprehensive process descriptions in the music therapy log. Therefore instruments that help the clinician in reducing and structuring this information are needed....... Danish and Norwegian music therapist have collaborated on developing a one page sheet with a structured form where they after each music therapy session document their use of methods and techniques in individual music therapy with persons with dementia. With this instrument therapists have easy access...

ITER-FEAT safety

International Nuclear Information System (INIS)

Gordon, C.W.; Bartels, H.-W.; Honda, T.; Raeder, J.; Topilski, L.; Iseli, M.; Moshonas, K.; Taylor, N.; Gulden, W.; Kolbasov, B.; Inabe, T.; Tada, E.

2001-01-01

Safety has been an integral part of the design process for ITER since the Conceptual Design Activities of the project. The safety approach adopted in the ITER-FEAT design and the complementary assessments underway, to be documented in the Generic Site Safety Report (GSSR), are expected to help demonstrate the attractiveness of fusion and thereby set a good precedent for future fusion power reactors. The assessments address ITER's radiological hazards taking into account fusion's favourable safety characteristics. The expectation that ITER will need regulatory approval has influenced the entire safety design and assessment approach. This paper summarises the ITER-FEAT safety approach and assessments underway. (author)

New Safety rules

CERN Multimedia

Safety Commission

2008-01-01

The revision of CERN Safety rules is in progress and the following new Safety rules have been issued on 15-04-2008: Safety Procedure SP-R1 Establishing, Updating and Publishing CERN Safety rules: http://cern.ch/safety-rules/SP-R1.htm; Safety Regulation SR-S Smoking at CERN: http://cern.ch/safety-rules/SR-S.htm; Safety Regulation SR-M Mechanical Equipment: http://cern.ch/safety-rules/SR-M.htm; General Safety Instruction GSI-M1 Standard Lifting Equipment: http://cern.ch/safety-rules/GSI-M1.htm; General Safety Instruction GSI-M2 Standard Pressure Equipment: http://cern.ch/safety-rules/GSI-M2.htm; General Safety Instruction GSI-M3 Special Mechanical Equipment: http://cern.ch/safety-rules/GSI-M3.htm. These documents apply to all persons under the Director General’s authority. All Safety rules are available at the web page: http://www.cern.ch/safety-rules The Safety Commission

Development of digital library system on regulatory documents for nuclear power plants

International Nuclear Information System (INIS)

Lee, K. H.; Kim, K. J.; Yoon, Y. H.; Kim, M. W.; Lee, J. I.

2001-01-01

The main objective of this study is to establish nuclear regulatory document retrieval system based on internet. With the advancement of internet and information processing technology, information management patterns are going through a new paradigm. Getting along the current of the time, it is general tendency to transfer paper-type documents into electronic-type documents through document scanning and indexing. This system consists of nuclear regulatory documents, nuclear safety documents, digital library, and information system with index and full text

Safety and Toxicology of Cannabinoids.

Science.gov (United States)

Sachs, Jane; McGlade, Erin; Yurgelun-Todd, Deborah

2015-10-01

There is extensive research on the safety, toxicology, potency, and therapeutic potential of cannabis. However, uncertainty remains facilitating continued debate on medical and recreational cannabis policies at the state and federal levels. This review will include a brief description of cannabinoids and the endocannabinoid system; a summary of the acute and long-term effects of cannabis; and a discussion of the therapeutic potential of cannabis. The conclusions about safety and efficacy will then be compared with the current social and political climate to suggest future policy directions and general guidelines.

Supporting documents for LLL area 27 (410 area) safety analysis reports, Nevada Test Site

Energy Technology Data Exchange (ETDEWEB)

Odell, B. N. [comp.

1977-02-01

The following appendices are common to the LLL Safety Analysis Reports Nevada Test Site and are included here as supporting documents to those reports: Environmental Monitoring Report for the Nevada Test Site and Other Test Areas Used for Underground Nuclear Detonations, U. S. Environmental Protection Agency, Las Vegas, Rept. EMSL-LV-539-4 (1976); Selected Census Information Around the Nevada Test Site, U. S. Environmental Protection Agency, Las Vegas, Rept. NERC-LV-539-8 (1973); W. J. Hannon and H. L. McKague, An Examination of the Geology and Seismology Associated with Area 410 at the Nevada Test Site, Lawrence Livermore Laboratory, Livermore, Rept. UCRL-51830 (1975); K. R. Peterson, Diffusion Climatology for Hypothetical Accidents in Area 410 of the Nevada Test Site, Lawrence Livermore Laboratory, Livermore, Rept. UCRL-52074 (1976); J. R. McDonald, J. E. Minor, and K. C. Mehta, Development of a Design Basis Tornado and Structural Design Criteria for the Nevada Test Site, Nevada, Lawrence Livermore Laboratory, Livermore, Rept. UCRL-13668 (1975); A. E. Stevenson, Impact Tests of Wind-Borne Wooden Missiles, Sandia Laboratories, Tonopah, Rept. SAND 76-0407 (1976); and Hydrology of the 410 Area (Area 27) at the Nevada Test Site.

Safety improvements of Temelin NPP

International Nuclear Information System (INIS)

Vita, J.

2000-01-01

A detailed overview is given of the efforts made to enhance the safety level of the plant considering recommendations of a number of assessment missions. A list is presented of 10 international missions of the IAEA at the Temelin plant, covering the period 1990 to 1998. For each mission the date and objective is given, the focus of the assessment is characterized, the international participation of experts is specified, and the main conclusions of the experts is reproduced. A commented list of 60 main design changes and safety improvements is also included, as they were implemented in the wake of various safety assessments. An overview of the Temelin safety improvement programme is attached, comprising brief descriptions of 30 planned improvement items together with the time schedules. (A.K.)

Development and Application of Level 2 Probabilistic Safety Assessment for Nuclear Power Plants. Specific Safety Guide

International Nuclear Information System (INIS)

2010-01-01

The objective of this Safety Guide is to provide recommendations for meeting the IAEA safety requirements in performing or managing a level 2 probabilistic safety assessment (PSA) project for a nuclear power plant; thus it complements the Safety Guide on level 1 PSA. One of the aims of this Safety Guide is to promote a standard framework, standard terms and a standard set of documents for level 2 PSAs to facilitate regulatory and external peer review of their results. It describes all elements of the level 2 PSA that need to be carried out if the starting point is a fully comprehensive level 1 PSA. Contents: 1. Introduction; 2. PSA project management and organization; 3. Identification of design aspects important to severe accidents and acquisition of information; 4. Interface with level 1 PSA: Grouping of sequences; 5. Accident progression and containment analysis; 6. Source terms for severe accidents; 7. Documentation of the analysis: Presentation and interpretation of results; 8. Use and applications of the PSA; Annex I: Example of a typical schedule for a level 2 PSA; Annex II: Computer codes for simulation of severe accidents; Annex III: Sample outline of documentation for a level 2 PSA study.

Guidelines for the Review of Research Reactor Safety: Revised Edition. Reference Document for IAEA Integrated Safety Assessment of Research Reactors (INSARR)

International Nuclear Information System (INIS)

2013-01-01

The Integrated Safety Assessment of Research Reactors (INSARR) is an IAEA safety review service available to Member States with the objective of supporting them in ensuring and enhancing the safety of their research reactors. This service consists of performing a comprehensive peer review and an assessment of the safety of the respective research reactor. The reviews are based on IAEA safety standards and on the provisions of the Code of Conduct on the Safety of Research Reactors. The INSARR can benefit both the operating organizations and the regulatory bodies of the requesting Member States, and can include new research reactors under design or operating research reactors, including those which are under a Project and Supply Agreement with the IAEA. The first IAEA safety evaluation of a research reactor operated by a Member State was completed in October 1959 and involved the Swiss 20 MW DIORIT research reactor. Since then, and in accordance with its programme on research reactor safety, the IAEA has conducted safety review missions in its Member States to enhance the safety of their research reactor facilities through the application of the Code of Conduct on the Safety of Research Reactors and the relevant IAEA safety standards. About 320 missions in 51 Member States were undertaken between 1972 and 2012. The INSARR missions and other limited scope safety review missions are conducted following the guidelines presented in this publication, which is a revision of Guidelines for the Review of Research Reactor Safety (IAEA Services Series No. 1), published in December 1997. This publication details those IAEA safety standards and guidance publications relevant to the safety of research reactors that have been revised or published since 1997. The purpose of this publication is to give guidance on the preparation, implementation, reporting and follow-up of safety review missions. It is also intended to be of assistance to operators and regulators in conducting

Technical safety requirements (TSR) for waste receiving and processing (WRAP) facility

International Nuclear Information System (INIS)

Weidert, J.R.

1997-01-01

The scope of this TSR document is based on the WRAP Final Safety Analysis Report (HNF-SD-W026-SAR-002) and supporting documents. The administrative controls set forth in this TSR document are derived from the WRAP Final Safety Analysis Report

Guidance for the definition and application of probabilistic safety criteria

International Nuclear Information System (INIS)

Holmberg, J.-E.; Knochenhauer, M.

2011-05-01

The project 'The Validity of Safety Goals' has been financed jointly by NKS (Nordic Nuclear Safety Research), SSM (Swedish Radiation Safety Authority) and the Swedish and Finnish nuclear utilities. The national financing went through NPSAG, the Nordic PSA Group (Swedish contributions) and SAFIR2010, the Finnish research programme on NPP safety (Finnish contributions). The project has been performed in four phases during 2006-2010. This guidance document aims at describing, on the basis of the work performed throughout the project, issues to consider when defining, applying and interpreting probabilistic safety criteria. Thus, the basic aim of the document is to serve as a checklist and toolbox for the definition and application of probabilistic safety criteria. The document describes the terminology and concepts involved, the levels of criteria and relations between these, how to define a probabilistic safety criterion, how to apply a probabilistic safety criterion, on what to apply the probabilistic safety criterion, and how to interpret the result of the application. The document specifically deals with what makes up a probabilistic safety criterion, i.e., the risk metric, the frequency criterion, the PSA used for assessing compliance and the application procedure for the criterion. It also discusses the concept of subsidiary criteria, i.e., different levels of safety goals. The results from the project can be used as a platform for discussions at the utilities on how to define and use quantitative safety goals. The results can also be used by safety authorities as a reference for risk-informed regulation. The outcome can have an impact on the requirements on PSA, e.g., regarding quality, scope, level of detail, and documentation. Finally, the results can be expected to support on-going activities concerning risk-informed applications. (Author)

Guidance for the definition and application of probabilistic safety criteria

Energy Technology Data Exchange (ETDEWEB)

Holmberg, J.-E. (VTT Technical Research Centre of Finland (Finland)); Knochenhauer, M. (Scandpower AB (Sweden))

2011-05-15

The project 'The Validity of Safety Goals' has been financed jointly by NKS (Nordic Nuclear Safety Research), SSM (Swedish Radiation Safety Authority) and the Swedish and Finnish nuclear utilities. The national financing went through NPSAG, the Nordic PSA Group (Swedish contributions) and SAFIR2010, the Finnish research programme on NPP safety (Finnish contributions). The project has been performed in four phases during 2006-2010. This guidance document aims at describing, on the basis of the work performed throughout the project, issues to consider when defining, applying and interpreting probabilistic safety criteria. Thus, the basic aim of the document is to serve as a checklist and toolbox for the definition and application of probabilistic safety criteria. The document describes the terminology and concepts involved, the levels of criteria and relations between these, how to define a probabilistic safety criterion, how to apply a probabilistic safety criterion, on what to apply the probabilistic safety criterion, and how to interpret the result of the application. The document specifically deals with what makes up a probabilistic safety criterion, i.e., the risk metric, the frequency criterion, the PSA used for assessing compliance and the application procedure for the criterion. It also discusses the concept of subsidiary criteria, i.e., different levels of safety goals. The results from the project can be used as a platform for discussions at the utilities on how to define and use quantitative safety goals. The results can also be used by safety authorities as a reference for risk-informed regulation. The outcome can have an impact on the requirements on PSA, e.g., regarding quality, scope, level of detail, and documentation. Finally, the results can be expected to support on-going activities concerning risk-informed applications. (Author)

