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Sample records for assessment requirement document

  1. Emergency Response Capability Baseline Needs Assessment - Requirements Document

    Energy Technology Data Exchange (ETDEWEB)

    Sharry, J A

    2016-10-04

    This document was prepared by John A. Sharry, LLNL Fire Marshal and LLNL Division Leader for Fire Protection and reviewed by LLNL Emergency Management Department Head James Colson. The document follows and expands upon the format and contents of the DOE Model Fire Protection Baseline Capabilities Assessment document contained on the DOE Fire Protection Web Site, but only addresses emergency response.

  2. TRANSPORTATION SYSTEM REQUIREMENTS DOCUMENT

    International Nuclear Information System (INIS)

    2004-01-01

    This document establishes the Transportation system requirements for the U.S. Department of Energy's (DOE's) Civilian Radioactive Waste Management System (CRWMS). These requirements are derived from the Civilian Radioactive Waste Management System Requirements Document (CRD). The Transportation System Requirements Document (TSRD) was developed in accordance with LP-3.1Q-OCRWM, Preparation, Review, and Approval of Office of National Transportation Level-2 Baseline Requirements. As illustrated in Figure 1, the TSRD forms a part of the DOE Office of Civilian Radioactive Waste Management (OCRWM) Technical Baseline

  3. Transportation System Requirements Document

    International Nuclear Information System (INIS)

    1993-09-01

    This Transportation System Requirements Document (Trans-SRD) describes the functions to be performed by and the technical requirements for the Transportation System to transport spent nuclear fuel (SNF) and high-level radioactive waste (HLW) from Purchaser and Producer sites to a Civilian Radioactive Waste Management System (CRWMS) site, and between CRWMS sites. The purpose of this document is to define the system-level requirements for Transportation consistent with the CRWMS Requirement Document (CRD). These requirements include design and operations requirements to the extent they impact on the development of the physical segments of Transportation. The document also presents an overall description of Transportation, its functions, its segments, and the requirements allocated to the segments and the system-level interfaces with Transportation. The interface identification and description are published in the CRWMS Interface Specification

  4. Lawrence Livermore National Laboratory Emergency Response Capability Baseline Needs Assessment Requirement Document

    Energy Technology Data Exchange (ETDEWEB)

    Sharry, J A

    2009-12-30

    This revision of the LLNL Fire Protection Baseline Needs Assessment (BNA) was prepared by John A. Sharry, LLNL Fire Marshal and LLNL Division Leader for Fire Protection and reviewed by Martin Gresho, Sandia/CA Fire Marshal. The document follows and expands upon the format and contents of the DOE Model Fire Protection Baseline Capabilities Assessment document contained on the DOE Fire Protection Web Site, but only address emergency response. The original LLNL BNA was created on April 23, 1997 as a means of collecting all requirements concerning emergency response capabilities at LLNL (including response to emergencies at Sandia/CA) into one BNA document. The original BNA documented the basis for emergency response, emergency personnel staffing, and emergency response equipment over the years. The BNA has been updated and reissued five times since in 1998, 1999, 2000, 2002, and 2004. A significant format change was performed in the 2004 update of the BNA in that it was 'zero based.' Starting with the requirement documents, the 2004 BNA evaluated the requirements, and determined minimum needs without regard to previous evaluations. This 2010 update maintains the same basic format and requirements as the 2004 BNA. In this 2010 BNA, as in the previous BNA, the document has been intentionally divided into two separate documents - the needs assessment (1) and the compliance assessment (2). The needs assessment will be referred to as the BNA and the compliance assessment will be referred to as the BNA Compliance Assessment. The primary driver for separation is that the needs assessment identifies the detailed applicable regulations (primarily NFPA Standards) for emergency response capabilities based on the hazards present at LLNL and Sandia/CA and the geographical location of the facilities. The needs assessment also identifies areas where the modification of the requirements in the applicable NFPA standards is appropriate, due to the improved fire protection

  5. Waste management system requirements document

    International Nuclear Information System (INIS)

    1991-02-01

    This volume defines the top level requirements for the Mined Geologic Disposal System (MGDS). It is designed to be used in conjunction with Volume 1 of the WMSR, General System Requirements. It provides a functional description expanding the requirements allocated to the MGDS in Volume 1 and elaborates on each requirement by providing associated performance criteria as appropriate. Volumes 1 and 4 of the WMSR provide a minimum set of requirements that must be satisfied by the final MGDS design. This document sets forth specific requirements that must be fulfilled. It is not the intent or purpose of this top level document to describe how each requirement is to be satisfied in the final MGDS design. Each subsequent level of the technical document hierarchy must provide further guidance and definition as to how each of these requirements is to be implemented in the design. It is expected that each subsequent level of requirements will be significantly more detailed. Section 2 of this volume provides a functional description of the MGDS. Each function is addressed in terms of requirements, and performance criteria. Section 3 provides a list of controlling documents. Each document cited in a requirement of Chapter 2 is included in this list and is incorporated into this document as a requirement on the final system. The WMSR addresses only federal requirements (i.e., laws, regulations and DOE orders). State and local requirements are not addressed. However, it will be specifically noted at the potentially affected WMSR requirements that there could be additional or more stringent regulations imposed by a state or local requirements or administering agency over the cited federal requirements

  6. Waste Management System Requirement document

    International Nuclear Information System (INIS)

    1990-04-01

    This volume defines the top level technical requirements for the Monitored Retrievable Storage (MRS) facility. It is designed to be used in conjunction with Volume 1, General System Requirements. Volume 3 provides a functional description expanding the requirements allocated to the MRS facility in Volume 1 and, when appropriate, elaborates on requirements by providing associated performance criteria. Volumes 1 and 3 together convey a minimum set of requirements that must be satisfied by the final MRS facility design without unduly constraining individual design efforts. The requirements are derived from the Nuclear Waste Policy Act of 1982 (NWPA), the Nuclear Waste Policy Amendments Act of 1987 (NWPAA), the Environmental Protection Agency's (EPA) Environmental Standards for the Management and Disposal of Spent Nuclear Fuel (40 CFR 191), NRC Licensing Requirements for the Independent Storage of Spent Nuclear and High-Level Radioactive Waste (10 CFR 72), and other federal statutory and regulatory requirements, and major program policy decisions. This document sets forth specific requirements that will be fulfilled. Each subsequent level of the technical document hierarchy will be significantly more detailed and provide further guidance and definition as to how each of these requirements will be implemented in the design. Requirements appearing in Volume 3 are traceable into the MRS Design Requirements Document. Section 2 of this volume provides a functional breakdown for the MRS facility. 1 tab

  7. Data requirement comparison between the fixed site upgrade rule guidance compendium and the Structured Assessment Approach Licensee Submittal Document

    Energy Technology Data Exchange (ETDEWEB)

    Parziale, A.A.; Sacks, I.J.

    1980-12-01

    We compared the Structured Assessment Approach's (SAA) Licensee Submittal Document (LSD) with the Fixed Site Physical Protection Upgrade Rule Guidance Compendium Standard Format and Content (SFC) Guide using correlation matrices to see how well the data requirements of the SFC Guide coincided with those of a specific automated vulnerability assessment technique for fixed-site nuclear fuel cycle facilities, namely, SAA. We found that a limited SAA assessment is possible using the SFC Guide, but significant and critical safeguards vulnerabilities might be missed. Also, it was found that in some cases the organization and format of the SFC Guide input data and information made the preparation of data for the SAA somewhat awkward. 2 refs., 2 tabs.

  8. Documentation requirements for radiation sterilization

    DEFF Research Database (Denmark)

    Miller, A.

    1995-01-01

    Several standards are recently approved or are under development by the standard organizations ISO and CEN in the field of radiation sterilization. Particularly in Europe these standards define new requirements on some issues and on other issues they emphasize the necessary documentation for appr......Several standards are recently approved or are under development by the standard organizations ISO and CEN in the field of radiation sterilization. Particularly in Europe these standards define new requirements on some issues and on other issues they emphasize the necessary documentation...... for approval of radiation sterilized products. The impact of these standards on the radiation sterilization is discussed, with special attention given to a few special issues, mainly traceability and uncertainty of measurement results....

  9. The European Utility Requirement Document

    International Nuclear Information System (INIS)

    Roche, I.I.

    1999-01-01

    The major European electricity producers work on a common requirement document for future LWR plants since 1992. They aim at requirements acceptable together by the owners, the public and the authorities. Thus the designers can develop standard LWR designs acceptable everywhere in Europe and the utilities can open their consultations to vendors on common bases. Such a standardisation promotes an improvement of generation costs and of safety : public and authorities acceptance should be improved as well ; significant savings are expected in development and construction costs. Since the early stages of the project, the EUR group has grown significantly. It now includes utilities from nine European countries. Utilities from two other European countries are joining the group. Specific cooperation agreements are also in progress with a few extra-European partners

  10. A Study on the Quantitative Assessment Method of Software Requirement Documents Using Software Engineering Measures and Bayesian Belief Networks

    International Nuclear Information System (INIS)

    Eom, Heung Seop; Kang, Hyun Gook; Park, Ki Hong; Kwon, Kee Choon; Chang, Seung Cheol

    2005-01-01

    One of the major challenges in using the digital systems in a NPP is the reliability estimation of safety critical software embedded in the digital safety systems. Precise quantitative assessment of the reliability of safety critical software is nearly impossible, since many of the aspects to be considered are of qualitative nature and not directly measurable, but they have to be estimated for a practical use. Therefore an expert's judgment plays an important role in estimating the reliability of the software embedded in safety-critical systems in practice, because they can deal with all the diverse evidence relevant to the reliability and can perform an inference based on the evidence. But, in general, the experts' way of combining the diverse evidence and performing an inference is usually informal and qualitative, which is hard to discuss and will eventually lead to a debate about the conclusion. We have been carrying out research on a quantitative assessment of the reliability of safety critical software using Bayesian Belief Networks (BBN). BBN has been proven to be a useful modeling formalism because a user can represent a complex set of events and relationships in a fashion that can easily be interpreted by others. In the previous works we have assessed a software requirement specification of a reactor protection system by using our BBN-based assessment model. The BBN model mainly employed an expert's subjective probabilities as inputs. In the process of assessing the software requirement documents we found out that the BBN model was excessively dependent on experts' subjective judgments in a large part. Therefore, to overcome the weakness of our methodology we employed conventional software engineering measures into the BBN model as shown in this paper. The quantitative relationship between the conventional software measures and the reliability of software were not identified well in the past. Then recently there appeared a few researches on a ranking of

  11. Molten Salt Reactor Experiment Facility (Building 7503) standards/requirements identification document adherence assessment plan at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1996-02-01

    This is the Phase 2 (adherence) assessment plan for the Building 7503 Molten Salt Reactor Experiment (MSRE) Facility standards/requirements identification document (S/RID). This document outlines the activities to be conducted from FY 1996 through FY 1998 to ensure that the standards and requirements identified in the MSRE S/RID are being implemented properly. This plan is required in accordance with the Department of Energy Implementation Plan for Defense Nuclear Facilities Safety Board Recommendation 90-2, November 9, 1994, Attachment 1A. This plan addresses the major aspects of the adherence assessment and will be consistent with Energy Systems procedure QA-2. 7 ''Surveillances.''

  12. Waste Management System Requirements Document

    International Nuclear Information System (INIS)

    1992-02-01

    This DCP establishes an interim plan for the Office of Civilian Radioactive Waste Management (OCRWM) technical baseline until the results of the OCRWM Document Hierarchy Task Force can be implemented. This plan is needed to maintain continuity in the Program for ongoing work in the areas of Waste Acceptance, Transportation, Monitored Retrievable Storage (MRS) and Yucca Mountain Site Characterization

  13. Civilian Radioactive Waste Management System Requirements Document

    International Nuclear Information System (INIS)

    1992-12-01

    This document specifies the top-level requirements for the Civilian Radioactive Waste Management System (CRWMS). The document is referred to herein as the CRD, for CRWMS Requirements document. The OCRWM System Engineering Management Plan (SEMP) establishes the technical document hierarchy (hierarchy of technical requirements and configuration baseline documents) for the CRWMS program. The CRD is the top-level document in this hierarchy. The immediate subordinate documents are the System Requirements Documents (SRDS) for the four elements of the CRWMS and the Interface Specification (IFS). The four elements of the CRWMS are the Waste Acceptance System, the Transportation System, the Monitored Retrievable Storage (MRS) System and the Mined Geologic Disposal System (MGDS). The Interface Specification describes the six inter-element interfaces between the four elements. This hierarchy establishes the requirements to be addressed by the design of the system elements. Many of the technical requirements for the CRWMS are documented in a variety of Federal regulations, DOE directives and other Government documentation. It is the purpose of the CRD to establish the technical requirements for the entire program. In doing so, the CRD summarizes source documentation for requirements that must be addressed by the program, specifies particular requirements, and documents derived requirements that are not covered in regulatory and other Government documentation, but are necessary to accomplish the mission of the CRWMS. The CRD defines the CRWMS by identifying the top-level functions the elements must perform (These top-level functions were derived using functional analysis initially documented in the Physical System Requirements (PSR) documents). The CRD also defines the top-level physical architecture of the system and allocates the functions and requirements to the architectural elements of the system

  14. Building 894 hazards assessment document

    International Nuclear Information System (INIS)

    Banda, Z.; Williams, M.

    1996-07-01

    The Department of Energy Order 5500.3A requires facility-specific hazards assessments be prepared, maintained, and used for emergency planning purposes. This hazards assessment document describes the chemical and radiological hazards associated with Building 894. The entire inventory was subjected to the screening criteria for potential airborne impact to onsite and offsite individuals out of which 9 chemicals were kept for further evaluation. The air dispersion model, ALOHA, estimated pollutant concentrations downwind from the source of a release, taking into consideration the toxicological and physical characteristics of the release site, the atmospheric conditions, and the circumstances of the release. The greatest distance at which a postulated facility event will produce consequences exceeding the Early Severe Health Effects threshold is 130 meters. The highest emergency classification is a General Emergency. The Emergency Planning Zone is a nominal 130 meter area that conforms to DOE boundaries and physical/jurisdictional boundaries such as fence lines and streets

  15. Building 6630 hazards assessment document

    International Nuclear Information System (INIS)

    Williams, M.; Banda, Z.

    1996-10-01

    The Department of Energy Order 5500.3A requires facility-specific hazards assessments be prepared, maintained, and used for emergency planning purposes. This hazards assessment document describes the chemical and radiological hazards associated with Building 6630. The entire inventory was subjected to the screening criteria for potential airborne impact to onsite and offsite individuals out of which one chemical was kept for further evaluation. The air dispersion model, ALOHA, estimated pollutant concentrations downwind from the source of a release, taking into consideration the toxicological and physical characteristics of the chemical release site, the atmospheric conditions, and the circumstances of the release. The greatest distance at which a postulated facility event will produce consequences exceeding the Early Severe Health Effects threshold is 76 meters. The highest emergency classification is an Alert. The Emergency Planning Zone is a nominal 100 meter area that conforms to DOE boundaries and physical/jurisdictional boundaries such as fence lines and streets

  16. Mined Geologic Disposal System Requirements Document

    International Nuclear Information System (INIS)

    1993-01-01

    This Mined Geologic Disposal System Requirements document (MGDS-RD) describes the functions to be performed by, and the requirements for, a Mined Geologic Disposal System (MGDS) for the permanent disposal of spent nuclear fuel (SNF) and commercial and defense high level radioactive waste (HLW) in support of the Civilian Radioactive Waste Management System (CRWMS). The development and control of the MGDS-RD is quality-affecting work and is subject to the Department of Energy (DOE) Office of Civilian Radioactive Waste Management (OCRWM) Quality Assurance Requirements Document (QARD). As part of the technical requirements baseline, it is also subject to Baseline Management Plan controls. The MGDS-RD and the other program-level requirements documents have been prepared and managed in accordance with the Technical Document Preparation Plan (TDPP) for the Preparation of System Requirements Documents

  17. TWRS configuration management requirement source document

    International Nuclear Information System (INIS)

    Vann, J.M.

    1997-01-01

    The TWRS Configuration Management (CM) Requirement Source document prescribes CM as a basic product life-cycle function by which work and activities are conducted or accomplished. This document serves as the requirements basis for the TWRS CM program. The objective of the TWRS CM program is to establish consistency among requirements, physical/functional configuration, information, and documentation for TWRS and TWRS products, and to maintain this consistency throughout the life-cycle of TWRS and the product, particularly as changes are being made

  18. 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

  19. Waste Acceptance System Requirements document (WASRD)

    International Nuclear Information System (INIS)

    1993-01-01

    This Waste Acceptance System Requirements document (WA-SRD) describes the functions to be performed and the technical requirements for a Waste Acceptance System for accepting spent nuclear fuel (SNF) and high-level radioactive waste (HLW) into the Civilian Radioactive Waste Management System (CRWMS). This revision of the WA-SRD addresses the requirements for the acceptance of HLW. This revision has been developed as a top priority document to permit DOE's Office of Environmental Restoration and Waste Management (EM) to commence waste qualification runs at the Savannah River Site's (SRS) Defense Waste Processing Facility (DWPF) in a timely manner. Additionally, this revision of the WA-SRD includes the requirements from the Physical System Requirements -- Accept Waste document for the acceptance of SNF. A subsequent revision will fully address requirements relative to the acceptance of SNF

  20. 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.

  1. 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

  2. Mined Geologic Disposal System Requirements Document

    International Nuclear Information System (INIS)

    1994-03-01

    This Mined Geologic Disposal System Requirements Document (MGDS-RD) describes the functions to be performed by, and the requirements for, a Mined Geologic Disposal System (MGDS) for the permanent disposal of spent nuclear fuel (SNF) (including SNF loaded in multi-purpose canisters (MPCs)) and commercial and defense high-level radioactive waste (HLW) in support of the Civilian Radioactive Waste Management System (CRWMS). The purpose of the MGDS-RD is to define the program-level requirements for the design of the Repository, the Exploratory Studies Facility (ESF), and Surface Based Testing Facilities (SBTF). These requirements include design, operation, and decommissioning requirements to the extent they impact on the physical development of the MGDS. The document also presents an overall description of the MGDS, its functions (derived using the functional analysis documented by the Physical System Requirements (PSR) documents as a starting point), its segments as described in Section 3.1.3, and the requirements allocated to the segments. In addition, the program-level interfaces of the MGDS are identified. As such, the MGDS-RD provides the technical baseline for the design of the MGDS

  3. From document to database: modernizing requirements management

    International Nuclear Information System (INIS)

    Giajnorio, J.; Hamilton, S.

    2007-01-01

    The creation, communication, and management of design requirements are central to the successful completion of any large engineering project, both technically and commercially. Design requirements in the Canadian nuclear industry are typically numbered lists in multiple documents created using word processing software. As an alternative, GE Nuclear Products implemented a central requirements management database for a major project at Bruce Power. The database configured the off-the-shelf software product, Telelogic Doors, to GE's requirements structure. This paper describes the advantages realized by this scheme. Examples include traceability from customer requirements through to test procedures, concurrent engineering, and automated change history. (author)

  4. Supplemental design requirements document, Project W026

    International Nuclear Information System (INIS)

    Weidert, J.R.

    1993-01-01

    This document supplements and extends the Functional Design Criteria, SP-W026-FDC-001, for the Waste Receiving and Processing Facility (WRAP), Module 1. It provides additional detailed requirements, summarizes key Westinghouse Hanford Company design guidance, and establishes baseline technical agreements to be used in definitive design of the WRAP-1 facility. Revision 3 of the Supplemental Design Requirements Document has been assigned an Impact Level of 3ESQ based on the content of the entire revision. The actual changes made from Revision 2 have an Impact Level of 3S and the basis for these changes was previously reviewed and approved per WHC correspondence No. 9355770

  5. Hanford Tanks Initiative requirements and document management process guide

    International Nuclear Information System (INIS)

    Schaus, P.S.

    1998-01-01

    This revision of the guide provides updated references to project management level Program Management and Assessment Configuration Management activities, and provides working level directions for submitting requirements and project documentation related to the Hanford Tanks Initiative (HTI) project. This includes documents and information created by HTI, as well as non-HTI generated materials submitted to the project

  6. Managing Requirements-Documents to Data

    Science.gov (United States)

    Orr, Kevin; Hudson, Abe

    2017-01-01

    Managing Requirements on long term projects like International Space Station (ISS) can go thru many phases, from initial product development to almost over 20 years of operations and sustainment. Over that time many authorized changes have been made to the requirement set, that apply to any new systems that would visit the ISS today, like commercial cargo/crew vehicles or payloads. Explore the benefits of managing requirements in a database while satisfying traditional documents needs for contracts and stakeholder/user consumption that are not tied into the database.

  7. FIREX mission requirements document for renewable resources

    Science.gov (United States)

    Carsey, F.; Dixon, T.

    1982-01-01

    The initial experimental program and mission requirements for a satellite synthetic aperture radar (SAR) system FIREX (Free-Flying Imaging Radar Experiment) for renewable resources is described. The spacecraft SAR is a C-band and L-band VV polarized system operating at two angles of incidence which is designated as a research instrument for crop identification, crop canopy condition assessments, soil moisture condition estimation, forestry type and condition assessments, snow water equivalent and snow wetness assessments, wetland and coastal land type identification and mapping, flood extent mapping, and assessment of drainage characteristics of watersheds for water resources applications. Specific mission design issues such as the preferred incidence angles for vegetation canopy measurements and the utility of a dual frequency (L and C-band) or dual polarization system as compared to the baseline system are addressed.

  8. Documentation design for probabilistic risk assessment

    International Nuclear Information System (INIS)

    Parkinson, W.J.; von Herrmann, J.L.

    1985-01-01

    This paper describes a framework for documentation design of probabilistic risk assessment (PRA) and is based on the EPRI document NP-3470 ''Documentation Design for Probabilistic Risk Assessment''. The goals for PRA documentation are stated. Four audiences are identified which PRA documentation must satisfy, and the documentation consistent with the needs of the various audiences are discussed, i.e., the Summary Report, the Executive Summary, the Main Report, and Appendices. The authors recommend the documentation specifications discussed herein as guides rather than rigid definitions

  9. Assessment of LANL beryllium waste management documentation

    International Nuclear Information System (INIS)

    Danna, J.G.; Jennrich, E.A.; Lund, D.M.; Davis, K.D.; Hoevemeyer, S.S.

    1991-04-01

    The objective of this report is to determine present status of the preparation and implementation of the various high priority documents required to properly manage the beryllium waste generated at the Laboratory. The documents being assessed are: Waste Acceptance Criteria, Waste Characterization Plan, Waste Certification Plan, Waste Acceptance Procedures, Waste Characterization Procedures, Waste Certification Procedures, Waste Training Procedures and Waste Recordkeeping Procedures. Beryllium is regulated (as a dust) under 40 CFR 261.33 as ''Discarded commercial chemical products, off specification species, container residues and spill residues thereof.'' Beryllium is also identified in the 3rd thirds ruling of June 1, 1990 as being restricted from land disposal (as a dust). The beryllium waste generated at the Laboratory is handled separately because beryllium has been identified as a highly toxic carcinogenic material

  10. 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.

  11. 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

  12. 22 CFR 40.71 - Documentation requirements for immigrants.

    Science.gov (United States)

    2010-04-01

    ... 22 Foreign Relations 1 2010-04-01 2010-04-01 false Documentation requirements for immigrants. 40... NONIMMIGRANTS AND IMMIGRANTS UNDER THE IMMIGRATION AND NATIONALITY ACT, AS AMENDED Documentation Requirements § 40.71 Documentation requirements for immigrants. INA 212(a)(7)(A) is not applicable at the time of...

  13. Advanced Materials Laboratory hazards assessment document

    Energy Technology Data Exchange (ETDEWEB)

    Barnett, B.; Banda, Z.

    1995-10-01

    The Department of Energy Order 55OO.3A requires facility-specific hazards assessments be prepared, maintained, and used for emergency planning purposes. This hazards assessment document describes the chemical and radiological hazards associated with the AML. The entire inventory was screened according to the potential airborne impact to onsite and offsite individuals. The air dispersion model, ALOHA, estimated pollutant concentrations downwind from the source of a release, taking into consideration the toxicological and physical characteristics of the release site, the atmospheric conditions, and the circumstances of the release. The greatest distance at which a postulated facility event will produce consequences exceeding the Early Severe Health Effects threshold is 23 meters. The highest emergency classification is a General Emergency. The Emergency Planning Zone is a nominal area that conforms to DOE boundaries and physical/jurisdictional boundaries such as fence lines and streets.

  14. Tank waste remediation system functions and requirements document

    International Nuclear Information System (INIS)

    Carpenter, K.E

    1996-01-01

    This is the Tank Waste Remediation System (TWRS) Functions and Requirements Document derived from the TWRS Technical Baseline. The document consists of several text sections that provide the purpose, scope, background information, and an explanation of how this document assists the application of Systems Engineering to the TWRS. The primary functions identified in the TWRS Functions and Requirements Document are identified in Figure 4.1 (Section 4.0) Currently, this document is part of the overall effort to develop the TWRS Functional Requirements Baseline, and contains the functions and requirements needed to properly define the top three TWRS function levels. TWRS Technical Baseline information (RDD-100 database) included in the appendices of the attached document contain the TWRS functions, requirements, and architecture necessary to define the TWRS Functional Requirements Baseline. Document organization and user directions are provided in the introductory text. This document will continue to be modified during the TWRS life-cycle

  15. Tank waste remediation system functions and requirements document

    Energy Technology Data Exchange (ETDEWEB)

    Carpenter, K.E

    1996-10-03

    This is the Tank Waste Remediation System (TWRS) Functions and Requirements Document derived from the TWRS Technical Baseline. The document consists of several text sections that provide the purpose, scope, background information, and an explanation of how this document assists the application of Systems Engineering to the TWRS. The primary functions identified in the TWRS Functions and Requirements Document are identified in Figure 4.1 (Section 4.0) Currently, this document is part of the overall effort to develop the TWRS Functional Requirements Baseline, and contains the functions and requirements needed to properly define the top three TWRS function levels. TWRS Technical Baseline information (RDD-100 database) included in the appendices of the attached document contain the TWRS functions, requirements, and architecture necessary to define the TWRS Functional Requirements Baseline. Document organization and user directions are provided in the introductory text. This document will continue to be modified during the TWRS life-cycle.

  16. Spectrum analysis on quality requirements consideration in software design documents.

    Science.gov (United States)

    Kaiya, Haruhiko; Umemura, Masahiro; Ogata, Shinpei; Kaijiri, Kenji

    2013-12-01

    Software quality requirements defined in the requirements analysis stage should be implemented in the final products, such as source codes and system deployment. To guarantee this meta-requirement, quality requirements should be considered in the intermediate stages, such as the design stage or the architectural definition stage. We propose a novel method for checking whether quality requirements are considered in the design stage. In this method, a technique called "spectrum analysis for quality requirements" is applied not only to requirements specifications but also to design documents. The technique enables us to derive the spectrum of a document, and quality requirements considerations in the document are numerically represented in the spectrum. We can thus objectively identify whether the considerations of quality requirements in a requirements document are adapted to its design document. To validate the method, we applied it to commercial software systems with the help of a supporting tool, and we confirmed that the method worked well.

  17. Online mass storage system detailed requirements document

    Science.gov (United States)

    1976-01-01

    The requirements for an online high density magnetic tape data storage system that can be implemented in a multipurpose, multihost environment is set forth. The objective of the mass storage system is to provide a facility for the compact storage of large quantities of data and to make this data accessible to computer systems with minimum operator handling. The results of a market survey and analysis of candidate vendor who presently market high density tape data storage systems are included.

  18. Kauai Test Facility hazards assessment document

    Energy Technology Data Exchange (ETDEWEB)

    Swihart, A

    1995-05-01

    The Department of Energy Order 55003A requires facility-specific hazards assessment be prepared, maintained, and used for emergency planning purposes. This hazards assessment document describes the chemical and radiological hazards associated with the Kauai Test Facility, Barking Sands, Kauai, Hawaii. The Kauai Test Facility`s chemical and radiological inventories were screened according to potential airborne impact to onsite and offsite individuals. The air dispersion model, ALOHA, estimated pollutant concentrations downwind from the source of a release, taking into consideration the toxicological and physical characteristics of the release site, the atmospheric conditions, and the circumstances of the release. The greatest distance to the Early Severe Health Effects threshold is 4.2 kilometers. The highest emergency classification is a General Emergency at the {open_quotes}Main Complex{close_quotes} and a Site Area Emergency at the Kokole Point Launch Site. The Emergency Planning Zone for the {open_quotes}Main Complex{close_quotes} is 5 kilometers. The Emergency Planning Zone for the Kokole Point Launch Site is the Pacific Missile Range Facility`s site boundary.

  19. Kauai Test Facility hazards assessment document

    International Nuclear Information System (INIS)

    Swihart, A.

    1995-05-01

    The Department of Energy Order 55003A requires facility-specific hazards assessment be prepared, maintained, and used for emergency planning purposes. This hazards assessment document describes the chemical and radiological hazards associated with the Kauai Test Facility, Barking Sands, Kauai, Hawaii. The Kauai Test Facility's chemical and radiological inventories were screened according to potential airborne impact to onsite and offsite individuals. The air dispersion model, ALOHA, estimated pollutant concentrations downwind from the source of a release, taking into consideration the toxicological and physical characteristics of the release site, the atmospheric conditions, and the circumstances of the release. The greatest distance to the Early Severe Health Effects threshold is 4.2 kilometers. The highest emergency classification is a General Emergency at the open-quotes Main Complexclose quotes and a Site Area Emergency at the Kokole Point Launch Site. The Emergency Planning Zone for the open-quotes Main Complexclose quotes is 5 kilometers. The Emergency Planning Zone for the Kokole Point Launch Site is the Pacific Missile Range Facility's site boundary

  20. Technical requirements document for the waste flow analysis

    International Nuclear Information System (INIS)

    Shropshire, D.E.

    1996-05-01

    Purpose of this Technical Requirements Document is to define the top level customer requirements for the Waste Flow Analysis task. These requirements, once agreed upon with DOE, will be used to flow down subsequent development requirements to the model specifications. This document is intended to be a ''living document'' which will be modified over the course of the execution of this work element. Initial concurrence with the technical functional requirements from Environmental Management (EM)-50 is needed before the work plan can be developed

  1. Software requirements specification document for the AREST code development

    International Nuclear Information System (INIS)

    Engel, D.W.; McGrail, B.P.; Whitney, P.D.; Gray, W.J.; Williford, R.E.; White, M.D.; Eslinger, P.W.; Altenhofen, M.K.

    1993-11-01

    The Analysis of the Repository Source Term (AREST) computer code was selected in 1992 by the U.S. Department of Energy. The AREST code will be used to analyze the performance of an underground high level nuclear waste repository. The AREST code is being modified by the Pacific Northwest Laboratory (PNL) in order to evaluate the engineered barrier and waste package designs, model regulatory compliance, analyze sensitivities, and support total systems performance assessment modeling. The current version of the AREST code was developed to be a very useful tool for analyzing model uncertainties and sensitivities to input parameters. The code has also been used successfully in supplying source-terms that were used in a total systems performance assessment. The current version, however, has been found to be inadequate for the comparison and selection of a design for the waste package. This is due to the assumptions and simplifications made in the selection of the process and system models. Thus, the new version of the AREST code will be designed to focus on the details of the individual processes and implementation of more realistic models. This document describes the requirements of the new models that will be implemented. Included in this document is a section describing the near-field environmental conditions for this waste package modeling, description of the new process models that will be implemented, and a description of the computer requirements for the new version of the AREST code

  2. Project W-441 cold vacuum drying facility design requirements document

    International Nuclear Information System (INIS)

    O'Neill, C.T.

    1997-01-01

    This document has been prepared and is being released for Project W-441 to record the design basis for the design of the Cold Vacuum Drying Facility. This document sets forth the physical design criteria, Codes and Standards, and functional requirements that were used in the design of the Cold Vacuum Drying Facility. This document contains section 3, 4, 6, and 9 of the Cold Vacuum Drying Facility Design Requirements Document. The remaining sections will be issued at a later date. The purpose of the Facility is to dry, weld, and inspect the Multi-Canister Overpacks before transport to dry storage

  3. Transportation system requirements document. Revision 1 DCN01. Supplement

    International Nuclear Information System (INIS)

    1995-05-01

    The original Transportation System Requirements Document described the functions to be performed by and the technical requirements for the Transportation System to transport spent nuclear fuel (SNF) and high-level radioactive waste (HLW) from Purchaser and Producer sites to a Civilian Radioactive Waste Management System (CRWMS) site, and between CRWMS sites. The purpose of that document was to define the system-level requirements. These requirements include design and operations requirements to the extent they impact on the development of the physical segments of Transportation. The document also presented an overall description of Transportation, its functions, its segments, and the requirements allocated to the segments and the system-level interfaces with Transportation. This revision of the document contains only the pages that have been modified

  4. Assessment of LANL hazardous waste management documentation

    International Nuclear Information System (INIS)

    Davis, K.D.; Hoevemeyer, S.S.; Stirrup, T.S.; Jennrich, E.A.; Lund, D.M.

    1991-04-01

    The objective of this report is to present findings from evaluating the Los Alamos National Laboratory (LANL) ''Hazardous Waste Acceptance Criteria Receipt at TA-54, Area L'' to determine if it meets applicable DOE requirements. The guidelines and requirements for the establishment of a Hazardous Waste Acceptance Criteria (HW-WAC) are found in 40 CFR 260 to 270 and DOE Order 5820.2A. Neither set of requirements specifically require a WAC for the management of hazardous waste; however, the use of such documentation is logical and is consistent with the approach required for the management of radioactive waste. The primary purpose of a HW-WAC is to provide generators and waste management with established criteria that must be met before hazardous waste can be acceptable for treatment, storage and/or disposal. An annotated outline for a generic waste acceptance criteria was developed based on the requirements of 40 CFR 260 to 270 and DOE Order 5820.2A. The outline contains only requirements for hazardous waste, it does not address the radiological components of low-level mixed waste. The outline generated from the regulations was used for comparison to the LANL WAC For Chemical and Low-level Mixed Waste Receipt at TA-54, Area L. The major elements that should be addressed by a hazardous waste WAC were determined to be as follows: Waste Package/Container Requirements, Waste Forms, Land Disposal Restrictions, and Data Package-Certification ampersand Documentation

  5. Civilian Radioactive Waste Management System Requirements Document (CRP)

    International Nuclear Information System (INIS)

    C.A. Kouts

    2006-01-01

    The CRD addresses the requirements of Department of Energy (DOE) Order 413.3-Change 1, ''Program and Project Management for the Acquisition of Capital Assets'', by providing the Secretarial Acquisition Executive (Level 0) scope baseline and the Program-level (Level 1) technical baseline. The Secretarial Acquisition Executive approves the Office of Civilian Radioactive Waste Management's (OCRWM) critical decisions and changes against the Level 0 baseline; and in turn, the OCRWM Director approves all changes against the Level 1 baseline. This baseline establishes the top-level technical scope of the CRMWS and its three system elements, as described in section 1.3.2. The organizations responsible for design, development, and operation of system elements described in this document must therefore prepare subordinate project-level documents that are consistent with the CRD. Changes to requirements will be managed in accordance with established change and configuration control procedures. The CRD establishes requirements for the design, development, and operation of the CRWMS. It specifically addresses the top-level governing laws and regulations (e.g., ''Nuclear Waste Policy Act'' (NWPA), 10 Code of Federal Regulations (CFR) Part 63, 10 CFR Part 71, etc.) along with specific policy, performance requirements, interface requirements, and system architecture. The CRD shall be used as a vehicle to incorporate specific changes in technical scope or performance requirements that may have significant program implications. Such may include changes to the program mission, changes to operational capability, and high visibility stakeholder issues. The CRD uses a systems approach to: (1) identify key functions that the CRWMS must perform, (2) allocate top-level requirements derived from statutory, regulatory, and programmatic sources, and (3) define the basic elements of the system architecture and operational concept. Project-level documents address CRD requirements by further

  6. Documentation and verification required for type A packaging use

    Energy Technology Data Exchange (ETDEWEB)

    O`Brien, J.H.

    1997-07-30

    This document furnishes knowledge and methods for verifying compliance with the U.S. Department of Transportation (DOT) packaging requirements for shipping Type A quantities of radioactive material. The primary emphasis is on the requirements identified in 49 CFR 173.415(a), which states, ``Each offeror of a Specification 7A package must maintain on file for at least one year after the shipment, and shall provide to DOT on request, complete documentation of tests and an engineering evaluation of comparative data showing that the construction methods, packaging design, and materials of construction comply with that specification.`` This guidance document uses a checklist to show compliance.

  7. Documentation and verification required for type A packaging use

    International Nuclear Information System (INIS)

    O'Brien, J.H.

    1997-01-01

    This document furnishes knowledge and methods for verifying compliance with the U.S. Department of Transportation (DOT) packaging requirements for shipping Type A quantities of radioactive material. The primary emphasis is on the requirements identified in 49 CFR 173.415(a), which states, ''Each offeror of a Specification 7A package must maintain on file for at least one year after the shipment, and shall provide to DOT on request, complete documentation of tests and an engineering evaluation of comparative data showing that the construction methods, packaging design, and materials of construction comply with that specification.'' This guidance document uses a checklist to show compliance

  8. 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

  9. 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.

  10. 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.

  11. Assessment of LANL asbestos waste management documentation

    International Nuclear Information System (INIS)

    Davis, K.D.; Hoevemeyer, S.S.; Stirrup, T.S.; Jennrich, E.A.; Lund, D.M.

    1991-04-01

    The intent of this effort is to evaluate the Los Alamos National Laboratory (LANL) Waste Acceptance Criteria (WAC) for asbestos to determine if it meets applicable DOE, EPA, and OSHA requirements. There are numerous regulations that provide specific guidelines on the management of asbestos waste. An annotated outline for a generic asbestos WAC was developed using the type of information specified by 5820.2A. The outline itself is included in Appendix A. The major elements that should be addressed by the WAC were determined to be as follows: Waste Forms; Waste Content/Concentration; Waste Packaging; and Waste Documentation/Certification

  12. Functional requirements document for measuring emissions of airborne radioactive materials

    International Nuclear Information System (INIS)

    Glissmeyer, J.A.; Alvarez, J.L.; Hoover, M.D.; Newton, G.C.; McFarland, A.R.; Rodgers, J.C.

    1994-11-01

    This document states the general functional requirements for systems and procedures for measuring emissions of airborne radioactive materials from facilities administered by the Westinghouse Hanford Company (WHC). The following issues are addressed in this document: lg-bullet definition of the program objectives lg-bullet selection of the overall approach to collecting the samples lg-bullet sampling equipment design lg-bullet sampling equipment maintenance and quality assurance issues. The following issues are not addressed in this document: lg-bullet air sampling in work areas or containments lg-bullet selection of specific on-line sample monitoring instrumentation lg-bullet analyzing collected samples lg-bullet reporting and interpreting results. The document provides equipment design guidance that is performance based rather than prescriptive. Locations from which samples are obtained should exhibit mixing of the contaminants with the airstream and acceptable air flow characteristics. Sample collection equipment and effluent and sample flow elements should meet defined performance standards. Quality control and assurance requirements specific to sample collection, equipment inspection, and calibration are presented. Key sample collection performance requirements are summarized in Section 5.4. The intent of this document is to assist WHC in demonstrating a high quality of air emission measurements with verified system performance based on documented system design, testing, inspection, and maintenance

  13. 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.

  14. Detector Control System for an LHC experiment - User Requirements Document

    CERN Document Server

    CERN. Geneva

    1997-01-01

    The purpose of this document is to provide the user requirements for a detector control system kernel for the LHC experiments following the ESA standard PSS-05 [1]. The first issue will be used to provide the basis for an evaluation of possible development philosophies for a kernel DCS. As such it will cover all the major functionality but only to a level of detail sufficient for such an evaluation to be performed. Many of the requirements are therefore intentionally high level and generic, and are meant to outline the functionality that would be required of the kernel DCS, but not yet to the level of the detail required for implementation. The document is also written in a generic fashion in order not to rule out any implementation technology.

  15. 7 CFR 1488.8 - Documents required after delivery.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 10 2010-01-01 2010-01-01 false Documents required after delivery. 1488.8 Section... delivery. (a) CCC will purchase an exporter's account receivable only if the Treasurer, Commodity Credit... or Assistant Treasurer, CCC, after date of delivery of commodities exported or to be exported under...

  16. Assessment of LANL transuranic waste management documentation

    International Nuclear Information System (INIS)

    Davis, K.D.; Hoevemeyer, S.S.; McCance, C.H.; Jennrich, E.A.; Lund, D.M.

    1991-04-01

    This report presents the findings that resulted from the evaluation of the Los Alamos National Laboratory (LANL) TRU Waste Characterization Procedures, conducted to determine their compliance with applicable DOE requirements. The driving requirements for the procedures appear to be contained in DOE Order 5820.2A; specific reference is made to Chapter II of that document. In addition, the WIPP-WAC sets forth specific waste forms and establishes the basis for LANL's TRU Waste Acceptance Criteria; any characterization plan must utilize procedures that address the requirements of the WIPP-WAC in order to ensure compliance with it. The purpose of the characterization procedures is to provide details to waste generators and/or waste certifiers regarding how the characterization plan is implemented for the gathering of analytical and/or knowledge-of-process information to allow certification of the waste. An annotated outline was developed from those criteria found in Sections 4.0 and 5.0 of the WIPP-WAC. The annotated outline of elements that should be addressed in characterization procedures is provided

  17. Assessment of LANL solid low-level mixed waste documentation

    International Nuclear Information System (INIS)

    Jennrich, E.A.; Lund, D.M.; Davis, K.D.; Hoevemeyer, S.S.

    1991-04-01

    DOE Order 5820.2A requires that a system performance assessment be conducted to assure efficient and compliant management of all radioactive waste. The objective of this report is to determine the present status of the Radioactive Waste Operations Section and the Chemical Waste Operations Section capabilities regarding preparation and maintenance of appropriate criteria, plans, and procedures. Additionally, a comparison is made which identifies areas where these documents are not presently in existence or being fully implemented. The documents being assessed in this report are: Solid Low-Level Mixed Waste Acceptance Criteria, Solid Low-Level Mixed Waste Characterization Plan, Solid Low-Level Mixed waste Certification Plan, Solid Low-Level Mixed Waste Acceptance Procedures, Solid Low-Level Mixed Waste characterization Procedures, Solid Low-Level Mixed Waste Certification Procedures, Solid Low-Level Mixed Waste Training Procedures, and Solid Low-Level Mixed Waste Recordkeeping Requirements. This report compares the current status of preparation and implementation, by the Radioactive Waste Operations Section and the Chemical Waste Operations Section, of these documents to the requirements of DOE 5820.2A,. 40 CFR 260 to 270, and to recommended practice. Chapters 2 through 9 of the report presents the results of the comparison in tabular form for each of the documents being assessed, followed by narrative discussion of all areas which are perceived to be unsatisfactory or out of compliance with respect to the availability and content of the documents. The final subpart of each of the following chapters provides recommendations where documentation practices may be improved to achieve compliance or to follow the recommended practice

  18. Future CANDU nuclear power plant design requirements document executive summary

    International Nuclear Information System (INIS)

    Lee, Duk Su; Chang, Woo Hyun; Lee, Nam Young; S. A. Usmani

    1996-03-01

    The future CANDU Requirements Document (FCRED) describes a clear and complete statement of utility requirements for the next generation of CANDU nuclear power plants including those in Korea. The requirements are based on proven technology of PHWR experience and are intended to be consistent with those specified in the current international requirement documents. Furthermore, these integrated set of design requirements, incorporate utility input to the extent currently available and assure a simple, robust and more forgiving design that enhances the performance and safety. The FCRED addresses the entire plant, including the nuclear steam supply system and the balance of the plant, up to the interface with the utility grid at the distribution side of the circuit breakers which connect the switchyard to the transmission lines. Requirements for processing of low level radioactive waste at the plant site and spent fuel storage requirements are included in the FCRED. Off-site waste disposal is beyond the scope of the FCRED. 2 tabs., 1 fig. (Author) .new

  19. Fiscal year 1997-1998 waste information requirements document

    International Nuclear Information System (INIS)

    Poppiti, J.A.

    1997-01-01

    The Waste Information Requirements Document describes the activities of the Tank Waste Remediation System (TWRS) Characterization Project that provide characterization information on Hanford Site waste tanks. The characterization information is required to perform operations and meet the commitments of TWRS end users. These commitments are derived from the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement; the Recommendation 93-5 Implementation Plan to the Defense Nuclear Facilities Safety Board (DNFSB); and other directives as listed in Section 4.0. This Waste Information Requirement Document applies to Fiscal Years 1997 and 1998 activities. Its contents are based on the best information available in August 1997. The format and content are based on the directions of DOE-RL (Sieracki, 1997) and Fluor Daniel Hanford Incorporated (Umek, 1997). Activities, such as the revision of the Tank Characterization Technical Sampling Basis (Brown et al. 1997), the revision of the data quality objectives (DQOs), issue closures, discussions with Ecology, and management decisions may cause subsequent updates to the Waste Information Requirements Document

  20. Army Materiel Requirements Documents: Qualitative Analysis of Efficiency and Effectiveness

    Science.gov (United States)

    2013-06-01

    focuses on the program’s time to execute their mission based off the MRDs/MCDs. We measure efficiency based on two BPP initiatives: (1) Build...definitions of each BPP initiative during our interviews. A poor rating indicates the requirement documents did not sufficiently support the program...in terms of efficiency and effectiveness according to BPP initiatives. For efficiency, we assign a qualitative measure based on SME responses across

  1. Supplemental design requirements document solid waste operations complex

    International Nuclear Information System (INIS)

    Ocampo, V.P.; Boothe, G.F.; Broz, D.R.; Eaton, H.E.; Greager, T.M.; Huckfeldt, R.A.; Kooiker, S.L.; Lamberd, D.L.; Lang, L.L.; Myers, J.B.

    1994-11-01

    This document provides additional and supplemental information to the WHC-SD-W112-FDC-001, WHC-SD-W113-FDC-001, and WHC-SD-W100-FDC-001. It provides additional requirements for the design and summarizes Westinghouse Hanford Company key design guidance and establishes the technical baseline agreements to be used for definitive design common to the Solid Waste Operations Complex (SWOC) Facilities (Project W-112, Project W-113, and WRAP 2A)

  2. Design requirements document for Project W-465, immobilized low-activity waste interim storage

    International Nuclear Information System (INIS)

    Burbank, D.A.

    1998-01-01

    The scope of this Design Requirements Document (DRD) is to identify the functions and associated requirements that must be performed to accept, transport, handle, and store immobilized low-activity waste (ILAW) produced by the privatized Tank Waste Remediation System (TWRS) treatment contractors. The functional and performance requirements in this document provide the basis for the conceptual design of the TWRS ILAW Interim Storage facility project and provides traceability from the program level requirements to the project design activity. Technical and programmatic risk associated with the TWRS planning basis are discussed in the Tank Waste Remediation System Decisions and Risk Assessment (Johnson 1994). The design requirements provided in this document will be augmented by additional detailed design data documented by the project

  3. Environmental restoration remedial action quality assurance requirements document

    International Nuclear Information System (INIS)

    Cote, R.F.

    1991-01-01

    The environmental Restoration Remedial Action Quality Assurance Requirements Document (DOE/RL 90-28) defines the quality assurance program requirements for the US Department of Energy-Richland Field Office Environmental Restoration Remedial Action Program at the Hanford Site, Richland, Washington. This paper describes the objectives outlined in DOE/RL 90-28. 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

  4. Assessment model validity document FARF31

    International Nuclear Information System (INIS)

    Elert, Mark; Gylling Bjoern; Lindgren, Maria

    2004-08-01

    -fractures with flowing water and rock with porosity accessible only by diffusion. The approach furthermore assumes that the properties within the two porosity domains are averaged and also the transfer between the two domains is averaged.It is an important validation issue to verify that effective averaging of parameters can be performed and that suitable values can be derived. It can be shown that matrix interaction properties along a flow path can be integrated to an effective value and if the matrix depth can be considered as infinite, effective values may be derived also for the diffusion and sorption parameters. Thus, it is possible to derive effective parameters for sorbing radionuclides incorporating the total matrix effects along a flow path. This is strictly valid only for cases with no dispersion, but gives a good approximation as long as dispersion does not dominate the transport. FARF31 has been tested and compared with analytical solutions and other models and was found to correspond well within a wide range of input parameters. Support and documentation on how to use FARF31 are two important components to avoid calculation mistakes and obtain trustworthy results. The documentation describes handling and updates of the code. Test cases have been constructed which can be used to check updates and be used as templates. The development of the code is kept under source code control to fulfil quality assurance. The model is deemed to be well suited for performance assessments within the SKB framework

  5. Preliminary Design Requirements Document for Project W-314

    Energy Technology Data Exchange (ETDEWEB)

    MCGREW, D.L.

    2000-04-27

    This document sets forth functional requirements, performance requirements, and design constraints for the tank farm systems elements identified in Section 3.1 of this document. These requirements shall be used to develop the Design Requirements Baseline for those system elements. System Overview--The tank farm system at Hanford Site currently consists of 149 single shell tanks and 28 double shell tanks with associated facilities and equipment, located in 18 separate groupings. Each grouping is known as a tank farm. They are located in the areas designated as 200 West and 200 East. Table 1-1 shows the number of tanks in each farm. The farms are connected together through a transfer system consisting of piping, diversion boxes, Double Contained Receiver Tanks (DCRT) and other miscellaneous facilities and elements. The tank farm system also connects to a series of processing plants which generate radioactive and hazardous wastes. The primary functions of the tank farm system are to store, transfer, concentrate, and characterize radioactive and hazardous waste generated at Hanford, until the waste can be safely retrieved, processed and dispositioned. The systems provided by Project W-314 support the store and transfer waste functions. The system elements to be upgraded by Project W-314 are identified in Section 3.1.

  6. Preliminary Design Requirements Document for Project W-314

    International Nuclear Information System (INIS)

    MCGREW, D.L.

    2000-01-01

    This document sets forth functional requirements, performance requirements, and design constraints for the tank farm systems elements identified in Section 3.1 of this document. These requirements shall be used to develop the Design Requirements Baseline for those system elements. System Overview--The tank farm system at Hanford Site currently consists of 149 single shell tanks and 28 double shell tanks with associated facilities and equipment, located in 18 separate groupings. Each grouping is known as a tank farm. They are located in the areas designated as 200 West and 200 East. Table 1-1 shows the number of tanks in each farm. The farms are connected together through a transfer system consisting of piping, diversion boxes, Double Contained Receiver Tanks (DCRT) and other miscellaneous facilities and elements. The tank farm system also connects to a series of processing plants which generate radioactive and hazardous wastes. The primary functions of the tank farm system are to store, transfer, concentrate, and characterize radioactive and hazardous waste generated at Hanford, until the waste can be safely retrieved, processed and dispositioned. The systems provided by Project W-314 support the store and transfer waste functions. The system elements to be upgraded by Project W-314 are identified in Section 3.1

  7. Assessment of LANL solid low-level waste management documentation

    International Nuclear Information System (INIS)

    Klein, R.B.; Jennrich, E.A.; Lund, D.M.; Danna, J.G.; Davis, K.D.; Rutz, A.C.

    1991-04-01

    DOE Order 5820.2A requires that a system performance assessment be conducted to assure efficient and compliant management of all radioactive waste. The objective of this report is to determine the present status of the Radioactive Waste Operations Section's capabilities regarding preparation and maintenance of appropriate criteria, plans and procedures and identify particular areas where these documents are not presently in existence or being fully implemented. DOE Order 5820.2A, Radioactive Waste Management, Chapter III sets forth the requirements and guidelines for preparation and implementation of criteria, plans and procedures to be utilized in the management of solid low-level waste. The documents being assessed in this report are: Solid Low-Level Waste Acceptance Criteria, Solid Low-Level Waste Characterization Plan, Solid Low-Level Waste Certification Plan, Solid Low-Level Waste Acceptance Procedures, Solid Low-Level Waste Characterization Procedures, Solid Low-Level Waste Certification Procedures, Solid Low-Level Waste Training Procedures, and Solid Low-Level Waste Recordkeeping Procedures. Suggested outlines for these documents are presented as Appendix A

  8. 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

  9. Process of technical document quality assessment | Djebabra ...

    African Journals Online (AJOL)

    The most used instrument in training and scientific research is obviously the book which occupies since always a place of choice. Indeed, the book and more particularly the technical book are is used as a support, as well in the basic training as in the document is of good quality in order to have confidence in the services ...

