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

Science.gov (United States)

Hayhurst, Kelly J. (Editor)

2008-01-01

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

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

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.

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

Impact of an electronic health record operating room management system in ophthalmology on documentation time, surgical volume, and staffing.

Science.gov (United States)

Sanders, David S; Read-Brown, Sarah; Tu, Daniel C; Lambert, William E; Choi, Dongseok; Almario, Bella M; Yackel, Thomas R; Brown, Anna S; Chiang, Michael F

2014-05-01

Although electronic health record (EHR) systems have potential benefits, such as improved safety and quality of care, most ophthalmology practices in the United States have not adopted these systems. Concerns persist regarding potential negative impacts on clinical workflow. In particular, the impact of EHR operating room (OR) management systems on clinical efficiency in the ophthalmic surgery setting is unknown. To determine the impact of an EHR OR management system on intraoperative nursing documentation time, surgical volume, and staffing requirements. For documentation time and circulating nurses per procedure, a prospective cohort design was used between January 10, 2012, and January 10, 2013. For surgical volume and overall staffing requirements, a case series design was used between January 29, 2011, and January 28, 2013. This study involved ophthalmic OR nurses (n = 13) and surgeons (n = 25) at an academic medical center. Electronic health record OR management system implementation. (1) Documentation time (percentage of operating time documenting [POTD], absolute documentation time in minutes), (2) surgical volume (procedures/time), and (3) staffing requirements (full-time equivalents, circulating nurses/procedure). Outcomes were measured during a baseline period when paper documentation was used and during the early (first 3 months) and late (4-12 months) periods after EHR implementation. There was a worsening in total POTD in the early EHR period (83%) vs paper baseline (41%) (P system implementation was associated with worsening of intraoperative nursing documentation time especially in shorter procedures. However, it is possible to implement an EHR OR management system without serious negative impacts on surgical volume and staffing requirements.

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

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

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)

The System 80+ Standard Plant design control document. Volume 11

International Nuclear Information System (INIS)

1997-01-01

This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume covers parts 6 and 7 and appendix 7A for section 7 (Instrumentation and Control) of the ADM Design and Analysis. The topics covered by these are: other systems required for safety; control systems not required by safety; and CMF evaluation of limiting faults. Parts 1--3 of section 8 (Electric Power) of the ADM are also included in this volume. Topics covered by these parts are: introduction; offsite power system; and onsite power system

The System 80+ Standard Plant design control document. Volume 20

International Nuclear Information System (INIS)

1997-01-01

This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains 2 technical specifications bases as part of Appendix 16 A Tech Spec Bases. They are TS B3.8 Electrical Power Technical Systems Bases and TS B3.9 Refueling Operations Bases. All 3 parts of section 17 (QA) and all 10 parts of section 18 (Human Factors) of the ADM Design and Analysis are contained in this volume. Topics covered in section 17 are: design phase QA; operations phase QA; and design phase reliability assurance. Topics covered by section 18 are: design team organization; design goals; design process; functional task analysis; control room configuration; information presentation; control and monitoring; verification and validation; and review documents

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)

The System 80+ Standard Plant design control document. Volume 2

International Nuclear Information System (INIS)

1997-01-01

This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume covers the following information of the CDM: (2.8) Steam and power conversion; (2.9) Radioactive waste management; (2.10) Tech Support Center; (2.11) Initial test program; (2.12) Human factors; and sections 3, 4, and 5. Also covered in this volume are parts 1--6 of section 1 (General Plant Description) of the ADM Design and Analysis

Management plan documentation standard and Data Item Descriptions (DID). Volume of the information system life-cycle and documentation standards, volume 2

Science.gov (United States)

Callender, E. David; Steinbacher, Jody

1989-01-01

This is the second of five volumes of the Information System Life-Cycle and Documentation Standards. This volume provides a well-organized, easily used standard for management plans used in acquiring, assuring, and developing information systems and software, hardware, and operational procedures components, and related processes.

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

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

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

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

39 CFR 3050.26 - Documentation of demand elasticities and volume forecasts.

Science.gov (United States)

2010-07-01

... 39 Postal Service 1 2010-07-01 2010-07-01 false Documentation of demand elasticities and volume... § 3050.26 Documentation of demand elasticities and volume forecasts. By January 20 of each year, the Postal Service shall provide econometric estimates of demand elasticity for all postal products...

DART II documentation. Volume III. Appendices

Energy Technology Data Exchange (ETDEWEB)

1979-10-01

The DART II is a remote, interactive, microprocessor-based data acquistion system suitable for use with air monitors. This volume of DART II documentation contains the following appendixes: adjustment and calibration procedures; mother board signature list; schematic diagrams; device specification sheets; ROM program listing; 6800 microprocessor instruction list, octal listing; and cable lists. (RWR)

The System 80+ Standard Plant design control document. Volume 23

International Nuclear Information System (INIS)

1997-01-01

This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains part 16 References and Appendix 19 A Design Alternatives for section 19 (Probabilistic Risk Assessment) of the ADM Design and Analysis. Also covered is section 20 Unresolved Safety Issues of the ADM Design and Analysis. Finally sections 1--6 of the ADM Emergency Operations Guidelines are contained in this volume. Information covered in these sections include: standard post-trip actions; diagnostic actions; reactor trip recovery guideline; LOCA recovery; SG tube rupture recovery

The System 80+ Standard Plant design control document. Volume 21

International Nuclear Information System (INIS)

1997-01-01

This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains parts 1--10 of section 19 (Probabilistic Risk Assessment) of the ADM Design and Analysis. Topics covered are: methodology; initiating event evaluation; accident sequence determination; data analysis; systems analysis; external events analysis; shutdown risk assessment; accident sequence quantification; and sensitivity analysis. Also included in this volume are Appendix 19.8A Shutdown Risk Assessment and Appendix A to Appendix 19.8A Request for Information

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.

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

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

Science.gov (United States)

Hayhurst, Kelly J. (Editor)

2008-01-01

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

The System 80+ Standard Plant design control document. Volume 15

International Nuclear Information System (INIS)

1997-01-01

This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains all five parts of section 12 (Radiation Protection) of the ADM Design and Analysis. Topics covered are: ALARA exposures; radiation sources; radiation protection; dose assessment; and health physics program. All six parts and appendices A and B for section 13 (Conduct of Operations) of the ADM Design and Analysis are also contained in this volume. Topics covered are: organizational structure; training program; emergency planning; review and audit; plant procedures; industrial security; sabotage protection (App 13A); and vital equipment list (App 13B)

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

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...

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

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

Management control and status reports documentation standard and Data Item Descriptions (DID). Volume of the information system life-cycle and documentation standards, volume 5

Science.gov (United States)

Callender, E. David; Steinbacher, Jody

1989-01-01

This is the fifth of five volumes on Information System Life-Cycle and Documentation Standards. This volume provides a well organized, easily used standard for management control and status reports used in monitoring and controlling the management, development, and assurance of informations systems and software, hardware, and operational procedures components, and related processes.

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....

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

Fluor Daniel Hanford contract standards/requirements identification document

Energy Technology Data Exchange (ETDEWEB)

Bennett, G.L.

1997-04-24

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

Fluor Daniel Hanford company standards requirements identification document

International Nuclear Information System (INIS)

Bennett, G.L.

1997-01-01

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

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

Functional Requirements for Onboard Management of Space Shuttle Consumables. Volume 2

Science.gov (United States)

Graf, P. J.; Herwig, H. A.; Neel, L. W.

1973-01-01

This report documents the results of the study "Functional Requirements for Onboard Management of Space Shuttle Consumables." The study was conducted for the Mission Planning and Analysis Division of the NASA Lyndon B. Johnson Space Center, Houston, Texas, between 3 July 1972 and 16 November 1973. The overall study program objective was two-fold. The first objective was to define a generalized consumable management concept which is applicable to advanced spacecraft. The second objective was to develop a specific consumables management concept for the Space Shuttle vehicle and to generate the functional requirements for the onboard portion of that concept. Consumables management is the process of controlling or influencing the usage of expendable materials involved in vehicle subsystem operation. The report consists of two volumes. Volume I presents a description of the study activities related to general approaches for developing consumable management, concepts for advanced spacecraft applications, and functional requirements for a Shuttle consumables management concept. Volume II presents a detailed description of the onboard consumables management concept proposed for use on the Space Shuttle.