Probabilistic safety criteria at the safety function/system level

International Nuclear Information System (INIS)

1989-09-01

A Technical Committee Meeting was held in Vienna, Austria, from 26-30 January 1987. The objectives of the meeting were: to review the national developments of PSC at the level of safety functions/systems including future trends; to analyse basic principles, assumptions, and objectives; to compare numerical values and the rationale for choosing them; to compile the experience with use of such PSC; to analyse the role of uncertainties in particular regarding procedures for showing compliance. The general objective of establishing PSC at the level of safety functions/systems is to provide a pragmatic tool to evaluate plant safety which is placing emphasis on the prevention principle. Such criteria could thus lead to a better understanding of the importance to safety of the various functions which have to be performed to ensure the safety of the plant, and the engineering means of performing these functions. They would reflect the state-of-the-art in modern PSAs and could contribute to a balance in system design. This report, prepared by the participants of the meeting, reviews the current status and future trends in the field and should assist Member States in developing their national approaches. The draft of this document was also submitted to INSAG to be considered in its work to prepare a document on safety principles for nuclear power plants. Five papers presented at the meeting are also included in this publication. A separate abstract was prepared for each of these papers. Refs, figs and tabs

Briefing and debriefing in the cardiac operating room. Analysis of impact on theatre team attitude and patient safety.

Science.gov (United States)

Papaspyros, Sotiris C; Javangula, Kalyana C; Adluri, Rajeshwara Krishna Prasad; O'Regan, David J

2010-01-01

Error in health services delivery has long been recognised as a significant cause of inpatient morbidity and mortality. Root-cause analyses have cited communication failure as one of the contributing factors in adverse events. The formalised fighter pilot mission brief and debrief formed the basis of the National Aeronautics and Space Administration (NASA) crew resource management (CRM) concept produced in 1979. This is a qualitative analysis of our experience with the briefing-debriefing process applied to cardiac theatres. We instituted a policy of formal operating room (OR) briefing and debriefing in all cardiac theatre sessions. The first 118 cases were reviewed. A trouble-free operation was noted in only 28 (23.7%) cases. We experienced multiple problems in 38 (32.2%) cases. A gap was identified in the second order problem solving in relation to instrument repair and maintenance. Theatre team members were interviewed and their comments were subjected to qualitative analysis. The collaborative feeling is that communication has improved. The health industry may benefit from embracing the briefing-debriefing technique as an adjunct to continuous improvement through reflective learning, deliberate practice and immediate feedback. This may be the initial step toward a substantive and sustainable organizational transformation.

Early Musical Training in Bel Canto Vocal Technique: A Brief History and Philosophy.

Science.gov (United States)

Gerstein, Christine Wondolowski

This paper offers a brief history and philosophy of the origins of bel canto vocal style and describes the pedagogical methods used to achieve bel canto ideals in singing. The document discusses the adoption and development of this technique and how it developed over long periods of preparation in the foregoing centuries before the Baroque era.…

Advisory Committee on human radiation experiments. Final report, Supplemental Volume 2. Sources and documentation

International Nuclear Information System (INIS)

1995-01-01

This volume and its appendixes supplement the Advisory Committee's final report by reporting how we went about looking for information concerning human radiation experiments and intentional releases, a description of what we found and where we found it, and a finding aid for the information that we collected. This volume begins with an overview of federal records, including general descriptions of the types of records that have been useful and how the federal government handles these records. This is followed by an agency-by-agency account of the discovery process and descriptions of the records reviewed, together with instructions on how to obtain further information from those agencies. There is also a description of other sources of information that have been important, including institutional records, print resources, and nonprint media and interviews. The third part contains brief accounts of ACHRE's two major contemporary survey projects (these are described in greater detail in the final report and another supplemental volume) and other research activities. The final section describes how the ACHRE information-nation collections were managed and the records that ACHRE created in the course of its work; this constitutes a general finding aid for the materials deposited with the National Archives. The appendices provide brief references to federal records reviewed, descriptions of the accessions that comprise the ACHRE Research Document Collection, and descriptions of the documents selected for individual treatment. Also included are an account of the documentation available for ACHRE meetings, brief abstracts of the almost 4,000 experiments individually described by ACHRE staff, a full bibliography of secondary sources used, and other information

Advisory Committee on human radiation experiments. Final report, Supplemental Volume 2. Sources and documentation

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-01-01

This volume and its appendixes supplement the Advisory Committee`s final report by reporting how we went about looking for information concerning human radiation experiments and intentional releases, a description of what we found and where we found it, and a finding aid for the information that we collected. This volume begins with an overview of federal records, including general descriptions of the types of records that have been useful and how the federal government handles these records. This is followed by an agency-by-agency account of the discovery process and descriptions of the records reviewed, together with instructions on how to obtain further information from those agencies. There is also a description of other sources of information that have been important, including institutional records, print resources, and nonprint media and interviews. The third part contains brief accounts of ACHRE`s two major contemporary survey projects (these are described in greater detail in the final report and another supplemental volume) and other research activities. The final section describes how the ACHRE information-nation collections were managed and the records that ACHRE created in the course of its work; this constitutes a general finding aid for the materials deposited with the National Archives. The appendices provide brief references to federal records reviewed, descriptions of the accessions that comprise the ACHRE Research Document Collection, and descriptions of the documents selected for individual treatment. Also included are an account of the documentation available for ACHRE meetings, brief abstracts of the almost 4,000 experiments individually described by ACHRE staff, a full bibliography of secondary sources used, and other information.

Safety Assessment Document for the Spent Reactor Fuel Geologic Storage Test in the Climax Granite Stock at the Nevada Test site

International Nuclear Information System (INIS)

1980-01-01

The objective of the Spent Fuel Geologic Storage Test in the Climax Granite Stock is to evaluate the response of a granitic rock mass to the underground storage of encapsulated spent reactor fuel in a geometry that simulates a module of a large-scale geologic repository. This document reports an assessment of the safety of conducting this test. Descriptions are provided of the geography, meteorology, hydrology, geology, and seismology of the Climax Site; the effects of postulated natural phenomena and other activities at the nevada Test Site on the safety of the test; and the design and operation of the test facility and associated equipment. Evaluations are made of both the radiological and nonradiological impacts of normal operations, abnormal operations, and postulated accidents. It is concluded that conduct of the spent fuel test at the Climax Site will not result in any undue risk to the public, property, environment, or site employees

DOE standard: Firearms safety

International Nuclear Information System (INIS)

1996-02-01

Information in this document is applicable to all DOE facilities, elements, and contractors engaged in work that requires the use of firearms as provided by law or contract. The standard in this document provides principles and practices for implementing a safe and effective firearms safety program for protective forces and for non-security use of firearms. This document describes acceptable interpretations and methods for meeting Order requirements

DOE standard: Firearms safety

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-02-01

Information in this document is applicable to all DOE facilities, elements, and contractors engaged in work that requires the use of firearms as provided by law or contract. The standard in this document provides principles and practices for implementing a safe and effective firearms safety program for protective forces and for non-security use of firearms. This document describes acceptable interpretations and methods for meeting Order requirements.

Correlation between safety climate and contractor safety assessment programs in construction.

Science.gov (United States)

Sparer, Emily H; Murphy, Lauren A; Taylor, Kathryn M; Dennerlein, Jack T

2013-12-01

Contractor safety assessment programs (CSAPs) measure safety performance by integrating multiple data sources together; however, the relationship between these measures of safety performance and safety climate within the construction industry is unknown. Four hundred and one construction workers employed by 68 companies on 26 sites and 11 safety managers employed by 11 companies completed brief surveys containing a nine-item safety climate scale developed for the construction industry. CSAP scores from ConstructSecure, Inc., an online CSAP database, classified these 68 companies as high or low scorers, with the median score of the sample population as the threshold. Spearman rank correlations evaluated the association between the CSAP score and the safety climate score at the individual level, as well as with various grouping methodologies. In addition, Spearman correlations evaluated the comparison between manager-assessed safety climate and worker-assessed safety climate. There were no statistically significant differences between safety climate scores reported by workers in the high and low CSAP groups. There were, at best, weak correlations between workers' safety climate scores and the company CSAP scores, with marginal statistical significance with two groupings of the data. There were also no significant differences between the manager-assessed safety climate and the worker-assessed safety climate scores. A CSAP safety performance score does not appear to capture safety climate, as measured in this study. The nature of safety climate in construction is complex, which may be reflective of the challenges in measuring safety climate within this industry. Am. J. Ind. Med. 56:1463-1472, 2013. © 2013 Wiley Periodicals, Inc. © 2013 Wiley Periodicals, Inc.

Safety of installations

International Nuclear Information System (INIS)

2001-01-01

This document presents the fulfilling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 5 of the document contains some details about the siting, designed and construction, operation, maintenance, inspection, testing, procedures for responding to anticipated operational occurrences and accidents, engineering and technical support, reporting of significant incidents, operating experience feedback, radioactive waste and spent fuel

Safety of installations

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-09-01

This document presents the fulfilling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 5 of the document contains some details about the siting, designed and construction, operation, maintenance, inspection, testing, procedures for responding to anticipated operational occurrences and accidents, engineering and technical support, reporting of significant incidents, operating experience feedback, radioactive waste and spent fuel.

Safety of installations

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 5 of the document contains some details about the siting, designed and construction, operation, maintenance, inspection, testing, procedures for responding to anticipated operational occurrences and accidents, engineering and technical support, reporting of significant incidents, operating experience feedback, radioactive waste and spent fuel

Preliminary safety information document for the standard MHTGR. Volume 4

Energy Technology Data Exchange (ETDEWEB)

None

1986-01-01

This report contains information concerning: operational radionuclide control; occupational radiation protection, conduct of operations; initial test program; safety analysis; technical specifications; and quality assurance. (JDB)

Westinghouse Hanford Company (WHC) standards/requirements identification document (S/RID)

Energy Technology Data Exchange (ETDEWEB)

Bennett, G.L.

1996-03-15

This Standards/Requirements Identification Document (S/RID) set forth the Environmental Safety and Health (ES&H) standards/requirements for Westinghouse Hanford Company Level Programs, where implementation and compliance is the responsibility of these organizations. These standards/requirements are adequate to ensure the protection of the health and safety of workers, the public, and the environment.

Sharing information: Mixed-methods investigation of brief experiential interprofessional

Science.gov (United States)

Cocksedge, Simon; Barr, Nicky; Deakin, Corinne

In UK health policy ‘sharing good information is pivotal to improving care quality, safety, and effectiveness. Nevertheless, educators often neglect this vital communication skill. The consequences of brief communication education interventions for healthcare workers are not yet established. This study investigated a three-hour interprofessional experiential workshop (group work, theoretical input, rehearsal) training healthcare staff in sharing information using a clear structure (PARSLEY). Staff in one UK hospital participated. Questionnaires were completed before, immediately after, and eight weeks after training, with semistructured interviews seven weeks after training. Participants (n=76) were from assorted healthcare occupations (26% non-clinical). Knowledge significantly increased immediately after training. Self-efficacy, outcome expectancy, and motivation to use the structure taught were significantly increased immediately following training and at eight weeks. Respondents at eight weeks (n=35) reported their practice in sharing information had changed within seven days of training. Seven weeks after training, most interviewees (n=13) reported confidently using the PARSLEY structure regularly in varied settings. All had re-evaluated their communication practice. Brief training altered self-reported communication behaviour of healthcare staff, with sustained changes in everyday work. As sharing information is central to communication curricula, health policy, and shared decision-making, the effectiveness of brief teaching interventions has economic and educational implications.