  10. Vocational Assessment. Policy Paper Series: Document 6.

    Science.gov (United States)

    Stodden, Robert A., Ed.

    This collection of four policy papers on vocational assessment for the handicapped deals with personnel development, interagency coordination, current research and development, and providing individualized assessment services. Discussed in the initial paper on program improvement in vocational assessment for the handicapped are federal legislation…

  11. Requirements Document for Development of a Livermore Tomography Tools Interface

    Energy Technology Data Exchange (ETDEWEB)

    Seetho, I. M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2017-02-09

    In this document, we outline an exercise performed at LLNL to evaluate the user interface deficits of a LLNL-developed CT reconstruction software package, Livermore Tomography Tools (LTT). We observe that a difficult-to-use command line interface and the lack of support functions compound to generate a bottleneck in the CT reconstruction process when input parameters to key functions are not well known. Through the exercise of systems engineering best practices, we generate key performance parameters for a LTT interface refresh, and specify a combination of back-end (“test-mode” functions) and front-end (graphical user interface visualization and command scripting tools) solutions to LTT’s poor user interface that aim to mitigate issues and lower costs associated with CT reconstruction using LTT. Key functional and non-functional requirements and risk mitigation strategies for the solution are outlined and discussed.

  12. Assessment of LANL PCB waste management documentation

    International Nuclear Information System (INIS)

    David, K.D.; Hoevemeyer, S.S.; Stirrup, T.S.; Jennrich, E.A.; Lund, D.M.

    1991-04-01

    The objective of this report is to present findings from evaluating the Los Alamos National Laboratory (LANL) Polychlorinated Biphenyls (PCB) Waste Acceptance Criteria (WAC) to determine if it meets applicable DOE and Code of Federal Regulation (CFR) requirements. DOE Order 5820.2A and 40 CFR 761 (Polychlorinated Biphenyls Manufacturing, Processing, Distribution in Commerce, and Use Prohibitions) set forth requirements and guidelines for the establishment of Waste Acceptance Criteria. The primary purpose of a PCB WAC is to provide generators and waste management with established criteria that must be met before PCB wastes can be accepted for treatment, storage, and/or disposal. An annotated outline for a generic PCB WAC was developed based on the requirements of 5820.2A and 40 CFR 761. The major elements that should be addressed by a PCB WAC were determined to be as follows: Waste Package/Container, Waste Forms, PCB Concentrations, Labeling, and Data Package Certification

  13. Advanced Manufacturing Processes Laboratory Building 878 hazards assessment document

    International Nuclear Information System (INIS)

    Wood, C.; Thornton, W.; Swihart, A.; Gilman, T.

    1994-07-01

    The introduction of the hazards assessment process is to document the impact of the release of hazards at the Advanced Manufacturing Processes Laboratory (AMPL) that are significant enough to warrant consideration in Sandia National Laboratories' operational emergency management program. This hazards assessment is prepared in accordance with the Department of Energy Order 5500.3A requirement that facility-specific hazards assessments be prepared, maintained, and used for emergency planning purposes. This hazards assessment provides an analysis of the potential airborne release of chemicals associated with the operations and processes at the AMPL. This research and development laboratory develops advanced manufacturing technologies, practices, and unique equipment and provides the fabrication of prototype hardware to meet the needs of Sandia National Laboratories, Albuquerque, New Mexico (SNL/NM). The focus of the hazards assessment is the airborne release of materials because this requires the most rapid, coordinated emergency response on the part of the AMPL, SNL/NM, collocated facilities, and surrounding jurisdiction to protect workers, the public, and the environment

  14. Advanced Manufacturing Processes Laboratory Building 878 hazards assessment document

    Energy Technology Data Exchange (ETDEWEB)

    Wood, C.; Thornton, W.; Swihart, A.; Gilman, T.

    1994-07-01

    The introduction of the hazards assessment process is to document the impact of the release of hazards at the Advanced Manufacturing Processes Laboratory (AMPL) that are significant enough to warrant consideration in Sandia National Laboratories` operational emergency management program. This hazards assessment is prepared in accordance with the Department of Energy Order 5500.3A requirement that facility-specific hazards assessments be prepared, maintained, and used for emergency planning purposes. This hazards assessment provides an analysis of the potential airborne release of chemicals associated with the operations and processes at the AMPL. This research and development laboratory develops advanced manufacturing technologies, practices, and unique equipment and provides the fabrication of prototype hardware to meet the needs of Sandia National Laboratories, Albuquerque, New Mexico (SNL/NM). The focus of the hazards assessment is the airborne release of materials because this requires the most rapid, coordinated emergency response on the part of the AMPL, SNL/NM, collocated facilities, and surrounding jurisdiction to protect workers, the public, and the environment.

  15. Towards web documents quality assessment for digital humanities scholars

    NARCIS (Netherlands)

    Ceolin, D.; Noordegraaf, Julia; Aroyo, L.M.; van Son, C.M.; Nejdl, Wolfgang; Hall, Wendy; Parigi, Paolo; Staab, Steffen

    2016-01-01

    We present a framework for assessing the quality of Web documents, and a baseline of three quality dimensions: trustworthiness, objectivity and basic scholarly quality. Assessing Web document quality is a "deep data" problem necessitating approaches to handle both data size and complexity.

  16. Sandia Administrative Micrographics Facility, Building 802: Hazards assessment document

    International Nuclear Information System (INIS)

    Swihart, A.

    1994-12-01

    The Department of Energy Order 5500.3A requires facility-specific hazards assessments be prepared, maintained, and used for emergency planning purposes. This hazards assessment document describes the chemical and radiological hazards associated with the Sandia Administrative Micrographics Facility, Building 802. The entire inventory was screened according to the potential airborne impact to onsite and offsite individuals. The air dispersion model, ALOHA, estimated pollutant concentrations downwind from the source of a release, taking into consideration the toxicological and physical characteristics of the release site, the atmospheric conditions, and the circumstances of the release. The greatest distance at which a postulated facility event will produce consequences exceeding the Early Severe Health Effects threshold is 33 meters. The highest emergency classification is a Site Area Emergency. The Emergency Planning Zone is 75 meters

  17. Simulation Technology Laboratory Building 970 hazards assessment document

    International Nuclear Information System (INIS)

    Wood, C.L.; Starr, M.D.

    1994-11-01

    The Department of Energy Order 5500.3A requires facility-specific hazards assessments be prepared, maintained, and used for emergency planning purposes. This hazards assessment document describes the chemical and radiological hazards associated with the Simulation Technology Laboratory, Building 970. The entire inventory was screened according to the potential airborne impact to onsite and offsite individuals. The air dispersion model, ALOHA, estimated pollutant concentrations downwind from the source of a release, taking into consideration the toxicological and physical characteristics of the release site, the atmospheric conditions, and the circumstances of the release. The greatest distances at which a postulated facility event will produce consequences exceeding the ERPG-2 and Early Severe Health Effects thresholds are 78 and 46 meters, respectively. The highest emergency classification is a Site Area Emergency. The Emergency Planning Zone is 100 meters

  18. Glass Formulation and Fabrication Laboratory, Building 864, Hazards assessment document

    Energy Technology Data Exchange (ETDEWEB)

    Banda, Z.; Wood, C.L.

    1995-08-01

    The Department of Energy Order 5500.3A requires facility-specific hazards assessments be prepared, maintained, and used for emergency planning purposes. This hazards assessment document describes the chemical and radiological hazards associated with the Glass Formulation and Fabrication Laboratory, Building 864. The entire inventory was screened according to the potential airborne impact to onsite and offsite individuals. The air dispersion model, ALOHA, estimated pollutant concentrations downwind from the source of a release, taking into consideration the toxicological and physical characteristics of the release site, the atmospheric conditions, and the circumstances of the release. The greatest distances at which a postulated facility event will produce consequences exceeding the ERPG-2 threshold is 96 meters. The highest emergency classification is a Site Area Emergency. The Emergency Planning Zone is 100 meters.

  19. Standards/requirements identification documents (S/RIDS)

    International Nuclear Information System (INIS)

    Beckman, W.H.; Alhadeff, N.

    1994-01-01

    This paper describes the Fernald Environmental Restoration Management Corporation's (FERMCO) Standards/Requirement Identification Documents (S/RIDs) Development Program, the unique process used to implement it, and the status of the program. We will also discuss the lessons learned as the development program was implemented. The Department of Energy (DOE) established the Fernald site to produce uranium metals for the nation's defense programs in 1953. In 1989, DOE suspended production and, in 1991, the mission of the site was formally changed to one of environmental cleanup and restoration. The site was renamed the Fernald Environmental Management Project (FEMP) to reflect this change. From its inception until November 1992, the site was managed under a Management and Operating contract. As a result in the change in mission, DOE awarded an Environmental Restoration Management Contract (ERMC), focusing on restoration. FERMCO assumed management of the site December 1, 1992. The joint DOE/FERMCO mission is to protect human health and the environment through the safe, early, and least-cost final clean-up of the site in compliance with all applicable regulations and commitments while addressing stakeholder concerns. DOE has managed nuclear facilities primarily through its oversight of Management and Operating contractors. These contractors were responsible for formulating, selecting, and administering standards controlling design, construction, operations, and maintenance. The DOE Operations Office Manager was responsible for approving individual contractor practices and the governing site standards and requirements to be met. Due to the absence of comprehensive nuclear industry standards when most DOE sites were first established, Management and Operating contractors had to apply existing non-nuclear industry standards and, in many cases, formulate new technical standards to address unique applications

  20. 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

  1. 22 CFR 203.7 - IPVO initial documentation requirements.

    Science.gov (United States)

    2010-04-01

    ... structure; (4) Statement of tax exemption or a comparable document from the country of its origin; (5... IPVO's country of domicile by an independent certified public accountant (CPA) and in U.S. dollars; (6...

  2. Documentation of torture victims, assessment of the start procedure for medico-legal documentation.

    Science.gov (United States)

    Mandel, Lene; Worm, Lise

    2007-01-01

    A Pilot Study was performed at the Rehabilitation and Research Centre for Torture Victims (RCT) in Copenhagen in order to explore the possibilities for adding a medico-legal documentation component to the rehabilitation of torture victims already taking place. It describes the process and results on implementing medico-legal documentation in a rehabilitative setting. A modified version of the Guidelines in the Istanbul Protocol was developed on the basis of the review of literature and current practices described in "Documentation of torture victims, implementation of medico-legal protocols". The modified guidelines were tested on five clients. The aim was twofold: 1) To assess the client's attitude towards the idea of adding a documentation component to the rehabilitation process and: 2) To assess the practical circumstances of implementing the Istanbul Protocol in the everyday life of a rehabilitation centre. Results show that all five clients were positive towards the project and found comfort in being able to contribute to the fight against impunity. Also, the Pilot Study demonstrated that a large part of the medico-legal documentation was already obtained in the rehabilitation process. It was however not accessible due to lack of systematization and a data registering system. There are thus important synergies in collecting data for rehabilitation and documentation but a joint database system is necessary to realize these synergies.

  3. Laboratory Biosafety and Biosecurity Risk Assessment Technical Guidance Document

    Energy Technology Data Exchange (ETDEWEB)

    Astuto-Gribble, Lisa M; Caskey, Susan Adele

    2014-07-01

    The purpose of this document is threefold: 1) to describe the laboratory bio safety and biosecurity risk assessment process and its conceptual framework; 2) provide detailed guidance and suggested methodologies on how to conduct a risk assessment; and 3) present some practical risk assessment process strategies using realistic laboratory scenarios.

  4. Wind turbine environmental assessment -- Vol 1: Screening document

    International Nuclear Information System (INIS)

    2000-04-01

    The environmental effects of the proposed construction and operation of up to three wind turbines on the Toronto waterfront are evaluated in accordance with the requirements of the Canadian Environmental Assessment Act (CEAA) and Regulations. The nine sections of the report provide background on the environmental assessment and the wind turbine project; provide justification for the project and describes alternative sites and wind turbine technologies; outlines the scope of the project; sketches the biophysical and socio-economic environment; presents an evaluation of the environmental impacts and proposed mitigating measures; describes the public consultation program that was carried out; summarizes the comments received from interested parties; presents the conclusion of the environmental impact assessment; and responds to the public comments received on the draft screening document. Most of the concerns raised involved avoidance reactions by birds, disruption or fragmentation of wildlife, the potential for high kill rate of small nocturnal migrants and young birds, and the effect of noise on breeding birds. The overall recommendation of the consultants is that the project is not likely to cause significant adverse environmental effects and its construction and operations should be authorized. 115 refs., 8 tabs., 2 figs. (14 appendices are in volume 2)

  5. Understanding the technical content of requirements in specification document

    DEFF Research Database (Denmark)

    Sudin, Mohd Nizam Bin; Ahmed-Kristensen, Saeema

    2011-01-01

    development process, is essential to be devised in advance. To achieve this aim, understanding how to formulate a good requirement is necessary and it is only possible if design engineers understand the technical content of a requirement. In aiming to understand the technical content of a requirement...

  6. Exploration on Automated Software Requirement Document Readability Approaches

    OpenAIRE

    Chen, Mingda; He, Yao

    2017-01-01

    Context. The requirements analysis phase, as the very beginning of software development process, has been identified as a quite important phase in the software development lifecycle. Software Requirement Specification (SRS) is the output of requirements analysis phase, whose quality factors play an important role in the evaluation work. Readability is a quite important SRS quality factor, but there are few available automated approaches for readability measurement, because of the tight depend...

  7. CH2M Hill Hanford Group, Inc., Standards and Requirements Identification Document (SRID) Requirements Management System and Requirements Specification

    International Nuclear Information System (INIS)

    JOHNSON, A.L.

    2000-01-01

    The current Tank Farm Contractor (TFC) for the U. S. Department of Energy, Office of River Protection (ORP), River Protection Project (RPP), CH2M Hill Hanford Group, Inc. (CHG), will use a computer based requirements management system. The system will serve as a tool to assist in identifying, capturing, and maintaining the Standards/Requirements Identification Document (S/RID) requirements and links to implementing procedures and other documents. By managing requirements as one integrated set, CHG will be able to carry out its mission more efficiently and effectively. CHG has chosen the Dynamic Object Oriented Requirements System (DOORS(trademark)) as the preferred computer based requirements management system. Accordingly, the S/RID program will use DOORS(trademark). DOORS(trademark) will replace the Environmental Requirements Management Interface (ERMI) system as the tool for S/RID data management. The DOORS(trademark) S/RID test project currently resides on the DOORSTM test server. The S/RID project will be migrated to the DOORS(trademark) production server. After the migration the S/RID project will be considered a production project and will no longer reside on the test server

  8. Hanford analytical services quality assurance requirements documents. Volume 1: Administrative Requirements

    International Nuclear Information System (INIS)

    Hyatt, J.E.

    1997-01-01

    Hanford Analytical Services Quality Assurance Requirements Document (HASQARD) is issued by the Analytical Services, Program of the Waste Management Division, US Department of Energy (US DOE), Richland Operations Office (DOE-RL). The HASQARD establishes quality requirements in response to DOE Order 5700.6C (DOE 1991b). The HASQARD is designed to meet the needs of DOE-RL for maintaining a consistent level of quality for sampling and field and laboratory analytical services provided by contractor and commercial field and laboratory analytical operations. The HASQARD serves as the quality basis for all sampling and field/laboratory analytical services provided to DOE-RL through the Analytical Services Program of the Waste Management Division in support of Hanford Site environmental cleanup efforts. This includes work performed by contractor and commercial laboratories and covers radiological and nonradiological analyses. The HASQARD applies to field sampling, field analysis, and research and development activities that support work conducted under the Hanford Federal Facility Agreement and Consent Order Tri-Party Agreement and regulatory permit applications and applicable permit requirements described in subsections of this volume. The HASQARD applies to work done to support process chemistry analysis (e.g., ongoing site waste treatment and characterization operations) and research and development projects related to Hanford Site environmental cleanup activities. This ensures a uniform quality umbrella to analytical site activities predicated on the concepts contained in the HASQARD. Using HASQARD will ensure data of known quality and technical defensibility of the methods used to obtain that data. The HASQARD is made up of four volumes: Volume 1, Administrative Requirements; Volume 2, Sampling Technical Requirements; Volume 3, Field Analytical Technical Requirements; and Volume 4, Laboratory Technical Requirements. Volume 1 describes the administrative requirements

  9. Probabilistic risk assessment (PRA) reference document. Final report

    International Nuclear Information System (INIS)

    Murphy, J.A.

    1984-09-01

    This document describes the current status of probabilistic risk assessment (PRA) as practiced in the nuclear reactor regulatory process. The PRA studies that have been completed or are under way are reviewed. The levels of maturity of the methodologies used in a PRA are discussed. Insights derived from PRAs are listed. The potential uses of PRA results for regulatory purposes are discussed. This document was issued for comment in February 1984 entitled Probabilistic Risk Assessment (PRA): Status Report and Guidance for Regulatory Application. The comments received on the draft have been considered for this final version of the report

  10. Guidelines on preparation of documentation required in PET radiopharmaceutical manufacturing

    International Nuclear Information System (INIS)

    2001-01-01

    This article made by the Nuclear Pharmacy Working Group, subcommittee on Medical Application of Cyclotron-Produced Radionuclides, Medical Science and Pharmaceutical Committee, Japan Radioisotope Association, described the actual examples of Standards, Standard Operating Procedure, Documents and so on for the purpose of operation along the Standards of Compounds Labeled with Positron Nuclides Approved as Established Techniques for Medical Use (2001 Revision). Examples were the organization for manufacturing and management, standard format of the product (for [ 18 F]2-deoxy-2-fluoro-D-glucose), standard for process control of manufacture, standard for control of manufacturing and hygiene, standard for quality, and standard operating procedures for entering and leaving the manufacturing facility, for the clean-bench and for the test of floating micro-particles. The second item involved the definition of the cyclotron target ( 18 O), generation of 18 F by the reaction (p, n), purification of the product, and prescription: the third item; storage of the product and manufacturing process control: and the fourth; education and training of personnel, and health management. (K.H.)

  11. 50 CFR 23.19 - What CITES documents are required to export Appendix-I plants?

    Science.gov (United States)

    2010-10-01

    ... 50 Wildlife and Fisheries 6 2010-10-01 2010-10-01 false What CITES documents are required to... ENDANGERED SPECIES OF WILD FAUNA AND FLORA (CITES) Prohibitions, Exemptions, and Requirements § 23.19 What CITES documents are required to export Appendix-I plants? Answer the questions in the following decision...

  12. EUR, an European utility requirements documents for future LWR power stations

    International Nuclear Information System (INIS)

    Berbey, Pierre; Lienard, Michel; Redon, Ramon; Essmann, Juergen; Taylor, David T.

    2004-01-01

    A group of the major European utilities are developing a common requirement document which will be used for the LWR nuclear power plants to be built in Europe from the beginning of the next century. This document provides harmonised policies and technical requirements that will allow the implementation of a design developed in one country into another one. The objectives and contents of the document, the organisation set up for its production and the main requirements are summarised in the paper. (author)

  13. Pedagogical Voyeurism: Dialogic Critique of Documentation and Assessment of Learning

    Science.gov (United States)

    Matusov, Eugene; Marjanovic-Shane, Ana; Meacham, Sohyun

    2016-01-01

    We challenge a common emphasis on documentation and assessment of learning for providing good education: from the mainstream of neoliberal accountability movement to the progressive Reggio Emilia schools. We develop these arguments through discussing: 1) immeasurableness of education and learning, 2) students' ownership/authorship of education and…

  14. A fully updated version of the European utility requirement (EUR) documents is to be available

    International Nuclear Information System (INIS)

    Chatry, J.P.; Berbey, P.

    2001-01-01

    The major European electricity producers have worked on a common requirement document for future LWR plants since 1992 to get specifications acceptable together by the owners, the public and the authorities. Thus the designers can develop standard LWR designs that could be acceptable everywhere in Europe and the utilities can open their consultations to vendors on common bases. Public and authority's acceptance should be improved as well. Significant savings are expected in development and construction costs. Since the release of the last versions of the EUR texts in 1996, a lot of work has been carried out: reviews by the regulators and other external organisations, comparisons, assessment of compliance of designs vs. EUR and clarification works on the controversial topics that deserved changes or clarification. At the beginning of 1999 enough material was available to start a complete revision of the EUR document. Volumes 1 and 2 of the EUR document list generic nuclear island requirements. The main NPP vendors are developing advanced LWR designs for the European market, with reference to the EUR document. Volume 3 deals with the application of EUR to those designs. The EUR utilities -with contributions of the vendors- are writing specific parts of the EUR document that address some of these designs. Each part includes a plant description and an assessment of its level of compliance with EUR. The first three parts deal with EPR (1500 MW PWR developed by NPI, Framatome and Siemens), EPP (1000 MW PWR with passive safety features developed by Westinghouse and Ansaldo) and BWR 90 (1300 MW BWR developed by ABB Atom). Two other subsets are: one for ABWR (1300 MW BWR developed by GE), the other one for SWR 1000 (1000 MW BWR with passive safety features developed by Siemens). This large and diverse set of designs actually gives the EUR document a very strong base. Revision B of Volume 4 incorporates responses to the comments collected on revision A. Considering all that

  15. 17 CFR 4.31 - Required delivery of Disclosure Document to prospective clients.

    Science.gov (United States)

    2010-04-01

    ... Disclosure Document to prospective clients. 4.31 Section 4.31 Commodity and Securities Exchanges COMMODITY... Advisors § 4.31 Required delivery of Disclosure Document to prospective clients. (a) Each commodity trading... prospective client a Disclosure Document containing the information set forth in §§ 4.34 and 4.35 for the...

  16. Functions and requirements document for interim store solidified high-level and transuranic waste

    Energy Technology Data Exchange (ETDEWEB)

    Smith-Fewell, M.A., Westinghouse Hanford

    1996-05-17

    The functions, requirements, interfaces, and architectures contained within the Functions and Requirements (F{ampersand}R) Document are based on the information currently contained within the TWRS Functions and Requirements database. The database also documents the set of technically defensible functions and requirements associated with the solidified waste interim storage mission.The F{ampersand}R Document provides a snapshot in time of the technical baseline for the project. The F{ampersand}R document is the product of functional analysis, requirements allocation and architectural structure definition. The technical baseline described in this document is traceable to the TWRS function 4.2.4.1, Interim Store Solidified Waste, and its related requirements, architecture, and interfaces.

  17. Analysis of the Extent of Completion of Skin Assessments and Documentation of Risk for Skin Breakdown in the Trauma Patient Who Experiences Hypovolemic Shock Requiring Massive Transfusion Resuscitation and Surgical Intervention

    Science.gov (United States)

    1991-01-01

    were circled on the data collection tool. If no documentation existed to evaluate this cue the answer no comment was circled. 28 Moisture. The cue of...was dry and intact. If no documentation existed to evaluate this cue according to these words, the answer no comment was circled. Activity. Activity...which to select included bedrest, up in chair, ambulate with assistance, up ad lib, or no comment . Mobility. Mobility was determined by the patient’s

  18. Assessing Requirements Quality through Requirements Coverage

    Science.gov (United States)

    Rajan, Ajitha; Heimdahl, Mats; Woodham, Kurt

    2008-01-01

    In model-based development, the development effort is centered around a formal description of the proposed software system the model. This model is derived from some high-level requirements describing the expected behavior of the software. For validation and verification purposes, this model can then be subjected to various types of analysis, for example, completeness and consistency analysis [6], model checking [3], theorem proving [1], and test-case generation [4, 7]. This development paradigm is making rapid inroads in certain industries, e.g., automotive, avionics, space applications, and medical technology. This shift towards model-based development naturally leads to changes in the verification and validation (V&V) process. The model validation problem determining that the model accurately captures the customer's high-level requirements has received little attention and the sufficiency of the validation activities has been largely determined through ad-hoc methods. Since the model serves as the central artifact, its correctness with respect to the users needs is absolutely crucial. In our investigation, we attempt to answer the following two questions with respect to validation (1) Are the requirements sufficiently defined for the system? and (2) How well does the model implement the behaviors specified by the requirements? The second question can be addressed using formal verification. Nevertheless, the size and complexity of many industrial systems make formal verification infeasible even if we have a formal model and formalized requirements. Thus, presently, there is no objective way of answering these two questions. To this end, we propose an approach based on testing that, when given a set of formal requirements, explores the relationship between requirements-based structural test-adequacy coverage and model-based structural test-adequacy coverage. The proposed technique uses requirements coverage metrics defined in [9] on formal high-level software

  19. Bioburden assessment and gamma radiation inactivation patterns in parchment documents

    International Nuclear Information System (INIS)

    Nunes, Inês; Mesquita, Nuno; Cabo Verde, Sandra; Carolino, Maria Manuela; Portugal, António; Botelho, Maria Luísa

    2013-01-01

    Parchment documents are part of our cultural heritage and, as historical artifacts that they are, should be preserved. The aim of this study was to validate an appropriate methodology to characterize the bioburden of parchment documents, and to assess the growth and gamma radiation inactivation patterns of the microbiota present in that material. Another goal was to estimate the minimum gamma radiation dose (D min ) to be applied for the decontamination of parchment as an alternative treatment to the current toxic chemical and non-chemical decontamination methods. Two bioburden assessment methodologies were evaluated: the Swab Method (SM) and the Destructive Method (DM). The recovery efficiency of each method was estimated by artificial contamination, using a Cladosporium cladosporioides spore suspension. The parchment samples' microbiota was typified using morphological methods and the fungal isolates were identified by ITS-DNA sequencing. The inactivation pattern was assessed using the DM after exposure to different gamma radiation doses, and using C. cladosporioides as reference. Based on the applied methodology, parchment samples presented bioburden values lower than 5×10 3 CFU/cm 2 for total microbiota, and lower than 10 CFU/cm 2 for fungal propagules. The results suggest no evident inactivation trend for the natural parchment microbiota, especially regarding the fungal community. A minimum gamma radiation dose (D min ) of 5 kGy is proposed for the decontamination treatment of parchment. Determining the minimal decontamination dose in parchment is essential for a correct application of gamma radiation as an alternative decontamination treatment for this type of documents avoiding the toxicity and the degradation promoted by the traditional chemical and non-chemical treatments. - Highlights: • Characterization of the microbial population of parchment documents. • Study the inactivation pattern of parchment microbiota by gamma radiation. • Assessment of

  20. 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

  1. Daily Encounter Cards—Evaluating the Quality of Documented Assessments

    Science.gov (United States)

    Cheung, Warren J.; Dudek, Nancy; Wood, Timothy J.; Frank, Jason R.

    2016-01-01

    ABSTRACT Background  Concerns over the quality of work-based assessment (WBA) completion has resulted in faculty development and rater training initiatives. Daily encounter cards (DECs) are a common form of WBA used in ambulatory care and shift work settings. A tool is needed to evaluate initiatives aimed at improving the quality of completion of this widely used form of WBA. Objective  The completed clinical evaluation report rating (CCERR) was designed to provide a measure of the quality of documented assessments on in-training evaluation reports. The purpose of this study was to provide validity evidence to support using the CCERR to assess the quality of DEC completion. Methods  Six experts in resident assessment grouped 60 DECs into 3 quality categories (high, average, and poor) based on how informative each DEC was for reporting judgments of the resident's performance. Eight supervisors (blinded to the expert groupings) scored the 10 most representative DECs in each group using the CCERR. Mean scores were compared to determine if the CCERR could discriminate based on DEC quality. Results  Statistically significant differences in CCERR scores were observed between all quality groups (P < .001). A generalizability analysis demonstrated the majority of score variation was due to differences in DECs. The reliability with a single rater was 0.95. Conclusions  The CCERR is a reliable and valid tool to evaluate DEC quality. It can serve as an outcome measure for studying interventions targeted at improving the quality of assessments documented on DECs. PMID:27777675

  2. Daily Encounter Cards-Evaluating the Quality of Documented Assessments.

    Science.gov (United States)

    Cheung, Warren J; Dudek, Nancy; Wood, Timothy J; Frank, Jason R

    2016-10-01

    Concerns over the quality of work-based assessment (WBA) completion has resulted in faculty development and rater training initiatives. Daily encounter cards (DECs) are a common form of WBA used in ambulatory care and shift work settings. A tool is needed to evaluate initiatives aimed at improving the quality of completion of this widely used form of WBA. The completed clinical evaluation report rating (CCERR) was designed to provide a measure of the quality of documented assessments on in-training evaluation reports. The purpose of this study was to provide validity evidence to support using the CCERR to assess the quality of DEC completion. Six experts in resident assessment grouped 60 DECs into 3 quality categories (high, average, and poor) based on how informative each DEC was for reporting judgments of the resident's performance. Eight supervisors (blinded to the expert groupings) scored the 10 most representative DECs in each group using the CCERR. Mean scores were compared to determine if the CCERR could discriminate based on DEC quality. Statistically significant differences in CCERR scores were observed between all quality groups ( P  evaluate DEC quality. It can serve as an outcome measure for studying interventions targeted at improving the quality of assessments documented on DECs.

  3. Preliminary design requirements document (DRD) for Project W-236B, ''Initial Pretreatment Module''

    International Nuclear Information System (INIS)

    Swanson, L.M.

    1995-01-01

    The scope of this Design Requirements Document (DRD) is to identify and define the functions, with associated requirements, which must be performed to separate Hanford Site tank waste supernatants into low-level and high-level fractions. This documents sets forth function requirements, performance requirements, and design constraints necessary to begin conceptual design for the Initial Pretreatment Module (IPM). System and physical interfaces between the IPM project and the Tank Waste Remediation System (TWRS) are identified. The constraints, performance requirements, and transfer of information and data across a technical interface will be documented in an Interface Control Document. Supplemental DRDs will be prepared to provide more detailed requirements specific to systems described in the DRD

  4. A fully updated version of the european utility requirement (EUR) document is available

    International Nuclear Information System (INIS)

    Berbey, P.

    2001-01-01

    The major European electricity producers have worked on a common requirement document for future LWR plants since 1992 to get specifications acceptable together by the owners, the public and the authorities. Thus the designers can develop standard LWR designs that could be acceptable everywhere in Europe and the utilities can open their consultations to vendors on common bases. Public and authority's acceptance should be improved as well. Significant savings are expected in development and construction costs. Since the release of the last versions of the EUR texts in 1996, a lot of work has been carried out: reviews by the regulators and other external organisations, comparisons, assessment of compliance of designs vs. EUR and clarification works on the controversial topics that deserved changes or clarification. At the beginning of 1999 enough material was available to start a complete revision of the EUR document. In-depth works have been carried out during the last couple of year to develop this revision. The European utilities and the vendors have now an updated and well-tuned tool that allow them to develop, to assess and eventually to order modern LWR designs well fitted to their actual needs. (author)

  5. Wildlife resource trends in the United States: A technical document supporting the 2000 RPA Assessment

    Science.gov (United States)

    Curtis H. Flather; Stephen J. Brady; Michael S. Knowles

    1999-01-01

    This report documents trends in wildlife resources for the nation as required by the Renewable Resources Planning Act (RPA) of 1974. The report focuses on recent historical trends in wildlife as one indicator of ecosystem health across the United States and updates wildlife trends presented in previous RPA Assessments. The report also shows short- and long-term...

  6. Requirements for the data transfer during the examination of design documentation

    Directory of Open Access Journals (Sweden)

    Karakozova Irina

    2017-01-01

    Full Text Available When you transfer the design documents to the examination office, number of incompatible electronic documents increases dramatically. The article discusses the way to solve the problem of transferring of the text and graphic data of design documentation for state and non-state expertise, as well as verification of estimates and requirement management. The methods for the recognition of the system elements and requirements for the transferring of text and graphic design documents are provided. The need to use the classification and coding of various elements of information systems (structures, objects, resources, requirements, contracts, etc. in data transferring systems is indicated separately. The authors have developed a sequence of document processing and transmission of data during the examination, and propose a language for describing the construction of the facility, taking into account the classification criteria of the structures and construction works.

  7. DOE Integrated Safeguards and Security (DISS) historical document archival and retrieval analysis, requirements and recommendations

    Energy Technology Data Exchange (ETDEWEB)

    Guyer, H.B.; McChesney, C.A.

    1994-10-07

    The overall primary Objective of HDAR is to create a repository of historical personnel security documents and provide the functionality needed for archival and retrieval use by other software modules and application users of the DISS/ET system. The software product to be produced from this specification is the Historical Document Archival and Retrieval Subsystem The product will provide the functionality to capture, retrieve and manage documents currently contained in the personnel security folders in DOE Operations Offices vaults at various locations across the United States. The long-term plan for DISS/ET includes the requirement to allow for capture and storage of arbitrary, currently undefined, clearance-related documents that fall outside the scope of the ``cradle-to-grave`` electronic processing provided by DISS/ET. However, this requirement is not within the scope of the requirements specified in this document.

  8. Document Level Assessment of Document Retrieval Systems in a Pairwise System Evaluation

    Science.gov (United States)

    Rajagopal, Prabha; Ravana, Sri Devi

    2017-01-01

    Introduction: The use of averaged topic-level scores can result in the loss of valuable data and can cause misinterpretation of the effectiveness of system performance. This study aims to use the scores of each document to evaluate document retrieval systems in a pairwise system evaluation. Method: The chosen evaluation metrics are document-level…

  9. 50 CFR 23.53 - What are the requirements for obtaining a retrospective CITES document?

    Science.gov (United States)

    2010-10-01

    ... retrospective CITES document? 23.53 Section 23.53 Wildlife and Fisheries UNITED STATES FISH AND WILDLIFE SERVICE... ENDANGERED SPECIES OF WILD FAUNA AND FLORA (CITES) Application Procedures, Criteria, and Conditions § 23.53 What are the requirements for obtaining a retrospective CITES document? (a) Purpose. Retrospective...

  10. Assessing the Readability of Medical Documents: A Ranking Approach.

    Science.gov (United States)

    Zheng, Jiaping; Yu, Hong

    2018-03-23

    The use of electronic health record (EHR) systems with patient engagement capabilities, including viewing, downloading, and transmitting health information, has recently grown tremendously. However, using these resources to engage patients in managing their own health remains challenging due to the complex and technical nature of the EHR narratives. Our objective was to develop a machine learning-based system to assess readability levels of complex documents such as EHR notes. We collected difficulty ratings of EHR notes and Wikipedia articles using crowdsourcing from 90 readers. We built a supervised model to assess readability based on relative orders of text difficulty using both surface text features and word embeddings. We evaluated system performance using the Kendall coefficient of concordance against human ratings. Our system achieved significantly higher concordance (.734) with human annotators than did a baseline using the Flesch-Kincaid Grade Level, a widely adopted readability formula (.531). The improvement was also consistent across different disease topics. This method's concordance with an individual human user's ratings was also higher than the concordance between different human annotators (.658). We explored methods to automatically assess the readability levels of clinical narratives. Our ranking-based system using simple textual features and easy-to-learn word embeddings outperformed a widely used readability formula. Our ranking-based method can predict relative difficulties of medical documents. It is not constrained to a predefined set of readability levels, a common design in many machine learning-based systems. Furthermore, the feature set does not rely on complex processing of the documents. One potential application of our readability ranking is personalization, allowing patients to better accommodate their own background knowledge. ©Jiaping Zheng, Hong Yu. Originally published in JMIR Medical Informatics (http://medinform.jmir.org), 23.03.2018.

  11. Case histories of environmental assessment documents for nuclear waste

    International Nuclear Information System (INIS)

    Vocke, R.W.

    1985-01-01

    Nuclear power programs and policies in the United States have been subject to environmental assessment under the National Environmental Policy Act (NEPA) since 1971. NEPA documentation prepared for programmatic policy decision-making fuel cycle and concurrent federal policy are examined as they relate to radioactive waste management in this paper. Key programmatic environmental impact statements that address radioactive waste management include: the Atomic Energy Commission document on management of commercial high level and transuranium-contaminated radioactive waste, which focussed on development of engineered retrievable surface storage facilities (RSSF); the Nuclear Regulatory Commission (NRC) document on use of recycled plutonium in mixed oxide fuel in light water cooled reactors, which focussed on plutonium recycle and RSSF; the NRC statement on handling of spent light water power reactor fuel, which focussed on spent fuel storage; and the Department of Energy (DOE) statement on management of commercially generated radioactive wastes, which focussed on development of deep geologic repositories. DOE is currently pursuing the deep geologic repository option, with monitored retrievable storage as a secondary option

  12. 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

  13. 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.

  14. System requirements and design description for the document basis database interface (DocBasis)

    International Nuclear Information System (INIS)

    Lehman, W.J.

    1997-01-01

    This document describes system requirements and the design description for the Document Basis Database Interface (DocBasis). The DocBasis application is used to manage procedures used within the tank farms. The application maintains information in a small database to track the document basis for a procedure, as well as the current version/modification level and the basis for the procedure. The basis for each procedure is substantiated by Administrative, Technical, Procedural, and Regulatory requirements. The DocBasis user interface was developed by Science Applications International Corporation (SAIC)

  15. Design requirements document for project W-520, immobilized low-activity waste disposal

    International Nuclear Information System (INIS)

    Ashworth, S.C.

    1998-01-01

    This design requirements document (DRD) identifies the functions that must be performed to accept, handle, and dispose of the immobilized low-activity waste (ILAW) produced by the Tank Waste Remediation System (TWRS) private treatment contractors and close the facility. It identifies the requirements that are associated with those functions and that must be met. The functional and performance requirements in this document provide the basis for the conceptual design of the Tank Waste Remediation System Immobilized Low-Activity Waste disposal facility project (W-520) and provides traceability from the program-level requirements to the project design activity

  16. Design requirements document for project W-520, immobilized low-activity waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Ashworth, S.C.

    1998-08-06

    This design requirements document (DRD) identifies the functions that must be performed to accept, handle, and dispose of the immobilized low-activity waste (ILAW) produced by the Tank Waste Remediation System (TWRS) private treatment contractors and close the facility. It identifies the requirements that are associated with those functions and that must be met. The functional and performance requirements in this document provide the basis for the conceptual design of the Tank Waste Remediation System Immobilized Low-Activity Waste disposal facility project (W-520) and provides traceability from the program-level requirements to the project design activity.

  17. Advanced light water reactor utility requirements document: Volume 1--ALWR policy and summary of top-tier requirements

    International Nuclear Information System (INIS)

    Anon.

    1990-01-01

    The U.S. utilities are leading an industry wide effort to establish the technical foundation for the design of the Advanced Light Water Reactor (ALWR). This effort, the ALWR Program, is being managed for the U.S. electric utility industry by the Electric Power Research Institute (EPRI) and includes participation and sponsorship of several international utility companies and close cooperation with the U.S. Department of Energy (DOE). The cornerstone of the ALWR Program is a set of utility design requirements which are contained in the ALWR Requirements Document. The purpose of the Requirement Document is to present a clear, complete statement of utility desires for their next generation of nuclear plants. The Requirements Document covers the entire plant up to the grid interface. It therefore is the basis for an integrated plant design, i.e., nuclear steam supply system and balance of plant, and it emphasizes those areas which are most important to the objective of achieving an ALWR which is excellent with respect to safety, performance, constructibility, and economics. The document applies to both Pressurized Water Reactors (PWRs) and Boiling Water Reactors (BWRs). The Requirements Document is organized in three volumes. Volume 1 summarizes AlWR Program policy statements and top-tier requirements. The top-tier design requirements are categorized by major functions, including safety and investment protection, performance, and design process and constructibility. There is also a set of general design requirements, such as simplification and proven technology, which apply broadly to the ALWR design, and a set of economic goals for the ALWR program. The top-tier design requirements are described further in Volume 1 and are formally invoked as requirements in Volumes 2 and 3

  18. Assessment of LANL transuranic mixed waste management documentation

    International Nuclear Information System (INIS)

    Davis, K.D.; Hoevemeyer, S.S.; McCance, C.H.; Jennrich, E.A.; Lund, D.M.

    1991-04-01

    The objective of this report is to present findings from the evaluation of the Los Alamos National Laboratory (LANL) TRU Mixed Waste Acceptance Criteria to determine its compliance with applicable DOE requirements. The driving requirements for s TRU Mixed Waste Acceptance Criteria are essentially those contained in the ''TRU Waste Acceptance Criteria for the Waste Isolation Pilot Plant'' or WIPP WAC (DOE Report WIPP-DOE-069), 40 CFR 261-270, and DOE Order 5820.2A (Radioactive Waste Management), specifically Chapter II which is entitled ''Management of Transuranic Waste''. The primary purpose of the LANL WAC is the establishment of those criteria that must be met by generators of TRU mixed waste before such waste can be accepted by the Waste Management Group. An annotated outline of a genetic TRU mixed waste acceptance criteria document was prepared from those requirements contained in the WIPP WAC, 40 CFR 261-270, and 5820.2A, and is based solely upon those requirements

  19. Technology needs assessment (TNA) resource document for South Africa

    CSIR Research Space (South Africa)

    Taviv, R

    2007-08-01

    Full Text Available TNA(Technology needs assessment) is a requirement of Article 4.5 of the UNFCCC ‘Technology Transfer’ is a broad set of processes covering the flows of know-how, experience and equipment for mitigating or adapting to climate change amongst different...

  20. Better Assessments Require Better Assessment Literacy

    Science.gov (United States)

    Stiggins, Rick

    2018-01-01

    Stiggins says that, to build better assessment systems, educators and education leaders need more opportunities to learn the basic principles of sound assessment practice. He lays out what he views as the fundamental elements of assessment literacy.

  1. A Framework for Requirement Elicitation, Analysis, Documentation and Prioritisation under Uncertainty

    NARCIS (Netherlands)

    Rajabali Nejad, Mohammadreza; Mladenov, V.

    2015-01-01

    This paper offers a pluralistic framework for coping with requirements in the early phases of design where there is lack of knowledge about a system, its architect and functions. The framework is used to elicit, analyze, document and prioritize the requirements. It embeds probabilistic approach and

  2. 42 CFR 495.336 - Health information technology planning advance planning document requirements (HIT PAPD).

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 5 2010-10-01 2010-10-01 false Health information technology planning advance... STANDARDS FOR THE ELECTRONIC HEALTH RECORD TECHNOLOGY INCENTIVE PROGRAM Requirements Specific to the Medicaid Program § 495.336 Health information technology planning advance planning document requirements...

  3. 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

  4. Documenting Matured Science: The BACC-Type Assessment Reports

    Science.gov (United States)

    Reckermann, M.; Omstedt, A. T.

    2016-12-01

    The BACC-type reports (BALTEX and Baltic Earth Assessment of Climate Change for the Baltic Sea region, BACC 2008 and BACC II 2015) represent an approach to assessing and making available current knowledge on regional climate change and its regional impacts on the physical, biogeochemical and biological environment (ecosystems, socio-economic sphere). The BACC assessments have originated in the BALTEX scientific research community (now Baltic Earth) and are coordinated by the International Baltic Earth Secretariat. The assessments are produced by teams of scientists from the region, led by lead authors who recruit experts from relevant topics to contribute. The report of 2015 was compiled by a different group of authors as 2008 to warrant independence of personal opinions and bias. The process is not externally funded and completely based on published scientific evidence, and not biased by political or economic interest groups. The BACC-type reports aim to bring together consolidated knowledge that has broad consensus in the scientific community, but also acknowledging issues for which contradicting opinions are found in the literature, so that no consensus can be reached ("consensus on dissensus"). An international steering committee is responsible for overlooking the process, and all manuscripts are anonymously peer-reviewed by independent international experts. Outreach to stakeholders and the public is an inherent aspect of this approach to document mature science. For the Baltic Sea, there is a close collaboration with HELCOM, the intergovernmental Baltic Marine Environment Protection Commission and the major regional science-policy interface in the Baltic Sea region. A summary for non-scientists was produced for the first BACC report and is in preparation for the second. Other BACC-type reports published are the climate report for the greater Hamburg area (published in 2011), and the NOSCCA report (North Sea Climate Change Assessment), published in 2016.

  5. Documentation assessment, Project C-018H, 200-E area effluent treatment facility

    International Nuclear Information System (INIS)

    Peres, M.W.; Connor, M.D.; Mertelendy, J.I.

    1994-01-01

    Project C-018H is one of the fourteen subprojects to the Hanford Environmental Compliance (HEC) Project. Project C-018H provides treatment and disposal for the 242-A Evaporator and PUREX plant process condensate waste streams. This project used the Integrated Management Team (IMT) approach proposed by RL. The IMT approach included all affected organizations on the project team to coordinate and execute all required project tasks, while striving to integrate and satisfy all technical, operational, functional, and organizational objectives. The HEC Projects were initiated in 1989. Project C-018H began in early 1990, with completion of construction currently targeted for mid-1995. This assessment was performed to evaluate the effectiveness of the management control on design documents and quality assurance records developed and submitted for processing, use, and retention for the Project. The assessment focused primarily on the overall adequacy and quality of the design documentation currently being submitted to the project document control function

  6. Project W-236A, work plan for preparation of a design requirements document

    International Nuclear Information System (INIS)

    Groth, B.D.

    1995-01-01

    This work plan outlines the tasks necessary, and defines the organizational responsibilities for preparing a Design Requirements Document (DRD) for project W-236A, Multi-Function Waste Tank Facility (MWTF). A DRD is a Systems Engineering document which bounds, at a high level, the requirements of a discrete system element of the Tank Waste Remediation System (TWRS) Program. This system element is usually assigned to a specific project, in this case the MWTF. The DRD is the document that connects the TWRS program requirements with the highest level projects requirements and provides the project's link to the overall TWRS mission. The MWTF DRD effort is somewhat unique in that the project is already in detailed design, whereas a DRO is normally prepared prior to preliminary design. The MWTF design effort was initiated with a Functional Design Criteria (FDC) and a Supplemental Design Requirements Document (SDRD) bounding the high level requirements. Another unique aspect of this effort is that some of the TWRS program requirements are still in development. Because of these unique aspects of the MWTF DRD development, the MWTF will be developed from existing TWRS Program requirements and project specific requirements contained in the FDC and SDRD. The following list describes the objectives of the MWTF DRD: determine the primary functions of the tanks through a functional decomposition of the TWRS Program high level functions; allocate the primary functions to a sub-system architecture for the tanks; define the fundamental design features in terms of performance requirements for the system and subsystems; identify system interfaces and design constraints; and document the results in a DRD

  7. Tank waste remediation system privatization infrastructure program requirements and document management process guide

    International Nuclear Information System (INIS)

    ROOT, R.W.

    1999-01-01

    This guide provides the Tank Waste Remediation System Privatization Infrastructure Program management with processes and requirements to appropriately control information and documents in accordance with the Tank Waste Remediation System Configuration Management Plan (Vann 1998b). This includes documents and information created by the program, as well as non-program generated materials submitted to the project. It provides appropriate approval/control, distribution and filing systems

  8. 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.

  9. 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

  10. Waste encapsulation storage facility (WESF) standards/requirements identification document (S/RIDS)

    Energy Technology Data Exchange (ETDEWEB)

    Maddox, B.S., Westinghouse Hanford

    1996-07-29

    This Standards/Requirements Identification Document (S/RID) sets forth the Environmental Safety and Health (ES{ampersand}H) standards/requirements for the Waste Encapsulation Storage Facility (WESF). 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.

  11. A pilot study on the evaluation of medical student documentation: assessment of SOAP notes

    Directory of Open Access Journals (Sweden)

    Ji-Hyun Seo

    2016-06-01

    Full Text Available Purpose: The purpose of this study was evaluation of the current status of medical students' documentation of patient medical records. Methods: We checked the completeness, appropriateness, and accuracy of 95 Subjective-Objective-Assessment-Plan (SOAP notes documented by third-year medical students who participated in clinical skill tests on December 1, 2014. Students were required to complete the SOAP note within 15 minutes of an standard patient (SP-encounter with a SP complaining rhinorrhea and warring about meningitis. Results: Of the 95 SOAP notes reviewed, 36.8% were not signed. Only 27.4% documented the patient’s symptoms under the Objective component, although all students completed the Subjective notes appropriately. A possible diagnosis was assessed by 94.7% students. Plans were described in 94.7% of the SOAP notes. Over half the students planned workups (56.7% for diagnosis and treatment (52.6%. Accurate documentation of the symptoms, physical findings, diagnoses, and plans were provided in 78.9%, 9.5%, 62.1%, and 38.0% notes, respectively. Conclusion: Our results showed that third-year medical students’ SOAP notes were not complete, appropriate, or accurate. The most significant problems with completeness were the omission of students’ signatures, and inappropriate documentation of the physical examinations conducted. An education and assessment program for complete and accurate medical recording has to be developed.

  12. ENHANCED CHARACTERIZATION OF THE REPOSITORY BLOCK REQUIREMENTS DOCUMENT (ECRB-RD)

    International Nuclear Information System (INIS)

    G.M. Teraoka

    1998-01-01

    This Enhanced Characterization of the Repository Block Requirements Document (ECRB-RD) provides applicable design and construction requirements for the Enhanced Characterization of the Repository Block (ECRB) East-West Drift and its associated equipment. This document also identifies the applicable requirements from the Exploratory Studies Facilities Design Requirements (ESFDR) Document (YMPICM-00 19, Revision 2, ICN- 1) for design and construction of the ECRB East-West Drift, ground support, constructor support utilities and components. These requirements have been tailored specifically for the ECRB East-West Drift design and construction. The allocated requirements for the ECRB East-West Drift are in Sections III through VI. The requirements in sections III through VI contain requirement numbers from the ESFDR, Rev 2, ICN-1 for reference back to the ESFDR. Each requirement in the ECRB-RD also identifies a trace to the Site Design and Test Requirements Document (YMP/CM-0021, Rev. 2, ICN-1) and 10CFR60 similar to the style used in the ESFDR. These traces to 10CFR60 are consistent with the 1995 version of 10CFR60 used by the SD and TRD and the ESFDR. Those ESFDR requirements statements that were technically modified are identified as such and those that were derived as part of this allocation are also identified. An activity evaluation has been performed in accordance with QAP-2-0 and has determined that the QA program is applicable to this document. Therefore, the development of this document was performed in compliance with QAP-3-5, Revision 7, Development of Technical Documents and checked and reviewed in compliance with Section 5.3. This is consistent with the IOC from R. Stambaugh to M. Lugo on the subject of ECRB-RD, Revision 1, TDPP Applicability (LV.SEI.,RMS.03/98-0 12, Dated 3/12/98). The ECRB East-West Drift includes those excavated underground openings to support enhanced characterization testing activities for the repository block and provides potential

  13. Determining if a change to a proposal requires additional NEPA documentation: the Smithsonian Solution; TOPICAL

    International Nuclear Information System (INIS)

    ECCLESTON, C.H.

    1999-01-01

    Proposed actions tend to evolve over time. Once National Environmental Policy Act (NEPA) documentation is completed, agencies are at risk that subsequent changes may not be adequately covered or that existing NEPA documentation maybe completely invalidated. Neither NEPA nor its subsequent regulations provide sufficient direction for determining the degree to which a proposed action may change before preparation of new or supplemental documentation is necessary. Yet, decisionmakers are routinely involved in determining if a change to a proposed action departs, to such an extent, from the description presented in the NEPA document that additional documentation is necessary. Experience demonstrates that no two decisionmakers will completely agree, one decisionmaker might believe that a particular change would not require additional documentation, while the other concludes the exact opposite. Lacking definitive direction, decisionmakers and critics alike may point to a universe of potential considerations as the basis for defending their claim that a change in an action does or does not require new or additional NEPA documentation. Assertions are often based on equivocal opinions that can be neither proved nor disproved. Moreover, decisionmakers are frequently placed in an arduous dilemma of justifying a decision, for which there is no generally accepted methodology on which to base the decision. Lack of definitive direction can prolong the decisionmaking process, resulting in project delays. This can also lead to inappropriate levels of NEPA documentation, inconsistencies in decisionmaking, and increased risk of a legal challenge because of insufficient documentation. Clearly, a more systematic and less subjective approach is needed, A tool for streamlining the NEPA process, by reducing this degree of subjectivity, is presented in this paper

  14. IDC Re-Engineering Phase 2 System Requirements Document V1.3.

    Energy Technology Data Exchange (ETDEWEB)

    Harris, James M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Burns, John F. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Satpathi, Meara Allena [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-12-01

    This System Requirements Document (SRD) defines waveform data processing requirements for the International Data Centre (IDC) of the Comprehensive Nuclear Test Ban Treaty Organization (CTBTO). The IDC applies, on a routine basis, automatic processing methods and interactive analysis to raw International Monitoring System (IMS) data in order to produce, archive, and distribute standard IDC products on behalf of all States Parties. The routine processing includes characterization of events with the objective of screening out events considered to be consistent with natural phenomena or non-nuclear, man-made phenomena. This document does not address requirements concerning acquisition, processing and analysis of radionuclide data but includes requirements for the dissemination of radionuclide data and products.