The System 80+ Standard Plant design control document. Volume 10

International Nuclear Information System (INIS)

1997-01-01

This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains Appendices 6A, 6B, and 6C for section 6 (Engineered Safety Features) of the ADM Design and Analysis. Also, parts 1--5 of section 7 (Instrumentation and Control) of the ADM Design and Analysis are covered. The following information is covered in these parts: introduction; reactor protection system; ESF actuation system; system required for safe shutdown; and safety-related display instrumentation

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

The System 80+ Standard Plant design control document. Volume 1

International Nuclear Information System (INIS)

1997-01-01

This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume covers the DCD introduction and contains sections 1 and parts 1--7 of section 2 of the CDM. Parts 1--7 included the following: (2.1) Design of SSC; (2.2) Reactor; (2.3) RCS and connected systems; (2.4) Engineered Safety Features; (2.5) Instrumentation and Control; (2.6) Electric Power; and (2.7) Auxiliary Systems

The System 80+ Standard Plant design control document. Volume 19

International Nuclear Information System (INIS)

1997-01-01

This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains five technical specification bases that are part of Appendix 16 A of the ADM Design and Analysis. They are: TS B3.3 Instrumentation Bases; TS B3.4 RCS Bases; TS B3.5 ECCS Bases; TS B3.6 Containment Systems Bases; and TS B3.7 Plant Systems Bases

The System 80+ Standard Plant design control document. Volume 24

International Nuclear Information System (INIS)

1997-01-01

This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains sections 7--11 of the ADM Emergency Operations Guidelines. Topics covered are: excess steam demand recovery; loss of all feedwater; loss of offsite power; station blackout recovery; and functional recovery guideline. Appendix A Severe Accident Management Guidelines and Appendix B Lower Mode Operational Guidelines are also included

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.

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.

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.

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

Community Documentation Centre on Industrial Risk. Volume 3 (consolidated volume containing also content of vol. 1 and 2)

International Nuclear Information System (INIS)

1990-09-01

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

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

The System 80+ Standard Plant design control document. Volume 17

International Nuclear Information System (INIS)

1997-01-01

This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains parts 2-7 and appendix 15A for section 15 (Accident Analysis) of the ADM Design and Analysis. Topics covered in these parts are: decrease in heat removal; decrease in RCS flow rate; power distribution anomalies; increase in RCS inventory; decrease in RCS inventory; release of radioactive materials. The appendix covers radiological release models. Also contained here are five technical specifications for section 16 (Technical Specifications) of the ADM Design and Analysis. They are: TS 1.0 Use and Applications; TS 2.0 Safety Limits; TS 3.0 LCO Availability; TS 3.1 Reactivity Control; and TS 3.2 Power Distribution

The System 80+ Standard Plant design control document. Volume 18

International Nuclear Information System (INIS)

1997-01-01

This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains the following technical specifications of section 16 (Technical Specifications) of the ADM Design and Analysis: TS 3.3 Instrumentation; TS 3.4 Reactor Coolant System; TS 3.5 Emergency Core Cooling System; TS 3.6 Containment Systems; TS 3.7 Plant Systems; TS 3.8 Electrical Power Systems; TS 3.9 Refueling Operations; TS 4.0 Design Features; TS 5.0 Administrative Controls. Appendix 16 A Tech Spec Bases is also included. It contains the following: TS B2.0 Safety Limits Bases; TS B3.0 LCO Applicability Bases; TS B3.1 Reactivity Control Bases; TS B3.2 Power Distribution Bases

77 FR 28281 - Withdrawal of Revocation of TSCA Section 4 Testing Requirements for One High Production Volume...

Science.gov (United States)

2012-05-14

... Withdrawal of Revocation of TSCA Section 4 Testing Requirements for One High Production Volume Chemical...]amino]- (CAS No. 1324-76-1), also known as C.I. Pigment Blue 61. EPA received an adverse comment regarding C.I. Pigment Blue 61. This document withdraws the revocation of testing requirements for C.I...

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

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

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.

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

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

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.

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

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.

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

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)

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)

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.

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.

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

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.

Underground Test Area Subproject Phase I Data Analysis Task. Volume VII - Tritium Transport Model Documentation Package

Energy Technology Data Exchange (ETDEWEB)

None

1996-12-01

Volume VII 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 tritium transport model 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.

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

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

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

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

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

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.

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

Structure and drafting of safeguards regulatory documents

International Nuclear Information System (INIS)

Cole, R.J.; Bennett, C.A.; Edelhertz, H.; Wood, M.T.; Brown, R.J.; Roberts, F.P.

1977-09-01

This study develops hypothesis about the relation between the structure and drafting of safeguards regulatory documents and the ability of document users to understand and implement them in a way that reflects the intent and requirements of the NRC. Four decisions are needed to improve communication: (1) Should improvement of safeguards regulatory documents as communication instruments be an explicit NRC program. (2) What specific methods of communication should be the focus of improvement efforts. (3) What actions to improve communications are feasible and desirable. (4) How should the NRC divide its available effort and resources among desirable actions in order to provide the most effective communication through regulatory documents. This volume contains: introduction, conceptual bases, legal requirements, targets, choice of documents, preparation of documents, readability, and further study of recommended changes in structure and drafting

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.

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

NASA software documentation standard software engineering program

Science.gov (United States)

1991-01-01

The NASA Software Documentation Standard (hereinafter referred to as Standard) can be applied to the documentation of all NASA software. This Standard is limited to documentation format and content requirements. It does not mandate specific management, engineering, or assurance standards or techniques. This Standard defines the format and content of documentation for software acquisition, development, and sustaining engineering. Format requirements address where information shall be recorded and content requirements address what information shall be recorded. This Standard provides a framework to allow consistency of documentation across NASA and visibility into the completeness of project documentation. This basic framework consists of four major sections (or volumes). The Management Plan contains all planning and business aspects of a software project, including engineering and assurance planning. The Product Specification contains all technical engineering information, including software requirements and design. The Assurance and Test Procedures contains all technical assurance information, including Test, Quality Assurance (QA), and Verification and Validation (V&V). The Management, Engineering, and Assurance Reports is the library and/or listing of all project reports.

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

Hanford spent nuclear fuel project recommended path forward, volume III: Alternatives and path forward evaluation supporting documentation

International Nuclear Information System (INIS)

Fulton, J.C.

1994-10-01

Volume I of the Hanford Spent Nuclear Fuel Project - Recommended Path Forward constitutes an aggressive series of projects to construct and operate systems and facilities to safely retrieve, package, transport, process, and store K Basins fuel and sludge. Volume II provided a comparative evaluation of four Alternatives for the Path Forward and an evaluation for the Recommended Path Forward. Although Volume II contained extensive appendices, six supporting documents have been compiled in Volume III to provide additional background for Volume II

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...

Model documentation Natural Gas Transmission and Distribution Model of the National Energy Modeling System. Volume 1

International Nuclear Information System (INIS)

1996-01-01

The Natural Gas Transmission and Distribution Model (NGTDM) of the National Energy Modeling System is developed and maintained by the Energy Information Administration (EIA), Office of Integrated Analysis and Forecasting. This report documents the archived version of the NGTDM that was used to produce the natural gas forecasts presented in the Annual Energy Outlook 1996, (DOE/EIA-0383(96)). The purpose of this report is to provide a reference document for model analysts, users, and the public that defines the objectives of the model, describes its basic approach, and provides detail on the methodology employed. Previously this report represented Volume I of a two-volume set. Volume II reported on model performance, detailing convergence criteria and properties, results of sensitivity testing, comparison of model outputs with the literature and/or other model results, and major unresolved issues

Model documentation Natural Gas Transmission and Distribution Model of the National Energy Modeling System. Volume 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-02-26

The Natural Gas Transmission and Distribution Model (NGTDM) of the National Energy Modeling System is developed and maintained by the Energy Information Administration (EIA), Office of Integrated Analysis and Forecasting. This report documents the archived version of the NGTDM that was used to produce the natural gas forecasts presented in the Annual Energy Outlook 1996, (DOE/EIA-0383(96)). The purpose of this report is to provide a reference document for model analysts, users, and the public that defines the objectives of the model, describes its basic approach, and provides detail on the methodology employed. Previously this report represented Volume I of a two-volume set. Volume II reported on model performance, detailing convergence criteria and properties, results of sensitivity testing, comparison of model outputs with the literature and/or other model results, and major unresolved issues.