READS: the rapid electronic assessment documentation system.

LENUS (Irish Health Repository)

Hickey, Ann

2012-12-13

Patient documentation is time consuming and can detract from care. The authors report a novel computer programme that manipulates routinely collected information to quantify nursing workload, along with the reason for admission, functional status, estimates of in-hospital mortality and life expectancy. The programme stores information in a database, and produces a print-out in a situation\\/background\\/assessment\\/recommendation (SBAR) format. The average time taken to enter 629 patient encounters was 6.6 minutes. Pain was the most common presentation for low workload patients, while high workload patients often presented with altered mental status and reduced mobility. There was only a modest correlation between the risk of death and nursing workload. The programme measures nursing workload without further paperwork, and improves routine documentation with a legible brief report that is automatically generated. This report can be shared and provides data that is immediately available for day-to-day care, audit, quality control and service planning.

Consensus document regarding cardiovascular safety at sports arenas

DEFF Research Database (Denmark)

Borjesson, Mats; Serratosa, Luis; Carre, Francois

2011-01-01

Mass gathering events in sports arenas create challenges regarding the cardiovascular safety of both athletes and spectators. A comprehensive medical action plan, to ensure properly applied cardiopulmonary resuscitation, and wide availability and use of automated external defibrillators (AEDs......), is essential to improving survival from sudden cardiac arrest at sporting events. This paper outlines minimum standards for cardiovascular care to assist in the planning of mass gathering sports events across Europe with the intention of local adaptation at individual sports arenas, to ensure the full...

Multivariate time series analysis of SafetyNet data. SafetyNet, Building the European Road Safety Observatory, Workpackage 7, Deliverable 7.7.

NARCIS (Netherlands)

Commandeur, J.J.F. Bijleveld, F.D. & Bergel, R.

2009-01-01

This deliverable provides an application of theories and methods documented in Deliverables 7.4 and 7.5 of work package 7 of the SafetyNet project. In this deliverable, use of select analysis techniques is demonstrated through real world road safety analysis problems, using aggregate data which may

Creating Access to Opportunities for Youth in Transition from Foster Care. An AYPF Policy Brief

Science.gov (United States)

Russ, Erin; Fryar, Garet

2014-01-01

What happens to youth in foster care when they turn 18? Many face unprecedented challenges like homelessness, lack of financial resources, difficulty accessing educational opportunities, and unemployment. In this issue brief, The American Youth Policy Forum (AYPF) document these challenges and opportunities in three distinct yet overlapping areas…

Do Foreclosures Affect Boston Public School Student Academic Performance? Public Policy Brief No. 13-5

Science.gov (United States)

Bradbury, Katharine; Burke, Mary A.; Triest, Robert K.

2013-01-01

Foreclosures have well-documented adverse consequences for families living in or owning properties undergoing foreclosure and on surrounding neighborhoods, but they may also have other costs. This policy brief summarizes our research on the impact of mortgage foreclosures on academic performance among Boston public school students. The data show…

Critical Characteristics of Radiation Detection System Components to be Dedicated for use in Safety Class and Safety Significant System

International Nuclear Information System (INIS)

DAVIS, S.J.

2000-01-01

This document identifies critical characteristics of components to be dedicated for use in Safety Significant (SS) Systems, Structures, or Components (SSCs). This document identifies the requirements for the components of the common, radiation area, monitor alarm in the WESF pool cell. These are procured as Commercial Grade Items (CGI), with the qualification testing and formal dedication to be performed at the Waste Encapsulation Storage Facility (WESF) for use in safety significant systems. System modifications are to be performed in accordance with the approved design. Components for this change are commercially available and interchangeable with the existing alarm configuration This document focuses on the operational requirements for alarm, declaration of the safety classification, identification of critical characteristics, and interpretation of requirements for procurement. Critical characteristics are identified herein and must be verified, followed by formal dedication, prior to the components being used in safety related applications

NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security, Issue no. 10, March 2009

International Nuclear Information System (INIS)

2009-03-01

The current issue contains information about the following meetings: Application of the Code of Conduct on the Safety of Research Reactors (the 'Code'). Environmental Modelling for Radiation Safety (EMRAS II); Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (the Joint Convention). The document also gives an overview on International Nuclear Security Advisory Service (INSServ)

National HTGR safety program

International Nuclear Information System (INIS)

Davis, D.E.; Kelley, A.P. Jr.

1982-01-01

This paper presents an overview of the National HTGR Program in the US with emphasis on the safety and licensing strategy being pursued. This strategy centers upon the development of an integrated approach to organizing and classifying the functions needed to produce safe and economical nuclear power production. At the highest level, four plant goals are defined - Normal Operation, Core and Plant Protection, Containment Integrity and Emergency Preparedness. The HTGR features which support the attainment of each goal are described and finally a brief summary is provided of the current status of the principal safety development program supporting the validation of the four plant goals

Experience with nuclear safety standards development in non-governmental international organizations

International Nuclear Information System (INIS)

Becker, K.

1985-01-01

Besides the IAEA as a 'governmental' organization dealing with basic safety recommendations addressed primarily to the national regulatory bodies in developing countries, two closely related non-governmental international standards organizations have gained extensive experience in the field of nuclear standardization. Over more than 25 years since their formation, both (a) the International Organization for Standardization's (ISO) Technical Committee 85 'Nuclear Energy', in particular in its Sub-Committee 3 'Reactor Technology and Safety' and (b) the International Electrotechnical Commission's (IEC) Technical Committee 45 'Nuclear Instrumentation' have published numerous standards. A brief review is given of these, draft standards, and other documents planned to become international standards. Many of them deal with rather specialized topics typical for 'industrial' standards such as standardized procedures, instruments, methods, materials, test methods, terminology, and signs and symbols, but others are directly related to more basic safety issues. In some areas such as quality assurance, seismic aspects of siting and terminology, there has been in the past occasional overlap in the activities of the NUSS programme, IEC and ISO. Letters of Understanding have since 1981 contributed to clarifying the borderlines and to avoiding redundant efforts. Also, some experiences and problems are described arising, for example, from the harmonization of different national safety philosophies and traditions into universally accepted international standards, and the transfer of international standards into national standards systems. Finally, based on a recent comprehensive compilation of some 3300 nuclear standards and standards projects, an attempt is made to present a cost/benefit analysis and an outlook on future developments. (author)

Safety culture: modern slogan or effective contribution to safety?

International Nuclear Information System (INIS)

Salm, M.

1994-01-01

Safety culture is defined and its impact on nuclear power plants is documented using the words of the INSAG of IAEA. Two examples from the field of aviation and space flight testify, that the upper management, by its sheer image, may considerably influence actions of the lower levels of the hierarchy. Management therefore can do a lot more for safety than is commonly assumed. Two examples, although separated by 57 years, show that the mentioned influence remains unchanged inspire of progress in management- and organisation-methods as well as in safety-engineering. Safety culture is an overriding element of safety, acting at all levels of a hierarchy. Its action is most important on those levels, for which precise reglementation is hardly possible. The chain of technical and organisational measures guarantees safety only under the condition, that it is embedded in 'safety culture'. Safety culture therefore merits our full attention. (author) 1 fig

Surgical Safety Training of World Health Organization Initiatives.

Science.gov (United States)

Davis, Christopher R; Bates, Anthony S; Toll, Edward C; Cole, Matthew; Smith, Frank C T; Stark, Michael

2014-01-01

Undergraduate training in surgical safety is essential to maximize patient safety. This national review quantified undergraduate surgical safety training. Training of 2 international safety initiatives was quantified: (1) World Health Organization (WHO) "Guidelines for Safe Surgery" and (2) Department of Health (DoH) "Principles of the Productive Operating Theatre." Also, 13 additional safety skills were quantified. Data were analyzed using Mann-Whitney U tests. In all, 23 universities entered the study (71.9% response). Safety skills from WHO and DoH documents were formally taught in 4 UK medical schools (17.4%). Individual components of the documents were taught more frequently (47.6%). Half (50.9%) of the additional safety skills identified were taught. Surgical societies supplemented safety training, although the total amount of training provided was less than that in university curricula (P < .0001). Surgical safety training is inadequate in UK medical schools. To protect patients and maximize safety, a national undergraduate safety curriculum is recommended. © 2013 by the American College of Medical Quality.

The Role of Documentation Quality in Anesthesia-Related Closed Claims: A Descriptive Qualitative Study.

Science.gov (United States)

Wilbanks, Bryan A; Geisz-Everson, Marjorie; Boust, Rebecca R

2016-09-01

Clinical documentation is a critical tool in supporting care provided to patients. Sound documentation provides a picture of clinical events that can be used to improve patient care. However, many other uses for clinical documentation are equally important. Such documentation informs clinical decision support tools, creates a legal record of patient care, assists in financial reimbursement of services, and serves as a repository for secondary data analysis. Conversely, poor documentation can impair patient safety and increase malpractice risk exposure by reflecting poor or inaccurate information that ultimately may guide patient care decisions.Through an examination of anesthesia-related closed claims, a descriptive qualitative study emerged, which explored the antecedents and consequences of documentation quality in the claims reviewed. A secondary data analysis utilized a database generated by the American Association of Nurse Anesthetists Foundation closed claim review team. Four major themes emerged from the analysis. Themes 1, 2, and 4 primarily describe how poor documentation quality can have negative consequences for clinicians. The third theme primarily describes how poor documentation quality that can negatively affect patient safety.

Westinghouse Hanford Company (WHC) standards/requirements identification document (S/RID)

International Nuclear Information System (INIS)

Bennett, G.L.

1996-01-01

This Standards/Requirements Identification Document (S/RID) set forth the Environmental Safety and Health (ES ampersand amp;H) standards/requirements for Westinghouse Hanford Company Level Programs, where implementation and compliance is the responsibility of these organizations. These standards/requirements are adequate to ensure the protection of the health and safety of workers, the public, and the environment

Review of Public Safety in Viewpoint of Complex Networks

International Nuclear Information System (INIS)

Gai Chengcheng; Weng Wenguo; Yuan Hongyong

2010-01-01

In this paper, a brief review of public safety in viewpoint of complex networks is presented. Public safety incidents are divided into four categories: natural disasters, industry accidents, public health and social security, in which the complex network approaches and theories are need. We review how the complex network methods was developed and used in the studies of the three kinds of public safety incidents. The typical public safety incidents studied by the complex network methods in this paper are introduced, including the natural disaster chains, blackouts on electric power grids and epidemic spreading. Finally, we look ahead to the application prospects of the complex network theory on public safety.

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

RADWASS update. Radioactive Waste Safety Standards Programme

International Nuclear Information System (INIS)

Delattre, D.