  15. IDC Re-Engineering Phase 2 System Requirements Document Version 1.4

    Energy Technology Data Exchange (ETDEWEB)

    Harris, James M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Burns, John F. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Satpathi, Meara Allena [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-01-01

    This System Requirements Document (SRD) defines waveform data processing requirements for the International Data Centre (IDC) of the Comprehensive Nuclear Test Ban Treaty Organization (CTBTO). The IDC applies, on a routine basis, automatic processing methods and interactive analysis to raw International Monitoring System (IMS) data in order to produce, archive, and distribute standard IDC products on behalf of all States Parties. The routine processing includes characterization of events with the objective of screening out events considered to be consistent with natural phenomena or non-nuclear, man-made phenomena. This document does not address requirements concerning acquisition, processing and analysis of radionuclide data, but includes requirements for the dissemination of radionuclide data and products.

  16. Step 1: Human System Interface (HSI) Functional Requirements Document (FRD). Version 2

    Science.gov (United States)

    2006-01-01

    This Functional Requirements Document (FRD) establishes a minimum set of Human System Interface (HSI) functional requirements to achieve the Access 5 Vision of "operating High Altitude, Long Endurance (HALE) Unmanned Aircraft Systems (UAS) routinely, safely, and reliably in the National Airspace System (NAS)". Basically, it provides what functions are necessary to fly UAS in the NAS. The framework used to identify the appropriate functions was the "Aviate, Navigate, Communicate, and Avoid Hazards" structure identified in the Access 5 FRD. As a result, fifteen high-level functional requirements were developed. In addition, several of them have been decomposed into low-level functional requirements to provide more detail.

  17. 1 CFR 5.2 - Documents required to be filed for public inspection and published.

    Science.gov (United States)

    2010-01-01

    ... inspection and published. 5.2 Section 5.2 General Provisions ADMINISTRATIVE COMMITTEE OF THE FEDERAL REGISTER THE FEDERAL REGISTER GENERAL § 5.2 Documents required to be filed for public inspection and published... Register and published in the Federal Register: (a) Presidential proclamations and Executive orders in the...

  18. 45 CFR 400.43 - Requirements for documentation of refugee status.

    Science.gov (United States)

    2010-10-01

    ... 45 Public Welfare 2 2010-10-01 2010-10-01 false Requirements for documentation of refugee status. 400.43 Section 400.43 Public Welfare Regulations Relating to Public Welfare OFFICE OF REFUGEE RESETTLEMENT, ADMINISTRATION FOR CHILDREN AND FAMILIES, DEPARTMENT OF HEALTH AND HUMAN SERVICES REFUGEE...

  19. 42 CFR 495.338 - Health information technology implementation advance planning document requirements (HIT IAPD).

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 5 2010-10-01 2010-10-01 false Health information technology implementation... CERTIFICATION STANDARDS FOR THE ELECTRONIC HEALTH RECORD TECHNOLOGY INCENTIVE PROGRAM Requirements Specific to the Medicaid Program § 495.338 Health information technology implementation advance planning document...

  20. 50 CFR 23.20 - What CITES documents are required for international trade?

    Science.gov (United States)

    2010-10-01

    ... international trade? 23.20 Section 23.20 Wildlife and Fisheries UNITED STATES FISH AND WILDLIFE SERVICE..., EXPORTATION, AND IMPORTATION OF WILDLIFE AND PLANTS (CONTINUED) CONVENTION ON INTERNATIONAL TRADE IN... CITES documents are required for international trade? (a) Purpose. Articles III, IV, and V of the Treaty...

  1. 50 CFR 23.18 - What CITES documents are required to export Appendix-I wildlife?

    Science.gov (United States)

    2010-10-01

    ... 50 Wildlife and Fisheries 6 2010-10-01 2010-10-01 false What CITES documents are required to export Appendix-I wildlife? 23.18 Section 23.18 Wildlife and Fisheries UNITED STATES FISH AND WILDLIFE..., EXPORTATION, AND IMPORTATION OF WILDLIFE AND PLANTS (CONTINUED) CONVENTION ON INTERNATIONAL TRADE IN...

  2. Supplemental design requirements document enhanced radioactive and mixed waste storage Phase V Project W-112

    International Nuclear Information System (INIS)

    Ocampo, V.P.; Boothe, G.F.; Greager, T.M.; Johnson, K.D.; Kooiker, S.L.; Martin, J.D.

    1994-11-01

    This document provides additional and supplemental information to WHC-SD-W112-FDC-001, Project W-112 for radioactive and mixed waste storage. It provides additional requirements for the design and summarizes Westinghouse Hanford Company key design guidance and establishes the technical baseline agreements to be used for definitive design of the Project W-112 facilities

  3. 48 CFR 752.7005 - Submission requirements for development experience documents.

    Science.gov (United States)

    2010-10-01

    ... (referenced in paragraph (a)(1) of this clause) in electronic format and hard copy (one copy) to U.S. Agency... final equivalent of the hard copy submitted. (iv) Acceptable software formats for electronic documents... paragraph (b)(1)(i) of this clause. (2) Format. (i) Descriptive information is required for all Contractor...

  4. Assessment and Documentation Considerations for Postsecondary Students with Learning Disabilities

    Science.gov (United States)

    Lindstrom, Jennifer H.; Lindstrom, Will

    2011-01-01

    In order to gain access to accommodations and services at colleges and universities, students with learning disabilities must provide documentation of their disabilities, and as students with learning disabilities access higher education at increasing rates, the need for documentation of their disabilities and its impact becomes even more…

  5. Determination of Waste Isolation Pilot Plant (WIPP) management and institutional requirements documents for contact-handled (CH) critical systems

    International Nuclear Information System (INIS)

    1990-01-01

    This document lists the critical requirements documents applicable to the receipt of contact-handled waste at the Waste Isolation Pilot Plant. It also describes the processes used to determine the applicability of each document. This analysis is based on the applicable documents that were in effect in the February 1988 time frame. 2 refs

  6. Fiscal Year 2001 Tank Characterization Technical Sampling Basis and Waste Information Requirements Document

    International Nuclear Information System (INIS)

    ADAMS, M.R.

    2000-01-01

    The Fiscal Year 2001 Tank Characterization Technical Sampling Basis and Waste Information Requirements Document (TSB-WIRD) has the following purposes: (1) To identify and integrate sampling and analysis needs for fiscal year (FY) 2001 and beyond. (2) To describe the overall drivers that require characterization information and to document their source. (3) To describe the process for identifying, prioritizing, and weighting issues that require characterization information to resolve. (4) To define the method for determining sampling priorities and to present the sampling priorities on a tank-by-tank basis. (5) To define how the characterization program is going to satisfy the drivers, close issues, and report progress. (6)To describe deliverables and acceptance criteria for characterization deliverables

  7. Guidance for preparing user requirements documents for small and medium reactors and their application

    International Nuclear Information System (INIS)

    2000-08-01

    During the past decade, several countries with highly developed nuclear power programs established user required documents (URDs) to guide the development and implementation of advanced light water reactors. These efforts built upon the extensive experience with operating reactors and included new insights from ongoing research and development to enhance the economic performance and safety of future nuclear power plants. Subsequently, a number of developing countries with plans for introducing nuclear energy into their national programs expressed strong interest in establishing analogous requirements. The IAEA has therefore taken the initiative to assist in the elaboration of such requirements. Building upon relevant documents this report recommends a URD structure and content outline to support developing countries in preparing their URDs for various applications of small and medium reactors (e.g. electricity generation and/or desalination). This report was prepared by representatives from both developing and developed Member States

  8. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 1

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    The purpose of this Requirements Identification Document (RID) section is to identify, in one location, all of the facility specific requirements and good industry practices which are necessary or important to establish an effective Issues Management Program for the Tank Farm Facility. The Management Systems Functional Area includes the site management commitment to environmental safety and health (ES&H) policies and controls, to compliance management, to development and management of policy and procedures, to occurrence reporting and corrective actions, resource and issue management, and to the self-assessment process.

  9. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 1

    International Nuclear Information System (INIS)

    1994-04-01

    The purpose of this Requirements Identification Document (RID) section is to identify, in one location, all of the facility specific requirements and good industry practices which are necessary or important to establish an effective Issues Management Program for the Tank Farm Facility. The Management Systems Functional Area includes the site management commitment to environmental safety and health (ES ampersand H) policies and controls, to compliance management, to development and management of policy and procedures, to occurrence reporting and corrective actions, resource and issue management, and to the self-assessment process

  10. 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.)

  11. Functional Requirements Document for HALE UAS Operations in the NAS: Step 1. Version 3

    Science.gov (United States)

    2006-01-01

    The purpose of this Functional Requirements Document (FRD) is to compile the functional requirements needed to achieve the Access 5 Vision of "operating High Altitude, Long Endurance (HALE) Unmanned Aircraft Systems (UAS) routinely, safely, and reliably in the national airspace system (NAS)" for Step 1. These functional requirements could support the development of a minimum set of policies, procedures and standards by the Federal Aviation Administration (FAA) and various standards organizations. It is envisioned that this comprehensive body of work will enable the FAA to establish and approve regulations to govern safe operation of UAS in the NAS on a routine or daily "file and fly" basis. The approach used to derive the functional requirements found within this FRD was to decompose the operational requirements and objectives identified within the Access 5 Concept of Operations (CONOPS) into the functions needed to routinely and safely operate a HALE UAS in the NAS. As a result, four major functional areas evolved to enable routine and safe UAS operations for an on-demand basis in the NAS. These four major functions are: Aviate, Navigate, Communicate, and Avoid Hazards. All of the functional requirements within this document can be directly traceable to one of these four major functions. Some functions, however, are traceable to several, or even all, of these four major functions. These cross-cutting functional requirements support the "Command / Control: function as well as the "Manage Contingencies" function. The requirements associated to these high-level functions and all of their supporting low-level functions are addressed in subsequent sections of this document.

  12. Examination to assess the clinical examination and documentation of spine pathology among orthopedic residents.

    Science.gov (United States)

    Haglin, Jack M; Zeller, John L; Egol, Kenneth A; Phillips, Donna P

    2017-12-01

    The Accreditation Council for Graduate Medical Education (ACGME) guidelines requires residency programs to teach and evaluate residents in six overarching "core competencies" and document progress through educational milestones. To assess the progress of orthopedic interns' skills in performing a history, physical examination, and documentation of the encounter for a standardized patient with spinal stenosis, an objective structured clinical examination (OSCE) was conducted for 13 orthopedic intern residents, following a 1-month boot camp that included communications skills and curriculum in history and physical examination. Interns were objectively scored based on their performance of the physical examination, communication skills, completeness and accuracy of their electronic medical record (EMR), and their diagnostic conclusions gleaned from the patient encounter. The purpose of this study was to meaningfully assess the clinical skills of orthopedic post-graduate year (PGY)-1 interns. The findings can be used to develop a standardized curriculum for documenting patient encounters and highlight common areas of weakness among orthopedic interns with regard to the spine history and physical examination and conducting complete and accurate clinical documentation. A major orthopedic specialty hospital and academic medical center. Thirteen PGY-1 orthopedic residents participated in the OSCE with the same standardized patient presenting with symptoms and radiographs consistent with spinal stenosis. Videos of the encounters were independently viewed and objectively evaluated by one investigator in the study. This evaluation focused on the completeness of the history and the performance and completion of the physical examination. The standardized patient evaluated the communication skills of each intern with a separate objective evaluation. Interns completed these same scoring guides to evaluate their own performance in history, physical examination, and communications

  13. Program prioritization system user requirements document for Gas Cooled Reactor Associates

    International Nuclear Information System (INIS)

    1981-01-01

    Efficient management of the national HTGR program requires the establishment of an information system that will facilitate a more rational allocation of resources and task prioritization consistent with program policies. The system described in this document provides a data analysis mechanism for processing top level summary status and planning information in a rapid, timely and selective manner. Data produced by the system can be used by management to provide a rational basis for prioritizing tasks, evaluating program changes and program planning regarding costs, schedules and overall program development logic. The purpose of this document is to delineate the program prioritization system (PPS) requirements for use as a guide to acquiring and implementing the system

  14. [Quality management and strategic consequences of assessing documentation and coding under the German Diagnostic Related Groups system].

    Science.gov (United States)

    Schnabel, M; Mann, D; Efe, T; Schrappe, M; V Garrel, T; Gotzen, L; Schaeg, M

    2004-10-01

    The introduction of the German Diagnostic Related Groups (D-DRG) system requires redesigning administrative patient management strategies. Wrong coding leads to inaccurate grouping and endangers the reimbursement of treatment costs. This situation emphasizes the roles of documentation and coding as factors of economical success. The aims of this study were to assess the quantity and quality of initial documentation and coding (ICD-10 and OPS-301) and find operative strategies to improve efficiency and strategic means to ensure optimal documentation and coding quality. In a prospective study, documentation and coding quality were evaluated in a standardized way by weekly assessment. Clinical data from 1385 inpatients were processed for initial correctness and quality of documentation and coding. Principal diagnoses were found to be accurate in 82.7% of cases, inexact in 7.1%, and wrong in 10.1%. Effects on financial returns occurred in 16%. Based on these findings, an optimized, interdisciplinary, and multiprofessional workflow on medical documentation, coding, and data control was developed. Workflow incorporating regular assessment of documentation and coding quality is required by the DRG system to ensure efficient accounting of hospital services. Interdisciplinary and multiprofessional cooperation is recognized to be an important factor in establishing an efficient workflow in medical documentation and coding.

  15. Electronic document management meets environmental restoration recordkeeping requirements: A case study

    International Nuclear Information System (INIS)

    Burnham, S.L.

    1995-01-01

    Efforts at migrating records management at five Department of Energy sites operated under management by Lockheed Martin Energy Systems, Inc. for Environmental Restoration (ER) business activities are described. The corporate environment, project definition, records keeping requirements are described first. Then an evaluation of electronic document management technologies and of internal and commercially available systems are provided. Finally adopted incremental implementation strategy and lessons learned are discussed

  16. Supplemental design requirements document, Multifunction Waste Tank Facility, Project W-236A. Revision 1

    International Nuclear Information System (INIS)

    Groth, B.D.

    1995-01-01

    The Multi-Function Waste Tank Facility (MWTF) consists of four, nominal 1 million gallon, underground double-shell tanks, located in the 200-East area, and two tanks of the same capacity in the 200-West area. MWTF will provide environmentally safe storage capacity for wastes generated during remediation/retrieval activities of existing waste storage tanks. This document delineates in detail the information to be used for effective implementation of the Functional Design Criteria requirements

  17. 50 CFR 300.185 - Documentation, reporting and recordkeeping requirements for consignment documents and re-export...

    Science.gov (United States)

    2010-10-01

    ... of presenting entry documentation for clearance by customs authorities (e.g., CBP Forms 7533 or 3461... apply to all imports of fish or fish products regulated under this subpart, into the Customs territory... landed overseas (HTS heading 9815). For insular possessions with customs territories separate from the...

  18. Documenting Evidence of Practice: The Power of Formative Assessment

    Science.gov (United States)

    Stefl-Mabry, Joette

    2018-01-01

    The field of school librarianship has long called for stronger evidence related to school libraries and student achievement (Stefl-Mabry and Raddick 2017; Stefl-Mabry et al. 2016; Morris and Cahill 2017). This article outlines a systematic method for school librarians to document student learning and provide tangible confirmation of their…

  19. HALE UAS Command and Control Communications: Step 1 - Functional Requirements Document. Version 4.0

    Science.gov (United States)

    2006-01-01

    The High Altitude Long Endurance (HALE) unmanned aircraft system (UAS) communicates with an off-board pilot-in-command in all flight phases via the C2 data link, making it a critical component for the UA to fly in the NAS safely and routinely. This is a new requirement in current FAA communications planning and monitoring processes. This document provides a set of comprehensive C2 communications functional requirements and performance guidelines to help facilitate the future FAA certification process for civil UAS to operate in the NAS. The objective of the guidelines is to provide the ability to validate the functional requirements and in future be used to develop performance-level requirements.

  20. Establishing a comprehensive risk assessment document for Fernald

    International Nuclear Information System (INIS)

    Nelson, K.A.; Janke, R.C.

    1995-01-01

    While in active operation from 1952 until 1989, the Feed Material Production Center (FMPC),currently referred to as the Fernald Environmental Management Project (FEMP), produced highly purified uranium metal for ultimate use in the manufacture of nuclear weapons. In 1986 the U.S. Environmental Protection Agency (EPA) and the DOE entered into a Federal Facility Compliance Agreement covering environmental impacts associated with the FMPC. In response to the FFCA, a sitewide Remedial Investigation/Feasibility Study (RI/FS) was initiated. Production was permanently suspended at the facility in 1989, and the focus has since shifted to environmental restoration and waste management activities. The original RI/FS work plan identified 39 units, but these were later categorized and grouped into 5 larger, more manageable units as follows: (1) operable unit 1 - waste pit area; (2) operable unit 2 - other solid waste units; (3) operable unit 3 - former production area; (4) operable unit 4- silos I through 4; and (5) operable unit 5 - environmental media. On June 29, 1990, a consent agreement (under Sec. 120 and 106[a] of CERCLA) between the DOE and EPA became effective. The purpose of this agreement was to achieve consistency between the operable units and ensure commitments to the RI/FS program without altering the underlying objectives. The consent agreement was amended the following year to revise the schedules for completing the remediation of the five operable units and to direct operable unit integration to ensure compliance with the residual risk requirements of the National Hazardous Substances and Oil Contingency Plan. This Amended Consent Agreement (ACA) was signed on September 20, 1991, and became effective on December 19, 1991. In accordance with provisions of the ACA, a methodology has been prepared for performing risk assessments and establishing risk-based remedial action goals at the FEMP

  1. Waste Receiving and Packaging, Module 2A, Supplemental Design Requirements Document

    International Nuclear Information System (INIS)

    Lamberd, D.L.; Boothe, G.F.; Hinkle, A.L.; Horgos, R.M.; LeClair, M.D.; Nash, C.R.; Ocampo, V.P.; Pauly, T.R.; Stroup, J.L.; Weingardt, K.M.

    1994-01-01

    The Supplemental Design Requirements Document (SDRD) is used to communicate plant design information from Westinghouse Hanford Company (WHC) to the US Department of Energy (DOE) and the cognizant Architect Engineer (A/E). Information in the SDRD serves two purposes: to convey design requirements that are too detailed for inclusion in a Functional Design Criteria (FDC) report; and to serve as a means of change control for design commitments in the Conceptual Design Report. The mission of WRAP 2A on the Hanford site is the treatment of contact handled low level mixed waste (MW) for final disposal. The overall systems engineering steps used to reach construction and operation of WRAP 2A are depicted in Figure 1. The WRAP 2A SDRD focuses on the requirements to address the functional analysis provided in Figure 1. This information is provided in sections 2 through 5 of this SDRD. The mission analysis and functional analysis are to be provided in a separate supporting document. The organization of sections 2 through 5 corresponds to the requirements identified in the WRAP 2A functional analysis

  2. Documentation of in-training assessment for radiology trainees

    International Nuclear Information System (INIS)

    Long, Gillian

    2001-01-01

    AIM: To determine if the assessment of radiology trainees can be improved by modifying the in-training assessment form issued by the Royal College of Radiologists (RCR). MATERIALS AND METHODS: A qualitative study comparing the RCR assessment form with other alternative forms in use in the U.K. Individual semi-structured interviews were conducted with trainees (21) and trainers (18) in Sheffield to collect their views on the RCR form and an alternative form introduced on the North Trent Training Scheme. A postal questionnaire was sent to Heads of Training (24) to find out what assessment forms were in use at other centres and collect their views on the different forms. RESULTS: Trainees and trainers in Sheffield were virtually unanimous in their support of the new North Trent assessment form. The main advantages perceived were the encouragement of appraisal, setting of objectives and feedback from the trainees. Six other radiology training centres were using alternative assessment forms and all believed their forms had advantages over the RCR in-training assessment form. CONCLUSION: The results of this study suggest that the assessment process for radiology trainees can be improved by modifications to the RCR in-training assessment form and allows various recommendations to be made. Long, G. (2001)

  3. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 2

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    The Quality Assurance Functional Area Requirements Identification Document (RID), addresses the programmatic requirements that ensure risks and environmental impacts are minimized, ensure safety, reliability, and performance are maximized through the application of effective management systems commensurate with the risks posed by the Tank Farm Facility and its operation. This RID incorporates guidance intended to provide Tank Farms management with the necessary requirements information to develop, upgrade, or assess the effectiveness of a Quality Assurance Program in the performance of organizational and functional activities. Quality Assurance is defined as all those planned and systematic actions necessary to provide adequate confidence that a facility, structure, system, or component will perform satisfactorily and safely in service. This document will provide the specific requirements to meet DNFSB recommendations and the guidance provided in DOE Order 5700.6C, utilizing industry codes, standards, regulatory guidelines, and industry good practices that have proven to be essential elements for an effective and efficient Quality Assurance Program as the nuclear industry has matured over the last thirty years.

  4. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 2

    International Nuclear Information System (INIS)

    1994-04-01

    The Quality Assurance Functional Area Requirements Identification Document (RID), addresses the programmatic requirements that ensure risks and environmental impacts are minimized, ensure safety, reliability, and performance are maximized through the application of effective management systems commensurate with the risks posed by the Tank Farm Facility and its operation. This RID incorporates guidance intended to provide Tank Farms management with the necessary requirements information to develop, upgrade, or assess the effectiveness of a Quality Assurance Program in the performance of organizational and functional activities. Quality Assurance is defined as all those planned and systematic actions necessary to provide adequate confidence that a facility, structure, system, or component will perform satisfactorily and safely in service. This document will provide the specific requirements to meet DNFSB recommendations and the guidance provided in DOE Order 5700.6C, utilizing industry codes, standards, regulatory guidelines, and industry good practices that have proven to be essential elements for an effective and efficient Quality Assurance Program as the nuclear industry has matured over the last thirty years

  5. NRC review of Electric Power Research Institute's Advanced Light Reactor Utility Requirements Document - Program summary, Project No. 669

    International Nuclear Information System (INIS)

    1992-08-01

    The staff of the US Nuclear Regulatory Commission has prepared Volume 1 of a safety evaluation report (SER), ''NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document -- Program Summary,'' to document the results of its review of the Electric Power Research Institute's ''Advanced Light Water Reactor Utility Requirements Document.'' This SER provides a discussion of the overall purpose and scope of the Requirements Document, the background of the staff's review, the review approach used by the staff, and a summary of the policy and technical issues raised by the staff during its review

  6. High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 5

    International Nuclear Information System (INIS)

    1994-04-01

    The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 5) outlines the standards and requirements for the Fire Protection and Packaging and Transportation sections

  7. High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 4

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 4) presents the standards and requirements for the following sections: Radiation Protection and Operations.

  8. High level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 6

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 6) outlines the standards and requirements for the sections on: Environmental Restoration and Waste Management, Research and Development and Experimental Activities, and Nuclear Safety.

  9. High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Document (S/RID) is contained in multiple volumes. This document (Volume 2) presents the standards and requirements for the following sections: Quality Assurance, Training and Qualification, Emergency Planning and Preparedness, and Construction.

  10. High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 2

    International Nuclear Information System (INIS)

    1994-04-01

    The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Document (S/RID) is contained in multiple volumes. This document (Volume 2) presents the standards and requirements for the following sections: Quality Assurance, Training and Qualification, Emergency Planning and Preparedness, and Construction

  11. High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID)

    International Nuclear Information System (INIS)

    1994-04-01

    The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 3) presents the standards and requirements for the following sections: Safeguards and Security, Engineering Design, and Maintenance

  12. High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID)

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 3) presents the standards and requirements for the following sections: Safeguards and Security, Engineering Design, and Maintenance.

  13. 50 CFR 23.25 - What additional information is required on a non-Party CITES document?

    Science.gov (United States)

    2010-10-01

    ... a non-Party CITES document? 23.25 Section 23.25 Wildlife and Fisheries UNITED STATES FISH AND... IN ENDANGERED SPECIES OF WILD FAUNA AND FLORA (CITES) Prohibitions, Exemptions, and Requirements § 23.25 What additional information is required on a non-Party CITES document? (a) Purpose. Under Article...

  14. High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 4

    International Nuclear Information System (INIS)

    1994-04-01

    The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 4) presents the standards and requirements for the following sections: Radiation Protection and Operations

  15. 23 CFR 420.111 - What are the documentation requirements for use of FHWA planning and research funds?

    Science.gov (United States)

    2010-04-01

    ... and Research Funds § 420.111 What are the documentation requirements for use of FHWA planning and... 23 Highways 1 2010-04-01 2010-04-01 false What are the documentation requirements for use of FHWA planning and research funds? 420.111 Section 420.111 Highways FEDERAL HIGHWAY ADMINISTRATION, DEPARTMENT OF...

  16. 20 CFR 669.660 - What planning documents and information are required in the application for MSFW youth grants and...

    Science.gov (United States)

    2010-04-01

    ... 20 Employees' Benefits 3 2010-04-01 2010-04-01 false What planning documents and information are... PROGRAM UNDER TITLE I OF THE WORKFORCE INVESTMENT ACT The MSFW Youth Program § 669.660 What planning...? The required planning documents and other required information and the submission dates for filing are...

  17. High level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 6

    International Nuclear Information System (INIS)

    1994-04-01

    The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 6) outlines the standards and requirements for the sections on: Environmental Restoration and Waste Management, Research and Development and Experimental Activities, and Nuclear Safety

  18. Rangeland resource trends in the United States: A technical document supporting the 2000 USDA Forest Service RPA Assessment

    Science.gov (United States)

    John E. Mitchell

    2000-01-01

    This report documents trends in America's rangelands as required by the Renewable Resources Planning Act of 1974. The Forest Service has conducted assessments of the rangeland situation for 30 years. Over this period, rangeland values and uses have gradually shifted from concentrating upon forage production and meeting increasing demand for red meat to a more...

  19. CANDU-9/480-SEU fuel handling system assessment document

    International Nuclear Information System (INIS)

    Hwang, Jeong Ki; Jo, C. H.; Kim, H. M.; Morikawa, D. T.

    1996-11-01

    This report summarize the rationale for the CANDU 9 fuel handling system, and the design choices recommended for components of the system. Some of the design requirements applicable to the CANDU 9 480-SEU fuel handling design choices are described. These requirements imposed by the CANDU 9 project. And the design features for the key components of fuel handling system, such as the fuelling machine, the carriage, the new fuel transfer system and the irradiated fuel transfer system, are described. The carriage seismic load evaluations relevant to the design are contained in the appendices. The majority of the carriage components are acceptable, or will likely be acceptable with some redesign. The concept for the CANDU 9 fuel handling system is based on proven CANDU designs, or on improved CANDU technology. Although some development work must be done, the fuel handling concept is judged to be feasible for the CANDU 9 480-SEU reactor. (author). 2 refs

  20. Safety assessment document for the dynamic test complex (Building 836)

    International Nuclear Information System (INIS)

    Odell, B.N.; Pfeifer, H.E.

    1981-01-01

    A safety assessment was performed to determine if potential accidents at the 836 Complex at Site 300 could present undue hazards to the general public, personnel at Site 300, or have an adverse effect on the environment. The credible accidents that might have an effect on these facilities or have off-site consequences were considered. These were earthquake, extreme wind (including missiles), lightning, flood, criticality, high explosive (H) detonation that disperses uranium and beryllium, spontaneous oxidation of plutonium, explosions due to finely divided particles, and a fire

  1. Safety assessment document for the dynamic test complex (Building 836)

    Energy Technology Data Exchange (ETDEWEB)

    Odell, B.N.; Pfeifer, H.E.

    1981-11-24

    A safety assessment was performed to determine if potential accidents at the 836 Complex at Site 300 could present undue hazards to the general public, personnel at Site 300, or have an adverse effect on the environment. The credible accidents that might have an effect on these facilities or have off-site consequences were considered. These were earthquake, extreme wind (including missiles), lightning, flood, criticality, high explosive (H) detonation that disperses uranium and beryllium, spontaneous oxidation of plutonium, explosions due to finely divided particles, and a fire.

  2. Supplmental design requirements document enhanced radioactive and mixed waste storage: Phase 5, Project W-113

    International Nuclear Information System (INIS)

    Ocampo, V.P.

    1994-11-01

    This Supplemental Design Requirements Document (SDRD) is used to communicate Project W-113 specific plant design information from Westinghouse Hanford Company (WHC) to the United States Department of Energy (DOE) and the cognizant Architect Engineer (A/E). The SDRD is prepared after the completion of the project Conceptual Design report (CDR) and prior to the initiation of definitive design. Information in the SDRD serves two purposes: to convey design requirements that are too detailed for inclusion in the Functional Design Criteria (FDC) report and to serve as a means of change control for design commitments in the Title I and Title II design. The Solid Waste Retrieval Project (W-113) SDRD has been restructured from the equipment based outline used in previous SDRDs to a functional systems outline. This was done to facilitate identification of deficiencies in the information provided in the initial draft SDRD and aid design confirmation. The format and content of this SDRD adhere as closely as practicable to the requirements of WHC-CM-6-1, Standard Engineering Practices for Functional Design Criteria

  3. H2FIRST Hydrogen Contaminant Detector Task: Requirements Document and Market Survey

    Energy Technology Data Exchange (ETDEWEB)

    Terlip, Danny [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Ainscough, Chris [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Buttner, William [National Renewable Energy Laboratory (NREL), Golden, CO (United States); McWhorter, Scott [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2015-04-20

    The rollout of hydrogen fueling stations, and the fuel cell electric vehicles (FCEV) they support, requires the assurance of high quality hydrogen at the dispensing point. Automotive fuel cells are sensitive to a number of chemicals that can be introduced into the dispensed fuel at multiple points. Quality assurance and quality control methods are employed by the industry to ensure product quality, but they are not completely comprehensive and can fail at various points in the hydrogen pathway from production to dispensing. This reality leaves open the possibility of a station unknowingly dispensing harmful contaminants to a FCEV which, depending on the contaminant, may not be discovered until the FCEV is irreparably damaged. This situation is unacceptable. A hydrogen contaminant detector (HCD), defined as a combination of a gas analyzer and the components necessary for fuel stream integration, installed at hydrogen stations is one method for preventing poor quality gas from reaching an FCEV. This document identifies the characteristics required of such a device by industry and compares those requirements with the current state of commercially available gas analysis technology.

  4. 10-MWe pilot-plant-receiver panel test requirements document solar thermal test facility

    Energy Technology Data Exchange (ETDEWEB)

    1978-08-25

    Testing plans for a full-scale test receiver panel and supporting hardware which essentially duplicate both physically and functionally, the design planned for the Barstow Solar Pilot Plant are presented. Testing is to include operation during normal start and shutdown, intermittent cloud conditions, and emergencies to determine the panel's transient and steady state operating characteristics and performance under conditions equal to or exceeding those expected in the pilot plant. The effects of variations of input and output conditions on receiver operation are also to be investigated. Test hardware are described, including the pilot plant receiver, the test receiver assembly, receiver panel, flow control, electrical control and instrumentation, and structural assembly. Requirements for the Solar Thermal Test Facility for the tests are given. The safety of the system is briefly discussed, and procedures are described for assembly, installation, checkout, normal and abnormal operations, maintenance, removal and disposition. Also briefly discussed are quality assurance, contract responsibilities, and test documentation. (LEW)

  5. The control of documents maintained in the electronic media and the requirements of NBR ISO/IEC 17025 and adequacy for PNQ

    Directory of Open Access Journals (Sweden)

    Anselmo Ferreira de Castro

    2006-01-01

    Full Text Available During the assessments carried out by the authors at the diverse laboratories pertaining to the network of accredited laboratories - known as the Brazilian Calibration Network (RBC - the authors verified the difficulties that these laboratories had in meeting the requirements of NBR ISO/IEC 17025:2001 (Standard, related to the maintenance of documents in the electronic media. More and more laboratories are substituting traditional control with electronic document control, which allows for more agility in the recovery of information. These laboratories implement policies and procedures; however, they still feel insecure, in some way, as to how to meet all of these requirements, thereby giving rise to difficulties in the implementation of such. The aim of this paper is to discuss the control of documents stored in the electronic media, adopting requirement 4.3 of the Standard as the reference, and aiming, in this manner, to harmonize the assessment process of the procedures of document management in the electronic media, and to assist the laboratories in the interpretation of the Standard, so that they may implement systems that are adequate to their actual necessities and to their structural size, while at the same time complying with the referred to requirement. This work will not broach the treatment given to the records (requirement 4.12 of the Standard, facts (requirement 5.4.7 nor to the electronic transmission of results (requirement 5.10.7, leaving these subjects for posterior discussions.

  6. Method for assessing software reliability of the document management system using the RFID technology

    Directory of Open Access Journals (Sweden)

    Kiedrowicz Maciej

    2016-01-01

    Full Text Available The deliberations presented in this study refer to the method for assessing software reliability of the docu-ment management system, using the RFID technology. A method for determining the reliability structure of the dis-cussed software, understood as the index vector for assessing reliability of its components, was proposed. The model of the analyzed software is the control transfer graph, in which the probability of activating individual components during the system's operation results from the so-called operational profile, which characterizes the actual working environment. The reliability structure is established as a result of the solution of a specific mathematical software task. The knowledge of the reliability structure of the software makes it possible to properly plan the time and finan-cial expenses necessary to build the software, which would meet the reliability requirements. The application of the presented method is illustrated by the number example, corresponding to the software reality of the RFID document management system.

  7. Safety assessment document for the Dynamic Test Complex B854

    International Nuclear Information System (INIS)

    Odell, B.N.; Pfeifer, H.E.

    1981-01-01

    A safety assessment was performed to determine if potential accidents at the 854 Complex at Site 300 could present undue hazards to the general public, personnel at Site 300, or have an adverse effect on the environment. The credible accidents that might have an effect on these facilities or have off-site consequences were considered. These were earthquake, extreme wind (including missiles), lightning, flood, criticality, high explosive (HE) detonation that disperses uranium and beryllium, spontaneous oxidation of plutonium, explosions due to finely divided particles, and a fire. Seismic and extreme wind (including missiles) analyses indicate that the buildings are basically sound. The lightning protection system is in the process of being upgraded to meet AMCR 385-100. These buildings are located high above the dry creek bed so that a flood is improbable. The probability of high explosive detonation involving plutonium is very remote since the radioactive materials are encased and plutonium and HE are not permitted concurrently in the same area at Site 300. (The exception to this policy is that explosive actuating devices are sometimes located in assemblies containing fissile materials. However, an accidental actuation will not affect the safe containment of the plutonium within the assembly.) There is a remote possibility of an HE explosion involving uranium and beryllium since these are permitted in the same area.The possibility of a criticality accident is very remote since the fissile materials are doubly encased in stout metal containers. All operations involving these materials are independently reviewed and inspected by the Criticality Safety Office. It was determined that a fire was unlikely due to the low fire loading and the absence of ignition sources. It was also determined that the consequences of any accidents were reduced by the remote location of these facilities, their design, and by administrative controls

  8. Technical support document for proposed 1994 revision of the MEC thermal envelope requirements

    Energy Technology Data Exchange (ETDEWEB)

    Conner, C.C.; Lucas, R.G.

    1994-03-01

    This report documents the development of the proposed revision of the Council of American Building Officials` (CABO) 1994 supplement to the 1993 Model Energy Code (MEC) building thermal envelope requirements for maximum component U{sub 0}-value. The 1994 amendments to the 1993 MEC were established in last year`s code change cycle and did not change the envelope requirements. The research underlying the proposed MEC revision was conducted by Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE) Building Energy Standards program. The goal of this research was to develop revised guidelines based on an objective methodology that determines the most cost-effective (least total cost) combination of energy conservation measures (ECMs) (insulation levels and window types) for residential buildings. This least-cost set of ECMs was used as a basis for proposing revised MEC maximum U{sub 0}-values (thermal transmittances). ECMs include window types (for example, double-pane vinyl) and insulation levels (for example, R-19) for ceilings, walls, and floors.

  9. Financial effect of instituting Deficit Reduction Act documentation requirements in family planning clinics in Oregon.

    Science.gov (United States)

    Rodriguez, Maria Isabel; Angus, Lisa; Elman, Emily; Darney, Philip D; Caughey, Aaron B

    2011-06-01

    The study was conducted to estimate the long-term costs for implementing citizenship documentation requirements in a Medicaid expansion program for family planning services in Oregon. A decision-analytic model was developed using two perspectives: the state and society. Our primary outcome was future reproductive health care costs due to pregnancy in the next 5 years. A Markov structure was utilized to capture multiple future pregnancies. Model inputs were retrieved from the existing literature and local hospital and Medicaid data related to reimbursements. One-way and multi-way sensitivity analyses were conducted. A Monte Carlo simulation was performed to simultaneously incorporate uncertainty from all of the model inputs. Screening for citizenship results in a loss of $3119 over 5 years ($39,382 vs. $42,501) for the state and $4209 for society ($63,391 compared to $59,182) for adult women. Among adolescents, requiring proof of identity and citizenship results in a loss of $3123 for the state ($39,378 versus $42,501) and $4214 for society ($63,391 instead of $59,177). Screening for citizenship status in publicly funded family planning clinics leads to financial losses for the state and society. Copyright © 2011 Elsevier Inc. All rights reserved.

  10. 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

  11. Joint Simulation System (JSIMS) Functional Requirements Document (FRD); A User's Perspective on the Future, Version 1.O

    National Research Council Canada - National Science Library

    1996-01-01

    The purpose of this document is to define JSIMS functional requirements in a level of detail that is meaningful to both the JSIMS developmental community and the expected future users of the system...

  12. Summary of Energy Assessment Requirements under the Area Source Boiler Rule

    Science.gov (United States)

    This document provides an overview of the energy assessment requirements for the national emission standards for hazardous air pollutants (NESHAP) for area sources: industrial, commercial and Institutional boilers, 40 CFR Part 63, Subpart JJJJJJ.

  13. Underground Test Area Subproject Phase I Data Analysis Task. Volume VIII - Risk Assessment Documentation Package

    Energy Technology Data Exchange (ETDEWEB)

    None

    1996-12-01

    Volume VIII of the documentation for the Phase I Data Analysis Task performed in support of the current Regional Flow Model, Transport Model, and Risk Assessment for the Nevada Test Site Underground Test Area Subproject contains the risk assessment documentation. Because of the size and complexity of the model area, a considerable quantity of data was collected and analyzed in support of the modeling efforts. The data analysis task was consequently broken into eight subtasks, and descriptions of each subtask's activities are contained in one of the eight volumes that comprise the Phase I Data Analysis Documentation.

  14. Risk management measures for chemicals in consumer products: documentation, assessment, and communication across the supply chain.

    Science.gov (United States)

    Bruinen de Bruin, Yuri; Hakkinen, Pertti Bert; Lahaniatis, Majlinda; Papameletiou, Demosthenes; Del Pozo, Carlos; Reina, Vittorio; Van Engelen, Jacqueline; Heinemeyer, Gerhard; Viso, Anne Catherine; Rodriguez, Carlos; Jantunen, Matti

    2007-12-01

    This paper analyzes the way risk management measures (RMMs) for consumer products have been used to date in authority and industry risk assessments. A working concept for consumer product RMMs is developed, aimed at controlling, limiting or avoiding exposures, and helping to insure the safe use (or handling) of a substance as part of a consumer product. Particular focus is placed on new requirements introduced by REACH (registration, evaluation, and authorization of chemicals). A RMMs categorization approach is also developed, dividing consumer product RMMs into those that are product integrated and those that are communicated to consumers. For each of these categories, RMMs for normal use, accidental use or misuse need to be distinguished. The level of detail for documenting, assessing and communicating RMMs across supply chains can vary, depending on the type of the assessment (tiered approach). Information on RMMs was collected from published sources to demonstrate that a taxonomical approach using standard descriptors for RMMs libraries is needed for effective information exchange across supply chains.

  15. 50 CFR 23.51 - What are the requirements for issuing a partially completed CITES document?

    Science.gov (United States)

    2010-10-01

    ..., BARTER, EXPORTATION, AND IMPORTATION OF WILDLIFE AND PLANTS (CONTINUED) CONVENTION ON INTERNATIONAL TRADE... CITES documents only when: (i) The permitted trade will have a negligible impact or no impact on the... completed documents benefits both the permit holder and the issuing Management Authority. (2) The proposed...

  16. TECHNICAL BASIS FOR VENTILATION REQUIREMENTS IN TANK FARMS OPERATING SPECIFICATIONS DOCUMENTS

    Energy Technology Data Exchange (ETDEWEB)

    BERGLIN, E J

    2003-06-23

    This report provides the technical basis for high efficiency particulate air filter (HEPA) for Hanford tank farm ventilation systems (sometimes known as heating, ventilation and air conditioning [HVAC]) to support limits defined in Process Engineering Operating Specification Documents (OSDs). This technical basis included a review of older technical basis and provides clarifications, as necessary, to technical basis limit revisions or justification. This document provides an updated technical basis for tank farm ventilation systems related to Operation Specification Documents (OSDs) for double-shell tanks (DSTs), single-shell tanks (SSTs), double-contained receiver tanks (DCRTs), catch tanks, and various other miscellaneous facilities.

  17. BASINs 4.0 Climate Assessment Tool (CAT): Supporting Documentation and User's Manual (Final Report)

    Science.gov (United States)

    EPA announced the availability of the report, BASINS 4.0 Climate Assessment Tool (CAT): Supporting Documentation and User's Manual. This report was prepared by the EPA's Global Change Research Program (GCRP), an assessment-oriented program, that sits within the Office of R...

  18. Compilation of Quality Assurance Documentation for Analyses Performed for the Resumption of Transient Testing Environmental Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Schafer, Annette L. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Sondrup, A. Jeffrey [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2013-11-01

    This is a companion document to the analyses performed in support of the environmental assessment for the Resumption of Transient Fuels and Materials Testing. It is provided to allow transparency of the supporting calculations. It provides computer code input and output. The basis for the calculations is documented separately in INL (2013) and is referenced, as appropriate. Spreadsheets used to manipulate the code output are not provided.

  19. Assessment of requirements for dry towers

    Energy Technology Data Exchange (ETDEWEB)

    Peterson, D E; Sonnichsen, J C

    1976-09-01

    The regional limitations of surface water supplies in the U.S. were assessed with respect to the consumptive use requirements of wet cooling towers. The study simulated unit consumptive use factors by region, assessed regional water supplies, and examined electric load projections through 2000 A.D. to ascertain where and when water limitations may occur and, therefore, where dry cooling may be required. It was concluded that the cooling water supply situation in the United States through the year 2000 is adequate in most areas, but is uncertain over much of the Southwest. The uncertainty is related to increasing competition for the available supplies and to potential Federal and/or State policy decisions that may have a significant effect on power plant cooling. Limitations on coastal siting, seismic zone constraints, and state constraints on the purchase and transfer of water rights from other uses to cooling supply have the potential of bringing wet/dry or dry cooling into relatively common use in the 1990's. (LCL)

  20. Every document and picture tells a story: using internal corporate document reviews, semiotics, and content analysis to assess tobacco advertising.

    Science.gov (United States)

    Anderson, S J; Dewhirst, T; Ling, P M

    2006-06-01

    In this article we present communication theory as a conceptual framework for conducting documents research on tobacco advertising strategies, and we discuss two methods for analysing advertisements: semiotics and content analysis. We provide concrete examples of how we have used tobacco industry documents archives and tobacco advertisement collections iteratively in our research to yield a synergistic analysis of these two complementary data sources. Tobacco promotion researchers should consider adopting these theoretical and methodological approaches.

  1. Detailed requirements document for the Interactive Financial Management System (IFMS), volume 1

    Science.gov (United States)

    Dodson, D. B.

    1975-01-01

    The detailed requirements for phase 1 (online fund control, subauthorization accounting, and accounts receivable functional capabilities) of the Interactive Financial Management System (IFMS) are described. This includes information on the following: systems requirements, performance requirements, test requirements, and production implementation. Most of the work is centered on systems requirements, and includes discussions on the following processes: resources authority, allotment, primary work authorization, reimbursable order acceptance, purchase request, obligation, cost accrual, cost distribution, disbursement, subauthorization performance, travel, accounts receivable, payroll, property, edit table maintenance, end-of-year, backup input. Other subjects covered include: external systems interfaces, general inquiries, general report requirements, communication requirements, and miscellaneous. Subjects covered under performance requirements include: response time, processing volumes, system reliability, and accuracy. Under test requirements come test data sources, general test approach, and acceptance criteria. Under production implementation come data base establishment, operational stages, and operational requirements.

  2. 10 CFR 2.304 - Formal requirements for documents; signatures; acceptance for filing.

    Science.gov (United States)

    2010-01-01

    ... through the E-Filing system written testimony or hearing exhibits in advance of a hearing, the written... for filing. 2.304 Section 2.304 Energy NUCLEAR REGULATORY COMMISSION RULES OF PRACTICE FOR DOMESTIC...; signatures; acceptance for filing. (a) Docket numbers and titles. Each document filed in an adjudication to...

  3. 7 CFR 1484.53 - What are the requirements for documenting and reporting contributions?

    Science.gov (United States)

    2010-01-01

    ... contribution must be documented by the Cooperator, showing the method of computing non-cash contributions, salaries, and travel expenses. (b) Each Cooperator must keep records of the methods used to compute the value of non-cash contributions, and (1) Copies of invoices or receipts for expenses paid by the U.S...

  4. 41 CFR 102-118.565 - What documentation is required when filing an administrative claim?

    Science.gov (United States)

    2010-07-01

    ... 41 Public Contracts and Property Management 3 2010-07-01 2010-07-01 false What documentation is... Management Federal Property Management Regulations System (Continued) FEDERAL MANAGEMENT REGULATION..., reports and information available to GSA and/or to the agency involved and the written and documentary...

  5. Development and maintenance of product configuration systems: Requirements for a documentation tool

    DEFF Research Database (Denmark)

    Hvam, Lars; Christensen, Simon Pape; Jensen, Klaes Ladeby

    2005-01-01

    by letting a documentation tool handle trivial time consuming tasks (notification on change, consistency check etc.), as a computer often handles these tasks in a better way. Thus, a serious bottleneck in the maintenance of configuration systems can be eliminated by applying Information System (IS...

  6. Alternative Compliance: Guidelines for Preparing and Submitting a Waiver Request Application and Other Documentation Requirements (Book)

    Energy Technology Data Exchange (ETDEWEB)

    2010-11-01

    This document is designed to assist covered fleets interested in taking advantage of more flexible compliance options and to facilitate the transition from Standard Compliance to Alternative Compliance. It is designed to help fleets better understand the Alternative Compliance option and successfully complete the waiver application process.

  7. 75 FR 14361 - Notification, Documentation, and Recordkeeping Requirements for Inspected Establishments

    Science.gov (United States)

    2010-03-25

    ... error. Table 3--Number of Establishments, and Total and Average Cost in Size (x $1,000) Recall Number of... Activities (2010) (2011) (2012) (2013) (2014) Total Very Small 2,856 Recall-Procedures 2,030 278 286 295 304... 461 Total All 6,300 Recall-Procedures 4,454 610 628 647 666 7,005 development & updating. Documenting...

  8. Alternative Compliance: Guidelines for Preparing and Submitting a Waiver Request Application and Other Documentation Requirements

    Energy Technology Data Exchange (ETDEWEB)

    2013-03-01

    This document is designed to assist covered fleets interested in taking advantage of more flexible compliance options and to facilitate the transition from Standard Compliance to Alternative Compliance. It is designed to help fleets better understand the Alternative Compliance option and successfully complete the waiver application process.

  9. Alternative Compliance: Guidelines for Preparing and Submitting a Waiver Request Application and Other Documentation Requirements (Brochure)

    Energy Technology Data Exchange (ETDEWEB)

    2014-06-01

    This document is designed to assist covered fleets interested in taking advantage of more flexible compliance options and to facilitate the transition from Standard Compliance to Alternative Compliance. It is designed to help fleets better understand the Alternative Compliance option and successfully complete the waiver application process.

  10. Alternative Compliance: Guidelines for Preparing and Submitting a Waiver Request Application and Other Documentation Requirements

    Energy Technology Data Exchange (ETDEWEB)

    Sears, Ted [National Renewable Energy Lab. (NREL), Golden, CO (United States)

    2014-06-01

    This document is designed to assist covered fleets interested in taking advantage of more flexible compliance options and to facilitate the transition from Standard Compliance to Alternative Compliance. It is designed to help fleets better understand the Alternative Compliance option and successfully complete the waiver application process.

  11. Social Work Assessment Notes: A Comprehensive Outcomes-Based Hospice Documentation System.

    Science.gov (United States)

    Hansen, Angela Gregory; Martin, Ellen; Jones, Barbara L; Pomeroy, Elizabeth C

    2015-08-01

    This article describes the development of an integrated psychosocial patient and caregiver assessment and plan of care for hospice social work documentation. A team of hospice social workers developed the Social Work Assessment Notes as a quality improvement project in collaboration with the information technology department. Using the Social Work Assessment Tool as an organizing framework, this comprehensive hospice social work documentation system is designed to integrate assessment, planning, and outcomes measurement. The system was developed to guide the assessment of patients' and caregivers' needs related to end-of-life psychosocial issues, to facilitate collaborative care plan development, and to measure patient- and family-centered outcomes. Goals established with the patient and the caregiver are documented in the plan of care and become the foundation for patient-centered, strengths-based interventions. Likert scales are used to assign numerical severity levels for identified issues and progress made toward goals and to track the outcome of social work interventions across nine psychosocial constructs. The documentation system was developed for use in an electronic health record but can be used for paper charting. Future plans include automated aggregate outcomes measurement to identify the most effective interventions and best practices in end-of-life care.

  12. 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.

  13. 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

  14. Regulatory document R-104, Regulatory objectives, requirements and guidelines for the disposal of radioactive wastes - long-term aspects

    International Nuclear Information System (INIS)

    1987-01-01

    The purpose and scope of this document is to present the regulatory basis for judging the long-term acceptability of radioactive waste disposal options. The basic objectives of radioactive waste disposal are given as are the regulatory requirements to be satisfied. (NEA)

  15. Safeguards Guidance Document for Designers of Commercial Nuclear Facilities: International Nuclear Safeguards Requirements and Practices For Uranium Enrichment Plants

    Energy Technology Data Exchange (ETDEWEB)

    Robert Bean; Casey Durst

    2009-10-01

    This report is the second in a series of guidelines on international safeguards requirements and practices, prepared expressly for the designers of nuclear facilities. The first document in this series is the description of generic international nuclear safeguards requirements pertaining to all types of facilities. These requirements should be understood and considered at the earliest stages of facility design as part of a new process called “Safeguards-by-Design.” This will help eliminate the costly retrofit of facilities that has occurred in the past to accommodate nuclear safeguards verification activities. The following summarizes the requirements for international nuclear safeguards implementation at enrichment plants, prepared under the Safeguards by Design project, and funded by the U.S. Department of Energy (DOE) National Nuclear Security Administration (NNSA), Office of NA-243. The purpose of this is to provide designers of nuclear facilities around the world with a simplified set of design requirements and the most common practices for meeting them. The foundation for these requirements is the international safeguards agreement between the country and the International Atomic Energy Agency (IAEA), pursuant to the Treaty on the Non-proliferation of Nuclear Weapons (NPT). Relevant safeguards requirements are also cited from the Safeguards Criteria for inspecting enrichment plants, found in the IAEA Safeguards Manual, Part SMC-8. IAEA definitions and terms are based on the IAEA Safeguards Glossary, published in 2002. The most current specification for safeguards measurement accuracy is found in the IAEA document STR-327, “International Target Values 2000 for Measurement Uncertainties in Safeguarding Nuclear Materials,” published in 2001. For this guide to be easier for the designer to use, the requirements have been restated in plainer language per expert interpretation using the source documents noted. The safeguards agreement is fundamentally a

  16. Wildlife-associated recreation trends in the United States: a technical document supporting the Forest Service 2010 RPA Assessment

    Science.gov (United States)

    Miranda H. Mockrin; Richard A. Aiken; Curtis H. Flather

    2012-01-01

    The Forest and Rangeland Renewable Resources Planning Act (RPA) of 1974 requires periodic assessments of the condition and trends of the Nation's renewable natural resources. In this report, we document recent and historical trends in hunting and wildlife watching to fulfill RPA requirements. Using data from the U.S. Department of the Interior, Fish and Wildlife...