Development of the NRC`s Human Performance Investigation Process (HPIP). Volume 3, Development documentation

Energy Technology Data Exchange (ETDEWEB)

Paradies, M.; Unger, L. [System Improvements, Inc., Knoxville, TN (United States); Haas, P.; Terranova, M. [Concord Associates, Inc., Knoxville, TN (United States)

1993-10-01

The three volumes of this report detail a standard investigation process for use by US Nuclear Regulatory Commission (NRC) personnel when investigating human performance related events at nuclear power plants. The process, called the Human Performance Investigation Process (HPIP), was developed to meet the special needs of NRC personnel, especially NRC resident and regional inspectors. HPIP is a systematic investigation process combining current procedures and field practices, expert experience, NRC human performance research, and applicable investigation techniques. The process is easy to learn and helps NRC personnel perform better field investigations of the root causes of human performance problems. The human performance data gathered through such investigations provides a better understanding of the human performance issues that cause events at nuclear power plants. This document, Volume III, is a detailed documentation of the development effort and the pilot training program.

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.

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.

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.

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

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

International Nuclear Information System (INIS)

Gordillo, F.

2000-01-01

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

Reactor operation environmental information document

Energy Technology Data Exchange (ETDEWEB)

Haselow, J.S.; Price, V.; Stephenson, D.E.; Bledsoe, H.W.; Looney, B.B.

1989-12-01

The Savannah River Site (SRS) produces nuclear materials, primarily plutonium and tritium, to meet the requirements of the Department of Defense. These products have been formed in nuclear reactors that were built during 1950--1955 at the SRS. K, L, and P reactors are three of five reactors that have been used in the past to produce the nuclear materials. All three of these reactors discontinued operation in 1988. Currently, intense efforts are being extended to prepare these three reactors for restart in a manner that protects human health and the environment. To document that restarting the reactors will have minimal impacts to human health and the environment, a three-volume Reactor Operations Environmental Impact Document has been prepared. The document focuses on the impacts of restarting the K, L, and P reactors on both the SRS and surrounding areas. This volume discusses the geology, seismology, and subsurface hydrology. 195 refs., 101 figs., 16 tabs.

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

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

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

Energy Technology Data Exchange (ETDEWEB)

Maddox, B.S.

1996-01-01

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

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

International Nuclear Information System (INIS)

Maddox, B.S.

1996-01-01

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

Present status of the EUR document the challenge of new incorporations

International Nuclear Information System (INIS)

Alomar, F.

1998-01-01

EUR (European Utilities Requirements) Document is in process, with DTN's active participation since the beginning. Two new Utilities representing non-European Union Countries (Switzerland and Russia) have joined the EUR Document Group of Sponsoring Utilities, whose members up to now belonged to nine utilities from European Union Countries. Although, in general terms, this incorporation is enriching, this late arrival does present problems due to the fact that the document is now under discussion the incorporation of different technological practices, and last but not least, different Licensing Approaches. Should be remembered that currently an overall review by the different Regulatory Bodies is in process and an intervention by the E.C. is being prepared. Both inside and outside of the European Continent, other Utilities have also shown their interest in the EUR Document. EUR Document Volume 3 sets a compliance evaluation between Projects from different Nuclear Island Manufactures and EUR's Top Tier Requirements (established in Volume 1) and Detailed Requirements (established in Volume 2). Presently a comparison is being carried out for three Nuclear Island Suppliers: ABB, NPI (KWU and Framatome Joint Venture) and Westinghouse. In the near future it is foreseen to initiate compliance evaluation for two more N.I. suppliers: General Electric and Rosenergatom. Challenges of these new incorporations are analyzed in what follows. (Author)

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...

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

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.

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

Results of site validation experiments. Volume II. Supporting documents 5 through 14

Energy Technology Data Exchange (ETDEWEB)

1983-01-01

Volume II contains the following supporting documents: Summary of Geologic Mapping of Underground Investigations; Logging of Vertical Coreholes - ''Double Box'' Area and Exploratory Drift; WIPP High Precision Gravity Survey; Basic Data Reports for Drillholes, Brine Content of Facility Internal Strata; Mineralogical Content of Facility Interval Strata; Location and Characterization of Interbedded Materials; Characterization of Aquifers at Shaft Locations; and Permeability of Facility Interval Strate.

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...

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

International Nuclear Information System (INIS)

1995-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-01-01

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

Universal Documentation System Handbook. Volume 2: Program Requirements and Operations Requirements Documents

Science.gov (United States)

1979-11-01

plane. The local horizontal plane is de- lined as a plane normal to the geocentric position vector. Boxes 11J and UJ are the angles measured east...support the program/mission. BOX 1-9 Follow instructions for Pa«« 1010. BOX 10 LOCATION: Enter the areas or locations that are to be staffed with

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)

Title list of documents made publicly available, April 1-30, 1995. Volume 17, No. 4

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-06-01

This document is NUREG-0540, Volume 17, Number 4. The Title List of Documents Made Publicly Available is a monthly publication, It contains descriptions of the information received and generated by the US NRC. This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and (2) nondocketed material received and generated by the NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which the NRC maintains its regulatory records. This series of documents is indexed by a personal author index, a corporate source index, and a report number index.

Title list of documents made publicly available, April 1-30, 1995. Volume 17, No. 4

International Nuclear Information System (INIS)

1995-06-01

This document is NUREG-0540, Volume 17, Number 4. The Title List of Documents Made Publicly Available is a monthly publication, It contains descriptions of the information received and generated by the US NRC. This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and (2) nondocketed material received and generated by the NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which the NRC maintains its regulatory records. This series of documents is indexed by a personal author index, a corporate source index, and a report number index

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

Subsurface Contamination Focus Area technical requirements. Volume 1: Requirements summary

International Nuclear Information System (INIS)

Nickelson, D.; Nonte, J.; Richardson, J.

1996-10-01

This document summarizes functions and requirements for remediation of source term and plume sites identified by the Subsurface Contamination Focus Area. Included are detailed requirements and supporting information for source term and plume containment, stabilization, retrieval, and selective retrieval remedial activities. This information will be useful both to the decision-makers within the Subsurface Contamination Focus Area (SCFA) and to the technology providers who are developing and demonstrating technologies and systems. Requirements are often expressed as graphs or charts, which reflect the site-specific nature of the functions that must be performed. Many of the tradeoff studies associated with cost savings are identified in the text

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)

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.

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

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.

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

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...

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.)

PFP MICON DCS computer software documentation

Energy Technology Data Exchange (ETDEWEB)

Silvan, G.R.

1996-03-26

This document contains the complete printout of the MICON A/S system configuration used in the Plutonium Finishing Plant. The document is divided into several volumes. Volume 1 covers the workstation display and configuration. All other volumes contain the controller configurations, or programs.

PFP MICON DCS computer software documentation

International Nuclear Information System (INIS)

Silvan, G.R.

1996-01-01

This document contains the complete printout of the MICON A/S system configuration used in the Plutonium Finishing Plant. The document is divided into several volumes. Volume 1 covers the workstation display and configuration. All other volumes contain the controller configurations, or programs

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...

Exploring the Unknown: Selected Documents in the History of the U.S. Civil Space Program. Volume 4; Accessing Space

Science.gov (United States)

Logsdon, John M. (Editor); Williamson, Ray A. (Editor); Launius, Roger D. (Editor); Acker, Russell J. (Editor); Garber, Stephen J. (Editor); Friedman, Jonathan L. (Editor)

1999-01-01

The documents selected for inclusion in this volume are presented in four major chapters, each covering a particular aspect of access to space and the manner in which it has developed over time. These chapters focus on the evolution toward the giant Saturn V rocket, the development of the Space Shuttle, space transportation commercialization, and future space transportation possibilities. Each chapter in this volume is introduced by an overview essay, prepared by individuals who are particularly well qualified to write on the topic. In the main, these essays are intended to introduce and complement the documents in the chapter and to place them, for the most part, in a chronological and substantive context. Each essay contains references to the documents in the chapter it introduces, and many also contain references to documents in other chapters of the collection. These introductory essays are the responsibility of their individual authors, and the views and conclusions contained therein do not necessarily represent the opinions of either George Washington University or NASA.