2000-01-01

By the late 1980s, the issue of radioactive wastes and their management was becoming increasingly politically important. The IAEA responded by establishing a high profile family of safety standards, the Radioactive Waste Safety Standards (RADWASS). By this means, the IAEA intended to draw attention to the fact that well-established procedures for the safe management of radioactive wastes already were in place. The programme was intended to establish an ordered structure for safety documents on waste management and to ensure comprehensive coverage of all relevant subject areas. RADWASS documents are categorized under four subject areas - discharges, predisposal, disposal, and environmental restoration. The programme is overseen through a formalized review and approval mechanism that was established in 1996 for all safety standards activities. The Waste Safety Standards Committee (WASSC) is a standing body of senior regulatory officials with technical expertise in radioactive waste safety. To date, three Safety Requirements and seven Safety Guides have been issued

NIF special equipment construction health and safety plan

Energy Technology Data Exchange (ETDEWEB)

Sawicki, R.H.

1997-07-28

The purpose of this plan is to identify how the construction and deployment activities of the National Ignition Facility (NIF) Special Equipment (SE) will be safely executed. This plan includes an identification of (1) the safety-related responsibilities of the SE people and their interaction with other organizations involved; (2) safety related requirements, policies, and documentation; (3) a list of the potential hazards unique to SE systems and the mechanisms that will be implemented to control them to acceptable levels; (4) a summary of Environmental Safety and Health (ES&H) training requirements; and (5) requirements of contractor safety plans that will be developed and used by all SE contractors participating in site activities. This plan is a subsidiary document to the NIF Construction Safety Program (CSP) and is intended to compliment the requirements stated therein with additional details specific to the safety needs of the SE construction-related activities. If a conflict arises between these two documents, the CSP will supersede. It is important to note that this plan does not list all of the potential hazards and their controls because the design and safety analysis process is still ongoing. Additional safety issues win be addressed in the Final Safety Analysis Report, Operational Safety Procedures (OSPs), and other plans and procedures as described in Section 3.0 of this plan.

NIF special equipment construction health and safety plan

International Nuclear Information System (INIS)

Sawicki, R.H.

1997-01-01

The purpose of this plan is to identify how the construction and deployment activities of the National Ignition Facility (NIF) Special Equipment (SE) will be safely executed. This plan includes an identification of (1) the safety-related responsibilities of the SE people and their interaction with other organizations involved; (2) safety related requirements, policies, and documentation; (3) a list of the potential hazards unique to SE systems and the mechanisms that will be implemented to control them to acceptable levels; (4) a summary of Environmental Safety and Health (ES ampersand H) training requirements; and (5) requirements of contractor safety plans that will be developed and used by all SE contractors participating in site activities. This plan is a subsidiary document to the NIF Construction Safety Program (CSP) and is intended to compliment the requirements stated therein with additional details specific to the safety needs of the SE construction-related activities. If a conflict arises between these two documents, the CSP will supersede. It is important to note that this plan does not list all of the potential hazards and their controls because the design and safety analysis process is still ongoing. Additional safety issues win be addressed in the Final Safety Analysis Report, Operational Safety Procedures (OSPs), and other plans and procedures as described in Section 3.0 of this plan

LFR safety approach and main ELFR safety analysis results

International Nuclear Information System (INIS)

Bubelis, E.; Schikorr, M.; Frogheri, M.; Mansani, L.; Bandini, G.; Burgazzi, L.; Mikityuk, K.; Zhang, Y.; Lo Frano, R.; Forgione, N.

2013-01-01

LFR safety approach: → A global safety approach for the LFR reference plant has been assessed and the safety analyses methodology has been developed. → LFR follows the general guidelines of the Generation IV safety concept recommendations. Thus, improved safety and higher reliability are recognized as an essential priority. → The fundamental safety objectives and the Defence-in-Depth (DiD) approach, as described by IAEA Safety Guides, have been preserved. → The recommendations of the Risk and Safety Working Group (RSWG) of GEN-IV IF has been taken into account: • safety is to be “built-in” in the fundamental design rather than “added on”; • full implementation of the Defence-in-Depth principles in a manner that is demonstrably exhaustive, progressive, tolerant, forgiving and well-balanced; • “risk-informed” approach - deterministic approach complemented with a probabilistic one; • adoption of an integrated methodology that can be used to evaluate and document the safety of Gen IV nuclear systems - ISAM. In particular the OPT tool is the fundamental methodology used throughout the design process

FMCSA safety program effectiveness measurement : carrier intervention effectiveness model, version 1.0 : [analysis brief].

Science.gov (United States)

2015-01-01

The Carrier Intervention Effectiveness Model (CIEM) : provides the Federal Motor Carrier Safety : Administration (FMCSA) with a tool for measuring : the safety benefits of carrier interventions conducted : under the Compliance, Safety, Accountability...

Experience relevant to safety obtained from reactor decommissioning operations in the French Atomic Energy Commission

International Nuclear Information System (INIS)

Giraudel, B.; Langlois, G.

1979-01-01

From among the nuclear facilities constructed in France the authors cite eight large reactors, ranging from critical assemblies to power reactors, that have been finally shut-down since 1965. A brief account is given of the way in which the various operations were carried out after the final control rod drop, a distinction being drawn between the shut-down proper and the containment and dismantling work. A description is also given, from the technical and regulatory standpoint, of the final stage attained, and mention is made of French safety arrangements and of the part played by the safety services during decommissioning operations. Among the lessons derived from French experience, the authors mention the completion of operations without any serious safety problems, and with guarantees for the protection of personnel and the population as a whole, by conventional techniques; the advantage of planning decommissioning operations from the very beginning of construction of the facilities; and the importance of filing descriptive documents. In view of the experience gained, the French Atomic Energy Commission has devised internal procedures for facilitating the application of regulations governing the shut-down and decommissioning phases, which are aimed at preserving surveillance procedures similar to those in force during normal operation. (author)

Interim process report for the safety assessment SR-Can

International Nuclear Information System (INIS)

Sellin, Patrick

2004-08-01

This report is a documentation of buffer processes identified as relevant to the long-term safety of a KBS-3 repository. The report is part of the interim reporting of the safety assessment SR-Can, see further the Interim main report. The final SR-Can reporting will support SKB's application to build an Encapsulation plant for spent nuclear fuel and is to be produced in 2006. The purpose of this report is to document the scientific knowledge of the processes to a level required for an adequate treatment in the safety assessment. The documentation is thus from a scientific point of not exhaustive since such a treatment is neither necessary for the purposes of the safety assessment nor possible within the scope of an assessment. The purpose is further to determine the handling of each process in the safety assessment and to demonstrate how uncertainties are taken care of, given the suggested handling. The process documentation in the SR 97 version of the Process report is a starting point for this SR-Can interim version. As further described in the Interim main report, the list of relevant processes has been reviewed and slightly extended by comparison to other databases. Furthermore, the backfill has been included as a system part of its own, rather than being described together with the buffer as in SR 97. Apart from giving an interim account of the documentation and handling of buffer processes in SR-Can, this report is meant to serve as a template for the forthcoming documentation of processes occurring in other parts of the repository system. A complete list of processes can be found in the Interim FEP report for the safety assessment SR-Can. All material presented in this document is preliminary in nature and will possibly be updated as the SR-Can project progresses

Interim process report for the safety assessment SR-Can

Energy Technology Data Exchange (ETDEWEB)

Sellin, Patrick (ed.)

2004-08-01

This report is a documentation of buffer processes identified as relevant to the long-term safety of a KBS-3 repository. The report is part of the interim reporting of the safety assessment SR-Can, see further the Interim main report. The final SR-Can reporting will support SKB's application to build an Encapsulation plant for spent nuclear fuel and is to be produced in 2006. The purpose of this report is to document the scientific knowledge of the processes to a level required for an adequate treatment in the safety assessment. The documentation is thus from a scientific point of not exhaustive since such a treatment is neither necessary for the purposes of the safety assessment nor possible within the scope of an assessment. The purpose is further to determine the handling of each process in the safety assessment and to demonstrate how uncertainties are taken care of, given the suggested handling. The process documentation in the SR 97 version of the Process report is a starting point for this SR-Can interim version. As further described in the Interim main report, the list of relevant processes has been reviewed and slightly extended by comparison to other databases. Furthermore, the backfill has been included as a system part of its own, rather than being described together with the buffer as in SR 97. Apart from giving an interim account of the documentation and handling of buffer processes in SR-Can, this report is meant to serve as a template for the forthcoming documentation of processes occurring in other parts of the repository system. A complete list of processes can be found in the Interim FEP report for the safety assessment SR-Can. All material presented in this document is preliminary in nature and will possibly be updated as the SR-Can project progresses.

National briefing summaries: Nuclear fuel cycle and waste management

Energy Technology Data Exchange (ETDEWEB)

Schneider, K.J.; Bradley, D.J.; Fletcher, J.F.; Konzek, G.J.; Lakey, L.T.; Mitchell, S.J.; Molton, P.M.; Nightingale, R.E.

1991-04-01

Since 1976, the International Program Support Office (IPSO) at the Pacific Northwest Laboratory (PNL) has collected and compiled publicly available information concerning foreign and international radioactive waste management programs. This National Briefing Summaries is a printout of an electronic database that has been compiled and is maintained by the IPSO staff. The database contains current information concerning the radioactive waste management programs (with supporting information on nuclear power and the nuclear fuel cycle) of most of the nations (except eastern European countries) that now have or are contemplating nuclear power, and of the multinational agencies that are active in radioactive waste management. Information in this document is included for three additional countries (China, Mexico, and USSR) compared to the prior issue. The database and this document were developed in response to needs of the US Department of Energy.

National briefing summaries: Nuclear fuel cycle and waste management

International Nuclear Information System (INIS)

Schneider, K.J.; Bradley, D.J.; Fletcher, J.F.; Konzek, G.J.; Lakey, L.T.; Mitchell, S.J.; Molton, P.M.; Nightingale, R.E.

1991-04-01

Since 1976, the International Program Support Office (IPSO) at the Pacific Northwest Laboratory (PNL) has collected and compiled publicly available information concerning foreign and international radioactive waste management programs. This National Briefing Summaries is a printout of an electronic database that has been compiled and is maintained by the IPSO staff. The database contains current information concerning the radioactive waste management programs (with supporting information on nuclear power and the nuclear fuel cycle) of most of the nations (except eastern European countries) that now have or are contemplating nuclear power, and of the multinational agencies that are active in radioactive waste management. Information in this document is included for three additional countries (China, Mexico, and USSR) compared to the prior issue. The database and this document were developed in response to needs of the US Department of Energy

FMCSA safety program effectiveness measurement : Roadside Intervention Effectiveness Model, fiscal year 2010 : [analysis brief].

Science.gov (United States)

2014-11-01

Two of the Federal Motor Carrier Safety Administrations (FMCSAs) key safety programs are the Roadside Inspection and Traffic Enforcement programs. The Roadside Inspection program consists of roadside inspections performed by qualified safety in...

Probabilistic safety analysis : a new nuclear power plants licensing method

International Nuclear Information System (INIS)

Oliveira, L.F.S. de.

1982-04-01

After a brief retrospect of the application of Probabilistic Safety Analysis in the nuclear field, the basic differences between the deterministic licensing method, currently in use, and the probabilistic method are explained. Next, the two main proposals (by the AIF and the ACRS) concerning the establishment of the so-called quantitative safety goals (or simply 'safety goals') are separately presented and afterwards compared in their most fundamental aspects. Finally, some recent applications and future possibilities are discussed. (Author) [pt

Environmental restoration value engineering guidance document

International Nuclear Information System (INIS)

1995-07-01

This document provides guidance on Value Engineering (VE). VE is an organized team effort led by a person trained in the methodology to analyze the functions of projects, systems, equipment, facilities, services, and processes for achieving the essential functions at the lowest life cycle cost while maintaining required performance, reliability, availability, quality, and safety. VE has proven to be a superior tool to improve up-front project planning, cut costs, and create a better value for each dollar spent. This document forms the basis for the Environmental Restoration VE Program, describes the VE process, and provides recommendations on when it can be most useful on ER projects

14 CFR 415.33 - Safety organization.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 4 2010-01-01 2010-01-01 false Safety organization. 415.33 Section 415.33....33 Safety organization. (a) An applicant shall maintain a safety organization and document it by... communication, both within the applicant's organization and between the applicant and any federal launch range...