  17. Principles for social impact assessment: A critical comparison between the international and US documents

    International Nuclear Information System (INIS)

    Vanclay, Frank

    2006-01-01

    The 'International Principles for Social Impact Assessment' and the 'Principles and Guidelines for Social Impact Assessment in the USA', both developed under the auspices of the International Association for Impact Assessment and published in 2003, are compared. Major differences in the definition and approach to social impact assessment (SIA) are identified. The US Principles and Guidelines is shown to be positivist/technocratic while the International Principles is identified as being democratic, participatory and constructivist. Deficiencies in both documents are identified. The field of SIA is changing to go beyond the prevention of negative impacts, to include issues of building social capital, capacity building, good governance, community engagement and social inclusion

  18. Technical assessment of compliance with workplace air sampling requirements at WRAP

    International Nuclear Information System (INIS)

    HACKWORTH, M.F.

    1999-01-01

    The purpose of this Technical Assessment is to satisfy HSRCM-1, ''Hanford Site Radiological Control Manual'' Article 551.4 for a documented study of facility Workplace Air Monitoring (WAM) programs. HSRCM-1 is the primary guidance for radiological control at Waste Management Federal Services of Hanford, Inc. (WMH). The HSRCM-1 complies with Title 10. Part 835 of the Code of Federal Regulations (10CFR835). This document provides an evaluation of the compliance of the Waste Receiving and Processing facility (WRAP) WAM program to the criteria standards, requirements, and documents compliance with the requirements where appropriate. Where necessary, it also indicates changes needed to bring specific locations into compliance

  19. Technical Requirements Analysis and Control Systems (TRACS) Initial Operating Capability (IOC) documentation

    Science.gov (United States)

    Hammond, Dana P.

    1991-01-01

    The Technical Requirements Analysis and Control Systems (TRACS) software package is described. TRACS offers supplemental tools for the analysis, control, and interchange of project requirements. This package provides the fundamental capability to analyze and control requirements, serves a focal point for project requirements, and integrates a system that supports efficient and consistent operations. TRACS uses relational data base technology (ORACLE) in a stand alone or in a distributed environment that can be used to coordinate the activities required to support a project through its entire life cycle. TRACS uses a set of keyword and mouse driven screens (HyperCard) which imposes adherence through a controlled user interface. The user interface provides an interactive capability to interrogate the data base and to display or print project requirement information. TRACS has a limited report capability, but can be extended with PostScript conventions.

  20. Magnetohydrodynamics (MHD) Engineering Test Facility (ETF) 200 MWe power plant. Design Requirements Document (DRD)

    Science.gov (United States)

    Rigo, H. S.; Bercaw, R. W.; Burkhart, J. A.; Mroz, T. S.; Bents, D. J.; Hatch, A. M.

    1981-01-01

    A description and the design requirements for the 200 MWe (nominal) net output MHD Engineering Test Facility (ETF) Conceptual Design, are presented. Performance requirements for the plant are identified and process conditions are indicated at interface stations between the major systems comprising the plant. Also included are the description, functions, interfaces and requirements for each of these major systems. The lastest information (1980-1981) from the MHD technology program are integrated with elements of a conventional steam electric power generating plant.

  1. Assessment model validity document. NAMMU: A program for calculating groundwater flow and transport through porous media

    International Nuclear Information System (INIS)

    Cliffe, K.A.; Morris, S.T.; Porter, J.D.

    1998-05-01

    NAMMU is a computer program for modelling groundwater flow and transport through porous media. This document provides an overview of the use of the program for geosphere modelling in performance assessment calculations and gives a detailed description of the program itself. The aim of the document is to give an indication of the grounds for having confidence in NAMMU as a performance assessment tool. In order to achieve this the following topics are discussed. The basic premises of the assessment approach and the purpose of and nature of the calculations that can be undertaken using NAMMU are outlined. The concepts of the validation of models and the considerations that can lead to increased confidence in models are described. The physical processes that can be modelled using NAMMU and the mathematical models and numerical techniques that are used to represent them are discussed in some detail. Finally, the grounds that would lead one to have confidence that NAMMU is fit for purpose are summarised

  2. European utility requirements (EUR) volume 3 assessment for AP1000

    International Nuclear Information System (INIS)

    Saiu, G.; Demetri, K.J.

    2005-01-01

    The EUR (European Utility Requirements) Volume 3 is intended to report the Plant Description, the Compliance Assessment to EUR Volumes 1 and 2, and finally, the Specific Requirements for each specific Nuclear Power Plant Design considered by the EUR. Five subsets of EUR Volume 3, based on EUR Revision B, are already published; all of which are next generation plant designs being developed for Europe beyond 2000. They include : 1) EP1000 - Passive Pressurized Light Water Reactor (3-Loop, 1000 MWe) 2) EPR - Evolutionary Pressurized Light Water Reactor (1500 MWe) 3) BWR90/90+ - Evolutionary Boiling Water Reactor (1400 MWe) 4) ABWR - Evolutionary Boiling Water Reactor (1400 MWe) 5) SWR 1000 - Boiling Water Reactor With Passive Features (1000 MWe) In addition, the following subsets are currently being developed: 1) AP1000 - Passive Pressurized Light Water Reactor (2-Loop, 1117 MWe) 2) VVER AES 92 - Pressurized Water Reactor With Passive Features (1000 MWe) The purpose of this paper is to provide an overview of the program, which started in January 2004 with the EUR group to prepare an EUR Volume 3 Subset for the AP1000 nuclear plant design. The AP1000 EUR compliance assessment, to be performed against EUR Revision C requirements, is an important step for the evaluation of the AP1000 design for application in Europe. The AP1000 compliance assessment is making full use of AP1000 licensing documentation, EPP Phase 2 design activities and EP1000 EUR detailed compliance assessment. As of today, nearly all of the EUR Chapters have been discussed within the EUR Coordination Group. Based on the results of the compliance assessment, it can be stated that the AP1000 design shows a good level of compliance with the EUR Revision C requirements. Nevertheless, the compliance assessment has highlighted areas for where the AP1000 plant deviates from the EUR. The EPP design group has selected the most significant ones for performing detailed studies to quantify the degree of compliance

  3. Station set requirements document. Volume 82: Fire support. Book 2: Preliminary functional fire plan

    Science.gov (United States)

    Gray, N. C.

    1974-01-01

    The fire prevention/protection requirements for all shuttle facility and ground support equipment are presented for the hazardous operations. These include: preparing the orbiter for launch, launch operations, landing operations, safing operations, and associated off-line activities.

  4. Modelling requirements for future assessments based on FEP analysis

    International Nuclear Information System (INIS)

    Locke, J.; Bailey, L.

    1998-01-01

    This report forms part of a suite of documents describing the Nirex model development programme. The programme is designed to provide a clear audit trail from the identification of significant features, events and processes (FEPs) to the models and modelling processes employed within a detailed safety assessment. A scenario approach to performance assessment has been adopted. It is proposed that potential evolutions of a deep geological radioactive waste repository can be represented by a base scenario and a number of variant scenarios. The base scenario is chosen to be broad-ranging and to represent the natural evolution of the repository system and its surrounding environment. The base scenario is defined to include all those FEPs that are certain to occur and those which are judged likely to occur for a significant period of the assessment timescale. The structuring of FEPs on a Master Directed Diagram (MDD) provides a systematic framework for identifying those FEPs that form part of the natural evolution of the system and those, which may define alternative potential evolutions of the repository system. In order to construct a description of the base scenario, FEPs have been grouped into a series of conceptual models. Conceptual models are groups of FEPs, identified from the MDD, representing a specific component or process within the disposal system. It has been found appropriate to define conceptual models in terms of the three main components of the disposal system: the repository engineered system, the surrounding geosphere and the biosphere. For each of these components, conceptual models provide a description of the relevant subsystem in terms of its initial characteristics, subsequent evolution and the processes affecting radionuclide transport for the groundwater and gas pathways. The aim of this document is to present the methodology that has been developed for deriving modelling requirements and to illustrate the application of the methodology by

  5. Performing the processing required for automatically get a PDF/A version of the CERN Library documentation

    CERN Document Server

    Molina Garcia-Retamero, Antonio

    2015-01-01

    The aim of the project was to perform the processing required for automatically get a PDF/A version of the CERN Library documentation. For this, it is necessary to extract as much metadata as possible from the sources files, inject the required data into the original source files creating new ones ready for being compiled with all related dependencies. Besides, I’ve proposed the creation of a HTML version consistent with the PDF and navigable for easy access, I’ve been trying to perform some Natural Language Processing for extracting metadata, I’ve proposed the injection of the cern library documentation into the HTML version of the long writeups where it is referenced (for instance, when a CERN Library function is referenced in a sample code) Finally, I’ve designed and implemented a Graphical User Interface in order to simplify the process for the user.

  6. 40 CFR 60.2095 - What site-specific documentation is required?

    Science.gov (United States)

    2010-07-01

    .... (5) Procedures for operating the incinerator and associated air pollution control systems within the... incinerator operating limits. (7) Reporting and recordkeeping procedures. (8) The waste management plan... required? 60.2095 Section 60.2095 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR...

  7. Functional and operational requirements document : building 1012, Battery and Energy Storage Device Test Facility, Sandia National Laboratories, New Mexico.

    Energy Technology Data Exchange (ETDEWEB)

    Johns, William H. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2013-11-01

    This report provides an overview of information, prior studies, and analyses relevant to the development of functional and operational requirements for electrochemical testing of batteries and energy storage devices carried out by Sandia Organization 2546, Advanced Power Sources R&D. Electrochemical operations for this group are scheduled to transition from Sandia Building 894 to a new Building located in Sandia TA-II referred to as Building 1012. This report also provides background on select design considerations and identifies the Safety Goals, Stakeholder Objectives, and Design Objectives required by the Sandia Design Team to develop the Performance Criteria necessary to the design of Building 1012. This document recognizes the Architecture-Engineering (A-E) Team as the primary design entity. Where safety considerations are identified, suggestions are provided to provide context for the corresponding operational requirement(s).

  8. The Army Materiel Requirements Documents: Qualitative Analysis of Efficiency and Effectiveness

    Science.gov (United States)

    2013-06-30

    65 - k~î~ä=mçëíÖê~Çì~íÉ=pÅÜççä= We measure efficiency based on two BPP initiatives: (1) Build Stronger Partnerships With the Requirements...poor,” “average,” or “excellent” based on comments received from SMEs in relation to the definitions of each BPP initiative during our interviews. A...M-ATV, and JLTV and how well they rank in terms of efficiency and effectiveness according to BPP initiatives. For efficiency, we assign a

  9. Detailed requirements document for common software of shuttle program information management system

    Science.gov (United States)

    Everette, J. M.; Bradfield, L. D.; Horton, C. L.

    1975-01-01

    Common software was investigated as a method for minimizing development and maintenance cost of the shuttle program information management system (SPIMS) applications while reducing the time-frame of their development. Those requirements satisfying these criteria are presented along with the stand-alone modules which may be used directly by applications. The SPIMS applications operating on the CYBER 74 computer, are specialized information management systems which use System 2000 as a data base manager. Common software provides the features to support user interactions on a CRT terminal using form input and command response capabilities. These features are available as subroutines to the applications.

  10. Quality Improvement Initiative on Pain Knowledge, Assessment, and Documentation Skills of Pediatric Nurses.

    Science.gov (United States)

    Margonary, Heather; Hannan, Margaret S; Schlenk, Elizabeth A

    2017-01-01

    Pain treatment begins with a nurse’s assessment, which relies on effective assessment skills. Hospital settings have implemented pain assessment education, but there is limited evidence in pediatric transitional care settings. The purpose of this quality improvement (QI) initiative was to develop, implement, and evaluate an evidence-based pain education session with 20 nurses in a pediatric specialty hospital that provides transitional care. Specific aims were to assess nurses’ knowledge and attitudes of pain, and evaluate assessment skills based on nurses’ documentation. A prospective pre-post design with three assessments (baseline, post-intervention, and one-month follow-up) was used. The Shriner’s Pediatric Nurses’ Knowledge and Attitudes Regarding Pain questionnaire and an electronic health record review were completed at each assessment. There was significant improvement in nurses’ knowledge and attitudes of pain after the education session (F[2,6] = 50.281, p nurses significantly increased from 43.1% at baseline to 64.8% at post-intervention, and 67.7% at follow-up (χ²[2] = 20.55, p Nursing interventions for pain increased significantly, from 33.3% at baseline to 84.0% at post-intervention, and stabilized at 80.0% at follow-up (χ²[2] = 8.91, p = 0.012). Frequency of pain reassessments did not show a statistically significant change, decreasing from 77.8% at baseline to 44.0% at post-intervention and 40.0% at follow-up (χ²[2]= 3.538, p = 0.171). Nurses’ pain knowledge and documentation of assessment skills were improved in this QI initiative.

  11. NRC review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document - Evolutionary plant designs, Chapter 1, Project No. 669

    International Nuclear Information System (INIS)

    1992-08-01

    The staff of the US Nuclear Regulatory Commission has prepared Volume 2 (Parts 1 and 2) of a safety evaluation report (SER), ''NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document -- Evolutionary Plant Designs,'' to document the results of its review of the Electric Power Research Institute's ''Advanced Light Water Reactor Utility Requirements Document.'' This SER gives the results of the staff's review of Volume II of the Requirements Document for evolutionary plant designs, which consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant (approximately 1300 megawatts-electric)

  12. NRC review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document - Evolutionary plant designs, Chapters 2--13, Project No. 669

    International Nuclear Information System (INIS)

    1992-08-01

    The staff of the US Nuclear Regulatory Commission has prepared Volume 2 (Parts 1 and 2) of a safety evaluation report (SER), ''NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document -- Evolutionary Plant Designs,'' to document the results of its review of the Electric Power Research Institute's ''Advanced Light Water Reactor Utility Requirements Document.'' This SER gives the results of the staff's review of Volume II of the Requirements Document for evolutionary plant designs, which consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant (approximately 1300 megawatts-electric)

  13. Gamma radiation effects on physical properties of parchment documents: Assessment of Dmax

    International Nuclear Information System (INIS)

    Nunes, Inês; Mesquita, Nuno; Cabo Verde, Sandra; João Trigo, Maria; Ferreira, Armando; Manuela Carolino, Maria; Portugal, António; Luísa Botelho, Maria

    2012-01-01

    Parchments are important documents that give testimony for History; therefore these materials should be respected and preserved. Considering incremental biodeterioration problems that have to be faced daily, the Archive of the University of Coimbra (AUC) is involved in different scientific projects in order to evaluate and determine new methods for document decontamination and preservation. The aim of this study was to evaluate gamma radiation effects on the colour and texture of the AUC parchment documents. The assessment of these effects was used to estimate the maximum gamma radiation dose (D max ) that could guarantee parchment documents′ decontamination treatment, without significant alteration of their physical properties. Parchment samples were exposed to gamma radiation doses ranging from 10 to 30 kGy. The texture and colour of samples were assessed before and after the irradiation procedure, using a texture analyser and an electronic colorimeter. Hardness and springiness were determined based on texture spectra. Lightness (L⁎), Chroma (C), greenness vs. redness (a*) and yellowness vs. blueness (b*) values were obtained from colorimetric measures. Results indicate no significant effects of gamma radiation on the texture and colour of parchment for the studied doses. - Highlights: ► Study on the effects of gamma radiation in parchment physical properties. ► Evaluation of the uniformity of parchment samples′ physical parameters. ► Proposal of a maximum gamma radiation dose for parchment decontamination treatment.

  14. International review on safety requirements for the prototype fast breeder reactor “Monju” (Translated document)

    International Nuclear Information System (INIS)

    2016-02-01

    In response to the lessons learned from the serious nuclear accidents at the TEPCO's Fukushima Daiichi Nuclear Power Stations, an advisory committee, which was set up by the Japan Atomic Energy Agency, issued the report “Safety Requirements Expected to the Prototype Fast Breeder Reactor Monju” taking into account the SFR specific safety characteristics in July 2014. The report was reviewed by the leading international experts on SFR safety from five countries and one international organization in order to obtain independent and objective evaluation. The international review comments on each subsection were collected and compiled, and then a summary of results was derived through the discussion at the review meeting and individual feedbacks. As a result the basic concept for prevention of severe accidents and mitigation of their consequences of Monju is appropriate in consideration of SFR specific safety characteristics, and is in accordance with international common understanding. (author)

  15. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 5

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    The Fire Protection functional area for the Hanford Site Tank Farm facilities and support structures is based on the application of relevant DOE orders, regulations, and industry codes and standards. The fire protection program defined in this document may be divided into three areas: (1) organizational, (2) administrative programmatic features, and (3) technical features. The information presented in each section is in the form of program elements and orders, regulations, industry codes, and standards that serve as the attributes of a fire protection program for the Tank Farm facilities. Upon completion this document will be utilized as the basis to evaluate compliance of the fire protection program being implemented for the Tank Farm facilities with the requirements of DOE orders and industry codes and standards.

  16. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 5

    International Nuclear Information System (INIS)

    1994-04-01

    The Fire Protection functional area for the Hanford Site Tank Farm facilities and support structures is based on the application of relevant DOE orders, regulations, and industry codes and standards. The fire protection program defined in this document may be divided into three areas: (1) organizational, (2) administrative programmatic features, and (3) technical features. The information presented in each section is in the form of program elements and orders, regulations, industry codes, and standards that serve as the attributes of a fire protection program for the Tank Farm facilities. Upon completion this document will be utilized as the basis to evaluate compliance of the fire protection program being implemented for the Tank Farm facilities with the requirements of DOE orders and industry codes and standards

  17. Documentation of medical findings in radiation workers in the GDR to meet the requirements of ICRP publication 26

    International Nuclear Information System (INIS)

    Wolff, H.R.; Neumeister, K.

    1979-01-01

    Based on ICRP Publication 26, the future organization of the medical surveillance system for radiation workers in the GDR is considered in this paper. These radiation workers will also in future be medically supervised by means of pre-employment and routine examinations. It is considered necessary to have as extensive a registration as possible of information on medical examinations, working place analyses and incidents. Such data have to be collected and stored to be compared with other national and international projects (e.g. in the field of occupational health). In addition, they should permit epidemiological studies to be internationally co-ordinated. For this purpose, a documentation system has been prepared in the German Democratic Republic which is based on GDR experiences and makes it possible to specify the requirements of ICRP Publication 26. This system forms a new basis for mass examinations of occupationally exposed persons. Uniform examination methods tailored to meet the task of assuring occupational health in the GDR will be introduced. The documentation cards are meant to be used as clear-text cards suited for automatic reading by optical character recognition. The examination form consists of ten parts and comprises all details from working place situation to medical findings to laboratory results. It is felt that this new documentation system permits registration of all relevant data required for the effective radiation protection of man. On the basis of this documentation of findings, participation is scheduled in the respective international IAEA programmes and the studies proposed by the ICRP for problems of radiation-induced carcinogenesis and radiogenetics

  18. Design requirements document for the phase 1 privatization electrical power system

    Energy Technology Data Exchange (ETDEWEB)

    Singh, G.

    1997-10-31

    The electrical system for the Phase 1 privatization facilities will support the TWRS mission by providing the electrical power to the Phase 1 privatized facilities. This system will receive power from the Department of Energy-Richland Operations (RL) A4-8 230 kV transmission system powered from Bonneville Power Administration (BPA) Ashe and Midway 230 kV Substations. The existing RL 230 kV transmission line will be modified and looped 1021 into the new 230 kV substation bus. The new substation will be located in the vicinity of the privatized facilities, approximately 3.2 km (2 mi) south of the existing RL A4-8 230 kV transmission line. The substation will be capable of providing up to 40 MW of electrical power to support the Phase 1 privatization facilities and has space for accommodating future expansions. The substation will require at least two 230-13.8 kV transformers, 13.8 kV split bus switchgear, switchgear building, grounding transformers, instrument transformers, control and monitoring equipment, associated protection and isolation devices, lightning protection, yard lighting, cable and raceways, and infrastructure needed to provide desired availability and reliability. The power from the 13.8 kV switchgear located in the switchgear building will be delivered at the privatization facilities site boundaries. The 13.8 kV distribution system inside the privatization facilities site boundaries is the responsibility of the privatization contract.

  19. Design requirements document for the phase 1 privatization electrical power system

    International Nuclear Information System (INIS)

    Singh, G.

    1997-01-01

    The electrical system for the Phase 1 privatization facilities will support the TWRS mission by providing the electrical power to the Phase 1 privatized facilities. This system will receive power from the Department of Energy-Richland Operations (RL) A4-8 230 kV transmission system powered from Bonneville Power Administration (BPA) Ashe and Midway 230 kV Substations. The existing RL 230 kV transmission line will be modified and looped 1021 into the new 230 kV substation bus. The new substation will be located in the vicinity of the privatized facilities, approximately 3.2 km (2 mi) south of the existing RL A4-8 230 kV transmission line. The substation will be capable of providing up to 40 MW of electrical power to support the Phase 1 privatization facilities and has space for accommodating future expansions. The substation will require at least two 230-13.8 kV transformers, 13.8 kV split bus switchgear, switchgear building, grounding transformers, instrument transformers, control and monitoring equipment, associated protection and isolation devices, lightning protection, yard lighting, cable and raceways, and infrastructure needed to provide desired availability and reliability. The power from the 13.8 kV switchgear located in the switchgear building will be delivered at the privatization facilities site boundaries. The 13.8 kV distribution system inside the privatization facilities site boundaries is the responsibility of the privatization contract

  20. Population and harvest trends of big game and small game species: a technical document supporting the USDA Forest Service Interim Update of the 2000 RPA Assessment

    Science.gov (United States)

    Curtis H. Flather; Michael S. Knowles; Stephen J. Brady

    2009-01-01

    This technical document supports the Forest Service's requirement to assess the status of renewable natural resources as mandated by the Forest and Rangeland Renewable Resources Planning Act of 1974 (RPA). It updates past reports on national and regional trends in population and harvest estimates for species classified as big game and small game. The trends...

  1. Geographic patterns of at-risk species: A technical document supporting the USDA Forest Service Interim Update of the 2000 RPA Assessment

    Science.gov (United States)

    Curtis H. Flather; Michael S. Knowles; Jason McNees

    2008-01-01

    This technical document supports the Forest Service's requirement to assess the status of renewable natural resources as mandated by the Forest and Rangeland Renewable Resources Planning Act of 1974. It updates past reports on the trends and geographic patterns of species formally listed as threatened or endangered under the Endangered Species Act of 1973. We...

  2. Wildlife population and harvest trends in the United States: a technical document supporting the Forest Service 2010 RPA Assessment

    Science.gov (United States)

    Curtis H. Flather; Michael S. Knowles; Martin F. Jones; Carol Schilli

    2013-01-01

    The Forest and Rangeland Renewable Resources Planning Act (RPA) of 1974 requires periodic assessments of the condition and trends of the nation's renewable natural resources. Data from many sources were used to document recent historical trends in big game, small game, migratory game birds, furbearers, nongame, and imperiled species. Big game and waterfowl have...

  3. Fish and other aquatic resource trends in the United States: a technical document supporting the Forest Service 2010 RPA Assessment

    Science.gov (United States)

    Andrew J. Loftus; Curtis H. Flather

    2012-01-01

    The Forest and Rangeland Renewable Resources Planning Act (RPA) of 1974 requires periodic assessments of the status and trends in the Nation's renewable natural resources including fish and other aquatic species and their habitats. Data from a number of sources are used to document trends in habitat quality, populations, resource use, and patterns of imperilment...

  4. Assessment of Geothermal Data Resources and Requirements

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2008-09-01

    This paper is a review of Geothermal Technologies Program activities and archives related to data collection and analysis. It includes an assessment of the current state of geothermal data, future program and stakeholder data needs, existence of and access to critical data, and high-level direction and prioritization of next steps to meet the Program’s data needs.

  5. Health literacy, self-efficacy, and patients' assessment of medical disclosure and consent documentation.

    Science.gov (United States)

    Donovan-Kicken, Erin; Mackert, Michael; Guinn, Trey D; Tollison, Andrew C; Breckinridge, Barbara; Pont, Stephen J

    2012-01-01

    Informed consent documents are designed to convey the risks of medical procedures to patients, yet they are often difficult to understand; this is especially true for individuals with limited health literacy. An important opportunity for advancing knowledge about health literacy and informed consent involves examining the theoretical pathways that help to explain how health literacy relates to information processing when patients read consent forms. In this study, we proposed and tested a model that positioned self-efficacy as a mediator of the association between health literacy and patients' comprehension and assessment of informed consent documentation. Findings from structured interviews with patients (n = 254) indicated that lower health literacy predicted lower self-efficacy, which predicted feeling less well informed and less prepared, being more confused about the procedure and its hazards, and wanting more information about risks. Incorporating awareness of self-efficacy into disclosure documents and consent conversations may be a useful means of prompting patients to ask questions that can help them make informed decisions about care.

  6. The National Library of Kosovo "PJETER Bogdani" Rapid Condition Assessment and Documentation

    Science.gov (United States)

    Eppich, R.; Ramku, B.; Binakaj, N.

    2017-08-01

    The National Library of Kosovo "Pjetër Bogdani" is a symbol of Prishtina, Kosovo and the quest for knowledge. It is simultaneously an icon of modernity and symbol of the past. Unfortunately, it suffered through the Kosovo war and neglect in times of economic difficulty. It was also unfortunately featured in the British newspaper The Telegraph in their travel section: "One of the world's 30 ugliest buildings?" In late 2015 the Kosovo Architectural Foundation, a non-profit dedicated to spirit of creating and preserving unique architecture, became concerned with the reputation and condition of the Library and contacted the Kosovo Ministry of Culture, visited the site and initiated a project to raise awareness and document this modern masterpiece. The Getty Foundation and their Keeping it Modern grant program awarded funding for initial condition assessment, documentation, capacity building and investigations. This paper discusses the project to document and improve the image and awareness of this important structure and set priorities for its future.

  7. High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 7. Revision 1

    International Nuclear Information System (INIS)

    Burt, D.L.

    1994-04-01

    The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 7) presents the standards and requirements for the following sections: Occupational Safety and Health, and Environmental Protection

  8. High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 7. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Burt, D.L.

    1994-04-01

    The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 7) presents the standards and requirements for the following sections: Occupational Safety and Health, and Environmental Protection.

  9. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 3

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    The Safeguards and Security (S&S) Functional Area address the programmatic and technical requirements, controls, and standards which assure compliance with applicable S&S laws and regulations. Numerous S&S responsibilities are performed on behalf of the Tank Farm Facility by site level organizations. Certain other responsibilities are shared, and the remainder are the sole responsibility of the Tank Farm Facility. This Requirements Identification Document describes a complete functional Safeguards and Security Program that is presumed to be the responsibility of the Tank Farm Facility. The following list identifies the programmatic elements in the S&S Functional Area: Program Management, Protection Program Scope and Evaluation, Personnel Security, Physical Security Systems, Protection Program Operations, Material Control and Accountability, Information Security, and Key Program Interfaces.

  10. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 3

    International Nuclear Information System (INIS)

    1994-04-01

    The Safeguards and Security (S ampersand S) Functional Area address the programmatic and technical requirements, controls, and standards which assure compliance with applicable S ampersand S laws and regulations. Numerous S ampersand S responsibilities are performed on behalf of the Tank Farm Facility by site level organizations. Certain other responsibilities are shared, and the remainder are the sole responsibility of the Tank Farm Facility. This Requirements Identification Document describes a complete functional Safeguards and Security Program that is presumed to be the responsibility of the Tank Farm Facility. The following list identifies the programmatic elements in the S ampersand S Functional Area: Program Management, Protection Program Scope and Evaluation, Personnel Security, Physical Security Systems, Protection Program Operations, Material Control and Accountability, Information Security, and Key Program Interfaces

  11. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 4

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    Radiation protection of personnel and the public is accomplished by establishing a well defined Radiation Protection Organization to ensure that appropriate controls on radioactive materials and radiation sources are implemented and documented. This Requirements Identification Document (RID) applies to the activities, personnel, structures, systems, components, and programs involved in executing the mission of the Tank Farms. The physical boundaries within which the requirements of this RID apply are the Single Shell Tank Farms, Double Shell Tank Farms, 242-A Evaporator-Crystallizer, 242-S, T Evaporators, Liquid Effluent Retention Facility (LERF), Purgewater Storage Facility (PWSF), and all interconnecting piping, valves, instrumentation, and controls. Also included is all piping, valves, instrumentation, and controls up to and including the most remote valve under Tank Farms control at any other Hanford Facility having an interconnection with Tank Farms. The boundary of the structures, systems, components, and programs to which this RID applies, is defined by those that are dedicated to and/or under the control of the Tank Farms Operations Department and are specifically implemented at the Tank Farms.

  12. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 4

    International Nuclear Information System (INIS)

    1994-04-01

    Radiation protection of personnel and the public is accomplished by establishing a well defined Radiation Protection Organization to ensure that appropriate controls on radioactive materials and radiation sources are implemented and documented. This Requirements Identification Document (RID) applies to the activities, personnel, structures, systems, components, and programs involved in executing the mission of the Tank Farms. The physical boundaries within which the requirements of this RID apply are the Single Shell Tank Farms, Double Shell Tank Farms, 242-A Evaporator-Crystallizer, 242-S, T Evaporators, Liquid Effluent Retention Facility (LERF), Purgewater Storage Facility (PWSF), and all interconnecting piping, valves, instrumentation, and controls. Also included is all piping, valves, instrumentation, and controls up to and including the most remote valve under Tank Farms control at any other Hanford Facility having an interconnection with Tank Farms. The boundary of the structures, systems, components, and programs to which this RID applies, is defined by those that are dedicated to and/or under the control of the Tank Farms Operations Department and are specifically implemented at the Tank Farms

  13. Monitoring requirements for assessment of internal dose

    International Nuclear Information System (INIS)

    Eckerman, K.F.

    1985-01-01

    Data obtained by routine personnel monitoring is usually not a sufficient basis for estimation of dose. Collected data must be interpreted carefully and supplemented with appropriate information before reasonably accurate estimates of dose (i.e., accurate enough to indicate whether or nor personnel are exposed in excess of recommended limits) can be developed. When the exposure is of sufficient magnitude that a rather precise estimate of dose is needed, the health physicist will bring to bear on the problem other, more refined, methods of dosimetry. These might include a reconstruction of the incident and, for internal emitters, an extensive series of in vivo measurements or analyses of excreta. Thus, cases of special significance must often be evaluated using techniques and resources beyond those routinely employed. This is not a criticism of most routine monitoring programs. These programs are usually carefully designed in a manner commensurate with the degree of exposure routinely encountered and the requirement of a practical program of radiation protection. 10 refs

  14. Development of the Quality of Australian Nursing Documentation in Aged Care (QANDAC) instrument to assess paper-based and electronic resident records.

    Science.gov (United States)

    Wang, Ning; Björvell, Catrin; Hailey, David; Yu, Ping

    2014-12-01

    To develop an Australian nursing documentation in aged care (Quality of Australian Nursing Documentation in Aged Care (QANDAC)) instrument to measure the quality of paper-based and electronic resident records. The instrument was based on the nursing process model and on three attributes of documentation quality identified in a systematic review. The development process involved five phases following approaches to designing criterion-referenced measures. The face and content validities and the inter-rater reliability of the instrument were estimated using a focus group approach and consensus model. The instrument contains 34 questions in three sections: completion of nursing history and assessment, description of care process and meeting the requirements of data entry. Estimates of the validity and inter-rater reliability of the instrument gave satisfactory results. The QANDAC instrument may be a useful audit tool for quality improvement and research in aged care documentation. © 2013 ACOTA.

  15. RELAP-7 Software Verification and Validation Plan - Requirements Traceability Matrix (RTM) Part 2: Code Assessment Strategy, Procedure, and RTM Update

    Energy Technology Data Exchange (ETDEWEB)

    Yoo, Jun Soo [Idaho National Lab. (INL), Idaho Falls, ID (United States); Choi, Yong Joon [Idaho National Lab. (INL), Idaho Falls, ID (United States); Smith, Curtis Lee [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-09-01

    This document addresses two subjects involved with the RELAP-7 Software Verification and Validation Plan (SVVP): (i) the principles and plan to assure the independence of RELAP-7 assessment through the code development process, and (ii) the work performed to establish the RELAP-7 assessment plan, i.e., the assessment strategy, literature review, and identification of RELAP-7 requirements. Then, the Requirements Traceability Matrices (RTMs) proposed in previous document (INL-EXT-15-36684) are updated. These RTMs provide an efficient way to evaluate the RELAP-7 development status as well as the maturity of RELAP-7 assessment through the development process.

  16. Model documentation of assessment and nursing diagnosis in the practice of nursing care management for nursing students

    OpenAIRE

    A. Aziz Alimul Hidayat; M. Kes

    2015-01-01

    Model documentation of assessment and nursing diagnosis in the practice of nursing care management is an integration model in nursing care records, especially records nursing assessment and diagnosis in one format. This model can reduce the duration of the recording in nursing care, and make it easier for students to understand the nursing diagnosis, so that nursing interventions more effective. The purpose of this paper was to describes the form integration documentation of nursing assessmen...

  17. Assessment model validity document - HYDRASTAR. A stochastic continuum program for groundwater flow

    Energy Technology Data Exchange (ETDEWEB)

    Gylling, B. [Kemakta Konsult AB, Stockholm (Sweden); Eriksson, Lars [Equa Simulation AB, Sundbyberg (Sweden)

    2001-12-01

    The prevailing document addresses validation of the stochastic continuum model HYDRASTAR designed for Monte Carlo simulations of groundwater flow in fractured rocks. Here, validation is defined as a process to demonstrate that a model concept is fit for its purpose. Preferably, the validation is carried out by comparison of model predictions with independent field observations and experimental measurements. In addition, other sources can also be used to confirm that the model concept gives acceptable results. One method is to compare results with the ones achieved using other model concepts for the same set of input data. Another method is to compare model results with analytical solutions. The model concept HYDRASTAR has been used in several studies including performance assessments of hypothetical repositories for spent nuclear fuel. In the performance assessments, the main tasks for HYDRASTAR have been to calculate groundwater travel time distributions, repository flux distributions, path lines and their exit locations. The results have then been used by other model concepts to calculate the near field release and far field transport. The aim and framework for the validation process includes describing the applicability of the model concept for its purpose in order to build confidence in the concept. Preferably, this is made by comparisons of simulation results with the corresponding field experiments or field measurements. Here, two comparisons with experimental results are reported. In both cases the agreement was reasonably fair. In the broader and more general context of the validation process, HYDRASTAR results have been compared with other models and analytical solutions. Commonly, the approximation calculations agree well with the medians of model ensemble results. Additional indications that HYDRASTAR is suitable for its purpose were obtained from the comparisons with results from other model concepts. Several verification studies have been made for

  18. Assessment of Performance-based Requirements for Structural Design

    DEFF Research Database (Denmark)

    Hertz, Kristian Dahl

    2005-01-01

    and for a detailed assessment of the requirements. The design requirements to be used for a factory producing elements for industrial housing for unknown costumers are discussed, and a fully developed fire is recommended as a common requirement for domestic houses, hotels, offices, schools and hospitals. In addition...

  19. The advanced scenario analysis for performance assessment of geological disposal. Pt. 3. Main document

    International Nuclear Information System (INIS)

    Ohkubo, Hiroo

    2004-02-01

    In 'H12 Project to Establish Technical Basis for HLW Disposal in Japan' an approach that is based on an international consensus was adopted to develop scenarios to be considered in performance assessment. Adequacy of the approach was, in general term, appreciated through the peer review. However it was also suggested that there are issues related to improving transparency and traceability of the procedure. Therefore, in the current financial year, in the first place a scenario development methodology was constructed taking into account the requirements identified last year. Furthermore a practical work-frame was developed to support the activities related to the scenario development. This work-frame was applied to an example scenario to check its applicability and identify issues for further research. Secondly, scenario analysis method with regard to perturbation scenario has been studied. First of all, a survey of perturbation scenario discussed in different countries has been carried out and its assessment has been examined. Especially, in Japan, technical information has been classified in order to assess three scenarios, which are seismic activity, faulting and igneous activity. Then, on the basis of assumed occurrence pattern and influence pattern for each perturbation scenario, variant type that should be considered in this analysis has been identified, and the concept of treatment, modeling data and requirements have been clarified. As a result of these researches, a future direction for advanced scenario analysis on performance assessment has been indicated, as well as associated issues to be discussed have been clarified. (author)

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

    International Nuclear Information System (INIS)

    Jones, G.

    2013-01-01

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

  1. NRC review of Electric Power Research Institute's advanced light water reactor utility requirements document. Passive plant designs, chapter 1, project number 669

    International Nuclear Information System (INIS)

    1994-08-01

    The Electric Power Research Institute (EPRI) is preparing a compendium of technical requirements, referred to as the open-quotes Advanced Light Water Reactor [ALWR] Utility Requirements Documentclose quotes, that is acceptable to the design of an ALWR power plant. When completed, this document is intended to be a comprehensive statement of utility requirements for the design, construction, and performance of an ALWR power plant for the 1990s and beyond. The Requirements Document consists of three volumes. Volume 1, open-quotes ALWR Policy and Summary of Top-Tier Requirementsclose quotes, is a management-level synopsis of the Requirements Document, including the design objectives and philosophy, the overall physical configuration and features of a future nuclear plant design, and the steps necessary to take the proposed ALWR design criteria beyond the conceptual design state to a completed, functioning power plant. Volume II consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant [approximately 1350 megawatts-electric (MWe)]. Volume III contains utility design requirements for nuclear plants for which passive features will be used in their designs (approximately 600 MWe). In April 1992, the staff of the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, issued Volume 1 and Volume 2 (Parts 1 and 2) of its safety evaluation report (SER) to document the results of its review of Volumes 1 and 2 of the Requirements Document. Volume 1, open-quotes NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document - Program Summaryclose quotes, provided a discussion of the overall purpose and scope of the Requirements Document, the background of the staff's review, the review approach used by the staff, and a summary of the policy and technical issues raised by the staff during its review

  2. NRC review of Electric Power Research Institute's advanced light water reactor utility requirements document. Passive plant designs, chapters 2-13, project number 669

    International Nuclear Information System (INIS)

    1994-08-01

    The Electric Power Research Institute (EPRI) is preparing a compendium of technical requirements, referred to as the open-quotes Advanced Light Water Reactor [ALWR] Utility Requirements Documentclose quotes, that is acceptable to the design of an ALWR power plant. When completed, this document is intended to be a comprehensive statement of utility requirements for the design, construction, and performance of an ALWR power plant for the 1990s and beyond. The Requirements Document consists of three volumes. Volume I, open-quotes ALWR Policy and Summary of Top-Tier Requirementsclose quotes, is a management-level synopsis of the Requirements Document, including the design objectives and philosophy, the overall physical configuration and features of a future nuclear plant design, and the steps necessary to take the proposed ALWR design criteria beyond the conceptual design state to a completed, functioning power plant. Volume II consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant [approximately 1350 megawatts-electric (MWe)]. Volume III contains utility design requirements for nuclear plants for which passive features will be used in their designs (approximately 600 MWe). In April 1992, the staff of the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, issued Volume 1 and Volume 2 (Parts 1 and 2) of its safety evaluation report (SER) to document the results of its review of Volumes 1 and 2 of the Requirements Document. Volume 1, open-quotes NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document - Program Summaryclose quotes, provided a discussion of the overall purpose and scope of the Requirements Document, the background of the staff's review, the review approach used by the staff, and a summary of the policy and technical issues raised by the staff during its review

  3. A retrospective quality assessment of pre-hospital emergency medical documentation in motor vehicle accidents in south-eastern Norway

    Directory of Open Access Journals (Sweden)

    Staff Trine

    2011-03-01

    Full Text Available Abstract Background Few studies have evaluated pre-hospital documentation quality. We retrospectively assessed emergency medical service (EMS documentation of key logistic, physiologic, and mechanistic variables in motor vehicle accidents (MVAs. Methods Records from police, Emergency Medical Communication Centers (EMCC, ground and air ambulances were retrospectively collected for 189 MVAs involving 392 patients. Documentation of Glasgow Coma Scale (GCS, respiratory rate (RR, and systolic blood pressure (SBP was classified as exact values, RTS categories, clinical descriptions enabling post-hoc inference of RTS categories, or missing. The distribution of values of exact versus inferred RTS categories were compared (Chi-square test for trend. Results 25% of ground and 11% of air ambulance records were unretrieveable. Patient name, birth date, and transport destination was documented in >96% of ambulance records and 81% of EMCC reports. Only 54% of patient encounter times were transmitted to the EMCC, but 77% were documented in ground and 96% in air ambulance records. Ground ambulance records documented exact values of GCS in 48% and SBP in 53% of cases, exact RR in 10%, and RR RTS categories in 54%. Clinical descriptions made post-hoc inference of RTS categories possible in another 49% of cases for GCS, 26% for RR, and 20% for SBP. Air ambulance records documented exact values of GCS in 89% and SBP in 84% of cases, exact RR in 7% and RR RTS categories in 80%. Overall, for lower RTS categories of GCS, RR and SBP the proportion of actual documented values to inferred values increased (All: p Conclusion EMS documentation of logistic and mechanistic variables was adequate. Patient physiology was frequently documented only as descriptive text. Our finding indicates a need for improved procedures, training, and tools for EMS documentation. Documentation is in itself a quality criterion for appropriate care and is crucial to trauma research.

  4. Functional requirements document for NASA/MSFC Earth Science and Applications Division: Data and information system (ESAD-DIS). Interoperability, 1992

    Science.gov (United States)

    Stephens, J. Briscoe; Grider, Gary W.

    1992-01-01

    These Earth Science and Applications Division-Data and Information System (ESAD-DIS) interoperability requirements are designed to quantify the Earth Science and Application Division's hardware and software requirements in terms of communications between personal and visualization workstation, and mainframe computers. The electronic mail requirements and local area network (LAN) requirements are addressed. These interoperability requirements are top-level requirements framed around defining the existing ESAD-DIS interoperability and projecting known near-term requirements for both operational support and for management planning. Detailed requirements will be submitted on a case-by-case basis. This document is also intended as an overview of ESAD-DIs interoperability for new-comers and management not familiar with these activities. It is intended as background documentation to support requests for resources and support requirements.

  5. Assessment of effectiveness of geologic isolation systems. CIRMIS data system. Volume 1. Initialization, operation, and documentation

    International Nuclear Information System (INIS)

    Friedrichs, D.R.

    1980-01-01

    The Assessment of Effectiveness of Geologic Isolation Systems (AEGIS) Program is developing and applying the methodology for assessing the far-field, long-term post-closure safety of deep geologic nuclear waste repositories. AEGIS is being performed by Pacific Northwest Laboratory (PNL) under contract with the Office of Nuclear Waste Isolation (ONWI) for the Department of Energy (DOE). One task within AEGIS is the development of methodology for analysis of the consequences (water pathway) from loss of repository containment as defined by various release scenarios. The various input parameters required in the analysis are compiled in data systems. The data are organized and prepared by various input subroutines for use by the hydrologic and transport codes. The hydrologic models simulate the groundwater flow systems and provide water flow directions, rates, and velocities as inputs to the transport models. Outputs from the transport models are basically graphs of radionuclide concentration in the groundwater plotted against time. After dilution in the receiving surface-water body (e.g., lake, river, bay), these data are the input source terms for the dose models, if dose assessments are required. The dose models calculate radiation dose to individuals and populations. CIRMIS (Comprehensive Information Retrieval and Model Input Sequence) Data System, a storage and retrieval system for model input and output data, including graphical interpretation and display is described. This is the first of four volumes of the description of the CIRMIS Data System

  6. AMAT guidelines. Reference document for the IAEA Ageing Management Assessment Teams (AMATs)

    International Nuclear Information System (INIS)

    1999-01-01

    Effective ageing management is an important element for ensuring the safety of nuclear power plant. The IAEA Ageing Management Assessment Team (AMAT) programme provides advice and assistance to utilities or individual NPPs to strengthen and enhance the effectiveness of ageing management programs (AMPs). Such AMPs are required by an increasing number of safety utilities and implemented by an increasing number of utilities, often as a part of NPP life or life cycle management programs that involve the integration of ageing management and economic planning. The guidelines in this report are primarily intended for IAEA-led AMAT team members as a basic structure and common reference for peer reviews of AMPs

  7. Compilation of documented computer codes applicable to environmental assessment of radioactivity releases

    International Nuclear Information System (INIS)

    Hoffman, F.O.; Miller, C.W.; Shaeffer, D.L.; Garten, C.T. Jr.; Shor, R.W.; Ensminger, J.T.

    1977-04-01

    The objective of this paper is to present a compilation of computer codes for the assessment of accidental or routine releases of radioactivity to the environment from nuclear power facilities. The capabilities of 83 computer codes in the areas of environmental transport and radiation dosimetry are summarized in tabular form. This preliminary analysis clearly indicates that the initial efforts in assessment methodology development have concentrated on atmospheric dispersion, external dosimetry, and internal dosimetry via inhalation. The incorporation of terrestrial and aquatic food chain pathways has been a more recent development and reflects the current requirements of environmental legislation and the needs of regulatory agencies. The characteristics of the conceptual models employed by these codes are reviewed. The appendixes include abstracts of the codes and indexes by author, key words, publication description, and title

  8. Methodology and parameters for assessing human health effects for waste sites at the Savannah River Plant: Environmental information document

    International Nuclear Information System (INIS)

    King, C.M.; Marter, W.L.; Looney, B.B.; Pickett, J.B.

    1987-03-01

    This report provides a summary of the components of risk assessment and presents the technical basis for application of the risk evaluation process to the principal pollutants at SRP: radionuclides, toxic chemicals, and carcinogenic compounds. An extensive technical data base from the fields of radiation health physics, toxicology, and environmental sciences is required to accomplish this task. The origin and meaning of this data base is summarized for each class of contaminant and parameter values provided for use in numerical analysis of risk. The process of risk assessment is associated with uncertainties, a fact which is frequently stated in the technical literature addressing this subject. A review of risk assessment uncertainties and the limitations of predictive risk assessment are summarized. Risk estimators for each class of contaminants at the SRP have been tabulated for radionuclides, toxic chemicals, and carcinogens from the technical literature. Estimation of human health risk is not an additive process for radiation effects and chemical carcinogenesis since their respective dosimetric models are distinctly different even though the induction of cancer is reported to be the common end result. It is recommended in this report that risk estimation for radionuclides and chemical carcinogens should be tabulated separately and this recommendation has been applied in all environmental information documentation published by the Savannah River Laboratory. Impacts due to toxic chemicals in the biosphere should also be estimated as a separate entity since toxic chemical risk estimators are uniquely different and do not reflect the probability of a detrimental health effect. 23 refs., 4 figs., 13 tabs

  9. Basins 4.0 Climate Assessment Tool (Cat): Supporting Documentation and User Manual (External Review Draft)

    Science.gov (United States)

    EPA has released of the draft document solely for the purpose of pre-dissemination peer review under applicable Information Quality Guidelines (IQGs). This document has not been formally disseminated by EPA. It does not represent and should not be construed to represent any Agenc...

  10. Input data required for specific performance assessment codes

    International Nuclear Information System (INIS)

    Seitz, R.R.; Garcia, R.S.; Starmer, R.J.; Dicke, C.A.; Leonard, P.R.; Maheras, S.J.; Rood, A.S.; Smith, R.W.

    1992-02-01

    The Department of Energy's National Low-Level Waste Management Program at the Idaho National Engineering Laboratory generated this report on input data requirements for computer codes to assist States and compacts in their performance assessments. This report gives generators, developers, operators, and users some guidelines on what input data is required to satisfy 22 common performance assessment codes. Each of the codes is summarized and a matrix table is provided to allow comparison of the various input required by the codes. This report does not determine or recommend which codes are preferable

  11. Joint Improvised-Threat Defeat Agency Needs to Improve Assessment and Documentation of Counter-Improvised Explosive Device Initiatives (Redacted)

    Science.gov (United States)

    2016-08-09

    E XC E L L E N C E Joint Improvised ‑Threat Defeat Agency Needs to Improve Assessment and Documentation of Counter‑ Improvised Explosive Device...USE ONLY DODIG-2016-120 (Project No. D2015-D000AE-0222.000) │ i Results in Brief Joint Improvised ‑Threat Defeat Agency Needs to Improve Assessment and...Documentation of Counter‑ Improvised Explosive Device Initiatives Visit us at www.dodig.mil Objective Our audit objective was to determine whether

  12. Spatial patterns of land cover in the United States: a technical document supporting the Forest Service 2010 RPA Assessment

    Science.gov (United States)

    Kurt H. Riitters

    2011-01-01

    Land cover patterns inventoried from a national land cover map provide information about the landscape context and fragmentation of the Nation’s forests, grasslands, and shrublands. This inventory is required to quantify, map, and evaluate the capacities of landscapes to provide ecological goods and services sustainably. This report documents the procedures to...

  13. National projections of forest and rangeland condition indicators: a supporting technical document for the 1999 RPA assessment.

    Science.gov (United States)

    John Hof; Curtis Flather; Tony Baltic; Stephen. Davies

    1999-01-01

    The 1999 forest and rangeland condition indicator model is a set of independent econometric production functions for environmental outputs (measured with condition indicators) at the national scale. This report documents the development of the database and the statistical estimation required by this particular production structure with emphasis on two special...

  14. Uranium in Canada 1994 assessment of supply and requirements

    International Nuclear Information System (INIS)

    1994-11-01

    A summary of results of the annual assessment conducted by the Uranium Resource Appraisal Group of Natural Resources Canada. The appraisal group's mandate includes auditing the measured, indicated and inferred resources contained in Canadian uranium deposits mineable under current technological conditions in given price ranges and assessing the levels of Canadian uranium production that could by supported by these deposits. The group also relates known resources to domestic uranium requirements and export commitments. 2 tabs., 7 figs

  15. EFSA Guidance Document on the risk assessment of plant protection products on bees (Apis mellifera, Bombus spp. and solitary bees)

    NARCIS (Netherlands)

    Arnold, G.; Boesten, J.J.T.I.; Clook, M.

    2013-01-01

    The Guidance Document is intended to provide guidance for notifiers and authorities in the context of the review of plant protection products (PPPs) and their active substances under Regulation (EC) 1107/2009. The scientific opinion on the science behind the development of a risk assessment of plant

  16. 76 FR 58509 - Release of Risk and Exposure Assessment Planning Document for the Review of the National Ambient...

    Science.gov (United States)

    2011-09-21

    ... Assessment Planning Document for the Review of the National Ambient Air Quality Standards for Lead AGENCY... available for public review the Review of the National Ambient Air Quality Standards for Lead: Risk and... and/or welfare effects in this review of the national ambient air quality standards (NAAQS) for lead...

  17. Assessment of tritium breeding requirements for fusion power reactors

    International Nuclear Information System (INIS)

    Jung, J.

    1983-12-01

    This report presents an assessment of tritium-breeding requirements for fusion power reactors. The analysis is based on an evaluation of time-dependent tritium inventories in the reactor system. The method presented can be applied to any fusion systems in operation on a steady-state mode as well as on a pulsed mode. As an example, the UWMAK-I design was analyzed and it has been found that the startup inventory requirement calculated by the present method significantly differs from those previously calculated. The effect of reactor-parameter changes on the required tritium breeding ratio is also analyzed for a variety of reactor operation scenarios

  18. Biomass Assessment. Assessment of global biomass potentials and their links to food, water, biodiversity, energy demand and economy. Inventory and analysis of existing studies. Supporting document

    International Nuclear Information System (INIS)

    Dornburg, V.; Faaij, A.; Verweij, P.; Banse, M.; Van Diepen, K.; Van Keulen, H.; Langeveld, H.; Meeusen, M.; Van de Ven, G.; Wester, F.; Alkemade, R.; Ten Brink, B.; Van den Born, G.J.; Van Oorschot, M.; Ros, J.; Smout, F.; Van Vuuren, D.; Van den Wijngaart, R.; Aiking, H.; Londo, M.; Mozaffarian, H.; Smekens, K.; Lysen, E.