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...

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

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

Sandia National Laboratories/New Mexico Environmental Information Document - Volume II

Energy Technology Data Exchange (ETDEWEB)

GUERRERO, JOSEPH V.; KUZIO, KENNETH A.; JOHNS, WILLIAM H.; BAYLISS, LINDA S.; BAILEY-WHITE, BRENDA E.

1999-09-01

This Sandia National Laboratories/New Mexico Environmental Information Document (EID) compiles information on the existing environment, or environmental baseline, for SNUNM. Much of the information is drawn from existing reports and databases supplemented by new research and data. The SNL/NM EID, together with the Sandia National Laboratories/New Mexico Facilities and Safety Information Document, provide a basis for assessing the environment, safety, and health aspects of operating selected facilities at SNL/NM. The environmental baseline provides a record of the existing physical, biological, and socioeconomic environment at SNL/NLM prior to being altered (beneficially or adversely) by proposed programs or projects. More specifically, the EID provides information on the following topics: Geology; Land Use; Hydrology and Water Resources; Air Quality and Meteorology; Ecology; Noise and Vibration; Cultural Resources; Visual Resources; Socioeconomic and Community Services; Transportation; Material Management; Waste Management; and Regulatory Requirements.

Sandia National Laboratories/New Mexico Environmental Information Document - Volume 1

Energy Technology Data Exchange (ETDEWEB)

BAYLISS, LINDA S.; GUERRERO, JOSEPH V.; JOHNS, WILLIAM H.; KUZIO, KENNETH A.; BAILEY-WHITE, BRENDA E.

1999-09-01

This Sandia National Laboratories/New Mexico Environmental Information Document (EID) compiles information on the existing environment, or environmental baseline, for SNUNM. Much of the information is drawn from existing reports and databases supplemented by new research and data. The SNL/NM EID, together with the Sandia National Laboratories/New Mexico Facilities and Safety Information Document, provide a basis for assessing the environment, safety, and health aspects of operating selected facilities at SNL/NM. The environmental baseline provides a record of the existing physical, biological, and socioeconomic environment at SNL/NLM prior to being altered (beneficially or adversely) by proposed programs or projects. More specifically, the EID provides information on the following topics: Geology; Land Use; Hydrology and Water Resources; Air Quality and Meteorology; Ecology; Noise and Vibration; Cultural Resources; Visual Resources; Socioeconomic and Community Services; Transportation; Material Management; Waste Management; and Regulatory Requirements.

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...

Test design requirements for overcoring stress measurements

International Nuclear Information System (INIS)

Stickney, R.G.

1985-12-01

This document establishes the test design requirements for a series of overcoring stress measurements to be performed in the Exploratory Shaft Facility. The stress measurements will be made to determine the in situ state of stress within the candidate repository horizon and to determine the magnitude and distribution of the stresses induced by the mined openings of the facility. The overcoring technique involves the measurement of strain (or deformation) in a volume of rock as the stress acting on the rock volume is relieved. This document presents an overview of the measurements, including objectives and rationale for the measurements. A description of the measurements is included. The support requirements are identified as are constraints for the design of the measurements. Discussions on Quality Assurance and Safety are also included in the document. 13 refs

Superconducting Super Collider: Final environmental impact statement: Volume 2, Comment/response document: Summary and index

International Nuclear Information System (INIS)

1988-12-01

This volume is divided into five parts as follows: Summary and Index; Letters submitted by commenters in response to the Draft Environmental Impact Statement (DEIS) from date of issue through October 17, 1988; Transcripts of testimony at the public hearings conducted by the DOE in the vicinity of each site alternative; Letters postmarked after October 17, 1988; and Comment responses to both the letters and the testimony. This summary and index is published as a guide to the reader in reviewing this document. The summary is of the approximately 7000 comments received by the DOE from a total of about 5700 commenters. It was prepared as a general reference and guide to the readers of this volume. The Index follows the summary. The first index is an alphabetical listing of commenters (of both letters and transcripts) and indicates the number each commenter was assigned. The commenter numbers guide the reader to DOE comment responses in Volume 2B which are in numerical order

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

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.

High-level waste tank farm set point document

International Nuclear Information System (INIS)

Anthony, J.A. III.

1995-01-01

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

High-level waste tank farm set point document

Energy Technology Data Exchange (ETDEWEB)

Anthony, J.A. III

1995-01-15

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

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

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

Fuel Rod Consolidation Project: Phase 2, Final report: Volume 2, Appendices

International Nuclear Information System (INIS)

1987-01-01

This document, Volume 2, provides the appendices to Volume 1 of the Fuel Rod Consolidation Project. It provides information on the following: References; Trade-off Studies; Instrument List; RAM Data; Fabrication Specifications; Software Specifications; and Design Requirements

Model documentation: Natural Gas Transmission and Distribution Model of the National Energy Modeling System; Volume 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-02-24

The Natural Gas Transmission and Distribution Model (NGTDM) is a component of the National Energy Modeling System (NEMS) used to represent the domestic natural gas transmission and distribution system. NEMS is the third in a series of computer-based, midterm energy modeling systems used since 1974 by the Energy Information Administration (EIA) and its predecessor, the Federal Energy Administration, to analyze domestic energy-economy markets and develop projections. This report documents the archived version of NGTDM that was used to produce the natural gas forecasts used in support of the Annual Energy Outlook 1994, DOE/EIA-0383(94). The purpose of this report is to provide a reference document for model analysts, users, and the public that defines the objectives of the model, describes its basic design, provides detail on the methodology employed, and describes the model inputs, outputs, and key assumptions. It is intended to fulfill the legal obligation of the EIA to provide adequate documentation in support of its models (Public Law 94-385, Section 57.b.2). This report represents Volume 1 of a two-volume set. (Volume 2 will report on model performance, detailing convergence criteria and properties, results of sensitivity testing, comparison of model outputs with the literature and/or other model results, and major unresolved issues.) Subsequent chapters of this report provide: (1) an overview of the NGTDM (Chapter 2); (2) a description of the interface between the National Energy Modeling System (NEMS) and the NGTDM (Chapter 3); (3) an overview of the solution methodology of the NGTDM (Chapter 4); (4) the solution methodology for the Annual Flow Module (Chapter 5); (5) the solution methodology for the Distributor Tariff Module (Chapter 6); (6) the solution methodology for the Capacity Expansion Module (Chapter 7); (7) the solution methodology for the Pipeline Tariff Module (Chapter 8); and (8) a description of model assumptions, inputs, and outputs (Chapter 9).

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...

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...

The Einstein Observatory catalog of IPC x ray sources. Volume 1E: Documentation

Science.gov (United States)

Harris, D. E.; Forman, W.; Gioia, I. M.; Hale, J. A.; Harnden, F. R., Jr.; Jones, C.; Karakashian, T.; Maccacaro, T.; Mcsweeney, J. D.; Primini, F. A.

1993-01-01

The Einstein Observatory (HEAO-2, launched November 13, 1978) achieved radically improved sensitivity over previous x-ray missions through the use of focusing optics, which simultaneously afforded greatly reduced background and produced true images. During its 2.5-yr mission, the Einstein X-Ray Telescope was pointed toward some 5,000 celestial targets, most of which were detected, and discovered several thousand additional 'serendipitous' sources in the observed fields. This catalog contains contour diagrams and source data, obtained with the imaging proportional counter in the 0.16 to 3.5 keV energy band, and describes methods for recovering upper limits for any sky position within the observed images. The main catalog consists of six volumes (numbered 2 through 7) of right ascension ordered pages, each containing data for one observation. Along with the primary documentation describing how the catalog was constructed, volume 1 contains a complete source list, results for merged fields, a reference system to published papers, and data useful for calculating upper limits and fluxes.

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.

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

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...

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

Universal Documentation System Handbook. Volume 2. Requirement Formats and Instructions, Program Introduction, Program Requirements Document/Operations Requirements.