Good safety culture maintenance at Leningrad nuclear power plant

International Nuclear Information System (INIS)

Ardanov, A.

1996-01-01

The evidence in favour of the Leningrad NPP commitment to safety tasks, as the case is in the international practice, is The Safety Policy Statement document where safety is declared to be more significant than the power generation related issues, with the entire responsibility for the safety provision taken over by the operating utility. To avoid the situation when the stated safety tasks and policy remain only a declaration, the organizational structure of the operating utility was expanded to include The Safety Control Department and The Quality Control Department whose tasks encompass the control of the achieved safety level, development of recommendations, measures and actions aimed at the safety culture improvement, assessment and revision of the criteria and requirements to the personnel and management. Each individual at LNPP whose activity affects the plant safety has been familiarized with The Safety Policy Statement document

Good safety culture maintenance at Leningrad nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Ardanov, A [Safety Control Dept., Leningrad Nuclear Power Plant, Leningrad (Russian Federation)

1997-12-31

The evidence in favour of the Leningrad NPP commitment to safety tasks, as the case is in the international practice, is The Safety Policy Statement document where safety is declared to be more significant than the power generation related issues, with the entire responsibility for the safety provision taken over by the operating utility. To avoid the situation when the stated safety tasks and policy remain only a declaration, the organizational structure of the operating utility was expanded to include The Safety Control Department and The Quality Control Department whose tasks encompass the control of the achieved safety level, development of recommendations, measures and actions aimed at the safety culture improvement, assessment and revision of the criteria and requirements to the personnel and management. Each individual at LNPP whose activity affects the plant safety has been familiarized with The Safety Policy Statement document.

CANISTER HANDLING FACILITY CRITICALITY SAFETY CALCULATIONS

International Nuclear Information System (INIS)

C.E. Sanders

2005-01-01

This design calculation revises and updates the previous criticality evaluation for the canister handling, transfer and staging operations to be performed in the Canister Handling Facility (CHF) documented in BSC [Bechtel SAIC Company] 2004 [DIRS 167614]. The purpose of the calculation is to demonstrate that the handling operations of canisters performed in the CHF meet the nuclear criticality safety design criteria specified in the ''Project Design Criteria (PDC) Document'' (BSC 2004 [DIRS 171599], Section 4.9.2.2), the nuclear facility safety requirement in ''Project Requirements Document'' (Canori and Leitner 2003 [DIRS 166275], p. 4-206), the functional/operational nuclear safety requirement in the ''Project Functional and Operational Requirements'' document (Curry 2004 [DIRS 170557], p. 75), and the functional nuclear criticality safety requirements described in the ''Canister Handling Facility Description Document'' (BSC 2004 [DIRS 168992], Sections 3.1.1.3.4.13 and 3.2.3). Specific scope of work contained in this activity consists of updating the Category 1 and 2 event sequence evaluations as identified in the ''Categorization of Event Sequences for License Application'' (BSC 2004 [DIRS 167268], Section 7). The CHF is limited in throughput capacity to handling sealed U.S. Department of Energy (DOE) spent nuclear fuel (SNF) and high-level radioactive waste (HLW) canisters, defense high-level radioactive waste (DHLW), naval canisters, multicanister overpacks (MCOs), vertical dual-purpose canisters (DPCs), and multipurpose canisters (MPCs) (if and when they become available) (BSC 2004 [DIRS 168992], p. 1-1). It should be noted that the design and safety analyses of the naval canisters are the responsibility of the U.S. Department of the Navy (Naval Nuclear Propulsion Program) and will not be included in this document. In addition, this calculation is valid for the current design of the CHF and may not reflect the ongoing design evolution of the facility

Tank safety screening data quality objective. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Hunt, J.W.

1995-04-27

The Tank Safety Screening Data Quality Objective (DQO) will be used to classify 149 single shell tanks and 28 double shell tanks containing high-level radioactive waste into safety categories for safety issues dealing with the presence of ferrocyanide, organics, flammable gases, and criticality. Decision rules used to classify a tank as ``safe`` or ``not safe`` are presented. Primary and secondary decision variables used for safety status classification are discussed. The number and type of samples required are presented. A tabular identification of each analyte to be measured to support the safety classification, the analytical method to be used, the type of sample, the decision threshold for each analyte that would, if violated, place the tank on the safety issue watch list, and the assumed (desired) analytical uncertainty are provided. This is a living document that should be evaluated for updates on a semiannual basis. Evaluation areas consist of: identification of tanks that have been added or deleted from the specific safety issue watch lists, changes in primary and secondary decision variables, changes in decision rules used for the safety status classification, and changes in analytical requirements. This document directly supports all safety issue specific DQOs and additional characterization DQO efforts associated with pretreatment and retrieval. Additionally, information obtained during implementation can assist in resolving assumptions for revised safety strategies, and in addition, obtaining information which will support the determination of error tolerances, confidence levels, and optimization schemes for later revised safety strategy documentation.

DRY TRANSFER FACILITY CRITICALITY SAFETY CALCULATIONS

International Nuclear Information System (INIS)

C.E. Sanders

2005-01-01

This design calculation updates the previous criticality evaluation for the fuel handling, transfer, and staging operations to be performed in the Dry Transfer Facility (DTF) including the remediation area. The purpose of the calculation is to demonstrate that operations performed in the DTF and RF meet the nuclear criticality safety design criteria specified in the ''Project Design Criteria (PDC) Document'' (BSC 2004 [DIRS 171599], Section 4.9.2.2), the nuclear facility safety requirement in ''Project Requirements Document'' (Canori and Leitner 2003 [DIRS 166275], p. 4-206), the functional/operational nuclear safety requirement in the ''Project Functional and Operational Requirements'' document (Curry 2004 [DIRS 170557], p. 75), and the functional nuclear criticality safety requirements described in the ''Dry Transfer Facility Description Document'' (BSC 2005 [DIRS 173737], p. 3-8). A description of the changes is as follows: (1) Update the supporting calculations for the various Category 1 and 2 event sequences as identified in the ''Categorization of Event Sequences for License Application'' (BSC 2005 [DIRS 171429], Section 7). (2) Update the criticality safety calculations for the DTF staging racks and the remediation pool to reflect the current design. This design calculation focuses on commercial spent nuclear fuel (SNF) assemblies, i.e., pressurized water reactor (PWR) and boiling water reactor (BWR) SNF. U.S. Department of Energy (DOE) Environmental Management (EM) owned SNF is evaluated in depth in the ''Canister Handling Facility Criticality Safety Calculations'' (BSC 2005 [DIRS 173284]) and is also applicable to DTF operations. Further, the design and safety analyses of the naval SNF canisters are the responsibility of the U.S. Department of the Navy (Naval Nuclear Propulsion Program) and will not be included in this document. Also, note that the results for the Monitored Geologic Repository (MGR) Site specific Cask (MSC) calculations are limited to the

Containment safety margins

International Nuclear Information System (INIS)

Von Riesemann, W.A.

1980-01-01

Objective of the Containment Safety Margins program is the development and verification of methodologies which are capable of reliably predicting the ultimate load-carrying capability of light water reactor containment structures under accident and severe environments. The program was initiated in June 1980 at Sandia and this paper addresses the first phase of the program which is essentially a planning effort. Brief comments are made about the second phase, which will involve testing of containment models

Decision Document for Heat Removal from High-Level Waste Tanks

International Nuclear Information System (INIS)

WILLIS, W.L.

2000-01-01

This document establishes the combination of design and operational configurations that will be used to provide heat removal from high-level waste tanks during Phase 1 waste feed delivery to prevent the waste temperature from exceeding tank safety requirement limits. The chosen method--to use the primary and annulus ventilation systems to remove heat from the high-level waste tanks--is documented herein

An approach for Periodic Safety Review (PSR) of units 5 and 6 of Kozloduy NPP

International Nuclear Information System (INIS)

Kichev, Emil

2014-01-01

Periodic Safety Reviews (PSR) is complementary to the routine and special safety reviews and does not replaced them. It determines the level of compliance with current safety requirements and covers all safety aspects of NPP operation and all equipment (SSCs) on site. Three levels of importance are defined for the documents in PSR (towards higher conservatism): Bulgarian documents; IAEA documents; Documents of manufactures and suppliers of the equipment (SSCs). The scope and activities consists of four stages and includes 14 safety factors (SF). Cooperation with external companies and organizations in areas with proved experience is used.

Nuclear Criticality Safety Data Book

Energy Technology Data Exchange (ETDEWEB)

Hollenbach, D. F. [Y-12 National Security Complex, Oak Ridge, TN (United States)

2016-11-14

The objective of this document is to support the revision of criticality safety process studies (CSPSs) for the Uranium Processing Facility (UPF) at the Y-12 National Security Complex (Y-12). This design analysis and calculation (DAC) document contains development and justification for generic inputs typically used in Nuclear Criticality Safety (NCS) DACs to model both normal and abnormal conditions of processes at UPF to support CSPSs. This will provide consistency between NCS DACs and efficiency in preparation and review of DACs, as frequently used data are provided in one reference source.

Nuclear Criticality Safety Data Book

International Nuclear Information System (INIS)

Hollenbach, D. F.

2016-01-01

The objective of this document is to support the revision of criticality safety process studies (CSPSs) for the Uranium Processing Facility (UPF) at the Y-12 National Security Complex (Y-12). This design analysis and calculation (DAC) document contains development and justification for generic inputs typically used in Nuclear Criticality Safety (NCS) DACs to model both normal and abnormal conditions of processes at UPF to support CSPSs. This will provide consistency between NCS DACs and efficiency in preparation and review of DACs, as frequently used data are provided in one reference source.

Nuclear medicine software: safety aspects

International Nuclear Information System (INIS)

Anon.

1989-01-01

A brief editorial discusses the safety aspects of nuclear medicine software. Topics covered include some specific features which should be incorporated into a well-written piece of software, some specific points regarding software testing and legal liability if inappropriate medical treatment was initiated as a result of information derived from a piece of clinical apparatus incorporating a malfunctioning computer program. (U.K.)

NASA's Software Safety Standard

Science.gov (United States)

Ramsay, Christopher M.

2007-01-01

requirements. This allows the projects leeway to meet these requirements in many forms that best suit a particular project's needs and safety risk. In other words, it tells the project what to do, not how to do it. This update also incorporated advances in the state of the practice of software safety from academia and private industry. It addresses some of the more common issues now facing software developers in the NASA environment such as the use of Commercial-Off-the-Shelf Software (COTS), Modified OTS (MOTS), Government OTS (GOTS), and reused software. A team from across NASA developed the update and it has had both NASA-wide internal reviews by software engineering, quality, safety, and project management. It has also had expert external review. This presentation and paper will discuss the new NASA Software Safety Standard, its organization, and key features. It will start with a brief discussion of some NASA mission failures and incidents that had software as one of their root causes. It will then give a brief overview of the NASA Software Safety Process. This will include an overview of the key personnel responsibilities and functions that must be performed for safety-critical software.