    2008-01-01

    This supporting document contains the result from the inventory phase of the biomass assessment of global biomass potentials and their links to food, water, biodiversity, energy demand and economy. This study provides a comprehensive assessment of global biomass potential estimates, focusing on the various factors affecting these potentials, such as food supplies, water use, biodiversity, energy demands and agro-economics

  19. Graphics Standards in the Computer-aided Acquisition and Logistic Support (CALS) Program, Fiscal Year 1989. Volume 1. Test Requirements Document and Extended CGM (CGEM)

    Science.gov (United States)

    1990-07-01

    at the firet meng in Munich, it was foyud isthere exis•s some avedap between the stated goals of• • DG Standards and t•e CGt e SG con ded t in cumin ... stressing importance of liaison and harmonization with closely related groups; Japan - making suggestions that the NWI and Requirements Document be improved

  20. Development of a traceability analysis method based on case grammar for NPP requirement documents written in Korean language

    International Nuclear Information System (INIS)

    Yoo, Yeong Jae; Seong, Poong Hyun; Kim, Man Cheol

    2004-01-01

    Software inspection is widely believed to be an effective method for software verification and validation (V and V). However, software inspection is labor-intensive and, since it uses little technology, software inspection is viewed upon as unsuitable for a more technology-oriented development environment. Nevertheless, software inspection is gaining in popularity. KAIST Nuclear I and C and Information Engineering Laboratory (NICIEL) has developed software management and inspection support tools, collectively named 'SIS-RT.' SIS-RT is designed to partially automate the software inspection processes. SIS-RT supports the analyses of traceability between a given set of specification documents. To make SIS-RT compatible for documents written in Korean, certain techniques in natural language processing have been studied. Among the techniques considered, case grammar is most suitable for analyses of the Korean language. In this paper, we propose a methodology that uses a case grammar approach to analyze the traceability between documents written in Korean. A discussion regarding some examples of such an analysis will follow

  1. Future scenarios: a technical document supporting the Forest Service 2010 RPA Assessment

    Science.gov (United States)

    . USDA Forest Service.

    2012-01-01

    The Forest and Rangeland Renewable Resources Planning Act of 1974 (RPA) mandates a periodic assessment of the conditions and trends of the Nation's renewable resources on forests and rangelands. The RPA Assessment includes projections of resource conditions and trends 50 years into the future. The 2010 RPA Assessment used a set of future scenarios to provide a...

  2. Environmental assessments required to support nomination of sites

    International Nuclear Information System (INIS)

    Mussler, R.M.

    1984-01-01

    The Nuclear Waste Policy Act of 1982 establishes a schedule for siting the nation's first repository for nuclear waste and spent fuel. The Act assigns the primary responsibility for conducting this siting program to the Department ofEnergy. The provisions of the Act are reviewed, including six legal requirements that must be considered for each environmental assessment, each of which is discussed in detail

  3. Antimicrobial Exposure Assessment Task Force II (AEATF II) Volume 5: Governing Document for a Multi-Year Antimicrobial Chemical Exposure Monitoring Program (interim draft document with changes)

    Science.gov (United States)

    This document describes the overall scope of the AEATF II program, demonstrates the need for additional human exposure monitoring data and explains the proposed methodology for the exposure monitoring studies proposed for conduct by the AEATF II.

  4. RELAP-7 Code Assessment Plan and Requirement Traceability Matrix

    Energy Technology Data Exchange (ETDEWEB)

    Yoo, Junsoo; Choi, Yong-joon; Smith, Curtis L.

    2016-10-01

    The RELAP-7, a safety analysis code for nuclear reactor system, is under development at Idaho National Laboratory (INL). Overall, the code development is directed towards leveraging the advancements in computer science technology, numerical solution methods and physical models over the last decades. Recently, INL has also been putting an effort to establish the code assessment plan, which aims to ensure an improved final product quality through the RELAP-7 development process. The ultimate goal of this plan is to propose a suitable way to systematically assess the wide range of software requirements for RELAP-7, including the software design, user interface, and technical requirements, etc. To this end, we first survey the literature (i.e., international/domestic reports, research articles) addressing the desirable features generally required for advanced nuclear system safety analysis codes. In addition, the V&V (verification and validation) efforts as well as the legacy issues of several recently-developed codes (e.g., RELAP5-3D, TRACE V5.0) are investigated. Lastly, this paper outlines the Requirement Traceability Matrix (RTM) for RELAP-7 which can be used to systematically evaluate and identify the code development process and its present capability.

  5. 40 CFR 80.591 - What are the product transfer document requirements for additives to be used in diesel fuel?

    Science.gov (United States)

    2010-07-01

    ... Motor Vehicle Diesel Fuel; Nonroad, Locomotive, and Marine Diesel Fuel; and ECA Marine Fuel... content requirements for use in diesel motor vehicles and nonroad engines.”; or (2) For those additives... requirements for use in model year 2007 and newer diesel motor vehicles or model year 2011 and newer diesel...

  6. 78 FR 14510 - Notice of Availability of a Treatment Evaluation Document and an Environmental Assessment for...

    Science.gov (United States)

    2013-03-06

    ... crops and builds large, hard mounds that damage farm and field machinery. Imported fire ants are... regulations provide, among other things, that regulated articles requiring treatment prior to interstate...

  7. Is Your Biobank Up to Standards? A Review of the National Canadian Tissue Repository Network Required Operational Practice Standards and the Controlled Documents of a Certified Biobank.

    Science.gov (United States)

    Hartman, Victoria; Castillo-Pelayo, Tania; Babinszky, Sindy; Dee, Simon; Leblanc, Jodi; Matzke, Lise; O'Donoghue, Sheila; Carpenter, Jane; Carter, Candace; Rush, Amanda; Byrne, Jennifer; Barnes, Rebecca; Mes-Messons, Anne-Marie; Watson, Peter

    2018-02-01

    Ongoing quality management is an essential part of biobank operations and the creation of high quality biospecimen resources. Adhering to the standards of a national biobanking network is a way to reduce variability between individual biobank processes, resulting in cross biobank compatibility and more consistent support for health researchers. The Canadian Tissue Repository Network (CTRNet) implemented a set of required operational practices (ROPs) in 2011 and these serve as the standards and basis for the CTRNet biobank certification program. A review of these 13 ROPs covering 314 directives was conducted after 5 years to identify areas for revision and update, leading to changes to 7/314 directives (2.3%). A review of all internal controlled documents (including policies, standard operating procedures and guides, and forms for actions and processes) used by the BC Cancer Agency's Tumor Tissue Repository (BCCA-TTR) to conform to these ROPs was then conducted. Changes were made to 20/106 (19%) of BCCA-TTR documents. We conclude that a substantial fraction of internal controlled documents require updates at regular intervals to accommodate changes in best practices. Reviewing documentation is an essential aspect of keeping up to date with best practices and ensuring the quality of biospecimens and data managed by biobanks.

  8. Revk - a Tool for the Fulfilment of Requirements from National Rules for Tracking and Documentation of Radioactive Residual Material and Radioactive Waste

    International Nuclear Information System (INIS)

    Hartmann, B.; Haeger, M.; Gruendler, D.

    2006-01-01

    According to the German Radiation Protection Ordinance treatment, storage, whereabouts of radioactive material etc. have to be documented. Due to legal requirements an electronic documentation system for radioactive waste has to be installed. Within the framework of the currently largest decommissioning project of nuclear facilities by Energiewerke Nord GmbH, a material flow-waste tracking and control system (ReVK) has been developed, tailored to the special needs of the decommissioning of nuclear facilities. With this system it is possible to record radioactive materials which can be released after treatment or decay storage for restricted and unrestricted utilization. Radioactive waste meant for final storage can be registered and documented as well. Based on ORACLE, ReVK is a client/server data base system with the following modules: 1. data registration, 2. transport management, 3. waste tracking, 4. storage management, 5. container management, 6. reporting, 7. activity calculation, 8. examination of technical acceptance criteria for storages and final repositories. Furthermore ReVK provides a multitude of add-ons to meet special user needs, which enlarge the spectrum of application enormously. ReVK is validated and qualified, accepted by experts and authorities and fulfils the requirements for a radioactive waste documentation system. (authors)

  9. Uranium in Canada: 1980 assessment of supply and requirements

    International Nuclear Information System (INIS)

    1981-09-01

    This seventh annual assessment of Canada's uranium resources uses two price ranges: (a) up to $135/kg U and (b) from $135 to $200/kg U (Canadian dollars). Canada has measured reserves of 73000 tonnes U, indicated reserves of 185000 tonnes, and inferred reserves of 315000 tonnes U contained in mineable ore and recoverable at a cost of less than $200/kg U. The total of these three categories is 14000 tonnes less than in 1979. Of the total reserve about 18 percent will be needed to provide the 30-year fuelling requirements for the domestic nuclear program. Domestic utilities are required by federal law to contract for their forward 15-year fuelling requirements which, for the present capacity, amount to 31000 tonnes U. In 1980 Canada had seven uranium operations which in total produced 7145 tonnes U. These primary producers employed 6068 people. Annual primary production capability could grow from 8400 tonnes U in 1981 to 15000 tonnes in the mid-1980s. Prognosticated resources mineable at prices of $200/kg U or less are estimated to contain 445000 tonnes U; speculative resources in areas assessed during 1980 are thought to contain between 1.2 and 1.4 million tonnes. Uranium exploration expenditures in 1980 were an estimated $128 million. Exploration drilling and surface development drilling were 503300 metres, more than 70 percent of which was in Saskatchewan

  10. Risk assessment guidance document for the UMTRA project groundwater remediation phase

    International Nuclear Information System (INIS)

    1992-05-01

    The purpose of the groundwater remedial activities at the Uranium Mill Tailings Remedial Action (UMTRA) sites is to reduce, control, or eliminate risks to human health and the environment. This is in accordance with Subpart B of 40 CFR 192. According to this regulation, the need for groundwater restoration is based upon US Environmental Protection Agency (EPA)-defined groundwater cleanup standards and must be consistent with the National Environmental Policy Act (NEPA) process. Risk assessments will be used in the UMTRA Groundwater Program to aid in the evaluation of sites. Risk assessments are conducted for four purposes: (1) Preliminary risk assessments are used to aid in prioritizing sites, scope data collection, end determine if a site presents immediate health risks. (2) Baseline risk assessments provide a comprehensive integration and interpretation of demographic, geographic, physical, chemical, and biological factors at a site to determine the extent of actual or potential harm. This information Is used to determine the need for remedial action. (3) Risk evaluation of remedial alternatives is performed to evaluate risks to humans or the environment associated with the various remedial strategies. (4) After remediation, an evaluation of residual risks is conducted. The information gathered for each of these risk evaluations is used to determine the need for subsequent evaluation. Several sites may be eliminated after a preliminary risk assessment if there is no current or future threat to humans or the environment. Likewise, much of the data from a baseline risk assessment can be used to support alternate concentration limits or supplemental standards demonstrations, or identify sensitive habitats or receptors that may be of concern in selecting a remedy

  11. Licensing assessment of the CANDU pressurized heavy water reactor. Volume I. Preliminary safety information document

    International Nuclear Information System (INIS)

    1977-06-01

    The PHWR design contains certain features that will require significant modifications to comply with USNRC siting and safety requirements. The most significant of these features are the reactor vessel; control systems; quality assurance program requirements; seismic design of structures, systems and components; and providing an inservice inspection program capability. None of these areas appear insolvable with current state-of-the-art engineering or with upgrading of the quality assurance program for components constructed outside of the USA. In order to be licensed in the U. S., the entire reactor assembly would have to be redesigned to comply with ASME Boiler and Pressure Vessel Code, Section III, Division 1 and Division 2. A summary matrix at the end of this volume identifies compliance of the systems and structures of the PHWR plant with the USNRC General Design Criteria. The matrix further identifies the estimated incremental cost to a 600 MWe PHWR that would be required to license the plant in the U. S. Further, the matrix identifies whether or not the incremental licensing cost is size dependent and the relative percentage of the base direct cost of a Canadian sited plant

  12. Licensing assessment of the Candu Pressurized Heavy Water Reactor. Preliminary safety information document. Volume II

    International Nuclear Information System (INIS)

    1977-06-01

    ERDA has requested United Engineers and Constructors (UE and C) to evaluate the design of the Canadian natural uranium fueled, heavy water moderated (CANDU) nuclear reactor power plant to assess its conformance with the licensing criteria and guidelines of the U.S. Nuclear Regulatory Commission (USNRC) for light water reactors. This assessment was used to identify cost significant items of nonconformance and to provide a basis for developing a detailed cost estimate for a 1140 MWe, 3-loop Pressurized Heavy Water Reactor (PHWR) located at the Middletown, USA Site

  13. Assessment of produced water contaminated soils to determine remediation requirements

    International Nuclear Information System (INIS)

    Clodfelter, C.

    1995-01-01

    Produced water and drilling fluids can impact the agricultural properties of soil and result in potential regulatory and legal liabilities. Produced water typically is classified as saline or a brine and affects surface soils by increasing the sodium and chloride content. Sources of produced water which can lead to problems include spills from flowlines and tank batteries, permitted surface water discharges and pit areas, particularly the larger pits including reserve pits, emergency pits and saltwater disposal pits. Methods to assess produced water spills include soil sampling with various chemical analyses and surface geophysical methods. A variety of laboratory analytical methods are available for soil assessment which include electrical conductivity, sodium adsorption ratio, cation exchange capacity, exchangeable sodium percent and others. Limiting the list of analytical parameters to reduce cost and still obtain the data necessary to assess the extent of contamination and determine remediation requirements can be difficult. The advantage to using analytical techniques is that often regulatory remediation standards are tied to soil properties determined from laboratory analysis. Surface geophysical techniques can be an inexpensive method to rapidly determine the extent and relative magnitude of saline soils. Data interpretations can also provide an indication of the horizontal as well as the vertical extent of impacted soils. The following discussion focuses on produced water spills on soil and assessment of the impacted soil. Produced water typically contains dissolved hydrocarbons which are not addressed in this discussion

  14. Continuous Release-Emergency Response Notification System and Priority Assessment Model: Model documentation

    International Nuclear Information System (INIS)

    1991-01-01

    The purpose of the model documentation is to provide a detailed description of the modeling and risk analysis procedures used in CR-ERNS/PAM to assist OSCs and other Superfund decision-makers in interpreting the system results. PAM is a screening-level model; to properly interpret PAM's outputs, the user must understand the limitations and uncertainties in the equations and data used to generate these results. Chapter 2 presents the system's fate and transport models and describes the assumptions associated with these equations. Chapter 3 describes PAM's auxiliary data bases and provides the source(s) of each parameter and the methods by which values were selected. Chapter 4 explains the methods and exposure assumptions used to estimate exposures to hazardous substances and to evaluate the risks and hazards associated with these exposures. Chapter 5 presents examples of reports generated by PAM and explains the meaning of the 'flags' assigned to hazardous substances, media, and facilities. Appendix A contains versions of the fate and transport equations used for radionuclides. Appendix B contains copies of PAM's reports

  15. Outdoor recreation trends and futures: a technical document supporting the Forest Service 2010 RPA Assessment

    Science.gov (United States)

    H. Ken Cordell

    2012-01-01

    This publication presents a national study of outdoor recreation trends as part of the Renewable Resources Planning Act Assessment by the Forest Service, U.S. Department of Agriculture. The objectives are to review past trends in outdoor recreation participation by Americans, to describe in detail current outdoor recreation participation patterns, and to compare...

  16. U.S. forest products module : a technical document supporting the Forest Service 2010 RPA Assessment

    Science.gov (United States)

    Peter J. Ince; Andrew D. Kramp; Kenneth E. Skog; Henry N. Spelter; David N. Wear

    2011-01-01

    The U.S. Forest Products Module (USFPM) is a partial market equilibrium model of the U.S. forest sector that operates within the Global Forest Products Model (GFPM) to provide long-range timber market projections in relation to global economic scenarios. USFPM was designed specifically for the 2010 RPA forest assessment, but it is being used also in other applications...

  17. Tank 241-AY-102 Leak Assessment Supporting Documentation: Miscellaneous Reports, Letters, Memoranda, And Data

    International Nuclear Information System (INIS)

    Engeman, J. K.; Girardot, C. L.; Harlow, D. G.; Rosenkrance, C. L.

    2012-01-01

    This report contains reference materials cited in RPP-ASMT -53793, Tank 241-AY-102 Leak Assessment Report, that were obtained from the National Archives Federal Records Repository in Seattle, Washington, or from other sources including the Hanford Site's Integrated Data Management System database (IDMS)

  18. Tank 241-AY-102 Leak Assessment Supporting Documentation: Miscellaneous Reports, Letters, Memoranda, And Data

    Energy Technology Data Exchange (ETDEWEB)

    Engeman, J. K.; Girardot, C. L.; Harlow, D. G.; Rosenkrance, C. L.

    2012-12-20

    This report contains reference materials cited in RPP-ASMT -53793, Tank 241-AY-102 Leak Assessment Report, that were obtained from the National Archives Federal Records Repository in Seattle, Washington, or from other sources including the Hanford Site's Integrated Data Management System database (IDMS).

  19. Probabilistic risk assessment course documentation. Volume 7. Environmental transport and consequence analysis

    International Nuclear Information System (INIS)

    Ritchie, L.T.; Alpert, D.J.; Burke, R.P.; Ostmeyer, R.M.; Kaiser, G.D.; Runkle, G.E.; Woodard, K.

    1985-08-01

    Consequence models have been designed to assess health and economic risks from potential accidents at nuclear power plants. These models have been applied to an ever increasing variety of problems with ever increasing demands to improve modeling capabilities and provide greater realism. This course discusses the environmental transport of postulated radiological releases and the elements and purpose of accident consequence evaluation

  20. English Language Assessment in the Colleges of Applied Sciences in Oman: Thematic Document Analysis

    Science.gov (United States)

    Al Hajri, Fatma

    2014-01-01

    Proficiency in English language and how it is measured have become central issues in higher education research as the English language is increasingly used as a medium of instruction and a criterion for admission to education. This study evaluated the English language assessment in the foundation Programme at the Colleges of Applied sciences in…

  1. Ground Validation Assessments of GPM Core Observatory Science Requirements

    Science.gov (United States)

    Petersen, Walt; Huffman, George; Kidd, Chris; Skofronick-Jackson, Gail

    2017-04-01

    NASA Global Precipitation Measurement (GPM) Mission science requirements define specific measurement error standards for retrieved precipitation parameters such as rain rate, raindrop size distribution, and falling snow detection on instantaneous temporal scales and spatial resolutions ranging from effective instrument fields of view [FOV], to grid scales of 50 km x 50 km. Quantitative evaluation of these requirements intrinsically relies on GPM precipitation retrieval algorithm performance in myriad precipitation regimes (and hence, assumptions related to physics) and on the quality of ground-validation (GV) data being used to assess the satellite products. We will review GPM GV products, their quality, and their application to assessing GPM science requirements, interleaving measurement and precipitation physical considerations applicable to the approaches used. Core GV data products used to assess GPM satellite products include 1) two minute and 30-minute rain gauge bias-adjusted radar rain rate products and precipitation types (rain/snow) adapted/modified from the NOAA/OU multi-radar multi-sensor (MRMS) product over the continental U.S.; 2) Polarimetric radar estimates of rain rate over the ocean collected using the K-Pol radar at Kwajalein Atoll in the Marshall Islands and the Middleton Island WSR-88D radar located in the Gulf of Alaska; and 3) Multi-regime, field campaign and site-specific disdrometer-measured rain/snow size distribution (DSD), phase and fallspeed information used to derive polarimetric radar-based DSD retrievals and snow water equivalent rates (SWER) for comparison to coincident GPM-estimated DSD and precipitation rates/types, respectively. Within the limits of GV-product uncertainty we demonstrate that the GPM Core satellite meets its basic mission science requirements for a variety of precipitation regimes. For the liquid phase, we find that GPM radar-based products are particularly successful in meeting bias and random error requirements

  2. Asphalt Concrete Mixtures: Requirements with regard to Life Cycle Assessment

    Directory of Open Access Journals (Sweden)

    Jan Mikolaj

    2015-01-01

    Full Text Available Design of asphalt concrete, required properties of constituent materials and their mixing ratios, is of tremendous significance and should be implemented with consideration given to the whole life cycle of those materials and the final construction. Conformity with requirements for long term performance of embedded materials is the general objective of the Life Cycle Assessment (LCA. Therefore, within the assessment, material properties need to be evaluated with consideration given to the whole service life—from the point of embedding in the construction until their disposal or recycling. The evaluation focuses on verification of conformity with criteria set for these materials and should guarantee serviceability and performance during their whole service life. Recycling and reuse of asphalt concrete should be preferred over disposal of the material. This paper presents methodology for LCA of asphalt concrete. It was created to ensure not only applicability of the materials in the initial stage, at the point of their embedding, but their suitability in terms of normatively prescribed service performance of the final construction. Methods described and results are presented in a case study for asphalt mixture AC 11; I design.

  3. Photographic Documentation and Hand Eczema Severity Index for Severity Assessment of Hand Eczema

    DEFF Research Database (Denmark)

    Zabludovska, Kristine; Ibler, Kristina S; Jemec, Gregor B E

    2017-01-01

    .003), respectively, and major worsening, r = 0.41 (P = 0.021). With respect to minor changes, no statistically significant correlations were found (P > 0.05). CONCLUSIONS: In patients with mild HE, photographic assessment was found useful for major and moderate changes only. Further studies would need......BACKGROUND: Hand eczema (HE) is a fluctuating disease, and an objective assessment of HE severity is coveted. OBJECTIVES: This study was undertaken to test the association between Hand Eczema Severity Index (HECSI) score and panel scores of photographs taken by dermatologists. METHODS: A total...... were engaged in blinded evaluation of photographs. RESULTS: The highest correlation coefficients between delta HECSI scores and delta panel scores of photographs in the first and second evaluation rounds were found for moderate improvement and moderate worsening, rs = -0.46 (P = 0.009) and 0.52 (P = 0...

  4. Influence of pulmonary emphysema on COPD assessment test-oriented categorization in GOLD document.

    Science.gov (United States)

    Suzuki, Toshio; Tada, Yuji; Kawata, Naoko; Ikari, Jun; Kasahara, Yasunori; Sakurai, Yoriko; Iesato, Ken; Nishimura, Rintaro; West, James; Tatsumi, Koichiro

    2015-01-01

    The COPD assessment test (CAT) score is a key component of the multifactorial assessment of COPD in the Global initiative for chronic Obstructive Lung Disease (GOLD) guidelines of 2014. Nevertheless, little is known regarding the differences among COPD categories in terms of clinical parameters such as pulmonary function or radiological findings. Thus, our aims in this study were to evaluate the associations between CAT scores and pulmonary clinical parameters, and to investigate factors that could discriminate between a "less symptomatic group" (categories A and C) and a "more symptomatic group" (categories B and D) among stable COPD patients. We enrolled 200 outpatients at Chiba University Hospital. Study subjects were assessed by CAT, pulmonary function testing, and multidetector computed tomography (MDCT). We assessed possible correlations between these indices. CAT scores were negatively correlated with percentage of the forced expiratory volume in 1 second predicted value (FEV1 %predicted) and percentage of the diffusing capacity for carbon monoxide per liter of lung volume predicted value (DLCO/VA [%predicted]) results and positively correlated with low attenuation volume percentage (LAV%) and residual volume to total lung capacity ratios (RV/TLC). In the "more symptomatic group" (category B or D), the mean DLCO/VA (%predicted) was significantly lower and the mean LAV% and RV/TLC was significantly higher than those in the "less symptomatic group" (category A or C), respectively. Interestingly, those in category B had higher mean LAV% compared to those in category C. CAT scores were significantly correlated with pulmonary function parameters and emphysematous changes on MDCT. The new GOLD classification system would be a step toward a phenotypic approach, especially taking into account the degree of emphysema and hyperinflation.

  5. Quality assurance program for environmental assessment of Savannah River Plant waste sites: Environmental information document

    International Nuclear Information System (INIS)

    Looney, B.B.; King, C.M.; Stephenson, D.E.

    1987-03-01

    Forty-eight locations were identified that received a variety of radioactive and nonradioactive constituents during the past 35 years including surface impoundments and shallow land burial facilities. Detailed environmental assessments of existing waste disposal areas, as well as new waste disposal techniques and disposition of tritiated water, were completed to air in an evaluation of the low level, mixed and hazardous waste management activities. These assessments result in estimation of risk, or residual risk, posed by each disposal area to various receptors as a function of waste management alternative. For example, at existing waste sites, the closure actions evaluated were waste removal and closure, no waste removal and closure, and no action; several pathways/receptors were considered, including groundwater to river, groundwater to well, atmospheric transport, occupational exposure, direct exposure, and contamination followed by ingestion of crops and meat. Modeling of chemical transport in a variety of media was an integral part of the assessment process. The quality of the models used and the application of these models were assured by an explicit quality assurance program

  6. Baseline requirements for assessment of mining impact using biological monitoring

    International Nuclear Information System (INIS)

    Humphrey, C.L.; Dostine, P.L.

    1995-01-01

    Biological monitoring programmes for environmental protection should provide for both early detection of possible adverse effects, and assessment of the ecological significance of these effects. Monitoring techniques are required that include responses sensitive to the impact, that can be subjected to rigorous statistical analysis and for which statistical power is high. Such issues in baseline research of 'what and how to measure?' and 'for how long?' have been the focus of a programme being developed to monitor and assess effects of mining operations on the essentially pristine, freshwater ecosystems of the Alligator Rivers Region (ARR) in tropical northern Australia. Application of the BACIP (Before, After, Control, Impact, Paired differences) design, utilizing a form of temporal replication, to univariate (single species) and multivariate (community) data is described. The BACIP design incorporates data from single control and impact sites. We argue for modification of the design for particular studies conducted in streams, to incorporate additional independent control sites from adjacent catchment. Inferential power, by way of (i) more confidently attributing cause to an observed change and (ii) providing information about the ecological significance of the change, will be enhanced using a modified BACIP design. In highly valued environments such as the ARR, monitoring programmes require application of statistical tests with high power to guarantee that an impact no greater than a prescribed amount has gone undetected. A minimum number of baseline years using the BACIP approach would therefore be required in order to achieve some desired level of statistical power. This paper describes the results of power analyses conducted on 2-5 years (depending upon the technique) of baseline data from streams of the ARR and discuss the implications of these results for management. 44 refs., 1 tab., 3 figs

  7. Probabilistic risk assessment course documentation. Volume 3. System reliability and analysis techniques, Session A - reliability

    International Nuclear Information System (INIS)

    Lofgren, E.V.

    1985-08-01

    This course in System Reliability and Analysis Techniques focuses on the quantitative estimation of reliability at the systems level. Various methods are reviewed, but the structure provided by the fault tree method is used as the basis for system reliability estimates. The principles of fault tree analysis are briefly reviewed. Contributors to system unreliability and unavailability are reviewed, models are given for quantitative evaluation, and the requirements for both generic and plant-specific data are discussed. Also covered are issues of quantifying component faults that relate to the systems context in which the components are embedded. All reliability terms are carefully defined. 44 figs., 22 tabs

  8. macro-economic assessment of energy visions 2030-2050 by the ADEME - Technical document

    International Nuclear Information System (INIS)

    Callonnec, G.; Landa, G.; Maillet, P.; Reynes, F.

    2013-10-01

    After a brief presentation of the energy transition scenario designed by the ADEME and which is based on principles of efficiency and sobriety, and on a largely de-carbonated energy supply, this report presents the ThreeME model (ThreeME stands for macro-economic multi-sector model of assessment of energy and environment policies). It is a neo-Keynesian model which integrates a dynamic interaction between supply and demand. The application of this model to energy transition is discusses as well as the model calibration. Results are then discussed (reference scenario, modelling of the ADEME scenario) and expansionary effects are outlined in terms of household purchasing power, investment, employment, reduction of trade balance deficit, induced effects on GDP, shadow value of carbon, and public finances

  9. Estimation of geochemical parameters for assessing subsurface transport at the Savannah River Plant: Environmental information document

    International Nuclear Information System (INIS)

    Looney, B.B.; Grant, M.W.; King, C.M.

    1987-03-01

    Geochemical parameter estimates to be used in assessing the subsurface transport of chemicals from Savannah River Plant (SRP) waste sites are presented. Specifically, reference values for soil-solution distribution coefficients, solubility, leach rates, and retardation coefficients are estimated for 31 inorganic chemicals (assuming speciation is governed by reasonable assumptions about controlling variables such as Eh and pH) and 36 organic compounds. Additionally, facilitated transport (the association of chemicals with inorganic and organic ligands or colloids resulting in relatively high mobility) was estimated using field data to derive a fraction of the disposal mass which was assumed to be mobile. Hydrologic parameters such as dispersion coefficient, average moisture content in vadose zone, bulk density, and effective porosity are also presented. The estimates are based on site-specific studies when available, combined with technical literature

  10. Strategic environmental assessment in tourism planning - Extent of application and quality of documentation

    Energy Technology Data Exchange (ETDEWEB)

    Carvalho Lemos, Clara, E-mail: clara@sc.usp.br [Environmental Engineering Science, Engineering School of Sao Carlos, University of Sao Paulo, Av. Trabalhador Saocarlense, 400, Caixa Postal 292, Sao Carlos, Sao Paulo, 13566-590 (Brazil); Fischer, Thomas B., E-mail: fischer@liverpool.ac.uk [Department of Civic Design, University of Liverpool, 74 Bedford Street South, Liverpool, L69 7ZQ (United Kingdom); Pereira Souza, Marcelo, E-mail: mps@usp.br [Environmental Engineering Science, Engineering School of Sao Carlos, University of Sao Paulo, Av. Trabalhador Saocarlense, 400, Caixa Postal 292, Sao Carlos, Sao Paulo, 13566-590 (Brazil)

    2012-07-15

    Strategic environmental assessment (SEA) has been applied throughout the world in different sectors and in various ways. This paper reports on results of a PhD research on SEA applied to tourism development planning, reflecting the situation in mid-2010. First, the extent of tourism specific SEA application world-wide is established. Then, based on a review of the quality of 10 selected SEA reports, good practice, as well as challenges, trends and opportunities for tourism specific SEA are identified. Shortcomings of SEA in tourism planning are established and implications for future research are outlined. - Highlights: Black-Right-Pointing-Pointer The extent of tourism specific SEA practice is identified. Black-Right-Pointing-Pointer Selected SEA/Tourism reports are evaluated. Black-Right-Pointing-Pointer SEA application to tourism planning is still limited. Black-Right-Pointing-Pointer A number of shortcomings can be pointed out.

  11. Strategic environmental assessment in tourism planning — Extent of application and quality of documentation

    International Nuclear Information System (INIS)

    Carvalho Lemos, Clara; Fischer, Thomas B.; Pereira Souza, Marcelo

    2012-01-01

    Strategic environmental assessment (SEA) has been applied throughout the world in different sectors and in various ways. This paper reports on results of a PhD research on SEA applied to tourism development planning, reflecting the situation in mid-2010. First, the extent of tourism specific SEA application world-wide is established. Then, based on a review of the quality of 10 selected SEA reports, good practice, as well as challenges, trends and opportunities for tourism specific SEA are identified. Shortcomings of SEA in tourism planning are established and implications for future research are outlined. - Highlights: ► The extent of tourism specific SEA practice is identified. ► Selected SEA/Tourism reports are evaluated. ► SEA application to tourism planning is still limited. ► A number of shortcomings can be pointed out.

  12. UPSAT guidelines. 1996 edition. Reference document for IAEA Uranium Productions Safety Assessment Teams (UPSATs)

    International Nuclear Information System (INIS)

    1996-05-01

    The IAEA Uranium Production Safety Assessment Team (UPSAT) programme provides advice and assistance to Member States to enhance the safety and environmental performance of uranium production facilities during construction, commissioning and operation. Sound design and construction are prerequisite for the safe and environmentally responsible operation of uranium mines and mills. However, the safety of the facility depends ultimately on sound policies, procedures and practices; on the capability and reliability of the construction, commissioning and operating personnel; on comprehensive instructions; and on adequate resources. A positive attitude and conscientiousness on the part of the management and staff in discharging their responsibilities is important to safety. The UPSAT guidelines have been developed in the following areas: (1) management, organization and administration; (2) training and qualification; (3) operation (4) maintenance; (5) safety, fire protection, emergency planning, and preparedness; (6) radiation protection; (7) environmental monitoring programme; (8) construction management; (9) commissioning and decommissioning

  13. Safety assessment document (SAD) for the Princeton Beta Experiment Modification (PBX-M)

    International Nuclear Information System (INIS)

    Stencel, J.R.; Parsells, R.F.

    1988-04-01

    The Princeton Beta Experiment-Modification (PBX-M) is an experimental device of the tokamak type. A tokamak is characterized by a strong toroidal magnetic field composed of an externally driven component parallel to the torus centerline modified by the field produced by a transformer-driven current (OH) in the confined plasma. A second magnetic field parallel to the major toroidal axis is added to provide radial equilibrium for the plasma. As an advanced tokamak, PBX-M will have additional magnetic fields to reshape the plasma cross section from a circle into a kidney bean shape; it will also be equipped with 6MW or more of auxiliary heating power provided by four neutral beam injectors, with RF systems, and with an extensive set of diagnostics. Potential hazards associated with PBX-M, which are analyzed in this report, result from energy stored in the magnetic fields, high voltages necessary for the operation of some of the equipment and diagnostics, neutron radiation when the neutral beams are run with deuterium and x-rays, especially those emitted as a result of plasma-wall interaction. This report satisfies the requirements set forth in the PPPL Health and Safety Directives, specifically HSD-5003, and in DOE Order 5481.1B and its Chicago operations supplement (DOE86, DOE82)

  14. Using the Genetics Concept Assessment to document persistent conceptual difficulties in undergraduate genetics courses.

    Science.gov (United States)

    Smith, Michelle K; Knight, Jennifer K

    2012-05-01

    To help genetics instructors become aware of fundamental concepts that are persistently difficult for students, we have analyzed the evolution of student responses to multiple-choice questions from the Genetics Concept Assessment. In total, we examined pretest (before instruction) and posttest (after instruction) responses from 751 students enrolled in six genetics courses for either majors or nonmajors. Students improved on all 25 questions after instruction, but to varying degrees. Notably, there was a subgroup of nine questions for which a single incorrect answer, called the most common incorrect answer, was chosen by >20% of students on the posttest. To explore response patterns to these nine questions, we tracked individual student answers before and after instruction and found that particular conceptual difficulties about genetics are both more likely to persist and more likely to distract students than other incorrect ideas. Here we present an analysis of the evolution of these incorrect ideas to encourage instructor awareness of these genetics concepts and provide advice on how to address common conceptual difficulties in the classroom.

  15. A workshop on developing risk assessment methods for medical use of radioactive material. Volume 2: Supporting documents

    Energy Technology Data Exchange (ETDEWEB)

    Tortorelli, J.P. [ed.] [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)

    1995-08-01

    A workshop was held at the Idaho National Engineering Laboratory, August 16--18, 1994 on the topic of risk assessment on medical devices that use radioactive isotopes. Its purpose was to review past efforts to develop a risk assessment methodology to evaluate these devices, and to develop a program plan and a scoping document for future methodology development. This report contains presentation material and a transcript of the workshop. Participants included experts in the fields of radiation oncology, medical physics, risk assessment, human-error analysis, and human factors. Staff from the US Nuclear Regulatory Commission (NRC) associated with the regulation of medical uses of radioactive materials and with research into risk-assessment methods participated in the workshop. The workshop participants concurred in NRC`s intended use of risk assessment as an important technology in the development of regulations for the medical use of radioactive material and encouraged the NRC to proceed rapidly with a pilot study. Specific recommendations are included in the executive summary and the body of this report.

  16. Evaluation of models used for the assessment of radionuclide releases to the environment: summary of documentation, April 1976-June 1979

    International Nuclear Information System (INIS)

    Kanak, K.A.; Miller, C.W.

    1980-04-01

    A project is underway at Oak Ridge National Laboratory (ORNL) to identify models available for environmental radiological assessments; to evaluate model structure simplifying assumptions and data bases; to estimate their uncertainties; and, if possible, to recommend the models and parameters that are best suited to particular assessment situations. When needs are identified, recommendations are also made for further environmental and biomedical research. The purpose of this particular report is to summarize the progress made toward the goals of this project to date. Such progress is reflected in the documents produced by the staff of the project. Therefore, this report presents a compilation of the abstracts and summaries of the Laboratory reports, open literature publications, conference proceedings, and oral presentations prepared under the auspices of this project. A total of thirty-eight different papers are represented in this collection. The models considered in these materials are those developed for the prediction of atmospheric transport and deposition, surface water transport and sorption, terrestrial and aquatic food-chain bioaccumulation, and internal dosimetry. Topics covered in the report include: (1) methods for analyzing models; (2) analysis of model input parameters; (3) model validation studies; (4) assessments of particular nuclides and processes; (5) recommendations concerning models and parameters to be used for assessment purposes; and (6) models and computer codes developed during the course of the project. This report will serve as a guide to the literature for those involved with the use and application of environmental radiation assessment models

  17. A workshop on developing risk assessment methods for medical use of radioactive material. Volume 2: Supporting documents

    International Nuclear Information System (INIS)

    Tortorelli, J.P.

    1995-08-01

    A workshop was held at the Idaho National Engineering Laboratory, August 16--18, 1994 on the topic of risk assessment on medical devices that use radioactive isotopes. Its purpose was to review past efforts to develop a risk assessment methodology to evaluate these devices, and to develop a program plan and a scoping document for future methodology development. This report contains presentation material and a transcript of the workshop. Participants included experts in the fields of radiation oncology, medical physics, risk assessment, human-error analysis, and human factors. Staff from the US Nuclear Regulatory Commission (NRC) associated with the regulation of medical uses of radioactive materials and with research into risk-assessment methods participated in the workshop. The workshop participants concurred in NRC's intended use of risk assessment as an important technology in the development of regulations for the medical use of radioactive material and encouraged the NRC to proceed rapidly with a pilot study. Specific recommendations are included in the executive summary and the body of this report

  18. Ecological effects assessment: requirements vs state-of-the-art

    International Nuclear Information System (INIS)

    McKenzie, D.H.; Thomas, J.M.; Eberhardt, L.L.

    1981-05-01

    Concerns for environmental quality, the ecologist's understanding of ecosystems, and the ability to quantitatively sample and evaluate hypotheses have contributed to current requirements and the state-of-the-art in ecological effects assessments in refard to nuclear power plants. The current cooling system approaches, data collection programs, and ecological effects assessments reflect these contributions. Over a decade of experience provides the basis for a timely review and evaluation of current proactice. The magnitude of economic and environmental resources being committed to cooling system alternatives mandates that the decision-making process result in as many optimal choices as possible. In addition, the resources being devoted to environmental data collection and integration provide considerable motivation for providing meaningful input to the decision-making process. It is maintained that the input should be as quantitative and as free from subjective content as is reasonably possible. An alternative viewpoint suggests that the past several decades of experience be considered but a first step, and the current task to be one of designing a second step

  19. Integrating electromagnetic radiation hazard info the unique occupational risk assessment document

    International Nuclear Information System (INIS)

    Demaret, P.; Donati, P.

    2011-01-01

    The number of industrial applications involving electromagnetic waves has significantly increased in recent years. These applications are likely to expose operators to electromagnetic fields exceeding the limits laid down by European Parliament and Council Directive 2004/40/CE of 29 April 2004. A survey has identified the equipment emitting the most radiation and this has been classified into 8 families: resistance welding, magnetization, induction heating, magneto-scopy, dielectric loss welding, electrolysis, magnetic resonance imagery, microwaves. The equipment numbers per family was estimated by a market surveys, which specifically identified several tens of thousands of resistance welding- or magnetization-type machines. This survey enabled us to deduce that at least 100,000 operators in France would be at risk of exposure to electromagnetic fields. An assessment of exposure levels for operators at their workstations was undertaken for each equipment family. A group comprising specialists from INRS and the 9 CARSAT/CRAM Physical Measurement Centres measured electromagnetic fields at 635 workstations fitted with radiation emitting machinery. For each measurement, a severity index corresponding to the ratio of the measured value to the action-triggering value (ATV) recommended by European Parliament and Council Directive 2004/40/CE of 29 April 2004 was calculated. The results show that, for 7 equipment families out of the 8 retained, 25 - 50% of measurements gave electromagnetic field values exceeding the corresponding ATV. These results demonstrate the need for prevention means. In most cases, exposure reduction is achieved by moving the workstation away from the radiation source. Technical solutions do exist for certain equipments, such as shielding for microwave ovens and high-frequency presses, a grounding pad for tarpaulin welding, etc. (authors)

  20. Procedural Documentation and Accuracy Assessment of Bathymetric Maps and Area/Capacity Tables for Small Reservoirs

    Science.gov (United States)

    Wilson, Gary L.; Richards, Joseph M.

    2006-01-01

    Because of the increasing use and importance of lakes for water supply to communities, a repeatable and reliable procedure to determine lake bathymetry and capacity is needed. A method to determine the accuracy of the procedure will help ensure proper collection and use of the data and resulting products. It is important to clearly define the intended products and desired accuracy before conducting the bathymetric survey to ensure proper data collection. A survey-grade echo sounder and differential global positioning system receivers were used to collect water-depth and position data in December 2003 at Sugar Creek Lake near Moberly, Missouri. Data were collected along planned transects, with an additional set of quality-assurance data collected for use in accuracy computations. All collected data were imported into a geographic information system database. A bathymetric surface model, contour map, and area/capacity tables were created from the geographic information system database. An accuracy assessment was completed on the collected data, bathymetric surface model, area/capacity table, and contour map products. Using established vertical accuracy standards, the accuracy of the collected data, bathymetric surface model, and contour map product was 0.67 foot, 0.91 foot, and 1.51 feet at the 95 percent confidence level. By comparing results from different transect intervals with the quality-assurance transect data, it was determined that a transect interval of 1 percent of the longitudinal length of Sugar Creek Lake produced nearly as good results as 0.5 percent transect interval for the bathymetric surface model, area/capacity table, and contour map products.

  1. Safety assessment document for the environmental test complex (Building 834) at Site 300

    International Nuclear Information System (INIS)

    Odell, B.N.; Pfeifer, H.E.

    1981-01-01

    A safety assessment was performed to determine if accidents occurring at the 834 Complex at Site 300 could present undue hazards to the general public, personnel at Site 300, or have an adverse effect on the environment. The credible accidents that might have an effect on these facilities or have off-site consequences were considered. These were earthquake, extreme wind (including missiles), lightning, flood, criticality, high explosive (HE) detonation that disperses uranium and beryllium, spontaneous oxidation of plutonium, explosions due to finely divided particles, and a fire. Seismic and extreme wind (including missiles) analyses indicate that the buildings are basically sound. (However, there are a few recommendations to further enhance the structural integrity of these facilities). Additional lightning protection for these facilities is being installed. These buildings are located high above the dry creek bed so that a flood is improbable. A criticality or a high explosive detonation involving plutonium is very remote since the radioactive materials are encased and plutonium and HE are not permitted concurrently in the same area at Site 300. (The exceptions to this policy are that explosive actuating devices are sometimes located in assemblies containing fissile materials. However, a planned or accidental actuation will not effect the safe containment of the fissile material within the assembly). Even though the possibility of an HE explosion involving uranium and beryllium is remote, the off-site lung doses were calculated and found to be below the accepted standards. It was determined that a fire was unlikely due to the low fire loading and the absence of ignition sources. It was also determined that the consequences of any accidents were reduced by the remote location of these facilities, their design, and by administrative controls

  2. MICE - Absorber and focus coil safety working group design document: Preliminary design and assessments

    International Nuclear Information System (INIS)

    Barr, Giles; Baynham, Elwyn; Black, Edgar; Bradshaw, Tom; Cummings, Mary Anne; Green, Michael A.; Ishimoto, Shigeru; Ivanyushenkov, Yury; Lau, Wing; Zisman, Michael

    2003-01-01

    A Neutrino Factory based on a muon storage ring is the ultimate tool for studies of neutrino oscillations, including possibly the discovery of leptonic CP violation. it is also the first step toward a muon collider. To develop a stored-muon-beam facility to serve as a Neutrino Factory, it is necessary to ''cool'' a muon beam (decrease its phase-space volume). The short lifetime of the muon, 2.2 (micro)s at rest, eliminates all currently demonstrated cooling techniques and requires that a new, heretofore untried, technique--ionization cooling--be employed. Although ionization cooling of muons has never been demonstrated in practice, it has been shown by end-to-end simulation and design studies to be an important factor both for the performance and for the cost of a Neutrino Factory. This motivates an international program of R and D, including an experimental demonstration at Rutherford Appleton Laboratory (RAL). The aims of the international Muon Ionization Cooling Experiment are: (1) to show that it is possible to design, engineer and build a section of cooling channel capable of giving the desired performance for a Neutrino Factory; and (2) to place it in a muon beam and measure its performance in various modes of operation and beam conditions, thereby investigating the limits and practicality of cooling. The MICE collaboration has designed an experiment in which a section of an ionization cooling channel is exposed to a muon beam. This cooling channel assembles liquid-hydrogen absorbers providing energy loss and high-gradient radio frequency (RF) cavities to re-accelerate the particles, all tightly contained in a magnetic channel. It reduces the beam transverse emittance by > 10% for muon momenta between 140 and 240 MeV/c. The layout of the experiment is shown. They utilize one complete magnetic cell of the cooling channel, comprising three absorber-focus-coil (AFC) modules and two RF-coupling-coil (RFCC) modules. Spectrometers placed before and after the

  3. A synoptic review of U.S. rangelands: a technical document supporting the Forest Service 2010 RPA Assessment

    Science.gov (United States)

    Matthew Clark Reeves; John E. Mitchell

    2012-01-01

    The Renewable Resources Planning Act of 1974 requires the USDA Forest Service to conduct assessments of resource conditions. This report fulfills that need and focuses on quantifying extent, productivity, and health of U.S. rangelands. Since 1982, the area of U.S. rangelands has decreased at an average rate of 350,000 acres per year owed mostly to conversion to...

  4. Screening assessment and requirements for a comprehensive assessment: Volume 1, Draft. Columbia River comprehensive impact assessment

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-04-01

    To evaluate the impact to the Columbia River from the Hanford Site-derived contaminants, the U.S. Department of Energy, U.S. Environmental Protection Agency, and Washington State Department of Ecology initiated a study referred to as the Columbia River Comprehensive Impact Assessment (CRCIA). To address concerns about the scope and direction of CRCIA as well as enhance regulator, tribal, stockholder, and public involvement, the CRCIA Management Team was formed in August 1995. The Team agreed to conduct CRCIA using a phased approach. The initial phase, includes two components: 1) a screening assessment to evaluate the potential impact to the river, resulting from current levels of Hanford-derived contaminants in order to support decisions on Interim Remedial Measures, and 2) a definition of the essential work remaining to provide an acceptable comprehensive river impact assessment. The screening assessment is described in Part I of this report. The essential work remaining is Part II of this report. The objective of the screening assessment is to identify areas where the greatest potential exists for adverse effects on humans or the environment. Part I of this report discusses the scope, technical approach, and results of the screening assessment. Part II defines a new paradigm for predecisional participation by those affected by Hanford cleanup decisions.

  5. Screening assessment and requirements for a comprehensive assessment: Volume 1, Draft. Columbia River comprehensive impact assessment

    International Nuclear Information System (INIS)

    1997-04-01

    To evaluate the impact to the Columbia River from the Hanford Site-derived contaminants, the U.S. Department of Energy, U.S. Environmental Protection Agency, and Washington State Department of Ecology initiated a study referred to as the Columbia River Comprehensive Impact Assessment (CRCIA). To address concerns about the scope and direction of CRCIA as well as enhance regulator, tribal, stockholder, and public involvement, the CRCIA Management Team was formed in August 1995. The Team agreed to conduct CRCIA using a phased approach. The initial phase, includes two components: 1) a screening assessment to evaluate the potential impact to the river, resulting from current levels of Hanford-derived contaminants in order to support decisions on Interim Remedial Measures, and 2) a definition of the essential work remaining to provide an acceptable comprehensive river impact assessment. The screening assessment is described in Part I of this report. The essential work remaining is Part II of this report. The objective of the screening assessment is to identify areas where the greatest potential exists for adverse effects on humans or the environment. Part I of this report discusses the scope, technical approach, and results of the screening assessment. Part II defines a new paradigm for predecisional participation by those affected by Hanford cleanup decisions

  6. Guideline on radiation protection in medicine requires documentation of radioiodine therapy and follow-up. What are the benefits of an electronic database?

    International Nuclear Information System (INIS)

    Koch, W.; Rosa, F.; Knesewitsch, P.; Hahn, K.

    2005-01-01

    The lately updated German guideline on radiation protection in medicine (Richtlinie Strahlenschutz in der Medizin) requires the physician who administers radioactive substances for therapy, to perform and document follows-up. In order to decrease the administrative burden, an electronic database was developed that interfaces with a word processing software to generate written reports and statistic analysis. Methods: Based on Microsoft registered Access and Microsoft registered Visual Basic a database was created to monitor patients with benign and malignant thyroid disorders after radioiodine therapy. It permits automatic creation of therapy documents and necessary patient reports in Microsoft registered Word. Intuitive handling, third level of normalization in database architecture and automatic plausibility checks guarantee integrity of the data and the efficacy of the database. Results, conclusion: The new software has been a success in over 1500 patients and over 3800 in- and outpatient therapies and visits. The effort of data entry is easily offset by the automatic generation of the necessary patient reports. The required supervision of the follow-up appointments is now also user-friendly and efficient. (orig.)

  7. Component fragility analysis methodology for seismic risk assessment projects. Proven PSA safety document processing and assessment procedures

    International Nuclear Information System (INIS)

    Kolar, Ladislav

    2013-03-01

    The seismic risk task assessment task should be structured as follows: (i) Define all reactor unit building structures, components and equipment involved in the creation of an initiating event (IE) induced by an seismic event or contributing to the reliability of reactor unit response to an IE; (ii) construct and estimate of the fragility curves for the building and component groups sub (i); (iii) determine the HCLPF for each group of buildings, components or equipment; (iv) determine the nuclear source's seismic resistance (SME) as the minimum HCLPF from the group of equipment in the risk-dominant scenarios; (v) define the risk-limiting group of components, equipment and building structures to the SME value; (vi) based on the fragility levels, identify component groups for which a more detailed fragility analysis is needed; and (vii) recommend groups of equipment or building structures that should be taken into account with respect to the seismic risk, i.e. such groups of equipment or building structures as exhibit a low seismic resistance (HCLPF) and, at the same time, are involved to a significant extent in the reactor unit's seismic risk (are present in the dominant risk scenarios). (P.A.)