Science.gov (United States)

1989-08-01

horizontal plane is defined as a plane normal to the geocentric position vector. Inertial Azimuth Heading Angle entries are the angles measured east of north...0CATICN: Enter the areas or locations that are to be staffed with redical perscnel, i.e., Vandenberg AFB Hospital, PMIC; or offshore boats, etc. NUMB

Universal Documentation System Handbook. Volume 2. Requirement Formats and Instructions; Program Introduction, Program Requirements Document/Operations Requirements

Science.gov (United States)

1989-08-01

and the local horizontal plane, measured positive above the horizontal plane. The local horizontal plane is defined as a plane normal to the geocentric ...preparation instructions for Format 1000. LOCATION: Enter the areas or locations that are to be staffed with medical personnel, i.e., Vandenberg AFB

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

Tokamak Physics EXperiment (TPX): Toroidal field magnet design, development and manufacture. SDRL 32, Coil assembly documentation. Volume 5

International Nuclear Information System (INIS)

Weber, C.M.

1995-01-01

This document is intended to address the contract requirement for providing coil assembly documentation, as required in the applicable Statement of Work: 'Provide preliminary procedures and preliminary design and supporting analysis of the equipment, fixtures, and hardware required to integrate and align the impregnated coil assemblies with the coil cases and intercoil structure. Each of the three major processes associated with the coil case and intercoil structure (ICS), TF Case Fabrication, Coil Preparation for Case Assembly are examined in detail. The specific requirements, processes, equipment, and technical concerns for each of these assembly processes is presented

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

Three-dimensional measurement system for crime scene documentation

Science.gov (United States)

Adamczyk, Marcin; Hołowko, Elwira; Lech, Krzysztof; Michoński, Jakub; MÄ czkowski, Grzegorz; Bolewicki, Paweł; Januszkiewicz, Kamil; Sitnik, Robert

2017-10-01

Three dimensional measurements (such as photogrammetry, Time of Flight, Structure from Motion or Structured Light techniques) are becoming a standard in the crime scene documentation process. The usage of 3D measurement techniques provide an opportunity to prepare more insightful investigation and helps to show every trace in the context of the entire crime scene. In this paper we would like to present a hierarchical, three-dimensional measurement system that is designed for crime scenes documentation process. Our system reflects the actual standards in crime scene documentation process - it is designed to perform measurement in two stages. First stage of documentation, the most general, is prepared with a scanner with relatively low spatial resolution but also big measuring volume - it is used for the whole scene documentation. Second stage is much more detailed: high resolution but smaller size of measuring volume for areas that required more detailed approach. The documentation process is supervised by a specialised application CrimeView3D, that is a software platform for measurements management (connecting with scanners and carrying out measurements, automatic or semi-automatic data registration in the real time) and data visualisation (3D visualisation of documented scenes). It also provides a series of useful tools for forensic technicians: virtual measuring tape, searching for sources of blood spatter, virtual walk on the crime scene and many others. In this paper we present our measuring system and the developed software. We also provide an outcome from research on metrological validation of scanners that was performed according to VDI/VDE standard. We present a CrimeView3D - a software-platform that was developed to manage the crime scene documentation process. We also present an outcome from measurement sessions that were conducted on real crime scenes with cooperation with Technicians from Central Forensic Laboratory of Police.

Documentation for grants equal to tax model: Volume 3, Source code

International Nuclear Information System (INIS)

Boryczka, M.K.

1986-01-01

The GETT model is capable of forecasting the amount of tax liability associated with all property owned and all activities undertaken by the US Department of Energy (DOE) in site characterization and repository development. The GETT program is a user-friendly, menu-driven model developed using dBASE III/trademark/, a relational data base management system. The data base for GETT consists primarily of eight separate dBASE III/trademark/ files corresponding to each of the eight taxes (real property, personal property, corporate income, franchise, sales, use, severance, and excise) levied by State and local jurisdictions on business property and activity. Additional smaller files help to control model inputs and reporting options. Volume 3 of the GETT model documentation is the source code. The code is arranged primarily by the eight tax types. Other code files include those for JURISDICTION, SIMULATION, VALIDATION, TAXES, CHANGES, REPORTS, GILOT, and GETT. The code has been verified through hand calculations

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

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

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.

Integrating model of the Project Independence Evaluation System. Volume VI. Data documentation. Part I

Energy Technology Data Exchange (ETDEWEB)

Allen, B J

1979-02-01

This documentation describes the PIES Integrating Model as it existed on January 1, 1978. This volume contains two chapters. In Chapter I, Overview, the following subjects are briefly described: supply data, EIA projection series and scenarios, demand data and assumptions, and supply assumptions - oil and gas availabilities. Chapter II contains supply and demand data tables and sources used by the PIES Integrating Model for the mid-range scenario target years 1985 and 1990. Tabulated information is presented for demand, price, and elasticity data; coal data; imports data; oil and gas data; refineries data; synthetics, shale, and solar/geothermal data; transportation data; and utilities data.

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

Energy Technology Data Exchange (ETDEWEB)

1994-04-01

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

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

International Nuclear Information System (INIS)

1994-04-01

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

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...

Subsurface contamination focus area technical requirements. Volume II

International Nuclear Information System (INIS)

Nickelson, D.; Nonte, J.; Richardson, J.

1996-10-01

This is our vision, a vision that replaces the ad hoc or open-quotes delphiclose quotes method which is to get a group of open-quotes expertsclose quotes together and make decisions based upon opinion. To fulfill our vision for the Subsurface Contaminants Focus Area (SCFA), it is necessary to generate technical requirements or performance measures which are quantitative or measurable. Decisions can be supported if they are based upon requirements or performance measures which can be traced to the origin (documented) and are verifiable, i.e., prove that requirements are satisfied by inspection (show me), demonstration, analysis, monitoring, or test. The data from which these requirements are derived must also reflect the characteristics of individual landfills or plumes so that technologies that meet these requirements will necessarily work at specific sites. Other subjective factors, such as stakeholder concerns, do influence decisions. Using the requirements as a basic approach, the SCFA can depend upon objective criteria to help influence the areas of subjectivity, like the stakeholders. In the past, traceable requirements were not generated, probably because it seemed too difficult to do so. There are risks that the requirements approach will not be accepted because it is new and represents a departure from the historical paradigm

Subsurface contamination focus area technical requirements. Volume II

Energy Technology Data Exchange (ETDEWEB)

Nickelson, D.; Nonte, J.; Richardson, J.

1996-10-01

This is our vision, a vision that replaces the ad hoc or {open_quotes}delphi{close_quotes} method which is to get a group of {open_quotes}experts{close_quotes} together and make decisions based upon opinion. To fulfill our vision for the Subsurface Contaminants Focus Area (SCFA), it is necessary to generate technical requirements or performance measures which are quantitative or measurable. Decisions can be supported if they are based upon requirements or performance measures which can be traced to the origin (documented) and are verifiable, i.e., prove that requirements are satisfied by inspection (show me), demonstration, analysis, monitoring, or test. The data from which these requirements are derived must also reflect the characteristics of individual landfills or plumes so that technologies that meet these requirements will necessarily work at specific sites. Other subjective factors, such as stakeholder concerns, do influence decisions. Using the requirements as a basic approach, the SCFA can depend upon objective criteria to help influence the areas of subjectivity, like the stakeholders. In the past, traceable requirements were not generated, probably because it seemed too difficult to do so. There are risks that the requirements approach will not be accepted because it is new and represents a departure from the historical paradigm.

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)

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.

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...

Recommended criteria for the evaluation of on-site nuclear power plant emergency plans, volume II: criteria

International Nuclear Information System (INIS)

1997-01-01

A critical review of existing Canadian and international nuclear power plant (NPP) emergency plans, evaluation criteria, and approaches has been conducted to provide AECB staff with information which can be used to assess the adequacy of NPP on-site emergency response plans. The results of this work are published in two volumes. Volume I, Basis Document, provides the reasons why certain requirements are in place. It also gives comprehensive references to various standards.Volume II, Criteria, contains the criteria which relate to on-site actions and their integration with control room activities and the roles of off-site responsible organizations. The recommended criteria provide information on what is required, and not on how to accomplish the requirements. The licensees are given the latitude to decide on the methods and processes needed to meet the requirements. The documents do not address NPP off-site plans and response capability, or the control room emergency operating procedures and response capability. This report contains only Volume II: Criteria. 55 refs., 2 tabs., 1 fig

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.