Human Factors and Safety Culture in Maritime Safety (revised

Directory of Open Access Journals (Sweden)

Heinz Peter Berg

2013-09-01

Full Text Available As in every industry at risk, the human and organizational factors constitute the main stakes for maritime safety. Furthermore, several events at sea have been used to develop appropriate risk models. The investigation on maritime accidents is, nowadays, a very important tool to identify the problems related to human factor and can support accident prevention and the improvement of maritime safety. Part of this investigation should in future also be near misses. Operation of ships is full of regulations, instructions and guidelines also addressing human factors and safety culture to enhance safety. However, even though the roots of a safety culture have been established, there are still serious barriers to the breakthrough of the safety management. One of the most common deficiencies in the case of maritime transport is the respective monitoring and documentation usually lacking of adequacy and excellence. Nonetheless, the maritime area can be exemplified from other industries where activities are ongoing to foster and enhance safety culture.

Plutonium Finishing Plant (PFP) Standards/Requirements Identification Document (S/RID)

Energy Technology Data Exchange (ETDEWEB)

Maddox, B.S.

1996-01-01

This Standards/Requirements Identification Document (S/RID) sets forth the Environmental Safety and Health (ESH) standards/requirements for the Plutonium Finishing Plant (PFP). This S/RID is applicable to the appropriate life cycle phases of design, construction, operation, and preparation for decommissioning. These standards/requirements are adequate to ensure the protection of the health and safety of workers, the public, and the environment.

Plutonium Finishing Plant (PFP) Standards/Requirements Identification Document (S/RID)

International Nuclear Information System (INIS)

Maddox, B.S.

1996-01-01

This Standards/Requirements Identification Document (S/RID) sets forth the Environmental Safety and Health (ESH) standards/requirements for the Plutonium Finishing Plant (PFP). This S/RID is applicable to the appropriate life cycle phases of design, construction, operation, and preparation for decommissioning. These standards/requirements are adequate to ensure the protection of the health and safety of workers, the public, and the environment

Brief report: Associations between in-person and electronic bullying victimization and missing school because of safety concerns among U.S. high school students.

Science.gov (United States)

Steiner, Riley J; Rasberry, Catherine N

2015-08-01

Although associations between bullying and health risk behaviors are well-documented, research on bullying and education-related outcomes, including school attendance, is limited. This study examines associations between bullying victimization (in-person and electronic) and missing school because of safety concerns among a nationally representative sample of U.S. high school students. We used logistic regression analyses to analyze data from the 2013 national Youth Risk Behavior Survey of students in grades 9-12. In-person and electronic victimization were each associated with increased odds of missing school due to safety concerns compared to no bullying victimization. Having been bullied both in-person and electronically was associated with greater odds of missing school compared to electronic bullying only for female students and in-person bullying only for male students. Collaborations between health professionals and educators to prevent bullying may improve school attendance. Published by Elsevier Ltd.

Nuclear Safety Review for the Year 2012

International Nuclear Information System (INIS)

2012-07-01

The Nuclear Safety Review for the Year 2012 contains an analytical overview of the dominant trends, issues and challenges worldwide in 2011 and the Agency's efforts to strengthen the global nuclear safety framework. This year's report also highlights issues and activities related to the accident at the Fukushima Daiichi nuclear power plant. The analytical overview is supported by the Appendix at the end of this document, entitled: The IAEA Safety Standards: Activities during 2011. A draft version of the Nuclear Safety Review for the Year 2012 was submitted to the March 2012 session of the Board of Governors in document GOV/2012/6. The final version of the Nuclear Safety Review for the Year 2012 was prepared in light of the discussions held during the Board of Governors and also of the comments received.

ISS Crew Transportation and Services Requirements Document

Science.gov (United States)

Bayt, Robert L. (Compiler); Lueders, Kathryn L. (Compiler)

2016-01-01

The ISS Crew Transportation and Services Requirements Document (CCT-REQ-1130) contains all technical, safety, and crew health medical requirements that are mandatory for achieving a Crew Transportation System Certification that will allow for International Space Station delivery and return of NASA crew and limited cargo. Previously approved on TN23183.

14 CFR 431.33 - Safety organization.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 4 2010-01-01 2010-01-01 false Safety organization. 431.33 Section 431.33... Launch and Reentry of a Reusable Launch Vehicle § 431.33 Safety organization. (a) An applicant shall maintain a safety organization and document it by identifying lines of communication and approval authority...

Performance Testing Methodology for Safety-Critical Programmable Logic Controller

International Nuclear Information System (INIS)

Kim, Chang Ho; Oh, Do Young; Kim, Ji Hyeon; Kim, Sung Ho; Sohn, Se Do

2009-01-01

The Programmable Logic Controller (PLC) for use in Nuclear Power Plant safety-related applications is being developed and tested first time in Korea. This safety-related PLC is being developed with requirements of regulatory guideline and industry standards for safety system. To test that the quality of the developed PLC is sufficient to be used in safety critical system, document review and various product testings were performed over the development documents for S/W, H/W, and V/V. This paper provides the performance testing methodology and its effectiveness for PLC platform conducted by KOPEC

Nuclear power plants and safety; Elektrownie jadrowe i bezpieczenstwo

Energy Technology Data Exchange (ETDEWEB)

Celinski, Z. [Politechnika Warszawska, Warsaw (Poland)

1995-12-31

The brief scope on the state of nuclear energetics worldwide as well as development perspectives have been presented. The safety problems, economic competitiveness and public acceptance have been shown and discussed. 55 refs, 3 figs, 2 tabs.

XML: Solution for the integration of nuclear power plant data and technical documents

International Nuclear Information System (INIS)

Gordillo, F.

2000-01-01

Assuring proper operation of the systems that make up a nuclear power plant requires handling a massive amount of technical documents. This technical documentation, consisting mainly of system descriptions, operating and maintenance procedures, safety procedures, etc, presents particular characteristics, mainly: Great volume of information. High contents in figures and graphics. High reliability required. Multiple cross-references among documents. (Author)

Safety study application guide

International Nuclear Information System (INIS)

1993-07-01

Martin Marietta Energy Systems, Inc., (Energy Systems) is committed to performing and documenting safety analyses for facilities it manages for the Department of Energy (DOE). Included are analyses of existing facilities done under the aegis of the Safety Analysis Report Upgrade Program, and analyses of new and modified facilities. A graded approach is used wherein the level of analysis and documentation for each facility is commensurate with the magnitude of the hazard(s), the complexity of the facility and the stage of the facility life cycle. Safety analysis reports (SARs) for hazard Category 1 and 2 facilities are usually detailed and extensive because these categories are associated with public health and safety risk. SARs for Category 3 are normally much less extensive because the risk to public health and safety is slight. At Energy Systems, safety studies are the name given to SARs for Category 3 (formerly open-quotes lowclose quotes) facilities. Safety studies are the appropriate instrument when on-site risks are limited to irreversible consequences to a few people, and off-site consequences are limited to reversible consequences to a few people. This application guide provides detailed instructions for performing safety studies that meet the requirements of DOE Orders 5480.22, open-quotes Technical Safety Requirements,close quotes and 5480.23, open-quotes Nuclear Safety Analysis Reports.close quotes A seven-chapter format has been adopted for safety studies. This format allows for discussion of all the items required by DOE Order 5480.23 and for the discussions to be readily traceable to the listing in the order. The chapter titles are: (1) Introduction and Summary, (2) Site, (3) Facility Description, (4) Safety Basis, (5) Hazardous Material Management, (6) Management, Organization, and Institutional Safety Provisions, and (7) Accident Analysis

New IAEA guidance on safety culture

International Nuclear Information System (INIS)

Haage, Monica; )

2012-01-01

Monica Haage described a project for Kozloduy Nuclear Power Plant in Bulgaria which was also funded by the Norwegian government. This project included the development of guidance documents and training on self-assessment and continuous improvement of safety culture. A draft IAEA safety culture survey was also developed as part of this project in collaboration with St Mary's University, Canada. This project was conducted in parallel with an IAEA project to develop new safety reports on safety culture self-assessment and continuous improvement. A safety report on safety culture during the pre-operational phases of NPPs has also been drafted. The IAEA approach to safety culture assessment was outlined and core principles of the approach were discussed. These include the use of several assessment methods (survey, interview, observation, focus groups, document review), and two distinct levels of analysis. The first is a descriptive analysis of the observed cultural characteristics from each assessment method and overarching themes. This is followed by a 'normative' analysis comparing what has been observed with the desirable characteristics of a strong, positive, safety culture, as defined by the IAEA safety culture framework. The application of this approach during recent Operational Safety Assessment Review Team (OSART) missions was described along with key learning points

Nuclear data needs within the U. S. Nuclear Criticality Safety program

International Nuclear Information System (INIS)

McKnight, R.D.; Dunn, M.E.; Little, R.C.; Felty, J.R.; McKamy, J.N.

2008-01-01

This paper will present the nuclear data needs currently identified within the US Nuclear Criticality Safety Program (NCSP). It will identify the priority data needs; it will describe the process of prioritizing those needs; and it will provide brief examples of recent data advances which have successfully addressed some of the priority criticality safety data needs.

Nuclear power plant systems, structures and components and their safety classification

International Nuclear Information System (INIS)

2000-01-01

The assurance of a nuclear power plant's safety is based on the reliable functioning of the plant as well as on its appropriate maintenance and operation. To ensure the reliability of operation, special attention shall be paid to the design, manufacturing, commissioning and operation of the plant and its components. To control these functions the nuclear power plant is divided into structural and functional entities, i.e. systems. A systems safety class is determined by its safety significance. Safety class specifies the procedures to be employed in plant design, construction, monitoring and operation. The classification document contains all documentation related to the classification of the nuclear power plant. The principles of safety classification and the procedures pertaining to the classification document are presented in this guide. In the Appendix of the guide, examples of systems most typical of each safety class are given to clarify the safety classification principles

Probabilistic safety assessment for seismic events

International Nuclear Information System (INIS)

1993-10-01

This Technical Document on Probabilistic Safety Assessment for Seismic Events is mainly associated with the Safety Practice on Treatment of External Hazards in PSA and discusses in detail one specific external hazard, i.e. earthquakes

E-nursing documentation as a tool for quality assurance.

Science.gov (United States)

Rajkovic, Vladislav; Sustersic, Olga; Rajkovic, Uros

2006-01-01

The article presents the results of a project with which we describe the reengineering of nursing documentation. Documentation in nursing is an efficient tool for ensuring quality health care and consequently quality patient treatment along the whole clinical path. We have taken into account the nursing process and patient treatment based on Henderson theoretical model of nursing that consists of 14 basic living activities. The model of new documentation enables tracing, transparency, selectivity, monitoring and analyses. All these factors lead to improvements of a health system as well as to improved safety of patients and members of nursing teams. Thus the documentation was developed for three health care segments: secondary and tertiary level, dispensaries and community health care. The new quality introduced to the documentation process by information and communication technology is presented by a database model and a software prototype for managing documentation.

Quality assurance application in the documentation of nuclear research reactor

International Nuclear Information System (INIS)

Nababan, N.