  8. Automated Test Requirement Document Generation

    Science.gov (United States)

    1987-11-01

    DIAGNOSTICS BASED ON THE PRINCIPLES OF ARTIFICIAL INTELIGENCE ", 1984 International Test Conference, 01Oct84, (A3, 3, Cs D3, E2, G2, H2, 13, J6, K) 425...j0O GLOSSARY OF ACRONYMS 0 ABBREVIATION DEFINITION AFSATCOM Air Force Satellite Communication Al Artificial Intelligence ASIC Application Specific...In-Test Equipment (BITE) and AI ( Artificial Intelligence) - Expert Systems - need to be fully applied before a completely automated process can be

  9. BENCHPAR PROJECT. How to Incorporate ThermaI-Hydro-Mechanical Coupled Processes into Performance Assessments and Design Studies for Radioactive Waste Disposal in Geological Formations. Guidance Document

    International Nuclear Information System (INIS)

    Stephansson, O.; Andersson, Johan

    2005-02-01

    The objective of this Guidance Document is to provide advice on how to incorporate thermo-hydro-mechanical (THM) coupled processes into Performance Assessments (PAS) and design studies for radioactive waste disposal in geological formations to be experienced in a European context. The document has been generated by the EU research project BENCHPAR: Benchmark Tests and Guidance on Coupled Processes for Performance Assessment of Nuclear Waste Repositories. The document starts in Section 1 with an explanation of why numerical analyses incorporating THM mechanisms are required for radioactive waste studies and provides background material on the subject. Then, the THM processes and their interactions are explained in Section 2. Three case examples of THM numerical analysis are presented in Section 3 to illustrate the type of work that can be conducted to study the near-field, upscaling, and the far-field. For the three cases, there is discussion on the main findings, the relevance to a safety case, the relative importance of the different couplings, and the uncertainties involved. The importance and priority of the THM couplings are then summarized in Section 4. It is especially important to be able to technically audit the numerical analyses in order to establish that all the relevant variables, parameters and mechanisms have been included in the modelling and hence that the numerical model adequately represents the rock and engineering reality. Accordingly, recommended soft and hard auditing procedures are presented in Section 5. In this Guidance Document, we emphasize especially that the most important step in numerical modelling is not executing the calculations per se, but the earlier conceptualization of the problem regarding the dominant processes, the material properties and parameters, the engineering perturbations, and their mathematical presentations. The associated modelling component of addressing the uncertainties and estimating their influence on the

  10. Uranium in Canada: 1984 assessment of supply and requirements

    International Nuclear Information System (INIS)

    1985-09-01

    The success of uranium exploration efforts in Canada has continued, resulting in an overall increase in domestic uranium resource estimates for the principal resource categories. In 1984, Canada's five primary uranium producers employed some 5,800 people at their mining and milling operations, and produced concentrates containing some 11 170 tU. In 1984 the resource estimates were (in tonnes U recoverable): measured - 54 000; indicated - 233 000; inferred - 264 000. Canada's projected annual primary uranium production capability will stabilize at some 12 000 tU through the remainder of the 1980s. Should market conditions warrant, additional production centres could be developed to raise production capability to a level of 15 000 tU by the latter half of the 1990s. Prognosticated resources exploitable at uranium prices of $300/kg U or less are estimated to amount to 292 000 tU. Speculative resources of interest at prices of $300/kg U or less, in areas assessed during 1984, are thought to total approximately one million tU. Uranium exploration expenditures in Canada in 1983 and 1984 were an estimated $41 and $35 million, respectively. Exploration drilling and surface development drilling in 1983 and 1984 were reported to be 153 000 m and 197 000 m, respectively, some 85 per cent of which was in Saskatchewan. Canada's known uranium resources, recoverable at uranium prices of $150/kg U or less, are more than sufficient to meet the 30-year fuelling requirements of those reactors in Canada that are either in operation now or committed or expected to be in-service by 1995. Over the longer term, there is significant potential for discovering additional uranium resources in Canada

  11. Regulation No. 56/2006 Coll. of the Nuclear Regulatory Authority of the Slovak Republic dated as of January 12, 2006 on details concerning requirements for quality system documentation of authorisation holder, as well as details concerning quality requirements for nuclear installations, details concerning quality requirements for classified equipment and details concerning the scope of their approval

    International Nuclear Information System (INIS)

    2006-01-01

    This Regulation provides details of the requirements for quality system documentation holder, details of the quality requirements for nuclear installations, details concerning quality requirements for classified equipment and details of the scope of their approval. This Regulation came into force on March 1, 2006.

  12. Assessing the progress of rehabilitation in patients with ACL reconstruction using the International Knee Documentation Committee Subjective Knee Form

    International Nuclear Information System (INIS)

    Leguizamon, J H; Braidot, A; Catalfamo Formento, P

    2011-01-01

    There are numerous assessment tools designed to provide information on the results of reconstructive surgery of anterior cruciate ligament (ACL). They are also used for monitoring progress and facilitating clinical decision-making during the rehabilitation process. A brief summary of some existing tools specifically designed to evaluate knee ligament injuries is presented in this article. Then, one of those outcome measures, the International Knee Documentation Committee Subjective Knee Form (IKDC) was applied to a group of patients (N = 10) who had undergone surgery for ACL reconstruction. The patients attended the same physiotherapy service and followed a unified rehabilitation protocol. The assessment was performed twice: four and six months after surgery. The results showed an improvement in the rehabilitation of most patients tested (verified by a difference equal to or greater than 9 points on the IKDC outcome between measurements 1 and 2). The IKDC probed to be an instrument of quick and easy application. It provided quantitative data about the progress of rehabilitation and could be applied in everyday clinical physiotherapy practice. However, the results suggested considering the IKDC as one component of an evaluation kit to make decisions regarding the progress of the rehabilitation treatment.

  13. Subsurface Interim Measures/Interim Remedial Action Plan/Environmental Assessment and Decision Document, Operable Unit No. 2

    International Nuclear Information System (INIS)

    1992-01-01

    The subject Interim Measures/Interim Remedial Action plan/Environmental Assessment (IM/IRAP/EA) addresses residual free-phase volatile organic compound (VOC) contamination suspected in the subsurface within an area identified as Operable Unit No. 2 (OU2). This IM/IRAP/EA also addresses radionuclide contamination beneath the 903 Pad at OU2. Although subsurface VOC and radionuclide contamination on represent a source of OU2 ground-water contamination, they pose no immediate threat to public health or the environment. This IM/IRAP/EA identifies and evaluates interim remedial actions for removal of residual free-phase VOC contamination from three different subsurface environments at OU2. The term ''residual'' refers to the non-aqueous phase contamination remaining in the soil matrix (by capillary force) subsequent to the passage of non-aqueous or free-phase liquid through the subsurface. In addition to the proposed actions, this IM/IRAP/EA presents an assessment of the No Action Alternative. This document also considers an interim remedial action for the removal of radionuclides from beneath the 903 Pad

  14. IDC System Specification Document.

    Energy Technology Data Exchange (ETDEWEB)

    Clifford, David J.

    2014-12-01

    This document contains the system specifications derived to satisfy the system requirements found in the IDC System Requirements Document for the IDC Reengineering Phase 2 project. Revisions Version Date Author/Team Revision Description Authorized by V1.0 12/2014 IDC Reengineering Project Team Initial delivery M. Harris

  15. Technical assessment of compliance with workplace air sampling requirements in the 300 Area

    International Nuclear Information System (INIS)

    Olsen, P.A.

    1995-01-01

    The purpose of this Technical Work Document is to satisfy HSRCM-1, the ''Hanford Site Radiological Control Manual.'' Article 551.4 of that manual states a requirement for a documented study of facility workplace air sampling programs (WPAS). This first revision of the original Supporting Document covers the period from January 1, 1995 to December 31, 1995. HSRCM-1 is the primary guidance for radiological control at Westinghouse Hanford Company (WHC). It was written to implement DOE/EH-0256T ''US Department of Energy Radiological Control Manual'' as it applies to programs at Hanford. As such, it complies with Title 10, Part 835 of the Code of Federal Regulations. There are also several Department of Energy (DOE) Orders, national consensus standards, and reports that provide criteria, standards, and requirements for workplace air sampling programs. This document provides a summary of these, as they apply to WHC facility workplace air sampling programs. This document also provides an evaluation of the compliance of 300 Areas' workplace air sampling program to the criteria, standards, and requirements and documents compliance with the requirements where appropriate. Where necessary, it also indicates changes needed to bring specific locations into compliance. The areas evaluated were the 340 Facility, the Advanced Reactor Operations Division Facilities, the N Reactor Fuels Supply Facility, and The Geotechnical Engineering Laboratory

  16. 77 FR 31073 - Audit Requirements for Third Party Conformity Assessment Bodies

    Science.gov (United States)

    2012-05-24

    ... 1112 and 1118 Audit Requirements for Third Party Conformity Assessment Bodies and Requirements... PRODUCT SAFETY COMMISSION 16 CFR Part 1112 [CPSC Docket No. CPSC-2009-0061] Audit Requirements for Third... rule establishing requirements for the periodic audit of third party conformity assessment bodies as a...

  17. 17 CFR 240.17h-2T - Risk assessment reporting requirements for brokers and dealers.

    Science.gov (United States)

    2010-04-01

    ... requirements for brokers and dealers. 240.17h-2T Section 240.17h-2T Commodity and Securities Exchanges... Organizations § 240.17h-2T Risk assessment reporting requirements for brokers and dealers. (a) Reporting requirements of risk assessment information required to be maintained by section 240.17h-1T. (1) Every broker...

  18. 33 CFR 104.305 - Vessel Security Assessment (VSA) requirements.

    Science.gov (United States)

    2010-07-01

    ... baggage; and (vi) Vessel stores; (2) Threat assessments, including the purpose and methodology of the assessment, for the area or areas in which the vessel operates or at which passengers embark or disembark; (3... and control procedures; (ii) Identification systems; (iii) Surveillance and monitoring equipment; (iv...

  19. How do student nurses learn to care? An analysis of pre-registration adult nursing practice assessment documents.

    Science.gov (United States)

    Young, Kate; Godbold, Rosemary; Wood, Pat

    2018-01-01

    There is international concern about the quality of nursing in resource constrained, high technology health care settings. This paper reports findings from a research study which explored the experiences and views of those involved in the education and learning of 'caring' with adult pre-registration students. A novel dataset of 39 practice assessment documents (PADs) were randomly sampled and analysed across both bachelors and masters programmes from September 2014-July 2015. Using an appreciative enquiry approach, the Caring Behaviours Inventory aided analysis of qualitative text from both mentors and students within the PADs to identify how student nurses learn to care and to establish whether there were any differences between Masters and Bachelors students. In contrast with existing research, we found a holistic, melded approach to caring. This combined softer skills with highly technologized care, and flexible, tailored approaches to optimise individualised care delivery. Both of these were highly valued by both students and mentors. Pre-registration MSc students tended to have higher perceptual skills and be more analytical than their BSc counterparts. We found no evidence to suggest that caring behaviour or attitudes diminish over the course of either programme. Copyright © 2017 Elsevier Ltd. All rights reserved.

  20. Early Quantitative Assessment of Non-Functional Requirements

    NARCIS (Netherlands)

    Kassab, M.; Daneva, Maia; Ormandjieva, O.

    2007-01-01

    Non-functional requirements (NFRs) of software systems are a well known source of uncertainty in effort estimation. Yet, quantitatively approaching NFR early in a project is hard. This paper makes a step towards reducing the impact of uncertainty due to NRF. It offers a solution that incorporates

  1. Employing high resolution satellite imagery to document a rapid glacier surge in the Karakoram - risks and opportunities for hazard assessment

    Science.gov (United States)

    Steiner, J. F.; Kraaijenbrink, P. D. A.; Jiduc, S. G.; Immerzeel, W. W.

    2017-12-01

    Glacier surges occur regularly in the Karakoram but their driving mechanisms, recurrence and its relation to climatic change remain unclear. Since many glacier tongues in the region reach to very low elevations, local populations are often exposed to glacial hazards. While the scientific interpretation of hazard is one challenge, adequately communicating results to possibly affected stakeholders poses a different set of hurdles. Using DEMs as well as Landsat imagery in combination with high-resolution Planet imagery we quantify surface elevation changes and flow velocities to document a glacier surge of the Khurdopin glacier, located in a remote valley in Pakistan, in the first half of 2017. Results reveal that an accumulation of ice mass leads to a rapid surge in peaking with velocities above 5000 m a-1 or 0.5 m h-1 during a few days. Velocities increase steadily during a four-year build-up phase prior to the actual surge, while the remaining 15 years of the recurring cycle the glacier is quiescent. It is hypothesized that the surge is mainly initiated as a result of increased pressure melting caused by ice accumulation. However, surface observations show increased crevassing and disappearance of supra glacial ponds, which could have led to increased lubrication of the glacier bed. As a consequence of the surging tongue blocking the main valley a lake has formed and grown continuously in size over two months at a rate of up to 3000 m2 per day. Using satellite imagery with a frequent overpass rate we are able to (a) characterize the nature of glacier surges in the region with greater detail and (b) monitor the surge as well as the formation of the lake as it develops. Having developed a connection to local stakeholders we were able to provide rapid hazard assessments to affected communities, which can be employed to define possible actions. We show the potential of satellite imagery - freely available Landsat in combination with commercial Planet imagery -, which

  2. Standardization Documents

    Science.gov (United States)

    2011-08-01

    Specifications and Standards; Guide Specifications; CIDs; and NGSs . Learn. Perform. Succeed. STANDARDIZATION DOCUMENTS Federal Specifications Commercial...national or international standardization document developed by a private sector association, organization, or technical society that plans ...Maintain lessons learned • Examples: Guidance for application of a technology; Lists of options Learn. Perform. Succeed. DEFENSE HANDBOOK

  3. 10 CFR 63.114 - Requirements for performance assessment.

    Science.gov (United States)

    2010-01-01

    ... processes of engineered barriers in the performance assessment, including those processes that would adversely affect the performance of natural barriers. Degradation, deterioration, or alteration processes of... surrounding region to the extent necessary, and information on the design of the engineered barrier system...

  4. Scintigraphic assessment of liver function in patients requiring liver surgery

    NARCIS (Netherlands)

    Cieślak, K.P.

    2018-01-01

    This thesis addresses various aspects of assessment of liver function using a quantitative liver function test, 99mTc-mebrofenin hepatobiliary scintigraphy (HBS). HBS enables direct measurement of at least one of the liver’s true processes with minimal external interference and offers the

  5. 33 CFR 105.305 - Facility Security Assessment (FSA) requirements.

    Science.gov (United States)

    2010-07-01

    ... evacuation routes and assembly stations; and (viii) Existing security and safety equipment for protection of... protection systems; (iv) Procedural policies; (v) Radio and telecommunication systems, including computer... 33 Navigation and Navigable Waters 1 2010-07-01 2010-07-01 false Facility Security Assessment (FSA...

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

    International Nuclear Information System (INIS)

    2009-01-01

    Fundamental Safety Principles. Section 3 describes the graded approach to implementation of the requirements for safety assessment for different facilities and activities. Section 4 establishes the overall requirements for a safety assessment and specific requirements that relate to the assessment of features relevant to safety. Section 4 also establishes the requirements to address defence in depth and safety margins, to perform safety analysis, to document the safety assessment and to carry out an independent verification. Section 5 establishes the requirements for the management, use and maintenance of the safety assessment

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

    International Nuclear Information System (INIS)

    2009-01-01

    Fundamental Safety Principles. Section 3 describes the graded approach to implementation of the requirements for safety assessment for different facilities and activities. Section 4 establishes the overall requirements for a safety assessment and specific requirements that relate to the assessment of features relevant to safety. Section 4 also establishes the requirements to address defence in depth and safety margins, to perform safety analysis, to document the safety assessment and to carry out an independent verification. Section 5 establishes the requirements for the management, use and maintenance of the safety assessment

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

    International Nuclear Information System (INIS)

    2010-01-01

    Fundamental Safety Principles. Section 3 describes the graded approach to implementation of the requirements for safety assessment for different facilities and activities. Section 4 establishes the overall requirements for a safety assessment and specific requirements that relate to the assessment of features relevant to safety. Section 4 also establishes the requirements to address defence in depth and safety margins, to perform safety analysis, to document the safety assessment and to carry out an independent verification. Section 5 establishes the requirements for the management, use and maintenance of the safety assessment

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

    International Nuclear Information System (INIS)

    2009-01-01

    from the Fundamental Safety Principles. Section 3 describes the graded approach to implementation of the requirements for safety assessment for different facilities and activities. Section 4 establishes the overall requirements for a safety assessment and specific requirements that relate to the assessment of features relevant to safety. Section 4 also establishes the requirements to address defence in depth and safety margins, to perform safety analysis, to document the safety assessment and to carry out an independent verification. Section 5 establishes the requirements for the management, use and maintenance of the safety assessment

  10. Assessing User Needs and Requirements for Assistive Robots at Home.

    Science.gov (United States)

    Werner, Katharina; Werner, Franz

    2015-01-01

    'Robots in healthcare' is a very trending topic. This paper gives an overview of currently and commonly used methods to gather user needs and requirements in research projects in the field of assistive robotics. Common strategies between authors are presented as well as examples of exceptions, which can help future researchers to find methods suitable for their own work. Typical problems of the field are discussed and partial solutions are proposed.

  11. Software Requirement Specifications For ASocial Media Threat Assessment Tool

    Science.gov (United States)

    2017-12-01

    media means a much higher volume of threats than before, which taxes law enforcement’s ability to investigate each one. Complicating the investigation...Obtaining the identity of a Twitter account holder requires court paperwork based on probable cause or exigent circumstances. Second, social media...instant connectivity of social media means a much higher number of threats than before, which taxes law enforcement’s ability to investigate each one

  12. 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.

  13. Requirements for water assessment tools: An automotive industry perspective

    Directory of Open Access Journals (Sweden)

    Sherry A. Mueller

    2015-03-01

    Full Text Available Water availability is one of the greatest global sustainability challenges. Water is not available in adequate quantity and quality in many areas and water shortfalls are expected to increase. Businesses are facing water-related challenges due to inadequate water availability and poor resource management. Identifying and quantifying impacts is key to enabling companies to make effective management decisions. Several water assessment tools have been developed to help companies understand the complex nature of water challenges; however, there remain significant gaps in the datasets and inconsistencies in measurement and reporting of geographic water shortfalls. There is a need for more complete datasets containing information on water withdrawal and discharge, freshwater availability and depletion (spatially and temporally, water quality monitoring, reuse and recycling. We discuss four of the available water assessment tools (Global Water Tool, India Water Tool, Water Risk Filter and Aqueduct and highlight those elements most critical to water-related business decisions.

  14. 30 CFR 250.920 - What are the MMS requirements for assessment of fixed platforms?

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 2 2010-07-01 2010-07-01 false What are the MMS requirements for assessment of... Structures Inspection, Maintenance, and Assessment of Platforms § 250.920 What are the MMS requirements for... in API RP 2A-WSD, Section 17.3. If MMS objects to the assessment category you used for your...

  15. Documents for Recommended Toxicity Equivalency Factors for Human Health Risk Assessments of Dioxin and Dioxin-Like Compounds

    Science.gov (United States)

    This document describes the U.S. Environmental Protection Agency’s (U.S. EPA’s) updated approach for evaluating the human health risks from exposures to environmental media containing dioxin-like compounds (DLCs).

  16. Italian chapter of the International Society of cardiovascular ultrasound expert consensus document on training requirements for noncardiologists using hand-carried ultrasound devices.

    Science.gov (United States)

    Pelliccia, Francesco; Palmiero, Pasquale; Maiello, Maria; Losi, Maria-Angela

    2012-07-01

    Hand-carried ultrasound devices (HCDs), also named personal use echo, are pocket-size, compact, and battery-equipped echocardiographic systems. They have limited technical capabilities but offer some advantages compared with standard echocardiographic devices due to their simplicity of use, immediate availability at the patient's bedside, transportability, and relatively low cost. Current HCDs are considered as screening tools and are used to complement the physical examination by cardiologists. Many noncardiologic subspecialists, however, have adopted this technologic advancement rapidly raising the concern of an inappropriate use of HCD by health professionals who do not have any specific training. In keeping with the mission of the International Society of Cardiovascular Ultrasound to advance the science and art of cardiovascular ultrasound and encourage the knowledge of this subject, the purpose of this Expert Consensus document is to focus on the training for all health care professionals considering the use of HCD. Accordingly, this paper summarizes general aspects of HCD, such as technical characteristics and clinical indications, and then details the specific training requirements for noncardiologists (i.e., training program, minimum case load, duration, and certification of competence). © 2012, Wiley Periodicals, Inc.

  17. Performance Evaluation and Requirements Assessment for Gravity Gradient Referenced Navigation

    Directory of Open Access Journals (Sweden)

    Jisun Lee

    2015-07-01

    Full Text Available In this study, simulation tests for gravity gradient referenced navigation (GGRN are conducted to verify the effects of various factors such as database (DB and sensor errors, flight altitude, DB resolution, initial errors, and measurement update rates on the navigation performance. Based on the simulation results, requirements for GGRN are established for position determination with certain target accuracies. It is found that DB and sensor errors and flight altitude have strong effects on the navigation performance. In particular, a DB and sensor with accuracies of 0.1 E and 0.01 E, respectively, are required to determine the position more accurately than or at a level similar to the navigation performance of terrain referenced navigation (TRN. In most cases, the horizontal position error of GGRN is less than 100 m. However, the navigation performance of GGRN is similar to or worse than that of a pure inertial navigation system when the DB and sensor errors are 3 E or 5 E each and the flight altitude is 3000 m. Considering that the accuracy of currently available gradiometers is about 3 E or 5 E, GGRN does not show much advantage over TRN at present. However, GGRN is expected to exhibit much better performance in the near future when accurate DBs and gravity gradiometer are available.

  18. 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

  19. Maury Documentation

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Supporting documentation for the Maury Collection of marine observations. Includes explanations from Maury himself, as well as guides and descriptions by the U.S....

  20. Documentation Service

    International Nuclear Information System (INIS)

    Charnay, J.; Chosson, L.; Croize, M.; Ducloux, A.; Flores, S.; Jarroux, D.; Melka, J.; Morgue, D.; Mottin, C.

    1998-01-01

    This service assures the treatment and diffusion of the scientific information and the management of the scientific production of the institute as well as the secretariat operation for the groups and services of the institute. The report on documentation-library section mentions: the management of the documentation funds, search in international databases (INIS, Current Contents, Inspects), Pret-Inter service which allows accessing documents through DEMOCRITE network of IN2P3. As realizations also mentioned are: the setup of a video, photo database, the Web home page of the institute's library, follow-up of digitizing the document funds by integrating the CD-ROMs and diskettes, electronic archiving of the scientific production, etc

  1. 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)

  2. 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

  3. Assessing moderated mediation in linear models requires fewer confounding assumptions than assessing mediation.

    Science.gov (United States)

    Loeys, Tom; Talloen, Wouter; Goubert, Liesbet; Moerkerke, Beatrijs; Vansteelandt, Stijn

    2016-11-01

    It is well known from the mediation analysis literature that the identification of direct and indirect effects relies on strong no unmeasured confounding assumptions of no unmeasured confounding. Even in randomized studies the mediator may still be correlated with unobserved prognostic variables that affect the outcome, in which case the mediator's role in the causal process may not be inferred without bias. In the behavioural and social science literature very little attention has been given so far to the causal assumptions required for moderated mediation analysis. In this paper we focus on the index for moderated mediation, which measures by how much the mediated effect is larger or smaller for varying levels of the moderator. We show that in linear models this index can be estimated without bias in the presence of unmeasured common causes of the moderator, mediator and outcome under certain conditions. Importantly, one can thus use the test for moderated mediation to support evidence for mediation under less stringent confounding conditions. We illustrate our findings with data from a randomized experiment assessing the impact of being primed with social deception upon observer responses to others' pain, and from an observational study of individuals who ended a romantic relationship assessing the effect of attachment anxiety during the relationship on mental distress 2 years after the break-up. © 2016 The British Psychological Society.

  4. Health physics documentation

    International Nuclear Information System (INIS)

    Stablein, G.

    1980-01-01

    When dealing with radioactive material the health physicist receives innumerable papers and documents within the fields of researching, prosecuting, organizing and justifying radiation protection. Some of these papers are requested by the health physicist and some are required by law. The scope, quantity and deposit periods of the health physics documentation at the Karlsruhe Nuclear Research Center are presented and rationalizing methods discussed. The aim of this documentation should be the application of physics to accident prevention, i.e. documentation should protect those concerned and not the health physicist. (H.K.)

  5. Uranium in Canada: 1982 assessment of supply and requirements

    International Nuclear Information System (INIS)

    1983-09-01

    Estimates of Canada's uranium resources for 1982 remained essentially unchanged from those of 1980. However, the economic conditions facing the industry have changed greatly during the past few years as production costs continued to rise without corresponding increases in uranium prices. As a result, a smaller portion of Canada's uranium resources is of current economic interest. Total resources amount to 573 000 tonnes of uranium. Just over 10% of this uranium will be required domestically during the next 30 years to fuel the more than 15 000 megawatts of nuclear power capacity now operating or committed for operation in Canada by 1993. In 1982 seven uranium producers in Canada, directly employing 4800 people, produced concentrates containing 8075 tonnes of uranium. Based on currently committed expansion plans, Canada's projected annual production capability could grow to some 12 000 tonnes of uranium by 1986. Canadian producers shipped 7643 tonnes of uranium valued at some $838 millon in 1982. As of January 1, 1983, outstanding uranium export commitments amounted to 60 000 tonnes or roughly 10% of the total Canadian uranium resources mentioned above. Japan has been Canada's most important single customer in the past decade, receiving about 34% of Canada's total exports since 1972. Most of the remaining exports have gone to the European Economic Community (33%), other countries in Western Europe (18%), and the United States (15%). Substantial efforts in uranium exploration that have been continued, especially in northern Saskatchewan, where two-thirds of the $71 million total exploration expenditures of 1982 were incurred. This continued effort has led to the discovery of a number of important deposits over the past few years which could be developed if market conditions improve. It is estimated that total Canadian production capability could reach 15 000 tonnes of uranium annually by the mid-1990s

  6. ITER-EDA physics design requirements and plasma performance assessments

    International Nuclear Information System (INIS)

    Uckan, N.A.; Galambos, J.; Wesley, J.; Boucher, D.; Perkins, F.; Post, D.; Putvinski, S.

    1996-01-01

    Physics design guidelines, plasma performance estimates, and sensitivity of performance to changes in physics assumptions are presented for the ITER-EDA Interim Design. The overall ITER device parameters have been derived from the performance goals using physics guidelines based on the physics R ampersand D results. The ITER-EDA design has a single-null divertor configuration (divertor at the bottom) with a nominal plasma current of 21 MA, magnetic field of 5.68 T, major and minor radius of 8.14 m and 2.8 m, and a plasma elongation (at the 95% flux surface) of ∼1.6 that produces a nominal fusion power of ∼1.5 GW for an ignited burn pulse length of ≥1000 s. The assessments have shown that ignition at 1.5 GW of fusion power can be sustained in ITER for 1000 s given present extrapolations of H-mode confinement (τ E = 0.85 x τ ITER93H ), helium exhaust (τ* He /τ E = 10), representative plasma impurities (n Be /n e = 2%), and beta limit [β N = β(%)/(I/aB) ≤ 2.5]. The provision of 100 MW of auxiliary power, necessary to access to H-mode during the approach to ignition, provides for the possibility of driven burn operations at Q = 15. This enables ITER to fulfill its mission of fusion power (∼ 1--1.5 GW) and fluence (∼1 MWa/m 2 ) goals if confinement, impurity levels, or operational (density, beta) limits prove to be less favorable than present projections. The power threshold for H-L transition, confinement uncertainties, and operational limits (Greenwald density limit and beta limit) are potential performance limiting issues. Improvement of the helium exhaust (τ* He /τ E ≤ 5) and potential operation in reverse-shear mode significantly improve ITER performance

  7. Monitored Geologic Repository Project Description Document

    International Nuclear Information System (INIS)

    Curry, P. M.

    2001-01-01

    The primary objective of the Monitored Geologic Repository Project Description Document (PDD) is to allocate the functions, requirements, and assumptions to the systems at Level 5 of the Civilian Radioactive Waste Management System (CRWMS) architecture identified in Section 4. It provides traceability of the requirements to those contained in Section 3 of the ''Monitored Geologic Repository Requirements Document'' (MGR RD) (YMP 2000a) and other higher-level requirements documents. In addition, the PDD allocates design related assumptions to work products of non-design organizations. The document provides Monitored Geologic Repository (MGR) technical requirements in support of design and performance assessment in preparing for the Site Recommendation (SR) and License Application (LA) milestones. The technical requirements documented in the PDD are to be captured in the System Description Documents (SDDs) which address each of the systems at Level 5 of the CRWMS architecture. The design engineers obtain the technical requirements from the SDDs and by reference from the SDDs to the PDD. The design organizations and other organizations will obtain design related assumptions directly from the PDD. These organizations may establish additional assumptions for their individual activities, but such assumptions are not to conflict with the assumptions in the PDD. The PDD will serve as the primary link between the technical requirements captured in the SDDs and the design requirements captured in US Department of Energy (DOE) documents. The approved PDD is placed under Level 3 baseline control by the CRWMS Management and Operating Contractor (M and O) and the following portions of the PDD constitute the Technical Design Baseline for the MGR: the design characteristics listed in Table 1-1, the MGR Architecture (Section 4.1), the Technical Requirements (Section 5), and the Controlled Project Assumptions (Section 6)

  8. 76 FR 37704 - Federal Acquisition Regulation; Documenting Contractor Performance

    Science.gov (United States)

    2011-06-28

    ... Federal Acquisition Regulation; Documenting Contractor Performance AGENCY: Department of Defense (DoD..., and to require all past performance information be entered into the Contractor Performance Assessment... Contractor Performance Information. These changes provide Governmentwide standardized evaluation factors and...

  9. Exposure assessment of upper limb repetitive movements: a consensus document developed by the Technical Committee on Musculoskeletal Disorders of International Ergonomics Association (IEA) endorsed by International Commission on Occupational Health (ICOH).

    Science.gov (United States)

    Colombini, D; Occhipinti, E; Delleman, N; Fallentin, N; Kilbom, A; Grieco, A

    2001-01-01

    This consensus document intends to supply a set of definitions, criteria and procedures useful to describe and, wherever possible, to assess the work conditions that can represent a physical overload for the upper limbs. The document is aimed at all the operators, i.e. occupational doctors but mainly technicians, who are, involved in risk exposure assessment and management. The document intends to provide methods and procedures easily applicable in the field, possibly not requiring sophisticated instrumentation and when possible based on observation procedures. The proposed methods shall be based as far as possible on knowledge and data from scientific literature: should they be contradictory or deficient, reference will be made to standards or pre-standards issued by national and international agencies and bodies, with the experience of researchers involved and common sense. In this regard, it is to be emphasized that the potential users increasingly demand an easily applicable method for description and assessment of work with repetitive movements. The group intends to give a response even if there are still uncertainties from a strictly scientific standpoint: however the group commits itself to perform subsequent validations especially of as yet unconsolidated issues. This document focuses specifically on identification of risk factors and describes some of the methods that have been developed for evaluating them. There is a rapidly developing body of literature on job analysis and not yet agreement on a single best way to analyze jobs. Professional judgement is required to select the appropriate methods. Analysis and design of jobs should to be integrated into an ongoing ergonomics program that includes management commitment, training, health surveillance, and medical case management. In summing up this report, space must be given to the check lists that are so often seen in the medical press, although this is not the occasion to propose a detailed analytical

  10. 78 FR 56816 - Vidalia Onions Grown in Georgia; Change in Reporting and Assessment Requirements

    Science.gov (United States)

    2013-09-16

    ... to regulation under the order and approximately 80 onion producers in the designated production area...; FV13-955-1 FIR] Vidalia Onions Grown in Georgia; Change in Reporting and Assessment Requirements AGENCY... the reporting and assessment requirements prescribed under the marketing order for Vidalia onions...

  11. 28 CFR 105.11 - Individuals not requiring a security risk assessment.

    Science.gov (United States)

    2010-07-01

    ... requiring a security risk assessment. (a) Citizens and nationals of the United States. A citizen or national... 28 Judicial Administration 2 2010-07-01 2010-07-01 false Individuals not requiring a security risk assessment. 105.11 Section 105.11 Judicial Administration DEPARTMENT OF JUSTICE (CONTINUED) CRIMINAL HISTORY...

  12. Assessing students' performance in software requirements engineering education using scoring rubrics

    Science.gov (United States)

    Mkpojiogu, Emmanuel O. C.; Hussain, Azham

    2017-10-01

    The study investigates how helpful the use of scoring rubrics is, in the performance assessment of software requirements engineering students and whether its use can lead to students' performance improvement in the development of software requirements artifacts and models. Scoring rubrics were used by two instructors to assess the cognitive performance of a student in the design and development of software requirements artifacts. The study results indicate that the use of scoring rubrics is very helpful in objectively assessing the performance of software requirements or software engineering students. Furthermore, the results revealed that the use of scoring rubrics can also produce a good achievement assessments direction showing whether a student is either improving or not in a repeated or iterative assessment. In a nutshell, its use leads to the performance improvement of students. The results provided some insights for further investigation and will be beneficial to researchers, requirements engineers, system designers, developers and project managers.

  13. Technical assessment of compliance with work place air sampling requirements at T Plant. Revision No. 1

    International Nuclear Information System (INIS)

    Hackworth, M.F.

    1995-01-01

    The US DOE requires its contractors to conduct air sampling to detect and evaluate airborne radioactive material in the workplace. Hanford Reservation T Plant compliance with workplace air sampling requirements has been assessed. Requirements, basis for determining compliance and recommendations are included

  14. Old TNX Seepage Basin: Environmental information document

    International Nuclear Information System (INIS)

    Dunaway, J.K.; Johnson, W.F.; Kingley, L.E.; Simmons, R.V.; Bledsoe, H.W.; Smith, J.A.

    1986-12-01

    This document provides environmental information on postulated closure options for the Old TNX Seepage Basin at the Savannah River Plant and was developed as background technical documentation for the Department of Energy's proposed Environmental Impact Statement (EIS) on waste management activities for groundwater protection at the plant. The results of groundwater and atmospheric pathway analyses, accident analysis, and other environmental assessments discussed in this document are based upon a conservative analysis of all foreseeable scenarios as defined by the National Environmental Policy Act (40 CFR 1500-1508). The scenarios do not necessarily represent actual environmental conditions. This document is not meant to be used as a regulatory closure plan or other regulatory document to comply with required federal or state environmental regulations

  15. Recommended HSE-7 documents hierarchy

    International Nuclear Information System (INIS)

    Klein, R.B.; Jennrich, E.A.; Lund, D.M.; Danna, J.G.; Davis, K.D.; Rutz, A.C.

    1990-01-01

    This report recommends a hierarchy of waste management documents at Los Alamos National Laboratory (LANL or ''Laboratory''). The hierarchy addresses documents that are required to plan, implement, and document waste management programs at Los Alamos. These documents will enable the waste management group and the six sections contained within that group to satisfy requirements that are imposed upon them by the US Department of Energy (DOE), DOE Albuquerque Operations, US Environmental Protection Agency, various State of New Mexico agencies, and Laboratory management

  16. CMS DOCUMENTATION

    CERN Multimedia

    CMS TALKS AT MAJOR MEETINGS The agenda and talks from major CMS meetings can now be electronically accessed from the iCMS Web site. The following items can be found on: http://cms.cern.ch/iCMS/ General - CMS Weeks (Collaboration Meetings), CMS Weeks Agendas The talks presented at the Plenary Sessions. LHC Symposiums Management - CB - MB - FB - FMC Agendas and minutes are accessible to CMS members through their AFS account (ZH). However some linked documents are restricted to the Board Members. FB documents are only accessible to FB members. LHCC The talks presented at the ‘CMS Meetings with LHCC Referees’ are available on request from the PM or MB Country Representative. Annual Reviews The talks presented at the 2006 Annual reviews are posted.   CMS DOCUMENTS It is considered useful to establish information on the first employment of CMS doctoral students upon completion of their theses. Therefore it is requested that Ph.D students inform the CMS Secretariat a...

  17. CMS DOCUMENTATION

    CERN Multimedia

    CMS TALKS AT MAJOR MEETINGS The agenda and talks from major CMS meetings can now be electronically accessed from the iCMS Web site. The following items can be found on: http://cms.cern.ch/iCMS/ General - CMS Weeks (Collaboration Meetings), CMS Weeks Agendas The talks presented at the Plenary Sessions. LHC Symposiums Management - CB - MB - FB - FMC Agendas and minutes are accessible to CMS members through their AFS account (ZH). However some linked documents are restricted to the Board Members. FB documents are only accessible to FB members. LHCC The talks presented at the ‘CMS Meetings with LHCC Referees’ are available on request from the PM or MB Country Representative. Annual Reviews The talks presented at the 2006 Annual reviews are posted. CMS DOCUMENTS It is considered useful to establish information on the first employment of CMS doctoral students upon completion of their theses. Therefore it is requested that Ph.D students inform the CMS Secretariat about the natu...

  18. CMS DOCUMENTATION

    CERN Multimedia

    CMS TALKS AT MAJOR MEETINGS The agenda and talks from major CMS meetings can now be electronically accessed from the iCMS Web site. The following items can be found on: http://cms.cern.ch/iCMS/ General - CMS Weeks (Collaboration Meetings), CMS Weeks Agendas The talks presented at the Plenary Sessions. LHC Symposiums Management - CB - MB - FB - FMC Agendas and minutes are accessible to CMS members through their AFS account (ZH). However some linked documents are restricted to the Board Members. FB documents are only accessible to FB members. LHCC The talks presented at the ‘CMS Meetings with LHCC Referees’ are available on request from the PM or MB Country Representative. Annual Reviews The talks presented at the 2006 Annual reviews are posted. CMS DOCUMENTS It is considered useful to establish information on the first employment of CMS doctoral students upon completion of their theses. Therefore it is requested that Ph.D students inform the CMS Secretariat about the natur...

  19. CMS DOCUMENTATION

    CERN Multimedia

    CMS TALKS AT MAJOR MEETINGS The agenda and talks from major CMS meetings can now be electronically accessed from the iCMS Web site. The following items can be found on: http://cms.cern.ch/iCMS/ Management- CMS Weeks (Collaboration Meetings), CMS Weeks Agendas The talks presented at the Plenary Sessions. Management - CB - MB - FB Agendas and minutes are accessible to CMS members through their AFS account (ZH). However some linked documents are restricted to the Board Members. FB documents are only accessible to FB members. LHCC The talks presented at the ‘CMS Meetings with LHCC Referees’ are available on request from the PM or MB Country Representative. Annual Reviews The talks presented at the 2007 Annual reviews are posted. CMS DOCUMENTS It is considered useful to establish information on the first employment of CMS doctoral students upon completion of their theses. Therefore it is requested that Ph.D students inform the CMS Secretariat about the nature of employment and ...

  20. CMS DOCUMENTATION

    CERN Multimedia

    CMS TALKS AT MAJOR MEETINGS The agenda and talks from major CMS meetings can now be electronically accessed from the iCMS Web site. The following items can be found on: http://cms.cern.ch/iCMS/ Management- CMS Weeks (Collaboration Meetings), CMS Weeks Agendas The talks presented at the Plenary Sessions. Management - CB - MB - FB Agendas and minutes are accessible to CMS members through their AFS account (ZH). However some linked documents are restricted to the Board Members. FB documents are only accessible to FB members. LHCC The talks presented at the ‘CMS Meetings with LHCC Referees’ are available on request from the PM or MB Country Representative. Annual Reviews The talks presented at the 2007 Annual reviews are posted. CMS DOCUMENTS It is considered useful to establish information on the first employment of CMS doctoral students upon completion of their theses. Therefore it is requested that Ph.D students inform the CMS Secretariat about the nature of em¬pl...

  1. CMS DOCUMENTATION

    CERN Multimedia

    CMS TALKS AT MAJOR MEETINGS The agenda and talks from major CMS meetings can now be electronically accessed from the iCMS Web site. The following items can be found on: http://cms.cern.ch/iCMS/ General - CMS Weeks (Collaboration Meetings), CMS Weeks Agendas The talks presented at the Plenary Sessions. LHC Symposiums Management - CB - MB - FB - FMC Agendas and minutes are accessible to CMS members through their AFS account (ZH). However some linked documents are restricted to the Board Members. FB documents are only accessible to FB members. LHCC The talks presented at the ‘CMS Meetings with LHCC Referees’ are available on request from the PM or MB Country Representative. Annual Reviews The talks presented at the 2006 Annual reviews are posted. CMS DOCUMENTS It is considered useful to establish information on the first employment of CMS doctoral students upon completion of their theses. Therefore it is requested that Ph.D students inform the CMS Secretariat about the na...

  2. Mixed waste characterization reference document

    International Nuclear Information System (INIS)

    1997-09-01

    Waste characterization and monitoring are major activities in the management of waste from generation through storage and treatment to disposal. Adequate waste characterization is necessary to ensure safe storage, selection of appropriate and effective treatment, and adherence to disposal standards. For some wastes characterization objectives can be difficult and costly to achieve. The purpose of this document is to evaluate costs of characterizing one such waste type, mixed (hazardous and radioactive) waste. For the purpose of this document, waste characterization includes treatment system monitoring, where monitoring is a supplement or substitute for waste characterization. This document establishes a cost baseline for mixed waste characterization and treatment system monitoring requirements from which to evaluate alternatives. The cost baseline established as part of this work includes costs for a thermal treatment technology (i.e., a rotary kiln incinerator), a nonthermal treatment process (i.e., waste sorting, macronencapsulation, and catalytic wet oxidation), and no treatment (i.e., disposal of waste at the Waste Isolation Pilot Plant (WIPP)). The analysis of improvement over the baseline includes assessment of promising areas for technology development in front-end waste characterization, process equipment, off gas controls, and monitoring. Based on this assessment, an ideal characterization and monitoring configuration is described that minimizes costs and optimizes resources required for waste characterization

  3. Offshore Resource Assessment and Design Conditions: A Data Requirements and Gaps Analysis for Offshore Renewable Energy Systems

    Energy Technology Data Exchange (ETDEWEB)

    Elliott, Dennis [National Renewable Energy Lab. (NREL), Golden, CO (United States); Frame, Caitlin [National Oceanic and Atmospheric Administration (NOAA), Washington, DC (United States); Gill, Carrie [National Oceanic and Atmospheric Administration (NOAA), Washington, DC (United States); Hanson, Howard [Florida Atlantic Univ., Boca Raton, FL (United States); Moriarty, Patrick [National Renewable Energy Lab. (NREL), Golden, CO (United States); Powell, Mark [National Oceanic and Atmospheric Administration (NOAA), Washington, DC (United States); Shaw, William J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Wilczak, Jim [National Oceanic and Atmospheric Administration (NOAA), Washington, DC (United States); Wynne, Jason [Energetics, Columbia, MD (United States)

    2012-03-01

    The offshore renewable energy industry requires accurate meteorological and oceanographic (“metocean”) data for evaluating the energy potential, economic viability, and engineering requirements of offshore renewable energy projects. It is generally recognized that currently available metocean data, instrumentation, and models are not adequate to meet all of the stakeholder needs on a national scale. Conducting wind and wave resource assessments and establishing load design conditions requires both interagency collaboration as well as valuable input from experts in industry and academia. Under the Department of Energy and Department of Interior Memorandum of Understanding, the Resource Assessment and Design Condition initiative supports collaborative national efforts by adding to core atmospheric and marine science knowledge relevant to offshore energy development. Such efforts include a more thorough understanding and data collection of key metocean phenomena such as wind velocity and shear; low-level jets; ocean, tidal, and current velocities; wave characteristics; geotechnical data relating to surface and subsurface characteristics; seasonal and diurnal variations; and the interaction among these conditions. Figure 1 presents a graphical representation of some metocean phenomena that can impact offshore energy systems. This document outlines the metocean observations currently available; those that are not available; and those that require additional temporal-spatial coverage, resolution, or processing for offshore energy in an effort to gather agreed-upon, needed observations.

  4. Environmental Assessment for Electrical Power System Upgrades at Los Alamos National Laboratory, Los Alamos, New Mexico - Final Document

    Energy Technology Data Exchange (ETDEWEB)

    N/A

    2000-03-09

    The ''National Environmental Policy Act of 1969'' (NEPA) requires Federal agency officials to consider the environmental consequences of their proposed actions before decisions are made. In complying with NEPA, the United States (U.S.) Department of Energy (DOE) follows the Council on Environmental Quality (CEQ) regulations (40 Code of Federal Regulations [CFR] 1500-1508) and DOE's NEPA implementing procedures (10 CFR 1021). The purpose of an Environmental Assessment (EA) is to provide Federal decision makers with sufficient evidence and analysis to determine whether to prepare an Environmental Impact Statement (EIS) or issue a Finding of No Significant Impact. In this case, the DOE decision to be made is whether to construct and operate a 19.5-mile (mi) (31-kilometer [km]) electric transmission line (power line) reaching from the Norton Substation, west across the Rio Grande, to locations within the Los Alamos National Laboratory (LANL) Technical Areas (TAs) 3 and 5 at Los Alamos, New Mexico. The construction of one electric substation at LANL would be included in the project as would the construction of two line segments less than 1,200 feet (ft) (366 meters [m]) long that would allow for the uncrossing of a portion of two existing power lines. Additionally, a fiber optics communications line would be included and installed concurrently as part of the required overhead ground conductor for the power line. The new power line would improve the reliability of electric service in the LANL and Los Aktrnos County areas as would the uncrossing of the crossed segments of the existing lines. Additionally, installation of the new power line would enable the LANL and the Los Alamos County electric grid, which is a shared resource, to be adapted to accommodate the future import of increased power when additional power service becomes available in the northern New Mexico area. Similarly, the fiber optics line would allow DOE to take advantage of

  5. Mediator assessment, documentation, and disposition of child custody cases involving intimate partner abuse: a naturalistic evaluation of one county's practices.

    Science.gov (United States)

    Beck, Connie J A; Walsh, Michele E; Mechanic, Mindy B; Taylor, Caitilin S

    2010-06-01

    The contentious and costly nature of the adversarial process for resolving child custody disputes has prompted scholars, practitioners, and policy makers to advocate for the development and implementation of less divisive forms of dispute resolution, notably, mediation. Mediation has been championed for its potential to resolve disputes with less acrimony among disputants, reduced economic costs, increased satisfaction with outcomes, and fewer adverse consequences for family members. Despite the increasing popularity, arguments have cautioned against the use of mandated mediation when intimate partner abuse (IPA) is alleged. This research documents a mediation screening process and models mediators' decision-making process as instantiated, naturally, in one jurisdiction.

  6. Technical assessment of workplace air sampling requirements at tank farm facilities. Revision 1

    International Nuclear Information System (INIS)

    Olsen, P.A.

    1994-01-01

    WHC-CM-1-6 is the primary guidance for radiological control at Westinghouse Hanford Company (WHC). It was written to implement DOE N 5480.6 ''US Department of Energy Radiological Control Manual'' as it applies to programs at Hanford which are now overseen by WHC. As such, it complies with Title 10, Part 835 of the Code of Federal Regulations. In addition to WHC-CM-1-6, there is HSRCM-1, the ''Hanford Site Radiological Control Manual'' and several Department of Energy (DOE) Orders, national consensus standards, and reports that provide criteria, standards, and requirements for workplace air sampling programs. This document provides a summary of these, as they apply to WHC facility workplace air sampling programs. This document also provides an evaluation of the compliance of Tank Farms' workplace air sampling program to the criteria, standards, and requirements and documents compliance with the requirements where appropriate. Where necessary, it also indicates changes needed to bring specific locations into compliance

  7. Document Models

    Directory of Open Access Journals (Sweden)

    A.A. Malykh

    2017-08-01

    Full Text Available In this paper, the concept of locally simple models is considered. Locally simple models are arbitrarily complex models built from relatively simple components. A lot of practically important domains of discourse can be described as locally simple models, for example, business models of enterprises and companies. Up to now, research in human reasoning automation has been mainly concentrated around the most intellectually intensive activities, such as automated theorem proving. On the other hand, the retailer business model is formed from ”jobs”, and each ”job” can be modelled and automated more or less easily. At the same time, the whole retailer model as an integrated system is extremely complex. In this paper, we offer a variant of the mathematical definition of a locally simple model. This definition is intended for modelling a wide range of domains. Therefore, we also must take into account the perceptual and psychological issues. Logic is elitist, and if we want to attract to our models as many people as possible, we need to hide this elitism behind some metaphor, to which ’ordinary’ people are accustomed. As such a metaphor, we use the concept of a document, so our locally simple models are called document models. Document models are built in the paradigm of semantic programming. This allows us to achieve another important goal - to make the documentary models executable. Executable models are models that can act as practical information systems in the described domain of discourse. Thus, if our model is executable, then programming becomes redundant. The direct use of a model, instead of its programming coding, brings important advantages, for example, a drastic cost reduction for development and maintenance. Moreover, since the model is well and sound, and not dissolved within programming modules, we can directly apply AI tools, in particular, machine learning. This significantly expands the possibilities for automation and

  8. Assessment of documentation of DSM-IV-TR Criteria A for diagnosis of schizophrenia in psychiatric unit, tertiary hospital, Malaysia.

    Science.gov (United States)

    Maung, K; Ohnmar, H; Than, W; Ramli, M; Najwa Hanim, M R; Ali Sabri, R; Ahmad Zafri, A B

    The purposes of this study were to investigate the documentation of the DSM-IV-TR- Criteria A in diagnoses of schizophrenia and to identify the symptoms associated with over diagnosis of schizophrenia. This study involved a retrospective review and analysis of data from case notes. Data of 107 newly diagnosed patients with schizophrenia were keyed in and analyzed using SPSS v 19. The cases were then evaluated for the use of the DSM-IV-TR- Criteria A. Over diagnosis was noted in 37.39% of the patients. Disorganised behaviour (12.5%), affective flattening (12.5%), hallucination (16%) and non-bizarre delusion (18.3%) significantly contributed to the over-diagnosis of schizophrenia. Symptoms such as non-bizarre delusion and hallucination were the most commonly used in over-diagnosing schizophrenia and were statistically significant with p ≤0.05. There was a significant lack of DSM-IV-TR Criteria A among the data documented to diagnose schizophrenia and non-bizarre delusion and hallucination were the most commonly used in over-diagnosing schizophrenia. This key problem needs to be addressed. The reliability of a diagnosis is indispensable and achievable with the proper clinical application of DSM-IV-TR Criteria A. The DSM-IV-TR Criteria have been perceived to be useful and reliable and is most widely used throughout the world.

  9. Forest Resources of the United States, 2012: a technical document supporting the Forest Service 2010 update of the RPA Assessment

    Science.gov (United States)

    Sonja N. Oswalt; W. Brad Smith; Patrick D. Miles; Scott A. Pugh

    2014-01-01

    Forest resource statistics from the 2010 Resources Planning Act (RPA) Assessment were updated to provide current information on the Nation's forests as a baseline for the 2015 national assessment. Resource tables present estimates of forest area, volume, mortality, growth, removals, and timber products output in various ways, such as by ownership, region, or State...

  10. Projecting climate change in the United States: A technical document supporting the Forest Service RPA 2010 Assessment

    Science.gov (United States)

    Linda A. Joyce; David T. Price; David P. Coulson; Daniel W. McKenney; R. Martin Siltanen; Pia Papadopol; Kevin. Lawrence

    2014-01-01

    A set of climate change projections for the United States was developed for use in the 2010 USDA Forest Service RPA Assessment. These climate projections, along with projections for population dynamics, economic growth, and land use change in the United States, comprise the RPA scenarios and are used in the RPA Assessment to project future renewable resource conditions...

  11. Assessment of Quality Assurance Measures for Radioactive Material Transport Packages not Requiring Competent Authority Design Approval - 13282

    International Nuclear Information System (INIS)

    Komann, Steffen; Groeke, Carsten; Droste, Bernhard

    2013-01-01

    The majority of transports of radioactive materials are carried out in packages which don't need a package design approval by a competent authority. Low-active radioactive materials are transported in such packages e.g. in the medical and pharmaceutical industry and in the nuclear industry as well. Decommissioning of NPP's leads to a strong demand for packages to transport low and middle active radioactive waste. According to IAEA regulations the 'non-competent authority approved package types' are the Excepted Packages and the Industrial Packages of Type IP-1, IP-2 and IP-3 and packages of Type A. For these types of packages an assessment by the competent authority is required for the quality assurance measures for the design, manufacture, testing, documentation, use, maintenance and inspection (IAEA SSR 6, Chap. 306). In general a compliance audit of the manufacturer of the packaging is required during this assessment procedure. Their regulatory level in the IAEA regulations is not comparable with the 'regulatory density' for packages requiring competent authority package design approval. Practices in different countries lead to different approaches within the assessment of the quality assurance measures in the management system as well as in the quality assurance program of a special package design. To use the package or packaging in a safe manner and in compliance with the regulations a management system for each phase of the life of the package or packaging is necessary. The relevant IAEA-SSR6 chap. 801 requires documentary verification by the consignor concerning package compliance with the requirements. (authors)

  12. Assessment of Quality Assurance Measures for Radioactive Material Transport Packages not Requiring Competent Authority Design Approval - 13282

    Energy Technology Data Exchange (ETDEWEB)

    Komann, Steffen; Groeke, Carsten; Droste, Bernhard [BAM Federal Institute for Materials Research and Testing, Unter den Eichen 44-46, 12203 Berlin (Germany)

    2013-07-01

    The majority of transports of radioactive materials are carried out in packages which don't need a package design approval by a competent authority. Low-active radioactive materials are transported in such packages e.g. in the medical and pharmaceutical industry and in the nuclear industry as well. Decommissioning of NPP's leads to a strong demand for packages to transport low and middle active radioactive waste. According to IAEA regulations the 'non-competent authority approved package types' are the Excepted Packages and the Industrial Packages of Type IP-1, IP-2 and IP-3 and packages of Type A. For these types of packages an assessment by the competent authority is required for the quality assurance measures for the design, manufacture, testing, documentation, use, maintenance and inspection (IAEA SSR 6, Chap. 306). In general a compliance audit of the manufacturer of the packaging is required during this assessment procedure. Their regulatory level in the IAEA regulations is not comparable with the 'regulatory density' for packages requiring competent authority package design approval. Practices in different countries lead to different approaches within the assessment of the quality assurance measures in the management system as well as in the quality assurance program of a special package design. To use the package or packaging in a safe manner and in compliance with the regulations a management system for each phase of the life of the package or packaging is necessary. The relevant IAEA-SSR6 chap. 801 requires documentary verification by the consignor concerning package compliance with the requirements. (authors)

  13. Acute renal failure requiring renal replacement therapy in the intensive care unit: impact on prognostic assessment for shared decision making.