Satellite Power Systems (SPS) concept definition study. Volume 6: SPS technology requirements and verification

Science.gov (United States)

Hanley, G.

1978-01-01

Volume 6 of the SPS Concept Definition Study is presented and also incorporates results of NASA/MSFC in-house effort. This volume includes a supporting research and technology summary. Other volumes of the final report that provide additional detail are as follows: (1) Executive Summary; (2) SPS System Requirements; (3) SPS Concept Evolution; (4) SPS Point Design Definition; (5) Transportation and Operations Analysis; and Volume 7, SPS Program Plan and Economic Analysis.

Information base for waste repository design. Volume 5. Decommissioning of underground facilities. Technical report

International Nuclear Information System (INIS)

Giuffre, M.S.; Plum, R.L.; Koplik, C.M.; Talbot, R.

1979-03-01

This report is Volume 5 of a seven volume document on nuclear waste repository design issues. This report discusses the requirements for decommissioning a deep underground facility for the disposal of radioactive waste. The techniques for sealing the mined excavations are presented and an information base on potential backfill materials is provided. Possible requirements for monitoring the site are discussed. The performance requirements for backfill materials are outlined. The advantages and disadvantages of each sealing method are stated

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.''

Safety of magnetic fusion facilities: Volume 2, Guidance

International Nuclear Information System (INIS)

1995-01-01

This document provides guidance for the implementation of the requirements identified in Vol. 1 of this Standard. This guidance is intended for the managers, designers, operators, and other personnel with safety responsibilities for facilities designated as magnetic fusion facilities. While Vol. 1 is generally applicable in that requirements there apply to a wide range of fusion facilities, this volume is concerned mainly with large facilities such as the International Thermonuclear Experimental Reactor (ITER). Using a risk-based prioritization, the concepts presented here may also be applied to other magnetic fusion facilities. This volume is oriented toward regulation in the Department of Energy (DOE) environment

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...

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...

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.

User information document for WinGridder Version 3.0

International Nuclear Information System (INIS)

Pan, Lehua; Pan, Lehua

2007-01-01

WINGRIDDER V3.0 is a Windows-based software for designing and generating numerical grids for numerical simulators that are based on the 'integral finite difference' or the 'control volume' numerical scheme (e.g., TOUGH2, Pruess et al., 1996). The user can design and generate grid that properly represents the stratigraphic features, inclined faults, and repository. WINGRIDDER V3.0 is an upgrade from WINGRIDDER V2.0. This revision includes testable requirements as listed in the Requirements Document (RD), 10024-RD-3.0-00, Section 2. With new features, WINGRIDDER V3.0 adds the ability to generate a multiple-interactive-continuum (MINC) grid

Low-level radioactive waste from commercial nuclear reactors. Volume 3. Bibliographic abstracts of significant source documents. Part 1. Open-literature abstracts for low-level radioactive waste

International Nuclear Information System (INIS)

Bowers, M.K.; Rodgers, B.R.; Jolley, R.L.

1986-05-01

The overall task of this program was to provide an assessment of currently available technology for treating commercial low-level radioactive waste (LLRW), to initiate development of a methodology for choosing one technology for a given application, and to identify research needed to improve current treatment techniques and decision methodology. The resulting report is issued in four volumes. Volume 3 of this series is a collection of abstracts of most of the reference documents used for this study. Because of the large volume of literature, the abstracts have been printed in two separate parts. Volume 3, part 1 presents abstracts of the open literature relating to LLRW treatment methodologies. Some of these references pertain to treatment processes for hazardous wastes that may also be applicable to LLRW management. All abstracts have been limited to 21 lines (for brevity), but each abstract contains sufficient information to enable the reader to determine the potential usefulness of the source document and to locate each article. The abstracts are arranged alphabetically by author or organization, and indexed by keyword

Low-level radioactive waste from commercial nuclear reactors. Volume 3. Bibliographic abstracts of significant source documents. Part 1. Open-literature abstracts for low-level radioactive waste

Energy Technology Data Exchange (ETDEWEB)

Bowers, M.K.; Rodgers, B.R.; Jolley, R.L.

1986-05-01

The overall task of this program was to provide an assessment of currently available technology for treating commercial low-level radioactive waste (LLRW), to initiate development of a methodology for choosing one technology for a given application, and to identify research needed to improve current treatment techniques and decision methodology. The resulting report is issued in four volumes. Volume 3 of this series is a collection of abstracts of most of the reference documents used for this study. Because of the large volume of literature, the abstracts have been printed in two separate parts. Volume 3, part 1 presents abstracts of the open literature relating to LLRW treatment methodologies. Some of these references pertain to treatment processes for hazardous wastes that may also be applicable to LLRW management. All abstracts have been limited to 21 lines (for brevity), but each abstract contains sufficient information to enable the reader to determine the potential usefulness of the source document and to locate each article. The abstracts are arranged alphabetically by author or organization, and indexed by keyword.

LLCEDATA and LLCECALC for Windows version 1.0, Volume 1: User's manual

International Nuclear Information System (INIS)

McFadden, J.G.

1998-01-01

LLCEDATA and LLCECALC for Windows are user-friendly computer software programs that work together to determine the proper waste designation, handling, and disposition requirements for Long Length Contaminated Equipment (LLCE). LLCEDATA reads from a variety of data bases to produce an equipment data file (EDF) that represents a snapshot of both the LLCE and the tank it originates from. LLCECALC reads the EDF and a gamma assay (AV2) file that is produced by the Flexible Receiver Gamma Energy Analysis System. LLCECALC performs corrections to the AV2 file as it is being read and characterizes the LLCE. Both programs produce a variety of reports, including a characterization report and a status report. The status report documents each action taken by the user, LLCEDATA, and LLCECALC. Documentation for LLCEDATA and LLCECALC for Windows is available in three volumes. Volume 1 is a user's manual, which is intended as a quick reference for both LLCEDATA and LLCECALC. Volume 2 is a technical manual, and Volume 3 is a software verification and validation document

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.

ENDF/B summary documentation

International Nuclear Information System (INIS)

Garber, D.

1975-10-01

Descriptions of the evaluations contained in the ENDF/B library are given. The summary documentation presented is intended to be a more detailed description than the (File 1) comments contained in the computer-readable data files, but not so detailed as the formal reports describing each ENDF/B evaluation. The documentations were written by the CSEWG evaluators and compiled by NNCSC. Selected materials which comprise this volume include from 1 H to 244 Cm

Criteria Document for B-plant's Surveillance and Maintenance Phase Safety Basis Document

International Nuclear Information System (INIS)

SCHWEHR, B.A.

1999-01-01

This document is required by the Project Hanford Managing Contractor (PHMC) procedure, HNF-PRO-705, Safety Basis Planning, Documentation, Review, and Approval. This document specifies the criteria that shall be in the B Plant surveillance and maintenance phase safety basis in order to obtain approval of the DOE-RL. This CD describes the criteria to be addressed in the S and M Phase safety basis for the deactivated Waste Fractionization Facility (B Plant) on the Hanford Site in Washington state. This criteria document describes: the document type and format that will be used for the S and M Phase safety basis, the requirements documents that will be invoked for the document development, the deactivated condition of the B Plant facility, and the scope of issues to be addressed in the S and M Phase safety basis document

Interface control document between Analytical Services and Solid Waste Disposal Division

International Nuclear Information System (INIS)

Venetz, T.J.