1999-01-01

For each nuclear research reactor a document control system should be established and should be provide for preparation, review, approval, issuance, distribution, revision and validation (where appropriate) of documents essential to the management, performance and verification of work. In the document control system the responsibilities for each participating organization or individual should be defined in writing. The types of document include, but are not limited to document comprising the QA program, safety requirements, maintenance and operating procedures, inspection instructions, inspection and test reports, assessment reports, drawings, data files, calculations, specifications, computer codes, purchase orders and related documents, vendor supplied documents and work instruction. Management should identify the need for documents and should provide guidance to the organizations and people preparing them. The guidance should cover the status, scope and contents and the policies, standards and codes witch apply. It should also explain the need for feedback of experience. Plant modification or the results of assessments could also give rise to the need for a new document

The Safety Case and Safety Assessment for the Disposal of Radioactive Waste

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-09-15

This Safety Guide provides guidance and recommendations on meeting the safety requirements in respect of the safety case and supporting safety assessment for the disposal of radioactive waste. The safety case and supporting safety assessment provide the basis for demonstration of safety and for licensing of radioactive waste disposal facilities and assist and guide decisions on siting, design and operations. The safety case is also the main basis on which dialogue with interested parties is conducted and on which confidence in the safety of the disposal facility is developed. This Safety Guide is relevant for operating organizations preparing the safety case as well as for the regulatory body responsible for developing the regulations and regulatory guidance that determine the basis and scope of the safety case. Contents: 1. Introduction; 2. Demonstrating the safety of radioactive waste disposal; 3. Safety principles and safety requirements; 4. The safety case for disposal of radioactive waste; 5. Radiological impact assessment for the period after closure; 6. Specific issues; 7. Documentation and use of the safety case; 8. Regulatory review process.

Criticality safety benchmark evaluation project: Recovering the past

Energy Technology Data Exchange (ETDEWEB)

Trumble, E.F.

1997-06-01

A very brief summary of the Criticality Safety Benchmark Evaluation Project of the Westinghouse Savannah River Company is provided in this paper. The purpose of the project is to provide a source of evaluated criticality safety experiments in an easily usable format. Another project goal is to search for any experiments that may have been lost or contain discrepancies, and to determine if they can be used. Results of evaluated experiments are being published as US DOE handbooks.

Repository of not readily available documents for project W-320

Energy Technology Data Exchange (ETDEWEB)

Conner, J.C.

1997-04-18

The purpose of this document is to provide a readily available source of the technical reports needed for the development of the safety documentation provided for the waste retrieval sluicing system (WRSS), designed to remove the radioactive and chemical sludge from tank 241-C-106, and transport that material to double-shell tank 241-AY-102 via a new, temporary, shielded, encased transfer line.

Repository of not readily available documents for project W-320

International Nuclear Information System (INIS)

Conner, J.C.

1997-01-01

The purpose of this document is to provide a readily available source of the technical reports needed for the development of the safety documentation provided for the waste retrieval sluicing system (WRSS), designed to remove the radioactive and chemical sludge from tank 241-C-106, and transport that material to double-shell tank 241-AY-102 via a new, temporary, shielded, encased transfer line

High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 7

Energy Technology Data Exchange (ETDEWEB)

1994-04-01

This Requirements Identification Document (RID) describes an Occupational Health and Safety Program as defined through the Relevant DOE Orders, regulations, industry codes/standards, industry guidance documents and, as appropriate, good industry practice. The definition of an Occupational Health and Safety Program as specified by this document is intended to address Defense Nuclear Facilities Safety Board Recommendations 90-2 and 91-1, which call for the strengthening of DOE complex activities through the identification and application of relevant standards which supplement or exceed requirements mandated by DOE Orders. This RID applies to the activities, personnel, structures, systems, components, and programs involved in maintaining the facility and executing the mission of the High-Level Waste Storage Tank Farms.

High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 7

International Nuclear Information System (INIS)

1994-04-01

This Requirements Identification Document (RID) describes an Occupational Health and Safety Program as defined through the Relevant DOE Orders, regulations, industry codes/standards, industry guidance documents and, as appropriate, good industry practice. The definition of an Occupational Health and Safety Program as specified by this document is intended to address Defense Nuclear Facilities Safety Board Recommendations 90-2 and 91-1, which call for the strengthening of DOE complex activities through the identification and application of relevant standards which supplement or exceed requirements mandated by DOE Orders. This RID applies to the activities, personnel, structures, systems, components, and programs involved in maintaining the facility and executing the mission of the High-Level Waste Storage Tank Farms

Defense transuranic waste program strategy document

International Nuclear Information System (INIS)

1982-07-01

This document summarizes the strategy for managing transuranic (TRU) wastes generated in defense and research activities regulated by the US Department of Energy. It supercedes a document issued in July 1980. In addition to showing how current strategies of the Defense Transuranic Waste Program (DTWP) are consistent with the national objective of isolating radioactive wastes from the biosphere, this document includes information about the activities of the Transuranic Lead Organization (TLO). To explain how the DTWP strategy is implemented, this document also discusses how the TLO coordinates and integrates the six separate elements of the DTWP: (1) Waste Generation Site Activities, (2) Storage Site Activities, (3) Burial Site Activities, (4) Technology Development, (5) Transportation Development, and (6) Permanent Disposal. Storage practices for TRU wastes do not pose short-term hazards to public health and safety or to the environment. Isolation of TRU wastes in a deep-mined geologic repository is considered the most promising of the waste disposal alternatives available. This assessment is supported by the DOE Record of Decision to proceed with research and development work at the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico - a deep-mined geologic research and development project. In support of the WIPP research project and the permanent disposal of TRU waste, the DTWP strategy for the near term will concentrate on completion of procedures and the design and construction of all facilities necessary to certify newly-generated (NG) and stored TRU wastes for emplacement in the WIPP. In addition, the strategy involves evaluating alternatives for disposing of some transuranic wastes by methods which may allow for on-site disposal of these wastes and yet preserve adequate margins of safety to protect public health and the environment

Safety Evaluation of Roundabouts in Georgia

Science.gov (United States)

2018-02-28

Several previous studies have documented significant safety benefits of roundabouts in the United Sates. However, the safety benefits for a given roundabout may vary depending on factors such as the familiarity of the driving population to roundabout...

Safety first!

CERN Multimedia

2016-01-01

Among the many duties I assumed at the beginning of the year was the ultimate responsibility for Safety at CERN: the responsibility for the physical safety of the personnel, the responsibility for the safe operation of the facilities, and the responsibility to ensure that CERN acts in accordance with the highest standards of radiation and environmental protection.   The Safety Policy document drawn up in September 2014 is an excellent basis for the implementation of Safety in all areas of CERN’s work. I am happy to commit during my mandate to help meet its objectives, not least by ensuring the Organization makes available the necessary means to achieve its Safety objectives. One of the main objectives of the HSE (Occupational Health and Safety and Environmental Protection) unit in the coming months is to enhance the measures to minimise CERN’s impact on the environment. I believe CERN should become a role model for an environmentally-aware scientific research laboratory. Risk ...

Idaho National Engineering Laboratory (INEL) Environmental Restoration Program (ERP), Baseline Safety Analysis File (BSAF). Revision 1

Energy Technology Data Exchange (ETDEWEB)

1994-06-20

This document was prepared to take the place of a Safety Evaluation Report since the Baseline Safety Analysis File (BSAF)and associated Baseline Technical Safety Requirements (TSR) File do not meet the requirements of a complete safety analysis documentation. Its purpose is to present in summary form the background of how the BSAF and Baseline TSR originated and a description of the process by which it was produced and approved for use in the Environmental Restoration Program.The BSAF is a facility safety reference document for INEL environmental restoration activities including environmental remediation of inactive waste sites and decontamination and decommissioning (D&D) of surplus facilities. The BSAF contains safety bases common to environmental restoration activities and guidelines for performing and documenting safety analysis. The common safety bases can be incorporated by reference into the safety analysis documentation prepared for individual environmental restoration activities with justification and any necessary revisions. The safety analysis guidelines in BSAF provide an accepted method for hazard analysis; analysis of normal, abnormal, and accident conditions; human factors analysis; and derivation of TSRS. The BSAF safety bases and guidelines are graded for environmental restoration activities.

Idaho National Engineering Laboratory (INEL) Environmental Restoration Program (ERP), Baseline Safety Analysis File (BSAF). Revision 1

International Nuclear Information System (INIS)

1994-01-01

This document was prepared to take the place of a Safety Evaluation Report since the Baseline Safety Analysis File (BSAF)and associated Baseline Technical Safety Requirements (TSR) File do not meet the requirements of a complete safety analysis documentation. Its purpose is to present in summary form the background of how the BSAF and Baseline TSR originated and a description of the process by which it was produced and approved for use in the Environmental Restoration Program.The BSAF is a facility safety reference document for INEL environmental restoration activities including environmental remediation of inactive waste sites and decontamination and decommissioning (D ampersand D) of surplus facilities. The BSAF contains safety bases common to environmental restoration activities and guidelines for performing and documenting safety analysis. The common safety bases can be incorporated by reference into the safety analysis documentation prepared for individual environmental restoration activities with justification and any necessary revisions. The safety analysis guidelines in BSAF provide an accepted method for hazard analysis; analysis of normal, abnormal, and accident conditions; human factors analysis; and derivation of TSRS. The BSAF safety bases and guidelines are graded for environmental restoration activities

National briefing summaries: Nuclear fuel cycle and waste management

International Nuclear Information System (INIS)

Schneider, K.J.; Lakey, L.T.; Silviera, D.J.

1988-12-01

The National Briefing Summaries is a compilation of publicly available information concerning the nuclear fuel cycle and radioactive waste management strategies and programs of 21 nations, including the United States and three international agencies that have publicized their activities in this field. It presents available highlight information with references that may be used by the reader for additional information. The information in this document is compiled primarily for use by the US Department of Energy and other US federal agencies and their contractors to provide summary information on radioactive waste management activities in other countries. This document provides an awareness to managers and technical staff of what is occurring in other countries with regard to strategies, activities, and facilities. The information may be useful in program planning to improve and benefit United States' programs through foreign information exchange. Benefits to foreign exchange may be derived through a number of exchange activities

Guidance for implementing an environmental, safety, and health-assurance program. Volume 15. A model plan for line organization environmental, safety, and health-assurance programs

Energy Technology Data Exchange (ETDEWEB)

Ellingson, A.C.; Trauth, C.A. Jr.

1982-01-01

This is 1 of 15 documents designed to illustrate how an Environmental, Safety and Health (ES and H) Assurance Program may be implemented. The generic definition of ES and H Assurance Programs is given in a companion document entitled An Environmental, Safety and Health Assurance Program Standard. This particular document presents a model operational-level ES and H Assurance Program that may be used as a guide by an operational-level organization in developing its own plan. The model presented here reflects the guidance given in the total series of 15 documents.

The Development of child road safety competence : the new approach tо road safety education

OpenAIRE

Vilkonis, Rytis

2005-01-01

The education and information are the strategies of the Road safety. However, some of the documents and scientific findings revealed the chaotic, desultory and theoretically groundless Road safety education and it can be stated that Road safety education system in Lithuania is still being established. The shortage of the theoretical and empirical base of Road safety education is slowing down the process of the system development. Aim of the research is to disclose the assumptions for developm...

Safety-barrier diagrams as a tool for modelling safety of hydrogen applications

DEFF Research Database (Denmark)

Duijm, Nijs Jan; Markert, Frank

2009-01-01

Safety-barrier diagrams have proven to be a useful tool in documenting the safety measures taken to prevent incidents and accidents in process industry. Especially during the introduction of new hydrogen technologies or applications, as e.g. hydrogen refuelling stations, safety-barrier diagrams...... are considered a valuable supplement to other traditional risk analysis tools to support the communication with authorities and other stakeholders during the permitting process. Another advantage of safety-barrier diagrams is that they highlight the importance of functional and reliable safety barriers in any...... system and here is a direct focus on those barriers that need to be subject to safety management in terms of design and installation, operational use, inspection and monitoring, and maintenance. Safety-barrier diagrams support both quantitative and qualitative approaches. The paper will describe...