    Science.gov (United States)

    Johnson, Robert F; Gustin, Jillian

    2011-07-01

    A 69-year-old female was receiving renal replacement therapy (RRT) for acute renal failure (ARF) in an intensive care unit (ICU). Consultation was requested from the palliative medicine service to facilitate a shared decision-making process regarding goals of care. Clinician responsibility in shared decision making includes the formulation and expression of a prognostic assessment providing the necessary perspective for a spokesperson to match patient values with treatment options. For this patient, ARF requiring RRT in the ICU was used as a focal point for preparing a prognostic assessment. A prognostic assessment should include the outcomes of most importance to a discussion of goals of care: mortality risk and survivor functional status, in this case including renal recovery. A systematic review of the literature was conducted to document published data regarding these outcomes for adult patients receiving RRT for ARF in the ICU. Forty-one studies met the inclusion criteria. The combined mean values for short-term mortality, long-term mortality, renal-function recovery of short-term survivors, and renal-function recovery of long-term survivors were 51.7%, 68.6%, 82.0%, and 88.4%, respectively. This case example illustrates a process for formulating and expressing a prognostic assessment for an ICU patient requiring RRT for ARF. Data from the literature review provide baseline information that requires adjustment to reflect specific patient circumstances. The nature of the acute primary process, comorbidities, and severity of illness are key modifiers. Finally, the prognostic assessment is expressed during a family meeting using recommended principles of communication.

  14. Assessment of technical risks and R and D requirements for a magnetic confinement fusion fuel system. Final report

    International Nuclear Information System (INIS)

    DeFreece, D.A.

    1983-11-01

    This report documents a specific use and results of a novel technique for assessing the technical risks associated with the hardware development of a possible future commercial fusion power plant fuel system. Technical risk is defined as the risk that a particular technology or component which is currently under development will not achieve a set of required technical specifications. A technical risk assessment is the quantification of this risk. This Technical Risk Assessment (TRA) methodology was applied to a deuterium-tritium fuel system for a magnetic-confinement fusion power plant. The fuel system is defined to support a generic commercial reactor with at least two viable options for each critical subsystem. Each subsystem option is defined in detail including nominal performance requirements and subsystem interfaces. Subsystem experts were canvassed to obtain values for past, present and future technical performance parameters for each of the subsystem options. These forecasts are presented as probabilities of achieving given levels of performance in specific time periods for assumed funding scenarios. Several funding scenarios were examined to discern whether performance limitations are caused by funding or technology. A computerized Fuel System simulation is described which uses these subsystem performance parameter forecasts as inputs

  15. Orbitmpi Documentation

    International Nuclear Information System (INIS)

    Lowe, Lisa L.

    2000-01-01

    Orbitmpi is a parallelized version of Roscoe White's Orbit code. The code has been parallelized using MPI, which makes it portable to many types of machines. The guidelines used for the parallelization were to increase code performance with minimal changes to the code's original structure. This document gives a general description of how the parallel sections of the code run. It discusses the changes made to the original code and comments on the general procedure for future additions to Orbitmpi, as well as describing the effects of a parallelized random number generator on the code's output. Finally, the scaling results from Hecate and from Puffin are presented. Hecate is a 64-processor Origin 2000 machine, with MIPS R12000 processors and 16GB of memory, and Puffin is a PC cluster with 9 dual-processor 450 MHz Pentium III (18 processors max.), with 100Mbits ethernet communication

  16. Documentation of spectrom-32

    International Nuclear Information System (INIS)

    Callahan, G.D.; Fossum, A.F.; Svalstad, D.K.

    1989-01-01

    SPECTROM-32 is a finite element program for analyzing two-dimensional and axisymmetric inelastic thermomechanical problems related to the geological disposal of nuclear waste. The code is part of the SPECTROM series of special-purpose computer programs that are being developed by RE/SPEC Inc. to address many unique rock mechanics problems encountered in analyzing radioactive wastes stored in geologic formations. This document presents the theoretical basis for the mathematical models, the finite element formulation and solution procedure of the program, a description of the input data for the program, verification problems, and details about program support and continuing documentation. The computer code documentation is intended to satisfy the requirements and guidelines outlined in the document entitled Final Technical Position on Documentation of Computer Codes for High-Level Waste Management. The principal component models used in the program involve thermoelastic, thermoviscoelastic, thermoelastic-plastic, and thermoviscoplastic types of material behavior. Special material considerations provide for the incorporation of limited-tension material behavior and consideration of jointed material behavior. Numerous program options provide the capabilities for various boundary conditions, sliding interfaces, excavation, backfill, arbitrary initial stresses, multiple material domains, load incrementation, plotting database storage and access of results, and other features unique to the geologic disposal of radioactive wastes. Numerous verification problems that exercise many of the program options and illustrate the required data input and printed results are included in the documentation

  17. Functional Behavior Assessments and Behavior Intervention Plans: Legal Requirements and Professional Recommendations

    Science.gov (United States)

    Collins, Lauren W.; Zirkel, Perry A.

    2017-01-01

    Functional behavior assessments (FBAs) and behavior intervention plans (BIPs) are critical components in the education of students with, or at risk for, emotional disturbance (ED). The purpose of this article is to compare the legal requirements with the professional requirements for FBAs and BIPs. The comparison is first according to the…

  18. Technical basis document for internal dosimetry

    International Nuclear Information System (INIS)

    Hickman, D.P.

    1991-01-01

    This document provides the technical basis for the Chem-Nuclear Geotech (Geotech) internal dosimetry program. Geotech policy describes the intentions of the company in complying with radiation protection standards and the as low as reasonably achievable (ALARA) program. It uses this policy and applicable protection standards to derive acceptable methods and levels of bioassay to assure compliance. The models and computational methods used are described in detail within this document. FR-om these models, dose- conversion factors and derived limits are computed. These computations are then verified using existing documentation and verification information or by demonstration of the calculations used to obtain the dose-conversion factors and derived limits. Recommendations for methods of optimizing the internal dosimetry program to provide effective monitoring and dose assessment for workers are provided in the last section of this document. This document is intended to be used in establishing an accredited dosimetry program in accordance with expected Department of Energy Laboratory Accreditation Program (DOELAP) requirements for the selected radionuclides provided in this document, including uranium mill tailing mixtures. Additions and modifications to this document and procedures derived FR-om this document are expected in the future according to changes in standards and changes in programmatic mission

  19. Extremely secure identification documents

    International Nuclear Information System (INIS)

    Tolk, K.M.; Bell, M.

    1997-09-01

    The technology developed in this project uses biometric information printed on the document and public key cryptography to ensure that an adversary cannot issue identification documents to unauthorized individuals or alter existing documents to allow their use by unauthorized individuals. This process can be used to produce many types of identification documents with much higher security than any currently in use. The system is demonstrated using a security badge as an example. This project focused on the technologies requiring development in order to make the approach viable with existing badge printing and laminating technologies. By far the most difficult was the image processing required to verify that the picture on the badge had not been altered. Another area that required considerable work was the high density printed data storage required to get sufficient data on the badge for verification of the picture. The image processing process was successfully tested, and recommendations are included to refine the badge system to ensure high reliability. A two dimensional data array suitable for printing the required data on the badge was proposed, but testing of the readability of the array had to be abandoned due to reallocation of the budgeted funds by the LDRD office

  20. Comprehensive Psychopathological Assessment Based on the Association for Methodology and Documentation in Psychiatry (AMDP) System: Development, Methodological Foundation, Application in Clinical Routine, and Research

    Science.gov (United States)

    Stieglitz, Rolf-Dieter; Haug, Achim; Fähndrich, Erdmann; Rösler, Michael; Trabert, Wolfgang

    2017-01-01

    The documentation of psychopathology is core to the clinical practice of the psychiatrist and clinical psychologist. However, both in initial as well as further training and specialization in their fields, this particular aspect of their work receives scanty attention only. Yet, for the past 50 years, the Association for Methodology and Documentation in Psychiatry (AMDP) System has been in existence and available as a tool to serve precisely the purpose of offering a systematic introduction to the terminology and documentation of psychopathology. The motivation for its development was based on the need for an assessment procedure for the reliable documentation of the effectiveness of newly developed psychopharmacological substances. Subsequently, the AMDP-System began to be applied in the context of investigations into a number of methodological issues in psychiatry (e.g., the frequency and specificity of particular symptoms, the comparison of rating scales). The System then became increasingly important also in clinical practice and, today, represents the most used instrument for the documentation of psychopathology in the German-speaking countries of Europe. This paper intends to offer an overview of the AMDP-System, its origins, design, and functionality. After an initial account of the history and development of the AMDP-System, the discussion will in turn focus on the System’s underlying methodological principles, the transfer of clinical skills and competencies in its practical application, and its use in research and clinical practice. Finally, potential future areas of development in relation to the AMDP-System are explored. PMID:28439242

  1. Framework for Assessing the ICT Competency in Teachers up to the Requirements of "Teacher" Occupational Standard

    Science.gov (United States)

    Avdeeva, Svetlana; Zaichkina, Olga; Nikulicheva, Nataliya; Khapaeva, Svetlana

    2016-01-01

    The paper deals with problems of working out a test framework for the assessment of teachers' ICT competency in line with the requirements of "Teacher" occupational standard. The authors have analyzed the known approaches to assessing teachers' ICT competency--ISTE Standards and UNESCO ICT CFT and have suggested their own approach to…

  2. 76 FR 67622 - Modification of Regulatory Provisions Requiring Credit Rating or Assessments in Accordance With...

    Science.gov (United States)

    2011-11-02

    ... requirements to provide a credit rating or other credit assessment as part of an application for financial... that may affect family well-being. This rule would not have any impact on the autonomy or integrity of... rating or other credit assessment as part of an application for financial assistance or an application to...

  3. The psychiatric inpatient physical health assessment sheet (PIPHAS): a useful tool to improve the speed, efficiency, and documentation of physical examination in new psychiatric inpatients.

    Science.gov (United States)

    Pettipher, Alexander; Ovens, Richard

    2015-01-01

    There is increased morbidity and mortality among patients suffering from mental illness. This is believed to be multi-factorial. Poor access to healthcare, the stigma of mental illness, reduced clinic attendance, lifestyle factors, and side effects of medications are cited as possible contributing factors. It is therefore vital to perform a physical examination to identify previously undiagnosed conditions during the admission of a psychiatric inpatient. The Royal College of Psychiatrists recommends that all patients admitted to a psychiatric hospital should receive a full physical examination on admission, or within twenty-four hours of admission. A snapshot audit was carried out at Prospect Park Hospital in Reading, which highlighted that The Royal College of Psychiatrist's recommendation, along with Trust guidelines regarding physical examination were not being met, with only 78 out of 111 patients (70.3%) undergoing an examination during their admission. In addition to this, examinations were often poorly documented and not covering all examination domains. A psychiatric inpatient physical health assessment sheet (PIPHAS) was designed and introduced, providing a quick and standardised approach to the documentation of a physical examination. After the intervention was put into practice, its impact was assessed by performing a retrospective review of the admission clerking notes of the next 100 admissions to Prospect Park Hospital. Following the introduction of the PIPHAS form there was an increase in the number of patients undergoing physical examination on admission to hospital (75 out of 100 patients, 75%). There was also an increase in the thorough documentation of all examination domains (e.g. respiratory examination) for patients that had a completed PIPHAS form scanned within their medical records. This quality improvement project demonstrates that the PIPHAS form is a useful tool to improve the speed, efficiency, and documentation of a thorough physical

  4. Outlook to 2060 for world forests and forest industries: a technical document supporting the Forest Service 2010 RPA assessment

    Science.gov (United States)

    Joseph Buongiorno; Shushuai Zhu; Ronald Raunikar; Jeffrey P. Prestemon

    2012-01-01

    Four RPA scenarios corresponding with scenarios from the Third and Fourth Assessments of the Intergovernmental Panel on Climate Change were simulated with the Global Forest Products Model to project forest area, volume, products demand and supply, international trade, prices, and value added up to 2060 for Africa, Asia, Europe, North America, Oceania, South America,...

  5. Forest Service programs, authorities, and relationships: A technical document supporting the 2000 USDA Forest Service RPA Assessment

    Science.gov (United States)

    Ervin G. Schuster; Michael A. Krebs

    2003-01-01

    The Forest and Rangeland Renewable Resources Planning Act (RPA) of 1974, as amended, directs the Forest Service to prepare and update a renewable resources assessment that would include "a description of Forest Service programs and responsibilities , their interrelationships, and the relationship of these programs and responsibilities to public and private...

  6. Overview of the structured assessment approach and documentation of algorithms to compute the probability of adversary detection

    International Nuclear Information System (INIS)

    Rice, T.R.; Derby, S.L.

    1978-01-01

    The Structured Assessment Approach was applied to material control and accounting systems at facilities that process Special Nuclear Material. Four groups of analytical techniques were developed for four general adversory types. Probabilistic algorithms were developed and compared with existing algorithms. 20 figures

  7. Study on systematic integration technology of design and safety assessment for HLW geological disposal. 2. Research document

    International Nuclear Information System (INIS)

    Ishihara, Yoshinao; Fukui, Hiroshi; Sagawa, Hiroshi; Matsunaga, Kenichi; Ito, Takaya; Kohanawa, Osamu; Kuwayama, Yuki

    2003-02-01

    The present study was carried out relating to basic design of the Geological Disposal Technology Integration System' that will be systematized as knowledge base for design analysis and safety assessment of HLW geological disposal system by integrating organically and hierarchically various technical information in three study field. The key conclusions are summarized as follows: (1) As referring to the current performance assessment report, the technical information for R and D program of HLW geological disposal system was systematized hierarchically based on summarized information in a suitable form between the work flow (work item) and processes/characteristic flow (process item). (2) As the result of the systematized technical information, database structure and system functions necessary for development and construction to the computer system were clarified in order to secure the relation between technical information and data set for assessment of HLW geological disposal system. (3) The control procedure for execution of various analysis code used by design and safety assessment in HLW geological disposal study was arranged possibility in construction of 'Geological Disposal Technology Integration System' after investigating the distributed computing technology. (author)

  8. Projecting county-level populations under three future scenarios: a technical document supporting the Forest Service 2010 RPA Assessment

    Science.gov (United States)

    Stanley J. Zarnoch; H. Ken Cordell; Carter J. Betz

    2010-01-01

    County-level population projections from 2010 to 2060 are developed under three national population growth scenarios for reporting in the 2010 Renewable Resources Planning Act (RPA) Assessment. These population growth scenarios are tied to global futures scenarios defined by the Intergovernmental Panel on Climate Change (IPCC), a program within the United Nations...

  9. Assessment of compliance with regulatory requirements for a best estimate methodology for evaluation of ECCS

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Un Chul; Jang, Jin Wook; Lim, Ho Gon; Jeong, Ik [Seoul National Univ., Seoul (Korea, Republic of); Sim, Suk Ku [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    2000-03-15

    Best estimate methodology for evaluation of ECCS proposed by KEPCO(KREM) os using thermal-hydraulic best-estimate code and the topical report for the methodology is described that it meets the regulatory requirement of USNRC regulatory guide. In this research the assessment of compliance with regulatory guide. In this research the assessment of compliance with regulatory requirements for the methodology is performed. The state of licensing procedure of other countries and best-estimate evaluation methodologies of Europe is also investigated, The applicability of models and propriety of procedure of uncertainty analysis of KREM are appraised and compliance with USNRC regulatory guide is assessed.

  10. CMS DOCUMENTATION

    CERN Multimedia

    CMS TALKS AT MAJOR MEETINGS The agenda and talks from major CMS meetings can now be electronically accessed from the ICMS Web site. The following items can be found on: http://cms.cern.ch/iCMS Management – CMS Weeks (Collaboration Meetings), CMS Weeks Agendas The talks presented at the Plenary Sessions. Management – CB – MB – FB Agendas and minutes are accessible to CMS members through Indico. LHCC The talks presented at the ‘CMS Meetings with LHCC Referees’ are available on request from the PM or MB Country Representative. Annual Reviews The talks presented at the 2008 Annual Reviews are posted in Indico. CMS DOCUMENTS It is considered useful to establish information on the first employment of CMS doctoral student upon completion of their theses.  Therefore it is requested that Ph.D students inform the CMS Secretariat about the nature of employment and name of their first employer. The Notes, Conference Reports and Theses published si...

  11. Assessment of the Possibility of Using Unmanned Aerial Vehicles (UAVs) for the Documentation of Hiking Trails in Alpine Areas.

    Science.gov (United States)

    Ćwiąkała, Paweł; Kocierz, Rafał; Puniach, Edyta; Nędzka, Michał; Mamczarz, Karolina; Niewiem, Witold; Wiącek, Paweł

    2017-12-29

    The research described in this paper deals with the documentation of hiking trails in alpine areas. The study presents a novel research topic, applying up-to-date survey techniques and top quality equipment with practical applications in nature conservation. The research presents the initial part of the process-capturing imagery, photogrammetric processing, quality checking, and a discussion on possibilities of the further data analysis. The research described in this article was conducted in the Tatra National Park (TNP) in Poland, which is considered as one of the most-visited national parks in Europe. The exceptional popularity of this place is responsible for intensification of morphogenetic processes, resulting in the development of numerous forms of erosion. This article presents the outcomes of research, whose purpose was to verify the usability of UAVs to check the condition of hiking trails in alpine areas. An octocopter equipped with a non-metric camera was used for measurements. Unlike traditional methods of measuring landscape features, such a solution facilitates acquisition of quasi-continuous data that has uniform resolution throughout the study area and high spatial accuracy. It is also a relatively cheap technology, which is its main advantage over equally popular laser scanning. The paper presents the complete methodology of data acquisition in harsh conditions and demanding locations of hiking trails on steep Tatra slopes. The paper also describes stages that lead to the elaboration of basic photogrammetric products relying on structure from motion (SfM) technology and evaluates the accuracy of the materials obtained. Finally, it shows the applicability of the prepared products to the evaluation of the spatial reach and intensity of erosion along hiking trails, and to the study of plant succession or tree stand condition in the area located next to hiking trails.

  12. Assessment of the Possibility of Using Unmanned Aerial Vehicles (UAVs for the Documentation of Hiking Trails in Alpine Areas

    Directory of Open Access Journals (Sweden)

    Paweł Ćwiąkała

    2017-12-01

    Full Text Available The research described in this paper deals with the documentation of hiking trails in alpine areas. The study presents a novel research topic, applying up-to-date survey techniques and top quality equipment with practical applications in nature conservation. The research presents the initial part of the process—capturing imagery, photogrammetric processing, quality checking, and a discussion on possibilities of the further data analysis. The research described in this article was conducted in the Tatra National Park (TNP in Poland, which is considered as one of the most-visited national parks in Europe. The exceptional popularity of this place is responsible for intensification of morphogenetic processes, resulting in the development of numerous forms of erosion. This article presents the outcomes of research, whose purpose was to verify the usability of UAVs to check the condition of hiking trails in alpine areas. An octocopter equipped with a non-metric camera was used for measurements. Unlike traditional methods of measuring landscape features, such a solution facilitates acquisition of quasi-continuous data that has uniform resolution throughout the study area and high spatial accuracy. It is also a relatively cheap technology, which is its main advantage over equally popular laser scanning. The paper presents the complete methodology of data acquisition in harsh conditions and demanding locations of hiking trails on steep Tatra slopes. The paper also describes stages that lead to the elaboration of basic photogrammetric products relying on structure from motion (SfM technology and evaluates the accuracy of the materials obtained. Finally, it shows the applicability of the prepared products to the evaluation of the spatial reach and intensity of erosion along hiking trails, and to the study of plant succession or tree stand condition in the area located next to hiking trails.

  13. Nuclide documentation. Element specific parameter values used in the biospheric models of the safety assessments SR 97 and SAFE

    International Nuclear Information System (INIS)

    Karlsson, Sara; Bergstroem, Ulla

    2002-05-01

    In this report the element and nuclide specific parameter values used in the biospheric models of the safety assessments SR 97 and SAFE are presented. The references used are presented and where necessary the process of estimation of data is described. The parameters treated in this report are distribution coefficients in soil, organic soil and suspended matter in freshwater and brackish water, root uptake factors for pasturage, cereals, root crops and vegetables, bioaccumulation factors for freshwater fish, brackish water fish, freshwater invertebrates and marine water plants, transfer coefficients for transfer to milk and meat, translocation factors and dose coefficients for external exposure, ingestion (age-dependent values) and inhalation (age-dependent values). The radionuclides treated are those which could be of interest in the two safety assessments. Physical data such as half-lives and type of decay are also presented

  14. Nuclide documentation. Element specific parameter values used in the biospheric models of the safety assessments SR 97 and SAFE

    Energy Technology Data Exchange (ETDEWEB)

    Karlsson, Sara; Bergstroem, Ulla [Studsvik Eco and Safety AB, Nykoeping (Sweden)

    2002-05-01

    In this report the element and nuclide specific parameter values used in the biospheric models of the safety assessments SR 97 and SAFE are presented. The references used are presented and where necessary the process of estimation of data is described. The parameters treated in this report are distribution coefficients in soil, organic soil and suspended matter in freshwater and brackish water, root uptake factors for pasturage, cereals, root crops and vegetables, bioaccumulation factors for freshwater fish, brackish water fish, freshwater invertebrates and marine water plants, transfer coefficients for transfer to milk and meat, translocation factors and dose coefficients for external exposure, ingestion (age-dependent values) and inhalation (age-dependent values). The radionuclides treated are those which could be of interest in the two safety assessments. Physical data such as half-lives and type of decay are also presented.

  15. Monitored Geologic Repository Project Description Document

    International Nuclear Information System (INIS)

    Curry, P.

    2000-01-01

    The primary objective of the Monitored Geologic Repository Project Description Document (PDD) is to allocate the functions, requirements, and assumptions to the systems at Level 5 of the Civilian Radioactive Waste Management System (CRWMS) architecture identified in Section 4. It provides traceability of the requirements to those contained in Section 3 of the ''Monitored Geologic Repository Requirements Document'' (MGR RD) (CRWMS M and O 2000b) and other higher-level requirements documents. In addition, the PDD allocates design related assumptions to work products of non-design organizations. The document provides Monitored Geologic Repository (MGR) engineering design basis in support of design and performance assessment in preparing for the Site Recommendation (SR) and License Application (LA) milestones. The engineering design basis documented in the PDD is to be captured in the System Description Documents (SDDs) which address each of the systems at Level 5 of the CRWMS architecture. The design engineers obtain the engineering design basis from the SDDs and by reference from the SDDs to the PDD. The design organizations and other organizations will obtain design related assumptions directly from the PDD. These organizations may establish additional assumptions for their individual activities, but such assumptions are not to conflict with the assumptions in the PDD. The PDD will serve as the primary link between the engineering design basis captured in the SDDs and the design requirements captured in U.S. Department of Energy (DOE) documents. The approved PDD is placed under Level 3 baseline control by the CRWMS Management and Operating Contractor (M and O) and the following portions of the PDD constitute the Technical Design Baseline for the MGR: the design characteristics listed in Table 2-1, the MGR Architecture (Section 4.1),the Engineering Design Bases (Section 5), and the Controlled Project Assumptions (Section 6)

  16. Specific, Measureable, Attainable, Relevant, and Timely (SMART) Documents: Utilized in Assessing Socioeconomic Impacts of Cascading Infrastructure Disruptions

    Science.gov (United States)

    2017-02-01

    northeastern Nigeria (11o51’N, 13o05’E), with an estimated total population of 1.2 million. Con- current with rapid urban growth , the local government...dictions. Assessing individuals within the population allows analysis of so- cial well-being in relation to potential cascading infrastructure...Minnesota Population Center NBS National Bureau of Statistics, Nigeria NGO nongovernment organizations NPR National Public Radio SMART specific

  17. Assessment of infrastructure development requirements for embarking on nuclear power program in Macedonia

    International Nuclear Information System (INIS)

    Popov, N.; Ilijovski, I.; Popovski, V.

    2015-01-01

    Over the past decades nuclear energy has been proven as reliable and economical energy supply that is capable of meeting demanding energy market requirements. Many countries around the world consider entering into new nuclear energy programs and building new power reactors for satisfying their increasing electrical energy needs. A nuclear power program is a major undertaking requiring careful planning, preparation and investment, and human resources for building adequate nuclear infrastructure. Preparations for making a decision to enter into a new nuclear energy program requires a significant amount of financial and human resources, time, and assistance from already developed countries and international nuclear organizations. The International Atomic Energy Agency (IAEA) from Vienna provides technical help, financial assistance, and documented knowledge that are important for countries facing the challenge of entering nuclear programs for the first time. The IAEA organizes technical courses and information exchange meetings for new countries at which experiences and lessons learned are provided to new countries. This paper describes the key activities in the process for making a decision to enter a new nuclear energy program. It describes the efforts currently being conducted in the Republic of Macedonia in the direction of collecting information, performing various feasibility studies, and engaging in regional cooperation for utilizing experiences of the regional countries in performing such activities, and in developing their nuclear power programs. This paper also provides an overview of the IAEA documents and recommendations that are relevant for this topic

  18. Bleeding risk assessment and management in atrial fibrillation patients. Executive Summary of a Position Document from the European Heart Rhythm Association [EHRA], endorsed by the European Society of Cardiology [ESC] Working Group on Thrombosis.

    Science.gov (United States)

    Lip, Gregory Y H; Andreotti, Felicita; Fauchier, Laurent; Huber, Kurt; Hylek, Elaine; Knight, Eve; Lane, Deirdre; Levi, Marcel; Marín, Francisco; Palareti, Gualtiero; Kirchhof, Paulus

    2011-12-01

    In this executive summary of a Consensus Document from the European Heart Rhythm Association, endorsed by the European Society of Cardiology Working Group on Thrombosis, we comprehensively review the published evidence and propose a consensus on bleeding risk assessments in atrial fibrillation (AF) patients. The main aim of the document was to summarise 'best practice' in dealing with bleeding risk in AF patients when approaching antithrombotic therapy, by addressing the epidemiology and size of the problem, and review established bleeding risk factors. We also summarise definitions of bleeding in the published literature. Patient values and preferences balancing the risk of bleeding against thromboembolism as well as the prognostic implications of bleeding are reviewed. We also provide an overview of published bleeding risk stratification and bleeding risk schema. Brief discussion of special situations (e.g. periablation, peri-devices such as implantable cardioverter defibrillators [ICD] or pacemakers, presentation with acute coronary syndromes and/or requiring percutanous coronary interventions/stents and bridging therapy) is made, as well as a discussion of the prevention of bleeds and managing bleeding complications. Finally, this document puts forwards consensus statements that may help to define evidence gaps and assist in everyday clinical practice.

  19. Assessing supply-side barriers to uptake of intermittent preventive treatment for malaria in pregnancy: a qualitative study and document and record review in two regions of Uganda.

    Science.gov (United States)

    Rassi, Christian; Graham, Kirstie; Mufubenga, Patrobas; King, Rebecca; Meier, Joslyn; Gudoi, Sam Siduda

    2016-07-04

    Intermittent preventive treatment in pregnancy (IPTp) with sulfadoxine-pyrimethamine (SP), provided as part of routine antenatal care (ANC), is one of three malaria-in-pregnancy prevention and control mechanisms recommended by the World Health Organization (WHO). However, despite high ANC attendance and increased efforts to address known obstacles, IPTp uptake figures have remained low. This study aimed to identify and assess barriers that continue to impede IPTp uptake in Uganda, in particular for women who attend ANC. The paper focuses on supply-side barriers, i.e., challenges relating to the health service provider. In-depth interviews were conducted in two regions of Uganda in November 2013 and April/May 2014 with four different target audiences: seven district health officials, 15 health workers, 19 women who had attended ANC, and five opinion leaders. In addition, a document and record review was carried out at four health facilities. Guidelines with regard to IPTp provision in Uganda have been shown to be inconsistent and, at the time of the research, did not reflect the most recent WHO policy recommendation. There is a lack of training and supervision opportunities for health workers, resulting in poor knowledge of IPTp guidelines and uncertainty about the safety and efficacy of SP. ANC is not consistently offered in health facilities, leading to some women being denied services. While strengthening of the supply chain appears to have reduced the occurrence of stock-outs of SP in public facilities, stock-outs reportedly continue to occur in the private sector. There are also sources of data inaccuracy along the data recording and reporting chain, limiting policy makers' ability to react adequately to trends and challenges. Given the high ANC attendance rates in Uganda, supply-side barriers are likely to account for many missed opportunities for the provision of IPTp in Uganda. Improvements will require consistent provision of ANC, implementation of current

  20. Omega documentation

    Energy Technology Data Exchange (ETDEWEB)

    Howerton, R.J.; Dye, R.E.; Giles, P.C.; Kimlinger, J.R.; Perkins, S.T.; Plechaty, E.F.

    1983-08-01

    OMEGA is a CRAY I computer program that controls nine codes used by LLNL Physical Data Group for: 1) updating the libraries of evaluated data maintained by the group (UPDATE); 2) calculating average values of energy deposited in secondary particles and residual nuclei (ENDEP); 3) checking the libraries for internal consistency, especially for energy conservation (GAMCHK); 4) producing listings, indexes and plots of the library data (UTILITY); 5) producing calculational constants such as group averaged cross sections and transfer matrices for diffusion and Sn transport codes (CLYDE); 6) producing and updating standard files of the calculational constants used by LLNL Sn and diffusion transport codes (NDFL); 7) producing calculational constants for Monte Carlo transport codes that use group-averaged cross sections and continuous energy for particles (CTART); 8) producing and updating standard files used by the LLNL Monte Carlo transport codes (TRTL); and 9) producing standard files used by the LANL pointwise Monte Carlo transport code MCNP (MCPOINT). The first four of these functions and codes deal with the libraries of evaluated data and the last five with various aspects of producing calculational constants for use by transport codes. In 1970 a series, called PD memos, of internal and informal memoranda was begun. These were intended to be circulated among the group for comment and then to provide documentation for later reference whenever questions arose about the subject matter of the memos. They have served this purpose and now will be drawn upon as source material for this more comprehensive report that deals with most of the matters covered in those memos.

  1. Omega documentation

    International Nuclear Information System (INIS)

    Howerton, R.J.; Dye, R.E.; Giles, P.C.; Kimlinger, J.R.; Perkins, S.T.; Plechaty, E.F.

    1983-08-01

    OMEGA is a CRAY I computer program that controls nine codes used by LLNL Physical Data Group for: 1) updating the libraries of evaluated data maintained by the group (UPDATE); 2) calculating average values of energy deposited in secondary particles and residual nuclei (ENDEP); 3) checking the libraries for internal consistency, especially for energy conservation (GAMCHK); 4) producing listings, indexes and plots of the library data (UTILITY); 5) producing calculational constants such as group averaged cross sections and transfer matrices for diffusion and Sn transport codes (CLYDE); 6) producing and updating standard files of the calculational constants used by LLNL Sn and diffusion transport codes (NDFL); 7) producing calculational constants for Monte Carlo transport codes that use group-averaged cross sections and continuous energy for particles (CTART); 8) producing and updating standard files used by the LLNL Monte Carlo transport codes (TRTL); and 9) producing standard files used by the LANL pointwise Monte Carlo transport code MCNP (MCPOINT). The first four of these functions and codes deal with the libraries of evaluated data and the last five with various aspects of producing calculational constants for use by transport codes. In 1970 a series, called PD memos, of internal and informal memoranda was begun. These were intended to be circulated among the group for comment and then to provide documentation for later reference whenever questions arose about the subject matter of the memos. They have served this purpose and now will be drawn upon as source material for this more comprehensive report that deals with most of the matters covered in those memos

  2. 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

  3. Subsurface Interim Measures/Interim Remedial Action Plan/ Environmental Assessment and Decision Document, Operable Unit No. 2

    International Nuclear Information System (INIS)

    1992-01-01

    The subject Interim Measures/Interim Remedial Action plan/Environmental Assessment (IM/IRAP/EA) addresses residual free-phase volatile organic compound (VOC) contamination suspected in the subsurface within an area identified as Operable Unit No. 2 (OU2). This IM/IRAP/EA also addresses radionuclide contamination beneath the 903 Pad at OU2. Although subsurface VOC and radionuclide contamination on represent a source of OU2 ground-water contamination, they pose no immediate threat to public health or the environment. This volume contains five appendices

  4. Socioeconomic information, Plainsboro area, New Jersey: Supplementary documentation for an environmental assessment for the CIT [Compact Ignition Tokamak] at PPPL

    International Nuclear Information System (INIS)

    Bentz, L.K.; Bender, D.S.

    1987-07-01

    This report contains socioeconomic information on the Plainsboro, New Jersey, area, the proposed location of the Compact Ignition Tokamak (CIT) facility. It was prepared as supplemental information for an environmental assessment for the CIT at Princeton Plasma Physics Laboratory (PPPL). The report contains descriptions of the demographic, economic, and community resource characteristics, and, based on information available in early 1987, considers the socioeconomic effect of the proposed facility. In all areas examined, the anticipated socioeconomic impacts of the proposed CIT facility at PPPL are negligible or minimal. 29 refs., 8 figs., 24 tabs

  5. Functional requirements document for the Earth Observing System Data and Information System (EOSDIS) Scientific Computing Facilities (SCF) of the NASA/MSFC Earth Science and Applications Division, 1992

    Science.gov (United States)

    Botts, Michael E.; Phillips, Ron J.; Parker, John V.; Wright, Patrick D.

    1992-01-01

    Five scientists at MSFC/ESAD have EOS SCF investigator status. Each SCF has unique tasks which require the establishment of a computing facility dedicated to accomplishing those tasks. A SCF Working Group was established at ESAD with the charter of defining the computing requirements of the individual SCFs and recommending options for meeting these requirements. The primary goal of the working group was to determine which computing needs can be satisfied using either shared resources or separate but compatible resources, and which needs require unique individual resources. The requirements investigated included CPU-intensive vector and scalar processing, visualization, data storage, connectivity, and I/O peripherals. A review of computer industry directions and a market survey of computing hardware provided information regarding important industry standards and candidate computing platforms. It was determined that the total SCF computing requirements might be most effectively met using a hierarchy consisting of shared and individual resources. This hierarchy is composed of five major system types: (1) a supercomputer class vector processor; (2) a high-end scalar multiprocessor workstation; (3) a file server; (4) a few medium- to high-end visualization workstations; and (5) several low- to medium-range personal graphics workstations. Specific recommendations for meeting the needs of each of these types are presented.

  6. An assessment of partition and transmutation against UK requirements for radioactive waste management: supporting studies

    International Nuclear Information System (INIS)

    Cummings, R.; Crookshanks, C.E.; McAdams, R.; Rogers, J.M.; Sims, H.E.; Smith-Briggs, J.L.

    1996-06-01

    A study of partition and transmutation (P and T) has recently been reported: An Assessment of Partition and Transmutation Against UK Requirements for Radioactive Waste Management (DOE/RAS/96.007). The prospects were assessed for real safety or financial gains being made through the future use of partition and transmutation within the United Kingdom in radioactive waste management. The assessment was made by AEA Technology, on behalf of the Department of the Environment. The assessment was partly based on the results of a number of studies described here. (Author)

  7. Nagra technical report 14-03, characteristic dosage intervals and documentation for the assessment of barrier systems

    International Nuclear Information System (INIS)

    2014-12-01

    This comprehensive technical report published by the Swiss National Cooperative for the Disposal of Radioactive Wastes Nagra discusses the procedure for selecting sites for deep geological repositories for all categories of radioactive waste produced in Switzerland, as defined in the conceptual part of the Sectoral Plan for Deep Geological Repositories (BFE 2008). Analyses are presented and discussed that determine the priority host rocks for the disposal of low, intermediate and high level radioactive wastes. The evaluation of the effectiveness of the barrier systems is discussed. Also, analyses are presented and discussed in connection with the regions where sites for the repositories may be located. Important site-specific geological information is examined which is to be used in the assessment of possible repository sites from the safety analysis point of view

  8. Health Information Technology Evaluation Framework (HITREF) Comprehensiveness as Assessed in Electronic Point-of-Care Documentation Systems Evaluations.

    Science.gov (United States)

    Sockolow, Paulina S; Bowles, Kathryn H; Rogers, Michelle

    2015-01-01

    We assessed the Health Information Technology (HIT) Reference-based Evaluation Framework (HITREF) comprehensiveness in two HIT evaluations in settings different from that in which the HITREF was developed. Clinician satisfaction themes that emerged from clinician interviews in the home care and the hospital studies were compared to the framework components. Across both studies, respondents commented on 12 of the 20 HITREF components within 5 of the 6 HITREF concepts. No new components emerged that were missing from the HITREF providing evidence that the HITREF is a comprehensive framework. HITREF use in a range of HIT evaluations by researchers new to the HITREF demonstrates that it can be used as intended. Therefore, we continue to recommend the HITREF as a comprehensive, research-based HIT evaluation framework to increase the capacity of informatics evaluators' use of best practice and evidence-based practice to support the credibility of their findings for fulfilling the purpose of program evaluation.

  9. Documenting pharmacist interventions on an intranet.

    Science.gov (United States)

    Simonian, Armen I

    2003-01-15

    The process of developing and implementing an intranet Web site for clinical intervention documentation is described. An inpatient pharmacy department initiated an organizationwide effort to improve documentation of interventions by pharmacists at its seven hospitals to achieve real-time capture of meaningful benchmarking data. Standardization of intervention types would allow the health system to contrast and compare medication use, process improvement, and patient care initiatives among its hospitals. After completing a needs assessment and reviewing current methodologies, a computerized tracking tool was developed in-house and integrated with the organization's intranet. Representatives from all hospitals agreed on content and functionality requirements for the Web site. The site was completed and activated in February 2002. Before this Web site was established, the most documented intervention types were Renal Adjustment and Clarify Dose, with a daily average of four and three, respectively. After site activation, daily averages for Renal Adjustment remained unchanged, but Clarify Dose is now documented nine times per day. Drug Information and i.v.-to-p.o. intervention types, which previously averaged less than one intervention per day, are now documented an average of four times daily. Approximately 91% of staff pharmacists are using this site. Future plans for this site include enhanced accessibility to the site with wireless personal digital assistants. The design and implementation of an intranet Web site to document pharmacists' interventions doubled the rate of intervention documentation and standardized the intervention types among hospitals in the health system.

  10. The Johnson Space Center Management Information Systems (JSCMIS). 1: Requirements Definition and Design Specifications for Versions 2.1 and 2.1.1. 2: Documented Test Scenario Environments. 3: Security Design and Specifications

    Science.gov (United States)

    1986-01-01

    The Johnson Space Center Management Information System (JSCMIS) is an interface to computer data bases at NASA Johnson which allows an authorized user to browse and retrieve information from a variety of sources with minimum effort. This issue gives requirements definition and design specifications for versions 2.1 and 2.1.1, along with documented test scenario environments, and security object design and specifications.

  11. Document management in engineering construction

    International Nuclear Information System (INIS)

    Liao Bing

    2008-01-01

    Document management is one important part of systematic quality management, which is one of the key factors to ensure the construction quality. In the engineering construction, quality management and document management shall interwork all the time, to ensure the construction quality. Quality management ensures that the document is correctly generated and adopted, and thus the completeness, accuracy and systematicness of the document satisfy the filing requirements. Document management ensures that the document is correctly transferred during the construction, and various testimonies such as files and records are kept for the engineering construction and its quality management. This paper addresses the document management in the engineering construction based on the interwork of the quality management and document management. (author)

  12. Environmental assessment for the proposed CMR Building upgrades at the Los Alamos National Laboratory, Los Alamos, New Mexico. Final document

    International Nuclear Information System (INIS)

    1997-01-01

    In order to maintain its ability to continue to conduct uninterrupted radioactive and metallurgical research in a safe, secure, and environmentally sound manner, the US Department of Energy (DOE) proposes to upgrade the Los Alamos National Laboratory (LANL) Chemistry and Metallurgy Research (CMR) Building. The building was built in the early 1950s to provide a research and experimental facility for analytical chemistry, plutonium and uranium chemistry, and metallurgy. Today, research and development activities are performed involving nuclear materials. A variety of radioactive and chemical hazards are present. The CMR Building is nearing the end of its original design life and does not meet many of today's design codes and standards. The Proposed Action for this Environmental Assessment (EA) includes structural modifications to some portions of the CMR Building which do not meet current seismic criteria for a Hazard Category 2 Facility. Also included are upgrades and improvements in building ventilation, communications, monitoring, and fire protection systems. This EA analyzes the environmental effects of construction of the proposed upgrades. The Proposed Action will have no adverse effects upon agricultural and cultural resources, wetlands and floodplains, endangered and threatened species, recreational resources, or water resources. The Proposed Action would have negligible effects on human health and transportation, and would not pose a disproportionate adverse health or environmental impact on minority or low-income populations within an 80 kilometer (50 mile) radius of the CMR Building

  13. Environmental assessment for the proposed CMR Building upgrades at the Los Alamos National Laboratory, Los Alamos, New Mexico. Final document

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-02-04

    In order to maintain its ability to continue to conduct uninterrupted radioactive and metallurgical research in a safe, secure, and environmentally sound manner, the US Department of Energy (DOE) proposes to upgrade the Los Alamos National Laboratory (LANL) Chemistry and Metallurgy Research (CMR) Building. The building was built in the early 1950s to provide a research and experimental facility for analytical chemistry, plutonium and uranium chemistry, and metallurgy. Today, research and development activities are performed involving nuclear materials. A variety of radioactive and chemical hazards are present. The CMR Building is nearing the end of its original design life and does not meet many of today`s design codes and standards. The Proposed Action for this Environmental Assessment (EA) includes structural modifications to some portions of the CMR Building which do not meet current seismic criteria for a Hazard Category 2 Facility. Also included are upgrades and improvements in building ventilation, communications, monitoring, and fire protection systems. This EA analyzes the environmental effects of construction of the proposed upgrades. The Proposed Action will have no adverse effects upon agricultural and cultural resources, wetlands and floodplains, endangered and threatened species, recreational resources, or water resources. The Proposed Action would have negligible effects on human health and transportation, and would not pose a disproportionate adverse health or environmental impact on minority or low-income populations within an 80 kilometer (50 mile) radius of the CMR Building.

  14. Detailed requirements document for Stowage List and Hardware Tracking System (SLAHTS). [computer based information management system in support of space shuttle orbiter stowage configuration

    Science.gov (United States)

    Keltner, D. J.

    1975-01-01

    The stowage list and hardware tracking system, a computer based information management system, used in support of the space shuttle orbiter stowage configuration and the Johnson Space Center hardware tracking is described. The input, processing, and output requirements that serve as a baseline for system development are defined.

  15. Summary of utility/user requirements for and assessment of the MHTGR

    International Nuclear Information System (INIS)

    Mears, L.D.; Hoffman, D.P.

    1992-01-01

    Through Gas-Cooled Reactor Associates (GCRA), utilities provide end-user requirements, conduct ongoing technical and economic assessments and participate in the development of deployment strategies for the Modular High Temperature Gas-Cooled Reactor (MHTGR). It is GCRA's goal that the MHTGR be established as an attractive nuclear option for safe, reliable and economic energy supply with limited ownership risks. This report describes the rationale for the key GCRA requirements and presents a summary economic assessment of the reference, 4 module steam cycle design. (author)

  16. Biosphere modelling for safety assessment of geological disposal taking account of denudation of contaminated soils. Research document

    International Nuclear Information System (INIS)

    Kato, Tomoko

    2003-03-01

    Biosphere models for safety assessment of geological disposal have been developed on the assumption that the repository-derived radionuclides reach surface environment by groundwater. In the modelling, river, deep well and marine have been considered as geosphere-biosphere (GBIs) and some Japanese-specific ''reference biospheres'' have been developed using an approach consistent with the BIOMOVS II/BIOMASS Reference Biosphere Methodology. In this study, it is assumed that the repository-derived radionuclide would reach surface environment in the form of solid phase by uplift and erosion of contaminated soil and sediment. The radionuclides entered into the surface environment by these processes could be distributed between solid and liquid phases and could spread within the biosphere via solid phase and also liquid phase. Based on these concepts, biosphere model that considers variably saturated zone under surface soil (VSZ) as a GBI was developed for calculating the flux-to-dose conversion factors of three exposure groups (farming, freshwater fishing, marine fishing) based on the Reference Biosphere Methodology. The flux-to-dose conversion factors for faming exposure group were the highest, and ''inhalation of dust'', external irradiation from soil'' and ''ingestion of soil'' were the dominant exposure pathways for most of radionuclides considered in this model. It is impossible to compare the flux-to-dose conversion factors calculated by the biosphere model in this study with those calculated by the biosphere models developed in the previous studies because the migration processes considered when the radionuclides entered the surface environment through the aquifer are different among the models; i.e. it has been assumed that the repository-derived radionuclides entered the GBIs such as river, deep well and marine via groundwater without dilution and retardation at the aquifer in the previous biosphere models. Consequently, it must be modelled the migration of

  17. Assessment of Adverse Events in Protocols, Clinical Study Reports, and Published Papers of Trials of Orlistat: A Document Analysis.

    Directory of Open Access Journals (Sweden)

    Jeppe Bennekou Schroll

    2016-08-01

    Full Text Available Little is known about how adverse events are summarised and reported in trials, as detailed information is usually considered confidential. We have acquired clinical study reports (CSRs from the European Medicines Agency through the Freedom of Information Act. The CSRs describe the results of studies conducted as part of the application for marketing authorisation for the slimming pill orlistat. The purpose of this study was to study how adverse events were summarised and reported in study protocols, CSRs, and published papers of orlistat trials.We received the CSRs from seven randomised placebo controlled orlistat trials (4,225 participants submitted by Roche. The CSRs consisted of 8,716 pages and included protocols. Two researchers independently extracted data on adverse events from protocols and CSRs. Corresponding published papers were identified on PubMed and adverse event data were extracted from this source as well. All three sources were compared. Individual adverse events from one trial were summed and compared to the totals in the summary report. None of the protocols or CSRs contained instructions for investigators on how to question participants about adverse events. In CSRs, gastrointestinal adverse events were only coded if the participant reported that they were "bothersome," a condition that was not specified in the protocol for two of the trials. Serious adverse events were assessed for relationship to the drug by the sponsor, and all adverse events were coded by the sponsor using a glossary that could be updated by the sponsor. The criteria for withdrawal due to adverse events were in one case related to efficacy (high fasting glucose led to withdrawal, which meant that one trial had more withdrawals due to adverse events in the placebo group. Finally, only between 3% and 33% of the total number of investigator-reported adverse events from the trials were reported in the publications because of post hoc filters, though six of

  18. Securing XML Documents

    Directory of Open Access Journals (Sweden)

    Charles Shoniregun

    2004-11-01

    Full Text Available XML (extensible markup language is becoming the current standard for establishing interoperability on the Web. XML data are self-descriptive and syntax-extensible; this makes it very suitable for representation and exchange of semi-structured data, and allows users to define new elements for their specific applications. As a result, the number of documents incorporating this standard is continuously increasing over the Web. The processing of XML documents may require a traversal of all document structure and therefore, the cost could be very high. A strong demand for a means of efficient and effective XML processing has posed a new challenge for the database world. This paper discusses a fast and efficient indexing technique for XML documents, and introduces the XML graph numbering scheme. It can be used for indexing and securing graph structure of XML documents. This technique provides an efficient method to speed up XML data processing. Furthermore, the paper explores the classification of existing methods impact of query processing, and indexing.

  19. Edible safety requirements and assessment standards for agricultural genetically modified organisms.

    Science.gov (United States)

    Deng, Pingjian; Zhou, Xiangyang; Zhou, Peng; Du, Zhong; Hou, Hongli; Yang, Dongyan; Tan, Jianjun; Wu, Xiaojin; Zhang, Jinzhou; Yang, Yongcun; Liu, Jin; Liu, Guihua; Li, Yonghong; Liu, Jianjun; Yu, Lei; Fang, Shisong; Yang, Xiaoke

    2008-05-01

    This paper describes the background, principles, concepts and methods of framing the technical regulation for edible safety requirement and assessment of agricultural genetically modified organisms (agri-GMOs) for Shenzhen Special Economic Zone in the People's Republic of China. It provides a set of systematic criteria for edible safety requirements and the assessment process for agri-GMOs. First, focusing on the degree of risk and impact of different agri-GMOs, we developed hazard grades for toxicity, allergenicity, anti-nutrition effects, and unintended effects and standards for the impact type of genetic manipulation. Second, for assessing edible safety, we developed indexes and standards for different hazard grades of recipient organisms, for the influence of types of genetic manipulation and hazard grades of agri-GMOs. To evaluate the applicability of these criteria and their congruency with other safety assessment systems for GMOs applied by related organizations all over the world, we selected some agri-GMOs (soybean, maize, potato, capsicum and yeast) as cases to put through our new assessment system, and compared our results with the previous assessments. It turned out that the result of each of the cases was congruent with the original assessment.

  20. A 10-Year Assessment of Information and Communication Technology Tasks Required in Undergraduate Agriculture Courses

    Science.gov (United States)

    Edgar, Leslie D.; Johnson, Donald M.; Cox, Casandra

    2012-01-01

    This study sought to assess required information and communication technology (ICT) tasks in selected undergraduate agriculture courses in a land-grant university during a 10-year period. Selected agriculture faculty members in the fall 1999 (n = 63), 2004 (n = 55), and 2009 (n = 64) semesters were surveyed to determine the ICT tasks they required…

  1. Sample Size Requirements for Assessing Statistical Moments of Simulated Crop Yield Distributions

    NARCIS (Netherlands)

    Lehmann, N.; Finger, R.; Klein, T.; Calanca, P.

    2013-01-01

    Mechanistic crop growth models are becoming increasingly important in agricultural research and are extensively used in climate change impact assessments. In such studies, statistics of crop yields are usually evaluated without the explicit consideration of sample size requirements. The purpose of

  2. The water footprint of energy consumption: an assessment of water requirements of primary energy carriers

    NARCIS (Netherlands)

    Gerbens-Leenes, P.W.; Hoekstra, A.Y.; Van der Meer, T.H.

    2007-01-01

    Gerbens-Leenes, P.W., Hoekstra, A.Y., Van der Meer, T.H., 2007. The water footprint of energy consumption: an assessment of water requirements of primary energy carriers. In: proceedings ‘First World Water Sustainability-Renewable Energy Congress and Exhibition’. 25-28 November 2007, Maastricht, the

  3. 75 FR 77652 - Proposed Information Collection; Assessment of the Business Requirements and Benefits of Enhanced...

    Science.gov (United States)

    2010-12-13

    ... Collection; Assessment of the Business Requirements and Benefits of Enhanced National Elevation Data AGENCY... for The National Map. This study seeks to establish a baseline of national business needs and associated benefits for LiDAR to enhance the responsiveness of USGS programs, and to design an efficient...

  4. Employers Assessment of Work Ethics Required of University Business Education Graduates in South-South Nigeria

    Science.gov (United States)

    Okoro, James

    2014-01-01

    This study examined the employers assessment of work ethics required of university Business Education graduates in south south Nigeria. One research question and three hypotheses guided the study. The design of this study was a descriptive survey. The population of the study comprised 318 identified employers of Business Education graduates in…

  5. 78 FR 28118 - Vidalia Onions Grown in Georgia; Change in Reporting and Assessment Requirements

    Science.gov (United States)

    2013-05-14

    ... onion producers in the designated production area. Small agricultural service firms, which include...; FV13-955-1 IR] Vidalia Onions Grown in Georgia; Change in Reporting and Assessment Requirements AGENCY... Vidalia onions grown in Georgia (order). The order regulates the handling of Vidalia onions grown in...