1995-01-01

This interface control document (ICD) between Analytical Services and Solid Waste Disposal (SWD) establishes a baseline description of the support needed and the wastes that will require management as part of the interface between the two divisions. It is important that each division has a clear understanding of the other division's expectations regarding levels and type of support needed. This ICD deals with the waste sampling support needed by SWD and the waste generated by the specified analytical laboratories. The baseline description of wastes includes waste volumes, characteristics and shipping schedules, which will be used to plan the proper support requirements. The laboratories included in this document are 222-S Laboratory Facility, the Waste Sampling and Characterization Facility (WSCF) and the Chemical Engineering Laboratory. These three facilities provide support to the entire site and are not associated with one major program/facility. The laboratories associated with major facilities or programs such as Engineering/Environmental Development Laboratory at K Basins Operation are not within the scope of this document

The 18 basic requirement of quality assurance for American design NPP

International Nuclear Information System (INIS)

Baliza, Ana Rosa

2013-01-01

On April 17th, 1969, the Atomic Energy Commission (AEC) published in the U.S. Federal Register (FR), Volume 34, Number 73, a proposed amendment to 10CFR50 to insert Appendix B - 'Quality assurance criteria for Nuclear Power Plant'. This Appendix was officially approved on June 27th, 1970 and published in the FR, volume 35, number 125. Appendix B is the Quality Assurance document for U.S. nuclear facilities. This document establishes eighteen basic requirements (BR) to design, construction, manufacture and operation of structures, systems and components (SSC) related to safety. The 18 BR describe 'what' shall be done, but not 'how' to do. In order to standardize the actions of nuclear facilities during 10 CFR 50 App B implementation, the industry has developed some documents, the main ones are: ASME NQA-1 (Quality Assurance Requirements for Nuclear Facility Applications) and the series ANSI N 45.2 (Quality Assurance Program Requirements for Nuclear Facilities). Both documents are approved by the NRC (Nuclear Regulatory Commission). The NRC is the licensing body of U.S. nuclear facilities. In Brazil, the licensing body is CNEN (Comissao Nacional de Energia Nuclear). This paper describes the 18 BR for American Designed Nuclear Power Plant (NPP), applicable to Angra-1 NPP. (author)

Mod-5A wind turbine generator program design report. Volume 4: Drawings and specifications, book 2

Science.gov (United States)

1984-01-01

The design, development and analysis of the 7.3 MW MOD-5A wind turbine generator is documented. There are four volumes. This volume contains the drawings and specifications that were developed in preparation for building the MOD-5A wind turbine generator. This is the second book of volume four. Some of the items it contains are specs for the emergency shutdown panel, specs for the simulator software, simulator hardware specs, site operator terminal requirements, control data system requirements, software project management plan, elastomeric teeter bearing requirement specs, specs for the controls electronic cabinet, and specs for bolt pretensioning.

Documents on Disarmament.

Science.gov (United States)

Arms Control and Disarmament Agency, Washington, DC.

This publication, latest in a series of volumes issued annually since 1960, contains primary source documents on arms control and disarmament developments during 1969. The main chronological arrangement is supplemented by both chronological and topical lists of contents. Other reference aids include a subject/author index, and lists of…

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

Documentation for Grants Equal to Tax model: Volume 1, Technical description

International Nuclear Information System (INIS)

1986-01-01

A computerized model, the Grants Equal to Tax (GETT) model, was developed to assist in evaluating the amount of federal grant monies that would go to state and local jurisdictions under the provisions outlined in the Nuclear Waste Policy Act of 1982. The GETT model is capable of forecasting the amount of tax liability associated with all property owned and all activities undertaken by the US Department of Energy (DOE) in site characterization and repository development. The GETT program is a user-friendly, menu-driven model developed using dBASE III/trademark/, a relational data base management system. The data base for GETT consists primarily of eight separate dBASE III/trademark/ files corresponding to each of the eight taxes levied by state and local jurisdictions on business property and activity. Additional smaller files help to control model inputs and reporting options. Volume 1 of the GETT model documentation is a technical description of the program and its capabilities providing (1) descriptions of the data management system and its procedures; (2) formulas for calculating taxes (illustrated with flow charts); (3) descriptions of tax data base variables for the Deaf Smith County, Texas, Richton Dome, Mississippi, and Davis Canyon, Utah, salt sites; and (4) data inputs for the GETT model. 10 refs., 18 figs., 3 tabs

LLCEDATA and LLCECALC for Windows version 1.0, Volume 1: User`s manual

Energy Technology Data Exchange (ETDEWEB)

McFadden, J.G.

1998-09-04

LLCEDATA and LLCECALC for Windows are user-friendly computer software programs that work together to determine the proper waste designation, handling, and disposition requirements for Long Length Contaminated Equipment (LLCE). LLCEDATA reads from a variety of data bases to produce an equipment data file (EDF) that represents a snapshot of both the LLCE and the tank it originates from. LLCECALC reads the EDF and a gamma assay (AV2) file that is produced by the Flexible Receiver Gamma Energy Analysis System. LLCECALC performs corrections to the AV2 file as it is being read and characterizes the LLCE. Both programs produce a variety of reports, including a characterization report and a status report. The status report documents each action taken by the user, LLCEDATA, and LLCECALC. Documentation for LLCEDATA and LLCECALC for Windows is available in three volumes. Volume 1 is a user`s manual, which is intended as a quick reference for both LLCEDATA and LLCECALC. Volume 2 is a technical manual, and Volume 3 is a software verification and validation document.

Engineering Drawing Practices - Volume I of II: Aerospace and Ground Support Equipment

Science.gov (United States)

Schwindt, Paul A.

2015-01-01

This manual establishes the essential requirements and reference documents for the preparation and revision of digital product definition data sets prepared for or by NASA at KSC. This volume is only applicable to KSC in-house programs/projects. These requirements do not apply to the preparation of illustrations, artwork, or figures in technical publications.

Reactor operation environmental information document

Energy Technology Data Exchange (ETDEWEB)

Bauer, L.R.; Hayes, D.W.; Hunter, C.H.; Marter, W.L.; Moyer, R.A.

1989-12-01

This volume is a reactor operation environmental information document for the Savannah River Plant. Topics include meteorology, surface hydrology, transport, environmental impacts, and radiation effects. 48 figs., 56 tabs. (KD)

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.

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

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.

Supplement to nuclear EQ sourcebook: A compilation of documents for nuclear equipment qualification

International Nuclear Information System (INIS)

Anon.

1993-01-01

In the nuclear power industry, environmental and seismic qualification of safety-related electrical and instrumentation equipment is collectively known as Equipment Qualification (EQ). Related technology, as well as regulatory requirements, have evolved rapidly during the last 15 years. For environmental qualification, what began in 1971 with one trial-use guide (IEEE Std 323-1971), now stands as a full complement of Nuclear Regulatory Commission (NRC) rules, guides, and industry standards. As the original 1992 version of the Nuclear EQ Sourcebook was compiled to serve the user-community need for a complete and exhaustive single source of nuclear EQ documentation, this Supplement is published to provide the user community with nuclear EQ documentation revisions and updates that have been published since the publication of the original volume in May of 1992. The first volume of this publication included documents issued before December, 1991. That first volume was well received and also prompted positive response from industry on its usefulness and on recommendations to improve the completeness and enhance the ease of use. This Supplement, therefore, includes new documents, revisions, and updates issued and published since December 1991 and up to and including March 1993. It incorporates various enhancements in order to better serve the user community. One such enhancement included in this Supplement is the new Equipment Classification Index that is described in the User Guide section of this publication. 37 papers, including Bulletins, Federal rules, Generic Letters, Notices, Regulatory Guides, IEEE Standards, IEEE Recommended Practices, and IEEE Guides, have been processed separately for inclusion on the data base

The Gift Code User Manual. Volume I. Introduction and Input Requirements

Science.gov (United States)

1975-07-01

REPORT & PERIOD COVERED ‘TII~ GIFT CODE USER MANUAL; VOLUME 1. INTRODUCTION AND INPUT REQUIREMENTS FINAL 6. PERFORMING ORG. REPORT NUMBER ?. AuTHOR(#) 8...reverua side if neceaeary and identify by block number] (k St) The GIFT code is a FORTRANcomputerprogram. The basic input to the GIFT ode is data called

LLCEDATA and LLCECALC for Windows version 1.0, Volume 2: Technical manual

Energy Technology Data Exchange (ETDEWEB)

McFadden, J.G.