Examples of safety culture practices

International Nuclear Information System (INIS)

1997-01-01

This report has been prepared to illustrate the concepts and principles of safety culture produced in 1991 by the International Safety Advisory Group as 75-INSAG-4. It provides a small selection of examples taken from a worldwide collection of safety performance evaluations (e.g. IAEA safety series, national regulatory inspections, utility audits and a plant assessments). These documented evaluations collectively provide a database of safety performance strengths and weakness, and related safety culture observations. The examples which have been selected for inclusion in this report are those which are considered worthy of special mention and which illustrate a specific attribute of safety culture given in 75-INSAG-4

Monitored Retrievable Storage System Requirements Document. Revision 1

Energy Technology Data Exchange (ETDEWEB)

1994-03-01

This Monitored Retrievable Storage System Requirements Document (MRS-SRD) describes the functions to be performed and technical requirements for a Monitored Retrievable Storage (MRS) facility subelement and the On-Site Transfer and Storage (OSTS) subelement. The MRS facility subelement provides for temporary storage, at a Civilian Radioactive Waste Management System (CRWMS) operated site, of spent nuclear fuel (SNF) contained in an NRC-approved Multi-Purpose Canister (MPC) storage mode, or other NRC-approved storage modes. The OSTS subelement provides for transfer and storage, at Purchaser sites, of spent nuclear fuel (SNF) contained in MPCs. Both the MRS facility subelement and the OSTS subelement are in support of the CRWMS. The purpose of the MRS-SRD is to define the top-level requirements for the development of the MRS facility and the OSTS. These requirements include design, operation, and decommissioning requirements to the extent they impact on the physical development of the MRS facility and the OSTS. The document also presents an overall description of the MRS facility and the OSTS, their functions (derived by extending the functional analysis documented by the Physical System Requirements (PSR) Store Waste Document), their segments, and the requirements allocated to the segments. In addition, the top-level interface requirements of the MRS facility and the OSTS are included. As such, the MRS-SRD provides the technical baseline for the MRS Safety Analysis Report (SAR) design and the OSTS Safety Analysis Report design.

Interim safety basis compliance matrix for Trenches 31 and 34

International Nuclear Information System (INIS)

Ames, R.R.

1994-01-01

The tables provided in this document identify the specific requirements and basis for the administrative controls established in the Westinghouse Hanford Company (WHC) Solid Waste Burial Ground (SWBG) Interim Safety Basis (ISB) for operation of the Project W-025, Mixed Waste Lined Landfill (Trenches 31 and 34). The tables document the necessary controls and implementing procedures to ensure compliance with the requirements of the ISB. These requirements provide a basis for future Unreviewed Safety Questions (USQ) screening of applicable procedure changes, proposed physical modifications, tests, experiments, and occurrences. Table 1 provides the SWBG interim Operational Safety Requirements administrative controls matrix. The specific assumptions and commitments used in the safety analysis documents applicable to disposal of mixed wastes in Trenches 31 and 34 are provided in Table 2. Table 3 is provided to document the potential engineered and administrative mitigating features identified in the Preliminary Hazard Analysis (PHA) for disposal of mixed waste

Laboratory Safety Guide for Arkansas K-12 Schools.

Science.gov (United States)

Arkansas State Dept. of Education, Little Rock.

This document presents laboratory safety rules for Arkansas K-12 schools which were developed by the Arkansas Science Teachers Association (ASTA) and the Arkansas Department of Education (ADE). Contents include: (1) "Laboratory Safety Guide for Arkansas K-12 Schools"; (2) "Safety Considerations"; (3) "Safety Standards for Science Laboratories";…

Brief introduction of nuclear power plant emergency system EmInfoSys

International Nuclear Information System (INIS)

Xiao Yuhua; Zhao Zhigang

2014-01-01

Nuclear safety is the lifeline of nuclear energy and nuclear technology, nuclear accident emergency response is the last line of nuclear security defense, and is one of the important measures to ensure the healthy development of the nuclear energy safety. The establishment of complete function, sensitive reaction and efficient emergency management system for operation of nuclear and radiation accidents is an important task of nuclear security. From 2001 China Techenergy Co., Ltd. participated in the Qinshan, Tianwan, Ministry of Environmental Protection, Haiyang, Taishan, Fangchenggang, Sanmen, etc. nuclear emergency projects, and the nuclear emergency EmInfoSys (emergency management information system) platform was developed with independent intellectual property rights. A brief introduction about EmInfoSys system was performed in this paper. (authors)

National report of the Slovak Republic. Compiled in terms of the convention on nuclear safety. May 2007

International Nuclear Information System (INIS)

Balaj, J.; Konecny, L.; Rovny, J.; Metke, E.; Zemanova, D.; Turner, M.; Pospisil, M.; Jurina, V.; Rivny, I.; Soltes, L.; Petrik, T.; Petrovic, J.; Fazekasova, H.; Kobzova, D.; Trcka, T.; Maudry, J.; Betak, A.; Capkovic, J.

2007-05-01

A brief national safety report of the Slovak Republic compiled in terms of the joint convention on nuclear safety in 2007 is presented. This safety report consists of following chapters: (1) Introduction; (2) Nuclear installations in the Slovak Republic in terms of the Convention; (C) Scope of application; (3) Legislation and regulation; (4) General safety aspects; (5) Safety of nuclear installations in Slovakia; (6) Annexes

Environmental Restoration Remedial Action quality assurance requirements document

International Nuclear Information System (INIS)

1991-01-01

This document defines the quality assurance requirements for the US Department of Energy-Richland Operations Office Environmental Restoration Remedial Action program at the Hanford Site. The Environmental Restoration Remedial Action program implements significant commitments made by the US Department of Energy in the Hanford Federal Facility Agreement and Consent Order entered into with the Washington State Department of Ecology and the US Environmental Protection Agency. This document combines quality assurance requirements from various source documents into one set of requirements for use by the US Department of Energy-Richland Operations Office and other Environmental Restoration Remedial Action program participants. This document will serve as the basis for developing Quality Assurance Program Plans and implementing procedures by the participants. The requirements of this document will be applied to activities affecting quality, using a graded approach based on the importance of the item, service, or activity to the program objectives. The Quality Assurance Program that will be established using this document as the basis, together with other program and technical documents, form an integrated management control system for conducting the Environmental Restoration Remedial Action program activities in a manner that provides safety and protects the environment and public health

Nuclear fuel cycle safety research at Sandia Laboratories

International Nuclear Information System (INIS)

Ericson, D.M. Jr.

1978-11-01

This paper provides a brief introduction to Sandia Laboratories and an overview of Nuclear Regulatory Commission sponsored safety research with particular emphasis on light water reactor related activities. Several experimental and analytical programs are highlighted and the range of activities of a typical staff member illustrated

CANISTER HANDLING FACILITY CRITICALITY SAFETY CALCULATIONS

Energy Technology Data Exchange (ETDEWEB)

C.E. Sanders

2005-04-07

This design calculation revises and updates the previous criticality evaluation for the canister handling, transfer and staging operations to be performed in the Canister Handling Facility (CHF) documented in BSC [Bechtel SAIC Company] 2004 [DIRS 167614]. The purpose of the calculation is to demonstrate that the handling operations of canisters performed in the CHF meet the nuclear criticality safety design criteria specified in the ''Project Design Criteria (PDC) Document'' (BSC 2004 [DIRS 171599], Section 4.9.2.2), the nuclear facility safety requirement in ''Project Requirements Document'' (Canori and Leitner 2003 [DIRS 166275], p. 4-206), the functional/operational nuclear safety requirement in the ''Project Functional and Operational Requirements'' document (Curry 2004 [DIRS 170557], p. 75), and the functional nuclear criticality safety requirements described in the ''Canister Handling Facility Description Document'' (BSC 2004 [DIRS 168992], Sections 3.1.1.3.4.13 and 3.2.3). Specific scope of work contained in this activity consists of updating the Category 1 and 2 event sequence evaluations as identified in the ''Categorization of Event Sequences for License Application'' (BSC 2004 [DIRS 167268], Section 7). The CHF is limited in throughput capacity to handling sealed U.S. Department of Energy (DOE) spent nuclear fuel (SNF) and high-level radioactive waste (HLW) canisters, defense high-level radioactive waste (DHLW), naval canisters, multicanister overpacks (MCOs), vertical dual-purpose canisters (DPCs), and multipurpose canisters (MPCs) (if and when they become available) (BSC 2004 [DIRS 168992], p. 1-1). It should be noted that the design and safety analyses of the naval canisters are the responsibility of the U.S. Department of the Navy (Naval Nuclear Propulsion Program) and will not be included in this document. In addition, this calculation is valid for

Brief Assessment of Motor Function: Content Validity and Reliability of the Upper Extremity Gross Motor Scale

Science.gov (United States)

Cintas, Holly Lea; Parks, Rebecca; Don, Sarah; Gerber, Lynn

2011-01-01

Content validity and reliability of the Brief Assessment of Motor Function (BAMF) Upper Extremity Gross Motor Scale (UEGMS) were evaluated in this prospective, descriptive study. The UEGMS is one of five BAMF ordinal scales designed for quick documentation of gross, fine, and oral motor skill levels. Designed to be independent of age and…

Integrated Safety in ''SARAF'

International Nuclear Information System (INIS)

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

2004-01-01

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

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

International Nuclear Information System (INIS)

Armstrong, D.L.

1994-08-01

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

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

Energy Technology Data Exchange (ETDEWEB)

Armstrong, D.L.

1994-08-01

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

Basis Document for Sludge Stabilization

CERN Document Server

Risenmay, H R

2001-01-01

DOE-RL recently issued Safety Evaluation Report (SER) amendments to the PFP Final Safety Analysis Report, HNF-SD-CP-SAR-021 Rev. 2. The Justification for Continued Operations for 2736-ZB and plutonium oxides in BTCs Safety Basis change (letter DOE-RL ABD-074) was approved by one of the SERs. Also approved by SER was the revised accident analysis for Magnesium Hydroxide Precipitation Process (MHPP) gloveboxes HC-230C-3 and HC-230C-5 containing increased glovebox inventories and corresponding increases in seismic release consequence. Numerous implementing documents require revision and issuance to implement the SER approvals. The SER plutonium oxides into BTCs specifically limited the SER scope to ''pure or clean oxides, i.e., 85 wt% or grater Pu, in this feed change'' (SER Section 3.0 Base Information paragraph 4 [page 11]). Comprehensive USQ Evaluation PFP-2001-12 addressed the packaging of Pu alloy metals into BTCs, and the packaging of Pu alloy oxides (powders) into food pack cans and determined that the ac...

The Radiation Safety Culture: Image Gently

International Nuclear Information System (INIS)

Applegate, E.K.

2015-01-01

Barriers to Implementing Safety include Silos of Knowledge, Time, training and Resources. Creating a Safety Culture in Healthcare include Decreased authority gradients, Checklists and audits (QA), Use of structured language (SBAR), Situation, Background, Assessment, Recommendation Team briefings and debriefings (immediate learning, team building tools), Lifelong learning (PQI). Use of Collective Learning Opportunities - QA and PQI that include Web sites: IG, WFPI, IAEA, ISR and Data Registries: ACR . The Key Principles of Radiation Protection: When do we learn them? For Occupational Workers:Time, Distance and Shielding while those of For Patients: Justification, Optimization and Dose Limits (dose reference levels)

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

International Nuclear Information System (INIS)

1992-01-01

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