  6. 77 FR 31086 - Requirements Pertaining to Third Party Conformity Assessment Bodies

    Science.gov (United States)

    2012-05-24

    ... 22030 (April 20, 2011). Third Party Testing for Certain Children's Products; Toys: Requirements for... Bodies to Assess Conformity With the Limits on Phthalates in Children's Toys and Child Care Articles, 76... initiatives, including program development for third party testing of children's products. The commenter...

  7. Application of Grounded Theory in Determining Required Elements for IPv6 Risk Assessment Equation

    Directory of Open Access Journals (Sweden)

    Rosli Athirah

    2018-01-01

    Full Text Available The deployment of Internet Protocol version 6 (IPv6 has raised security concerns among the network administrators. Thus, in strengthening the network security, administrator requires an appropriate method to assess the possible risks that occur in their networks. Aware of the needs to calculate risk in IPv6 network, it is essential to an organization to have an equation that is flexible and consider the requirements of the network. However, the existing risk assessment equations do not consider the requirement of the network. Therefore, this paper presents the adaptation of grounded theory to search for elements that are needed to develop IPv6 risk assessment (IRA6 equation. The attack scenarios’ experiments; UDP Flooding, TCP Flooding and Multicast attacks were carried out in different network environment to show how the IPv6 risk assessment equation being used. The result shows that the IRA6 equation is more flexible to be used regardless the network sizes and easier to calculate the risk value compared to the existing risk assessment equations. Hence, network administrators can have a proper decision making and strategic planning for a robust network security.

  8. Assessing the Effect of an Educational Intervention on Nurses' and Patient Care Assistants' Comprehension and Documentation of Functional Ability in Pediatric Patients with Sickle Cell Disease.

    Science.gov (United States)

    Bernier, Katherine M; Strobel, Megan; Lucas, Ruth

    2018-04-13

    In 2014, the Youth Acute Pain Functional Ability Questionnaire (YAPFAQ) was developed to investigate patient's self-rated functional ability during times of acute pain in the inpatient clinical setting. Although it has great potential, the application of this tool has not been made a standard of care. The purpose of this multiple methods study was to determine if, through an educational intervention, hospital staff could consistently document the YAPFAQ in children with sickle cell disease (SCD) during a vaso-occlusive episode. Twenty-two staff members participated in an educational intervention and semi-structured group discussions. Pre/post surveys measured knowledge of the YAPFAQ before and after the intervention. Group discussions were recorded, transcribed verbatim, and analyzed for thematic clusters. Retrospective chart reviews of children with SCD were reviewed for YAPFAQ documentation frequency before and after the intervention. Staff knowledge of who completes the YAPFAQ increased after the intervention, (pcontinues to hold high potential for directing nursing care, but requires staff investment for clinical practice change. A seamless integration between nursing education and translation through EHR is recommended as technology continues to integrate into nursing practice. Copyright © 2018 Elsevier Inc. All rights reserved.

  9. 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)

  10. Assessing Energy Requirements in Women With Polycystic Ovary Syndrome: A Comparison Against Doubly Labeled Water.

    Science.gov (United States)

    Broskey, Nicholas T; Klempel, Monica C; Gilmore, L Anne; Sutton, Elizabeth F; Altazan, Abby D; Burton, Jeffrey H; Ravussin, Eric; Redman, Leanne M

    2017-06-01

    Weight loss is prescribed to offset the deleterious consequences of polycystic ovary syndrome (PCOS), but a successful intervention requires an accurate assessment of energy requirements. Describe energy requirements in women with PCOS and evaluate common prediction equations compared with doubly labeled water (DLW). Cross-sectional study. Academic research center. Twenty-eight weight-stable women with PCOS completed a 14-day DLW study along with measures of body composition and resting metabolic rate and assessment of physical activity by accelerometry. Total daily energy expenditure (TDEE) determined by DLW. TDEE was 2661 ± 373 kcal/d. TDEE estimated from four commonly used equations was within 4% to 6% of the TDEE measured by DLW. Hyperinsulinemia (fasting insulin and homeostatic model assessment of insulin resistance) was associated with TDEE estimates from all prediction equations (both r = 0.45; P = 0.02) but was not a significant covariate in a model that predicts TDEE. Similarly, hyperandrogenemia (total testosterone, free androgen index, and dehydroepiandrosterone sulfate) was not associated with TDEE. In weight-stable women with PCOS, the following equation derived from DLW can be used to determine energy requirements: TDEE (kcal/d) = 438 - [1.6 * Fat Mass (kg)] + [35.1 * Fat-Free Mass (kg)] + [16.2 * Age (y)]; R2 = 0.41; P = 0.005. Established equations using weight, height, and age performed well for predicting energy requirements in weight-stable women with PCOS, but more precise estimates require an accurate assessment of physical activity. Our equation derived from DLW data, which incorporates habitual physical activity, can also be used in women with PCOS; however, additional studies are needed for model validation. Copyright © 2017 Endocrine Society

  11. Electronic Braille Document Reader

    OpenAIRE

    Arif, Shahab; Holmes, Violeta

    2013-01-01

    This paper presents an investigation into developing a portable Braille device which would allow visually impaired individuals to read electronic documents by actuating Braille text on a finger. Braille books tend to be bulky in size due to the minimum size requirements for each Braille cell. E-books can be read in Braille using refreshable Braille displays connected to a computer. However, the refreshable Braille displays are expensive, bulky and are not portable. These factors restrict blin...

  12. Electronic Braille Document Reader

    OpenAIRE

    Arif, S.

    2012-01-01

    An investigation was conducted into developing a portable Braille device which would allow visually impaired individuals to read electronic documents by actuating Braille text on a finger. Braille books tend to be bulky in size due to the minimum size requirements for each Braille cell. E-books can be read in Braille using refreshable Braille displays connected to a computer. However, the refreshable Braille displays are expensive, bulky and are not portable. These factors restrict blind and ...

  13. 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.

  14. 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

  15. Radionuclide assessment of left ventricular function in patients requiring intraoperative balloon pump assistance

    International Nuclear Information System (INIS)

    Davies, R.A.; Laks, H.; Wackers, F.J.; Berger, H.J.; Williams, B.; Hammond, G.L.; Geha, A.S.; Gottschalk, A.; Zaret, B.L.

    1982-01-01

    Twenty-three surviving patients who were weaned from cardiopulmonary bypass with intraaortic balloon pump assistance returned for follow-up radionuclide left ventricular (LV) function and thallium 201 perfusion studies at a mean of 23 +/- 3 months following operation. It was found that despite profound intraoperative myocardial depression requiring intraaortic balloon assistance, 13 patients had no change (within 10%) in the resting LV ejection fraction compared with the preoperative measurement. Among all 23 patients, there was no difference between mean (+/- standard error of the mean) preoperative and postoperative resting LV ejection fraction (48 +/- 4 vs 46 +/- 4%, p . not significant [NS]). Only 11 patients had perioperative myocardial infarction documented by new Q waves in the electrocardiogram, by elevation of creatine kinase-MB fraction, or by defects on thallium 201 imaging not explained by documented myocardial infarction before operation. Overall, postoperative resting LV ejection fraction was not different from the preoperative value in patients with perioperative myocardial infarction (44 +/- 7 vs 47 +/- 5%, p . NS). Postoperative resting LV ejection fraction rose by greater than 10% compared with preoperative values in 4 patients (3 with aortic valve replacement), remained within the 10% limit in 9 patients, and fell by greater than 10% in 10 patients (7 with perioperative myocardial infarction). Only 4 out of 16 patients studied at follow-up with exercise radionuclide studies demonstrated a normal LV response to exercise (greater than 5% increase in LV ejection fraction). Thus, among survivors requiring intraaortic balloon pump assistance for weaning from cardiopulmonary bypass, LV performance at rest is frequently preserved. In addition, 11 of the 23 patients had evidence of perioperative myocardial infarction, indicating a component of reversible intraoperative LV dysfunction

  16. ITK optical links backup document

    CERN Document Server

    Huffman, B T; The ATLAS collaboration; Flick, T; Ye, J

    2013-01-01

    This document describes the proposed optical links to be used for the ITK in the phase II upgrade. The current R&D for optical links pursued in the Versatile Link group is reviewed. In particular the results demonstrating the radiation tolerance of all the on-detector components are documented. The bandwidth requirements and the resulting numerology are given.

  17. An assessment of seismic monitoring in the United States; requirement for an Advanced National Seismic System

    Science.gov (United States)

    ,

    1999-01-01

    This report assesses the status, needs, and associated costs of seismic monitoring in the United States. It sets down the requirement for an effective, national seismic monitoring strategy and an advanced system linking national, regional, and urban monitoring networks. Modernized seismic monitoring can provide alerts of imminent strong earthquake shaking; rapid assessment of distribution and severity of earthquake shaking (for use in emergency response); warnings of a possible tsunami from an offshore earthquake; warnings of volcanic eruptions; information for correctly characterizing earthquake hazards and for improving building codes; and data on response of buildings and structures during earthquakes, for safe, cost-effective design, engineering, and construction practices in earthquake-prone regions.

  18. Documentation of spectrom-41

    International Nuclear Information System (INIS)

    Svalstad, D.K.

    1989-01-01

    SPECTROM-41 is a finite element heat transfer computer program developed to analyze thermal problems related to nuclear waste disposal. The code is part of the SPECTROM (Special Purpose Engineering Codes for Thermal/ROck Mechanics) series of special purpose finite element programs that are continually being developed by RE/SPEC Inc. (RSI) to address the many unique formations. This document presents the theoretical basis for the mathematical model, the finite element formulation of the program, and a description of the input data for the program, along with details about program support and continuing documentation. The documentation is intended to satisfy the requirements and guidelines outlined in NUREG-0856. The principal component model used in the programs based on Fourier's law of conductance. Numerous program options provide the capability of considering various boundary conditions, material stratification and anisotropy, and time-dependent heat generation that are characteristic of problems involving the disposal of nuclear waste in geologic formation. Numerous verification problems are included in the documentation in addition to highlights of past and ongoing verification and validation efforts. A typical repository problem is solving using SPECTROM-41 to demonstrate the use of the program in addressing problems related to the disposal of nuclear waste

  19. Comparison of the guidance documents in support of EU risk assessments with those for the derivation of EU water quality standards

    NARCIS (Netherlands)

    Vos JH; Janssen MPM; SEC

    2005-01-01

    Risks of both new and existing substances and of biocides in Europe are being evaluated using the Technical Guidance Document (TGD). The European Water Framework Directive refers to this document for establishing Environmental Quality Standards (EQSs) for water. Another guidance document for the

  20. Virtual Library Design Document; TOPICAL

    International Nuclear Information System (INIS)

    M. A. deLamare

    2001-01-01

    The objective of this document is to establish a design for the virtual library user and administrative layers that complies with the requirements of the virtual library software specification and subordinate module specification

  1. Assessment of Today’s Mobile Banking Applications from the View of Customer Requirements

    OpenAIRE

    Pousttchi, Key; Schurig, Martin

    2004-01-01

    Mobile banking is a subset of electronic banking which underlies not only the determinants of the banking business but also the special conditions of mobile commerce. This paper analyzes customer needs and expectations from the mobile applications’ view and from the banking view in order to derive a defined set of requirements. Based on these results, existing mobile banking applications are assessed. Their major shortcomings are explained, opportunities for their improvement are shown and th...

  2. Technical support document: Energy efficiency standards for consumer products: Refrigerators, refrigerator-freezers, and freezers including draft environmental assessment, regulatory impact analysis

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    The Energy Policy and Conservation Act (P.L. 94-163), as amended by the National Appliance Energy Conservation Act of 1987 (P.L. 100-12) and by the National Appliance Energy Conservation Amendments of 1988 (P.L. 100-357), and by the Energy Policy Act of 1992 (P.L. 102-486), provides energy conservation standards for 12 of the 13 types of consumer products` covered by the Act, and authorizes the Secretary of Energy to prescribe amended or new energy standards for each type (or class) of covered product. The assessment of the proposed standards for refrigerators, refrigerator-freezers, and freezers presented in this document is designed to evaluate their economic impacts according to the criteria in the Act. It includes an engineering analysis of the cost and performance of design options to improve the efficiency of the products; forecasts of the number and average efficiency of products sold, the amount of energy the products will consume, and their prices and operating expenses; a determination of change in investment, revenues, and costs to manufacturers of the products; a calculation of the costs and benefits to consumers, electric utilities, and the nation as a whole; and an assessment of the environmental impacts of the proposed standards.

  3. 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

  4. Information requirements for the probabilistic risk assessment of underground disposal of low level wastes

    International Nuclear Information System (INIS)

    Sumerling, T.J.; Thompson, B.G.J.

    1987-01-01

    The UK Department of the Environment (DoE) will perform independent post-closure safety assessment of proposals for the disposal of low-level radioactive wastes in engineered facilities in shallow ground. In this paper, the DoE assessment criteria, methodology and modelling capabilities are outlined; the general characteristics of the information required are discussed; and the specific information needs, as presently perceived, are identified. It is concluded that: most of the data that can be obtained by direct means is provided by site investigations and research now in hand, although there may be uncertainty due to sparse regional data; some parameters can only be obtained by, or with the assistance of subjective judgment; the process of data reduction is not straight forward and adequate time must be allowed for this if a comprehensive and defensible assessment is to be constructed

  5. A framework for quality assessment of just-in-time requirements : The case of open source feature requests

    NARCIS (Netherlands)

    Heck, P.M.; Zaidman, A.E.

    2017-01-01

    Until now, quality assessment of requirements has focused on traditional up-front requirements. Contrasting these traditional requirements are just-in-time (JIT) requirements, which are by definition incomplete, not specific and might be ambiguous when initially specified, indicating a different

  6. Toxicity assessment strategies, data requirements, and risk assessment approaches to derive health based guidance values for non-relevant metabolites of plant protection products.

    Science.gov (United States)

    Dekant, Wolfgang; Melching-Kollmuss, Stephanie; Kalberlah, Fritz

    2010-03-01

    In Europe, limits for tolerable concentrations of "non-relevant metabolites" for active ingredients (AI) of plant protection products in drinking water between 0.1 and 10 microg/L are discussed depending on the toxicological information available. "Non-relevant metabolites" are degradation products of AIs, which do not or only partially retain the targeted toxicities of AIs. For "non-relevant metabolites" without genotoxicity (to be confirmed by testing in vitro), the application of the concept of "thresholds of toxicological concern" results in a health-based drinking water limit of 4.5 microg/L even for Cramer class III compounds, using the TTC threshold of 90 microg/person/day (divided by 10 and 2). Taking into account the thresholds derived from two reproduction toxicity data bases a drinking water limit of 3.0 microg/L is proposed. Therefore, for "non-relevant metabolites" whose drinking water concentration is below 3.0 microg/L, no toxicity testing is necessary. This work develops a toxicity assessment strategy as a basis to delineate health-based limits for "non-relevant metabolites" in ground and drinking water. Toxicological testing is recommended to investigate, whether the metabolites are relevant or not, based on the hazard properties of the parent AIs, as outlined in the SANCO Guidance document. Also, genotoxicity testing of the water metabolites is clearly recommended. In this publication, tiered testing strategies are proposed for non-relevant metabolites, when drinking water concentrations >3.0 microg/L will occur. Conclusions based on structure-activity relationships and the detailed toxicity database on the parent AI should be included. When testing in animals is required for risk assessment, key aspects are studies along OECD-testing guidelines with "enhanced" study designs addressing additional endpoints such as reproductive toxicity and a developmental screening test to derive health-based tolerable drinking water limits with a limited number

  7. Assessment of the requirements for DOE's annual report to congress on low-level radioactive waste

    International Nuclear Information System (INIS)

    1987-10-01

    The Low-level Radioactive Waste Policy Amendments Act of 1985 (PL99-240; LLRWPAA) requires the Department of Energy (DOE) to ''submit to Congress on an annual basis a report which: (1) summarizes the progress of low-level waste disposal siting and licensing activities within each compact region, (2) reviews the available volume reduction technologies, their applications, effectiveness, and costs on a per unit volume basis, (3) reviews interim storage facility requirements, costs, and usage, (4) summarizes transportation requirements for such wastes on an inter- and intra-regional basis, (5) summarizes the data on the total amount of low-level waste shipped for disposal on a yearly basis, the proportion of such wastes subjected to volume reduction, the average volume reduction attained,, and the proportion of wastes stored on an interim basis, and (6) projects the interim storage and final disposal volume requirements anticipated for the following year, on a regional basis (Sec. 7(b)).'' This report reviews and assesses what is required for development of the annual report specified in the LLRWPAA. This report addresses each of the subject areas set out in the LLRWPAA

  8. A Conceptual Methodology for Assessing Acquisition Requirements Robustness against Technology Uncertainties

    Science.gov (United States)

    Chou, Shuo-Ju

    2011-12-01

    In recent years the United States has shifted from a threat-based acquisition policy that developed systems for countering specific threats to a capabilities-based strategy that emphasizes the acquisition of systems that provide critical national defense capabilities. This shift in policy, in theory, allows for the creation of an "optimal force" that is robust against current and future threats regardless of the tactics and scenario involved. In broad terms, robustness can be defined as the insensitivity of an outcome to "noise" or non-controlled variables. Within this context, the outcome is the successful achievement of defense strategies and the noise variables are tactics and scenarios that will be associated with current and future enemies. Unfortunately, a lack of system capability, budget, and schedule robustness against technology performance and development uncertainties has led to major setbacks in recent acquisition programs. This lack of robustness stems from the fact that immature technologies have uncertainties in their expected performance, development cost, and schedule that cause to variations in system effectiveness and program development budget and schedule requirements. Unfortunately, the Technology Readiness Assessment process currently used by acquisition program managers and decision-makers to measure technology uncertainty during critical program decision junctions does not adequately capture the impact of technology performance and development uncertainty on program capability and development metrics. The Technology Readiness Level metric employed by the TRA to describe program technology elements uncertainties can only provide a qualitative and non-descript estimation of the technology uncertainties. In order to assess program robustness, specifically requirements robustness, against technology performance and development uncertainties, a new process is needed. This process should provide acquisition program managers and decision

  9. ELECTRICAL POWER SYSTEM DESCRIPTION DOCUMENT

    Energy Technology Data Exchange (ETDEWEB)

    M. Maniyar

    2004-06-22

    The purpose of this revision of the System Description Document (SDD) is to establish requirements that drive the design of the electrical power system and their bases to allow the design effort to proceed to License Application. This SDD is a living document that will be revised at strategic points as the design matures over time. This SDD identifies the requirements and describes the system design as they exist at this time, with emphasis on those attributes of the design provided to meet the requirements. This SDD has been developed to be an engineering tool for design control. Accordingly, the primary audience are design engineers. This type of SDD leads and follows the design process. It leads the design process with regard to the flow down of upper tier requirements onto the system. Knowledge of these requirements is essential to performing the design process. This SDD follows the design with regard to the description of the system. The description provided in the SDD is a reflection of the results of the design process to date. Functional and operational requirements applicable to this system are obtained from ''Project Functional and Operational Requirements'' (F&OR) (Siddoway, 2003). Other requirements to support the design process have been taken from higher level requirements documents such as ''Project Design Criteria Document'' (PDC) (Doraswamy 2004), the fire hazards analyses, and the preclosure safety analysis. The above mentioned low-level documents address ''Project Requirements Document'' (PRD) (Canori and Leitner 2003) requirements. This SDD includes several appendices with supporting information. Appendix B lists key system charts, diagrams, drawings, and lists; and Appendix C is a list of system procedures.

  10. Documentation of Cultural Heritage Objects

    Directory of Open Access Journals (Sweden)

    Jon Grobovšek

    2013-09-01

    Full Text Available EXTENDED ABSTRACT:The first and important phase of documentation of cultural heritage objects is to understand which objects need to be documented. The entire documentation process is determined by the characteristics and scope of the cultural heritage object. The next question to be considered is the expected outcome of the documentation process and the purpose for which it will be used. These two essential guidelines determine each stage of the documentation workflow: the choice of the most appropriate data capturing technology and data processing method, how detailed should the documentation be, what problems may occur, what the expected outcome is, what it will be used for, and the plan for storing data and results. Cultural heritage objects require diverse data capturing and data processing methods. It is important that even the first stages of raw data capturing are oriented towards the applicability of results. The selection of the appropriate working method can facilitate the data processing and the preparation of final documentation. Documentation of paintings requires different data capturing method than documentation of buildings or building areas. The purpose of documentation can also be the preservation of the contemporary cultural heritage to posterity or the basis for future projects and activities on threatened objects. Documentation procedures should be adapted to our needs and capabilities. Captured and unprocessed data are lost unless accompanied by additional analyses and interpretations. Information on tools, procedures and outcomes must be included into documentation. A thorough analysis of unprocessed but accessible documentation, if adequately stored and accompanied by additional information, enables us to gather useful data. In this way it is possible to upgrade the existing documentation and to avoid data duplication or unintentional misleading of users. The documentation should be archived safely and in a way to meet

  11. Documentation Requirements, Intrinsic Motivation, and Worker Absence

    DEFF Research Database (Denmark)

    Andersen, Lotte Bøgh; Kristensen, Nicolai; Holm Pedersen, Lene

    2015-01-01

    Command systems are widely used to monitor public service provision, but little is known about unintended effects on individual workers’ motivation and work effort. Using insights from motivation crowding theory, we estimate a SEM model that captures how Danish childcare assistants and social/hea......—and by drawing attention to possible downsides of command-and-control. Even though command systems can also have positive disciplining effects, knowledge about potential drawbacks is important for public managers.......Command systems are widely used to monitor public service provision, but little is known about unintended effects on individual workers’ motivation and work effort. Using insights from motivation crowding theory, we estimate a SEM model that captures how Danish childcare assistants and social...

  12. 22 CFR 201.52 - Required documents.

    Science.gov (United States)

    2010-04-01

    ... by an endorsement on or attachment to the invoice that payment has been made in the amount shown on... by USAID, the supplier has airmailed to the USAID Mission in the capital city of the cooperating... attachment to a copy of the invoice, a copy of the bill of lading (bearing a notation of the freight cost...

  13. MEGASTAR: The Meaning of Energy Growth: An Assessment of Systems, Technologies, and Requirements

    Science.gov (United States)

    1974-01-01

    A methodology for the display and analysis of postulated energy futures for the United States is presented. A systems approach that includes the methodology of technology assessment is used to examine three energy scenarios--the Westinghouse Nuclear Electric Economy, the Ford Technical Fix Base Case and a MEGASTAR generated Alternate to the Ford Technical Fix Base Case. The three scenarios represent different paths of energy consumption for the present to the year 2000. Associated with these paths are various mixes of fuels, conversion, distribution, conservation and end-use technologies. MEGASTAR presents the estimated times and unit requirements to supply the fuels, conversion and distribution systems for the postulated end uses for the three scenarios and then estimates the aggregate manpower, materials, and capital requirements needed to develop the energy system described by the particular scenario. The total requirements and the energy subsystems for each scenario are assessed for their primary impacts in the areas of society, the environment, technology and the economy.

  14. An assessment of the status and trends in satellite communications 1986-2000: An information document prepared for the Communications Subcommittee of the Space Applications Advisory Committee

    Science.gov (United States)

    Poley, W. A.; Stevens, G. H.; Stevenson, S. M.; Lekan, J.; Arth, C. H.; Hollansworth, J. E.; Miller, E. F.

    1986-01-01

    This is a response to a Space Applications Advisory Committee (SAAC) request for information about the status and trends in satellite communications, to be used to support efforts to conceive and recommend long range goals for NASA communications activities. Included in this document are assessments of: (1) the outlook for satellite communications, including current applications, potential future applications, and impact of the changing environment such as optical fiber networks, the Integrated Services Digital Network (ISDN) standard, and the rapidly growing market for Very Small Aperture Terminals (VSAT); (2) the restrictions imposed by our limited spectrum resource; and (3) technology needs indicated by future trends. Potential future systems discussed include: large powerful satellites for providing personal communications; VSAT compatible satellites with onboard switching and having voice capability; large satellites which offer a pervasive T1 network service (primarily for video-phone); and large geostationary communications facilities which support common use by several carriers. Also, discussion is included of NASA particular needs and possible future systems. Based on the mentioned system concepts, specific technology recommendations are provided for the time frames of now - 1993, 1994 - 2000, and 2000 - 2010.

  15. Assessing decision quality in patient-centred care requires a preference-sensitive measure

    Science.gov (United States)

    Kaltoft, Mette; Cunich, Michelle; Salkeld, Glenn; Dowie, Jack

    2014-01-01

    A theory-based instrument for measuring the quality of decisions made using any form of decision technology, including both decision-aided and unaided clinical consultations is required to enable person- and patient-centred care and to respond positively to individual heterogeneity in the value aspects of decision making. Current instruments using the term ‘decision quality’ have adopted a decision- and thus condition-specific approach. We argue that patient-centred care requires decision quality to be regarded as both preference-sensitive across multiple relevant criteria and generic across all conditions and decisions. MyDecisionQuality is grounded in prescriptive multi criteria decision analysis and employs a simple expected value algorithm to calculate a score for the quality of a decision that combines, in the clinical case, the patient’s individual preferences for eight quality criteria (expressed as importance weights) and their ratings of the decision just taken on each of these criteria (expressed as performance rates). It thus provides an index of decision quality that encompasses both these aspects. It also provides patients with help in prioritizing quality criteria for future decision making by calculating, for each criterion, the Incremental Value of Perfect Rating, that is, the increase in their decision quality score that would result if their performance rating on the criterion had been 100%, weightings unchanged. MyDecisionQuality, which is a web-based generic and preference-sensitive instrument, can constitute a key patient-reported measure of the quality of the decision-making process. It can provide the basis for future decision improvement, especially when the clinician (or other stakeholders) completes the equivalent instrument and the extent and nature of concordance and discordance can be established. Apart from its role in decision preparation and evaluation, it can also provide real time and relevant documentation for the patient

  16. Emergency Response Capability Baseline Needs Assessment Compliance Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Sharry, John A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2013-09-16

    This document is the second of a two-part analysis of Emergency Response Capabilities of Lawrence Livermore National Laboratory. The first part, 2013 Baseline Needs Assessment Requirements Document established the minimum performance criteria necessary to meet mandatory requirements. This second part analyses the performance of Lawrence Livermore Laboratory Emergency Management Department to the contents of the Requirements Document. The document was prepared based on an extensive review of information contained in the 2009 BNA, the 2012 BNA document, a review of Emergency Planning Hazards Assessments, a review of building construction, occupancy, fire protection features, dispatch records, LLNL alarm system records, fire department training records, and fire department policies and procedures.

  17. [Compliance with the requirements of paediatric emergency departments in Spain: a self-assessment survey].

    Science.gov (United States)

    Sánchez Etxaniz, J; Luaces I Cubells, C; Benito Fernández, J

    2011-08-01

    Paediatric emergency medicine in Spain is practiced in differently configured departments, staffing and organisation. Our goal was to determine the situation in Paediatric Emergency Departments (PED) and their adaptation to the quality standards proposed by the Spanish Society of Paediatric Emergencies. A self-assessment questionnaire on standards performance was sent to 47 PED directors by e-mail. It consisted of 101 items, 69 considered mandatory. According to the fulfilment of these 69 items 4 PED groups were selected: group I: in the best position (met 69), group II: requiring minimal changes (meeting 62-68), group III: requiring major changes (meeting 41-61); group IV: requiring a lot of major changes (meeting less than 41). Thirty nine questionnaires were completed in full. The PED included in the study tended to an average of 35310 annual emergencies (5000-115000). No PED was included in group I, 6 in II 27 in III and 6 in IV. There was a tendency towards higher compliance with standards in larger PED, but there was no significant relationship between the number of emergencies and the number of items fulfilled. 1. Staffing and architectural and organizational aspects may not be adequate to achieve optimal patient outcome in many PED in Spain. This fact does not appear to be related to the annual patient census. 2. The areas for improvement mainly affect functional issues that must be undertaken by those responsible. 3. A significant number of PED have serious architectural and staffing deficiencies, which would require economic measures by their managers. 4. Our self-assessment questionnaire identifies improvement actions. Copyright © 2010 Asociación Española de Pediatría. Published by Elsevier Espana. All rights reserved.

  18. Qualification of Simulation Software for Safety Assessment of Sodium Cooled Fast Reactors. Requirements and Recommendations

    Energy Technology Data Exchange (ETDEWEB)

    Brown, Nicholas R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Pointer, William David [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Sieger, Matt [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Flanagan, George F. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Moe, Wayne [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); HolbrookINL, Mark [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2016-04-01

    The goal of this review is to enable application of codes or software packages for safety assessment of advanced sodium-cooled fast reactor (SFR) designs. To address near-term programmatic needs, the authors have focused on two objectives. First, the authors have focused on identification of requirements for software QA that must be satisfied to enable the application of software to future safety analyses. Second, the authors have collected best practices applied by other code development teams to minimize cost and time of initial code qualification activities and to recommend a path to the stated goal.

  19. Preliminary Assessment of Operational Hazards and Safety Requirements for Airborne Trajectory Management (ABTM) Roadmap Applications

    Science.gov (United States)

    Cotton, William B.; Hilb, Robert; Koczo, Stefan, Jr.; Wing, David J.

    2016-01-01

    A set of five developmental steps building from the NASA TASAR (Traffic Aware Strategic Aircrew Requests) concept are described, each providing incrementally more efficiency and capacity benefits to airspace system users and service providers, culminating in a Full Airborne Trajectory Management capability. For each of these steps, the incremental Operational Hazards and Safety Requirements are identified for later use in future formal safety assessments intended to lead to certification and operational approval of the equipment and the associated procedures. Two established safety assessment methodologies that are compliant with the FAA's Safety Management System were used leading to Failure Effects Classifications (FEC) for each of the steps. The most likely FEC for the first three steps, Basic TASAR, Digital TASAR, and 4D TASAR, is "No effect". For step four, Strategic Airborne Trajectory Management, the likely FEC is "Minor". For Full Airborne Trajectory Management (Step 5), the most likely FEC is "Major".

  20. Tank Waste Remediation System tank waste pretreatment and vitrification process development testing requirements assessment

    International Nuclear Information System (INIS)

    Howden, G.F.

    1994-01-01

    A multi-faceted study was initiated in November 1993 to provide assurance that needed testing capabilities, facilities, and support infrastructure (sampling systems, casks, transportation systems, permits, etc.) would be available when needed for process and equipment development to support pretreatment and vitrification facility design and construction schedules. This first major report provides a snapshot of the known testing needs for pretreatment, low-level waste (LLW) and high-level waste (HLW) vitrification, and documents the results of a series of preliminary studies and workshops to define the issues needing resolution by cold or hot testing. Identified in this report are more than 140 Hanford Site tank waste pretreatment and LLW/HLW vitrification technology issues that can only be resolved by testing. The report also broadly characterizes the level of testing needed to resolve each issue. A second report will provide a strategy(ies) for ensuring timely test capability. Later reports will assess the capabilities of existing facilities to support needed testing and will recommend siting of the tests together with needed facility and infrastructure upgrades or additions

  1. Tank Waste Remediation System tank waste pretreatment and vitrification process development testing requirements assessment

    Energy Technology Data Exchange (ETDEWEB)

    Howden, G.F.

    1994-10-24

    A multi-faceted study was initiated in November 1993 to provide assurance that needed testing capabilities, facilities, and support infrastructure (sampling systems, casks, transportation systems, permits, etc.) would be available when needed for process and equipment development to support pretreatment and vitrification facility design and construction schedules. This first major report provides a snapshot of the known testing needs for pretreatment, low-level waste (LLW) and high-level waste (HLW) vitrification, and documents the results of a series of preliminary studies and workshops to define the issues needing resolution by cold or hot testing. Identified in this report are more than 140 Hanford Site tank waste pretreatment and LLW/HLW vitrification technology issues that can only be resolved by testing. The report also broadly characterizes the level of testing needed to resolve each issue. A second report will provide a strategy(ies) for ensuring timely test capability. Later reports will assess the capabilities of existing facilities to support needed testing and will recommend siting of the tests together with needed facility and infrastructure upgrades or additions.

  2. M-Area Settling Basin and vicinity: Environmental information document

    International Nuclear Information System (INIS)

    Pickett, J.B.; Colven, W.P.; Bledsoe, H.W.

    1986-12-01

    This document provides environmental information on postulated closure options for the M-Area Settling Basin and vicinity at the Savannah River Plant and was developed as background technical documentation for the Department of Energy's proposed Environmental Impact Statement (EIS) on waste management activities for groundwater protection at the plant. The results of groundwater and atmospheric pathway analyses, accident analysis, and other environmental assessments discussed in this document are based upon a conservative analysis of all foreseeable scenarios as defined by the National Environmental Policy Act (40 CFR 1500-1508). The scenarios do not necessarily represent actual environmental conditions. This document is not meant to be used as a closure plan or other regulatory document to comply with required federal or state environmental regulations

  3. L-Area Oil and Chemical Basin: Environmental information document

    International Nuclear Information System (INIS)

    Pekkala, R.O.; Price, V.; Bledsoe, H.W.

    1986-12-01

    This document provides environmental information on postulated closure options for the L-Area Oil and Chemical Basin at the Savannah River Plant and was developed as background technical documentation for the Department of Energy's proposed Environmental Impact Statement (EIS) on waste management activities for groundwater protection at the plant. The results of groundwater and atmospheric pathway analyses, accident analysis, and other environmental assessments discussed in this document are based upon a conservative analysis of all foreseeable scenarios as defined by the National Environmental Policy Act (40 CFR 1500-1508). The scenarios do not necessarily represent actual environmental conditions. This document is not meant to be used as a regulatory closure plan or other regulatory document to comply with required federal or state environmental regulations

  4. CMP [Chemicals, Metals, and Pesticides] Pits: Environmental information document

    International Nuclear Information System (INIS)

    Scott, S.C.; Kolb, N.L.; Price, V.; Bledsoe, H.W.

    1986-12-01

    This document provides environmental information on postulated closure options for the Chemicals, Metals, and Pesticides (CMP) Pits at the Savannah River Plant and was developed as background technical documentation for the Department of Energy's proposed Environmental Impact Statement (EIS) on waste management activities for groundwater protection at the plant. The results of groundwater and atmospheric pathway analyses, accident analysis, and other environmental assessments discussed in this document are based upon a conservative analysis of all foreseeable scenarios as defined by the National Environmental Policy Act (40 CFR 1500-1508). The scenarios do not necessarily represent actual environmental conditions. This document is not meant to be used as a regulatory closure plan or other regulatory document to comply with required federal or state environmental regulations

  5. 78 FR 12676 - Timing Requirements for the Submission of a Site Assessment Plan (SAP) or General Activities Plan...

    Science.gov (United States)

    2013-02-25

    ...: BOEM-2012-0077] RIN 1010-AD77 Timing Requirements for the Submission of a Site Assessment Plan (SAP) or... would amend the timing requirements for submitting a Site Assessment Plan (SAP) or General Activities... and grants will have a preliminary term of 12 months in which a lessee or grantee must submit a SAP or...

  6. The Quality of Canadian and U.S. Government Health Documents Remains Unchallenged Until Better Research Can Be Undertaken. A review of: Lambert, Frank. “Assessing the Authoritativeness of Canadian and American Health Documents: A Comparative Analysis Using Informetric Methodologies.” Government Information Quarterly 22.2 (2005: 277‐96.

    Directory of Open Access Journals (Sweden)

    Michael Corkett

    2006-12-01

    Full Text Available Objective ‐ To assess by means of citation analysis whether the public trust afforded health documents published by the Canadian and U.S. governments is appropriate, and to ascertain whether differences in the respective health care systems influence how publications are produced.Design – Comparative study.Setting – The Canadian Depository Service Program (DSP and the U.S. Department of Health and Human Services (DHHS websites.Subjects – One hundred sixty‐six electronic documents sourced from the DSP website, and 284 electronic documents sourced from the DHHS website.Methods – Subjects were randomly selected from repositories offering the most comprehensive collections. Documents with evidence of references to other works used in preparation were separated from thos ewithout such characteristics. Data variables were collected from documents with evidence of references. Statistical analysis of the data was undertaken.Main results – Of the respective samples, 89(53% from the DSP and 109 (38.4% from the DHHS contained references. Personal authors were identified in 46 (51.7% and 63(58% of the respective subsets. Handbooks and guidebooks accounted for the largest portion of the DSP subset (29; 32.6% and government periodicals were the largest constituent of the DHHS subset (41; 37.6%. Scholarly journals were the most common reference type for both the DSP (44% and the DHHS (58.5% subsets. The number of references per document was widely dispersed for both subsets; the DSP mean was approximately 64 (SD=114.68 and the DHHS was 73.71 (SD=168.85. Kruskal‐Wallis subset analysis of median number of references by document type found differences generalizable to the entire DSP (pConclusion – Significant differences in reference use frequencies between DSP and DHHS documents challenges Foskett’s stance that documents of value contain references (Foskett. Use of peer‐reviewed scholarly journals for both DSP and DHHS publications was

  7. ELECTRICAL SUPPORT SYSTEM DESCRIPTION DOCUMENT

    Energy Technology Data Exchange (ETDEWEB)

    S. Roy

    2004-06-24

    The purpose of this revision of the System Design Description (SDD) is to establish requirements that drive the design of the electrical support system and their bases to allow the design effort to proceed to License Application. This SDD is a living document that will be revised at strategic points as the design matures over time. This SDD identifies the requirements and describes the system design as they exist at this time, with emphasis on those attributes of the design provided to meet the requirements. This SDD has been developed to be an engineering tool for design control. Accordingly, the primary audience/users are design engineers. This type of SDD both ''leads'' and ''trails'' the design process. It leads the design process with regard to the flow down of upper tier requirements onto the system. Knowledge of these requirements is essential in performing the design process. The SDD trails the design with regard to the description of the system. The description provided in the SDD is a reflection of the results of the design process to date. Functional and operational requirements applicable to electrical support systems are obtained from the ''Project Functional and Operational Requirements'' (F&OR) (Siddoway 2003). Other requirements to support the design process have been taken from higher-level requirements documents such as the ''Project Design Criteria Document'' (PDC) (Doraswamy 2004), and fire hazards analyses. The above-mentioned low-level documents address ''Project Requirements Document'' (PRD) (Canon and Leitner 2003) requirements. This SDD contains several appendices that include supporting information. Appendix B lists key system charts, diagrams, drawings, and lists, and Appendix C includes a list of system procedures.

  8. ELECTRICAL SUPPORT SYSTEM DESCRIPTION DOCUMENT

    International Nuclear Information System (INIS)

    Roy, S.

    2004-01-01

    The purpose of this revision of the System Design Description (SDD) is to establish requirements that drive the design of the electrical support system and their bases to allow the design effort to proceed to License Application. This SDD is a living document that will be revised at strategic points as the design matures over time. This SDD identifies the requirements and describes the system design as they exist at this time, with emphasis on those attributes of the design provided to meet the requirements. This SDD has been developed to be an engineering tool for design control. Accordingly, the primary audience/users are design engineers. This type of SDD both ''leads'' and ''trails'' the design process. It leads the design process with regard to the flow down of upper tier requirements onto the system. Knowledge of these requirements is essential in performing the design process. The SDD trails the design with regard to the description of the system. The description provided in the SDD is a reflection of the results of the design process to date. Functional and operational requirements applicable to electrical support systems are obtained from the ''Project Functional and Operational Requirements'' (F andOR) (Siddoway 2003). Other requirements to support the design process have been taken from higher-level requirements documents such as the ''Project Design Criteria Document'' (PDC) (Doraswamy 2004), and fire hazards analyses. The above-mentioned low-level documents address ''Project Requirements Document'' (PRD) (Canon and Leitner 2003) requirements. This SDD contains several appendices that include supporting information. Appendix B lists key system charts, diagrams, drawings, and lists, and Appendix C includes a list of system procedures

  9. [The federal participation law : New requirements for needs assessment with special emphasis on medical rehabilitation services].

    Science.gov (United States)

    Schubert, Michael; Schian, Marcus; Viehmeier, Sarah

    2016-09-01

    The federal participation law (Bundesteilhabegesetz - BTHG) is one of the largest efforts in the last 15 years to reform the legal participation rights of people with disabilities. In particular, a number of enhancements are planned in the overall benefits law in Part 1 of Book IX in the Social Code (Sozialgesetzbuch - SGB), which applies to all rehabilitation carriers including general provisions and standards for needs assessment. This paper deals with the implications of these provisions and interacting standards, based on the draft bill of April 2016.The discussion takes place against the background of the regulatory objectives formulated in the ministerial draft itself, jurisprudential expertise on the effects of the current legal norms of the SGB IX as well as relevant professional political developments and statements by various stakeholders.The analysis shows a clear political commitment to increase the requirements for needs assessment in the overall law of the SGB IX and to express these more effectively. The draft bill seeks not only to modify procedures subsequent to the application for rehabilitation benefits, but also to precisely set out provisions on instruments for needs assessment in a new § 13. Common principles for these instruments of needs assessment should increase the cooperation, coordination and convergence among rehabilitation carriers.Nevertheless, with regard to the proposed regulatory texts, there is doubt that the objectives set by the draft bill itself will be achieved. For example, the required common principles for needs assessment are to be agreed upon based on the existing special legislation for the different rehabilitation carriers, without the SGB IX setting its own binding standards or framework principles. In addition, it lacks clear legal guidelines for the professional practice to make use of the bio-psycho-social model of the WHO and the ICF in the process of needs assessment. As a consequence the ICF cannot

  10. Risk-informed assessment of regulatory and design requirements for future nuclear power plants. Annual report

    International Nuclear Information System (INIS)

    2000-01-01

    OAK B188 Risk-informed assessment of regulatory and design requirements for future nuclear power plants. Annual report. The overall goal of this research project is to support innovation in new nuclear power plant designs. This project is examining the implications, for future reactors and future safety regulation, of utilizing a new risk-informed regulatory system as a replacement for the current system. This innovation will be made possible through development of a scientific, highly risk-formed approach for the design and regulation of nuclear power plants. This approach will include the development and/or confirmation of corresponding regulatory requirements and industry standards. The major impediment to long term competitiveness of new nuclear plants in the U.S. is the capital cost component--which may need to be reduced on the order of 35% to 40% for Advanced Light Water Reactors (ALWRS) such as System 80+ and Advanced Boiling Water Reactor (ABWR). The required cost reduction for an ALWR such as AP600 or AP1000 would be expected to be less. Such reductions in capital cost will require a fundamental reevaluation of the industry standards and regulatory bases under which nuclear plants are designed and licensed. Fortunately, there is now an increasing awareness that many of the existing regulatory requirements and industry standards are not significantly contributing to safety and reliability and, therefore, are unnecessarily adding to nuclear plant costs. Not only does this degrade the economic competitiveness of nuclear energy, it results in unnecessary costs to the American electricity consumer. While addressing these concerns, this research project will be coordinated with current efforts of industry and NRC to develop risk-informed, performance-based regulations that affect the operation of the existing nuclear plants; however, this project will go further by focusing on the design of new plants

  11. Risk-informed assessment of regulatory and design requirements for future nuclear power plants. Annual report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-08-01

    OAK B188 Risk-informed assessment of regulatory and design requirements for future nuclear power plants. Annual report. The overall goal of this research project is to support innovation in new nuclear power plant designs. This project is examining the implications, for future reactors and future safety regulation, of utilizing a new risk-informed regulatory system as a replacement for the current system. This innovation will be made possible through development of a scientific, highly risk-formed approach for the design and regulation of nuclear power plants. This approach will include the development and/or confirmation of corresponding regulatory requirements and industry standards. The major impediment to long term competitiveness of new nuclear plants in the U.S. is the capital cost component--which may need to be reduced on the order of 35% to 40% for Advanced Light Water Reactors (ALWRS) such as System 80+ and Advanced Boiling Water Reactor (ABWR). The required cost reduction for an ALWR such as AP600 or AP1000 would be expected to be less. Such reductions in capital cost will require a fundamental reevaluation of the industry standards and regulatory bases under which nuclear plants are designed and licensed. Fortunately, there is now an increasing awareness that many of the existing regulatory requirements and industry standards are not significantly contributing to safety and reliability and, therefore, are unnecessarily adding to nuclear plant costs. Not only does this degrade the economic competitiveness of nuclear energy, it results in unnecessary costs to the American electricity consumer. While addressing these concerns, this research project will be coordinated with current efforts of industry and NRC to develop risk-informed, performance-based regulations that affect the operation of the existing nuclear plants; however, this project will go further by focusing on the design of new plants.

  12. ENVIRONMENTAL RISK ASSESSMENT OF SOME COPPER BASED FUNGICIDES ACCORDING TO THE REQUIREMENTS OF GOOD LABORATORY PRACTICE

    Directory of Open Access Journals (Sweden)

    Marga GRĂDILĂ

    2015-10-01

    Full Text Available The paper presents data demonstrating the functionality of biological systems reconstituted with aquatic organisms developed under Good Laboratory Practice testing facility within Research - Development Institute for Plant Protection Bucharest for environmental risk assessment of four fungicides based on copper, according to Good Laboratory Practice requirements. For risk assessment, according to GLP were made the following steps: Good Laboratory Practice test facility was established, we have ensured adequate space for growth, acclimatization and testing for each test species, it was installed a complex water production instalation needed to perform tests, it was achieved control system for checking environmental conditions and have developed specific operating procedures that have been accredited according to Good Laboratory Practice.The results showed that biological systems model of the Good Laboratory Practice test facility in Research - Development Institute for Plant Protection meet the requirements of Organisation for Economic Co-operation and Development Guidelines regarding GLP, and after testing copper-based fungicides in terms of acute toxicity Cyprinus carpio and to Daphnia magna revealed that three of them (copper oxychloride, copper hydroxide and copper sulphate showed ecological efficiency, ie low toxicity. Metallic copper based fungicides showed a higher toxicity, resulting in fish toxicity symptoms: sleep, sudden immersion, faded, weakness, swimming in spiral, lack of balance, breathing slow and cumbersome, spasms and mortality.

  13. 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

  14. Generic safety documentation model

    International Nuclear Information System (INIS)

    Mahn, J.A.

    1994-04-01

    This document is intended to be a resource for preparers of safety documentation for Sandia National Laboratories, New Mexico facilities. It provides standardized discussions of some topics that are generic to most, if not all, Sandia/NM facilities safety documents. The material provides a ''core'' upon which to develop facility-specific safety documentation. The use of the information in this document will reduce the cost of safety document preparation and improve consistency of information

  15. Model-based Assessment for Balancing Privacy Requirements and Operational Capabilities

    Energy Technology Data Exchange (ETDEWEB)

    Knirsch, Fabian [Salzburg Univ. (Austria); Engel, Dominik [Salzburg Univ. (Austria); Frincu, Marc [Univ. of Southern California, Los Angeles, CA (United States); Prasanna, Viktor [Univ. of Southern California, Los Angeles, CA (United States)

    2015-02-17

    The smart grid changes the way energy is produced and distributed. In addition both, energy and information is exchanged bidirectionally among participating parties. Therefore heterogeneous systems have to cooperate effectively in order to achieve a common high-level use case, such as smart metering for billing or demand response for load curtailment. Furthermore, a substantial amount of personal data is often needed for achieving that goal. Capturing and processing personal data in the smart grid increases customer concerns about privacy and in addition, certain statutory and operational requirements regarding privacy aware data processing and storage have to be met. An increase of privacy constraints, however, often limits the operational capabilities of the system. In this paper, we present an approach that automates the process of finding an optimal balance between privacy requirements and operational requirements in a smart grid use case and application scenario. This is achieved by formally describing use cases in an abstract model and by finding an algorithm that determines the optimum balance by forward mapping privacy and operational impacts. For this optimal balancing algorithm both, a numeric approximation and – if feasible – an analytic assessment are presented and investigated. The system is evaluated by applying the tool to a real-world use case from the University of Southern California (USC) microgrid.

  16. SNF AGING SYSTEM DESCRIPTION DOCUMENT

    International Nuclear Information System (INIS)

    L.L. Swanson

    2005-01-01

    The purpose of this system description document (SDD) is to establish requirements that drive the design of the spent nuclear fuel (SNF) aging system and associated bases, which will allow the design effort to proceed. This SDD will be revised at strategic points as the design matures. This SDD identifies the requirements and describes the system design, as it currently exists, with emphasis on attributes of the design provided to meet the requirements. This SDD is an engineering tool for design control; accordingly, the primary audience and users are design engineers. This SDD is part of an iterative design process. It leads the design process with regard to the flow down of upper tier requirements onto the system. Knowledge of these requirements is essential in performing the design process. The SDD follows the design with regard to the description of the system. The description provided in the SDD reflects the current results of the design process. Throughout this SDD, the term aging cask applies to vertical site-specific casks and to horizontal aging modules. The term overpack is a vertical site-specific cask that contains a dual-purpose canister (DPC) or a disposable canister. Functional and operational requirements applicable to this system were obtained from ''Project Functional and Operational Requirements'' (F andOR) (Curry 2004 [DIRS 170557]). Other requirements that support the design process were taken from documents such as ''Project Design Criteria Document'' (PDC) (BSC 2004 [DES 171599]), ''Site Fire Hazards Analyses'' (BSC 2005 [DIRS 172174]), and ''Nuclear Safety Design Bases for License Application'' (BSC 2005 [DIRS 171512]). The documents address requirements in the ''Project Requirements Document'' (PRD) (Canori and Leitner 2003 [DIRS 166275]). This SDD includes several appendices. Appendix A is a Glossary; Appendix B is a list of key system charts, diagrams, drawings, lists and additional supporting information; and Appendix C is a list of

  17. Document development, management and transmission

    International Nuclear Information System (INIS)

    Meister, K.

    1998-01-01

    Environmental monitoring can only be carried out by means of cartographic outputs allowing the representation of information in a compressed way and with a local reference. On account of this requirement and the continuously growing importance of international data exchange the development of a universal tool for the combination of data to so-called documents has been started for the management and for the exchange of these documents with other systems. (R.P.)

  18. Instructions for submittal and control of FFTF design documents and design related documentation

    International Nuclear Information System (INIS)

    Grush, R.E.

    1976-10-01

    This document provides the system and requirements for management of FFTF technical data prepared by Westinghouse Hanford (HEDL), and design contractors, the construction contractor and lower tier equipment suppliers. Included in this document are provisions for the review, approval, release, change control, and accounting of FFTF design disclosure and base documentation. Also included are provisions for submittal of other design related documents for review and approval consistent with applicable requirements of RDT-Standard F 2-2, ''Quality Assurance Program Requirements.''

  19. Integrated Stamping Simulation Using State Of The Art Techniques To Fulfill Quality Assessment Requirements

    International Nuclear Information System (INIS)

    Ling, David; Lambriks, Marc; El Khaldi, Fouad

    2005-01-01

    The last few years have seen the use of stamping simulation evolve to the extent that it is now a mainstream activity; a core part of the press tool engineering process. Now, new requirements for the use of challenging materials like Dual phase / Complex phase steel, VHSS, and aluminum, together with more stringent quality expectations, and shorter development cycles, there is a need to assess the panel quality in a wider context, before committing to tool manufacture.The integrated approach from ESI Group allows early up-front feasibility assessment, geometry and process optimization, and detailed process validation all within one system. Rapid die design and quick forming simulation modules play an essential role in the early stages of the process. A seamless connection between simulation and geometry is a vital characteristic, with the accurate simulation being used to validate and fine tune the process in order to assess final component quality in unprecedented detail, utilizing some of the most accurate material models available today. The combination of the distributed memory processing (DMP) solver together with new cost effective cluster based compute servers provide a practical solution to the problems of 'one million element' model sizes, and more sophisticated modeling methodologies become realistic for the first time.It is no longer sufficient to merely focus on the draw die, forming simulation must now consider the entire die line up. Typically, around half of forming issues arise from the draw die, so the time has now come to address the other half as well! This paper will discuss how the PAM-STAMP 2G TM integrated solution is successfully used to deliver a positive business impact, by providing virtual panel quality assessment, tolerance control, and springback compensation. The paper will also discuss how other forming processes can be accurately modeled using the new modules

  20. 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.