1998-09-04

LLCEDATA and LLCECALC for Windows are user-friendly computer software programs that work together to determine the proper waste designation, handling, and disposition requirements for Long Length Contaminated Equipment (LLCE). LLCEDATA reads from a variety of databases to produce an equipment data file (EDF) that represents a snapshot of both the LLCE and the tank from which it originates. LLCECALC reads the EDF and the gamma assay (AV2) file that is produced by the Flexible Receiver Gamma Energy Analysis System. LLCECALC performs corrections to the AV2 file as it is being read and characterizes the LLCE Both programs produce a variety of reports, including a characterization report and a status report. The status report documents each action taken by the user, LLCEDA TA, and LLCECALC. Documentation for LLCEDA TA and LLCECALC for Windows is available in three volumes. Volume 1 is a user`s manual, which is intended as a quick reference for both LLCEDATA and LLCECALC. Volume 2 is a technical manual, which documents LLCEDATA and LLCECALCs methodology, structure, and format, provides sample calculations; discusses system limitations; and provides recommendations to the LLCE process. Volume 3 is a software verification and validation document LLCEDATA and LLCECALC for Windows are sponsored by the U.S.Department of Energy. They were developed and are maintained by Engineering, Waste Management Federal Services, Inc., Northwest Operations. Copies of the software and documentation are available by contacting Engineering, Waste Management Federal Services, Inc., Northwest Operations, Richland, Washington.

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.

FBI fingerprint identification automation study: AIDS 3 evaluation report. Volume 9: Functional requirements

Science.gov (United States)

1980-01-01

The current system and subsystem used by the Identification Division are described. System constraints that dictate the system environment are discussed and boundaries within which solutions must be found are described. The functional requirements were related to the performance requirements. These performance requirements were then related to their applicable subsystems. The flow of data, documents, or other pieces of information from one subsystem to another or from the external world into the identification system is described. Requirements and design standards for a computer based system are presented.

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.

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.

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...

International Nuclear Model. Volume 3. Program description

International Nuclear Information System (INIS)

Andress, D.

1985-01-01

This is Volume 3 of three volumes of documentation of the International Nuclear Model (INM). This volume presents the Program Description of the International Nuclear Model, which was developed for the Nuclear and Alternate Fuels Division (NAFD), Office of Coal, Nuclear, Electric and Alternate Fuels, Energy Information Administration (EIA), US Department of Energy (DOE). The International Nuclear Model (INM) is a comprehensive model of the commercial nuclear power industry. It simulates economic decisions for reactor deployment and fuel management decision based on an input set of technical economic and scenario parameters. The technical parameters include reactor operating characteristics, fuel cycle timing and mass loss factors, and enrichment tails assays. Economic parameters include fuel cycle costs, financial data, and tax alternatives. INM has a broad range of scenario options covering, for example, process constraints, interregional activities, reprocessing, and fuel management selection. INM reports reactor deployment schedules, electricity generation, and fuel cycle requirements and costs. It also has specialized reports for extended burnup and permanent disposal. Companion volumes to Volume 3 are: Volume 1 - Model Overview, and Volume 2 - Data Base Relationships

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

Improved Optical Document Security Techniques Based on Volume Holography and Lippmann Photography

Science.gov (United States)

Bjelkhagen, Hans I.

Optical variable devices (OVDs), such as holograms, are now common in the field of document security. Up until now mass-produced embossed holograms or other types of mass-produced OVDs are used not only for banknotes but also for personalized documents, such as passports, ID cards, travel documents, driving licenses, credit cards, etc. This means that identical OVDs are used on documents issued to individuals. Today, there is need for a higher degree of security on such documents and this chapter covers new techniques to make improved mass-produced or personalized OVDs.

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.

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

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

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

Spent Nuclear Fuel Project technical baseline document. Fiscal year 1995: Volume 1, Baseline description

International Nuclear Information System (INIS)

Womack, J.C.; Cramond, R.; Paedon, R.J.

1995-01-01

This document is a revision to WHC-SD-SNF-SD-002, and is issued to support the individual projects that make up the Spent Nuclear Fuel Project in the lower-tier functions, requirements, interfaces, and technical baseline items. It presents results of engineering analyses since Sept. 1994. The mission of the SNFP on the Hanford site is to provide safety, economic, environmentally sound management of Hanford SNF in a manner that stages it to final disposition. This particularly involves K Basin fuel, although other SNF is involved also

Gas Test Loop Functional and Technical Requirements

International Nuclear Information System (INIS)

Glen R. Longhurst; Soli T. Khericha; James L. Jones

2004-01-01

This document defines the technical and functional requirements for a gas test loop (GTL) to be constructed for the purpose of providing a high intensity fast-flux irradiation environment for developers of advanced concept nuclear reactors. This capability is needed to meet fuels and materials testing requirements of the designers of Generation IV (GEN IV) reactors and other programs within the purview of the Advanced Fuel Cycle Initiative (AFCI). Space nuclear power development programs may also benefit by the services the GTL will offer. The overall GTL technical objective is to provide developers with the means for investigating and qualifying fuels and materials needed for advanced reactor concepts. The testing environment includes a fast-flux neutron spectrum of sufficient intensity to perform accelerated irradiation testing. Appropriate irradiation temperature, gaseous environment, test volume, diagnostics, and access and handling features are also needed. This document serves to identify those requirements as well as generic requirements applicable to any system of this kind

Gas Test Loop Functional and Technical Requirements

Energy Technology Data Exchange (ETDEWEB)

Glen R. Longhurst; Soli T. Khericha; James L. Jones

2004-09-01

This document defines the technical and functional requirements for a gas test loop (GTL) to be constructed for the purpose of providing a high intensity fast-flux irradiation environment for developers of advanced concept nuclear reactors. This capability is needed to meet fuels and materials testing requirements of the designers of Generation IV (GEN IV) reactors and other programs within the purview of the Advanced Fuel Cycle Initiative (AFCI). Space nuclear power development programs may also benefit by the services the GTL will offer. The overall GTL technical objective is to provide developers with the means for investigating and qualifying fuels and materials needed for advanced reactor concepts. The testing environment includes a fast-flux neutron spectrum of sufficient intensity to perform accelerated irradiation testing. Appropriate irradiation temperature, gaseous environment, test volume, diagnostics, and access and handling features are also needed. This document serves to identify those requirements as well as generic requirements applicable to any system of this kind.

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...

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

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)

Mod-5A wind turbine generator program design report. Volume 2: Conceptual and preliminary design, book 2

Science.gov (United States)

1984-01-01

The design, development and analysis of the 7.3 MW MOD-5A wind tunnel generator is documented. There are four volumes. In Volume 2, book 2 the requirements and criteria for the design are presented. The development tests, which determined or characterized many of the materials and components of the wind turbine generator, are described.

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

Savannah River Site mixed waste Proposed Site Treatment Plan (PSTP). Volumes 1 and 2 and reference document: Revision 2

International Nuclear Information System (INIS)

Helmich, E.; Noller, D.K.; Wierzbicki, K.S.; Bailey, L.L.

1995-01-01

The DOE is required by the Resource Conservation and Recovery Act to prepare site treatment plans describing the development of treatment capacities and technologies for treating mixed waste. This proposed plan contains Savannah River Site's preferred options and schedules for constructing new facilities, and otherwise obtaining treatment for mixed wastes. The proposed plan consists of 2 volumes. Volume 1, Compliance Plan, identifies the capacity to be developed and the schedules as required. Volume 2, Background, provides a detailed discussion of the preferred options with technical basis, plus a description of the specific waste streams. Chapters are: Introduction; Methodology; Mixed low level waste streams; Mixed transuranic waste; High level waste; Future generation of mixed waste streams; Storage; Process for evaluation of disposal issues in support of the site treatment plans discussions; Treatment facilities and treatment technologies; Offsite waste streams for which SRS treatment is the Preferred Option (Naval reactor wastes); Summary information; and Acronyms and glossary. This revision does not contain the complete revised report, but only those pages that have been revised

EUDISED: European Documentation and Information System for Education. Volume II, National Reports.

Science.gov (United States)

Council of Europe, Strasbourg (France). Documentation Center for Education in Europe.

This study briefly describes the documentation and information projects of seven nations, stressing their use in the field of education. The sections are: (1) automated documentation and the human sciences in France, (2) documentation for education and the social sciences in the Federal Republic of Germany, (3) mechanized projects in library work…

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.)

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.

C-Band Airport Surface Communications System Standards Development. Phase II Final Report. Volume 1: Concepts of Use, Initial System Requirements, Architecture, and AeroMACS Design Considerations

Science.gov (United States)

Hall, Edward; Isaacs, James; Henriksen, Steve; Zelkin, Natalie

2011-01-01

This report is provided as part of ITT s NASA Glenn Research Center Aerospace Communication Systems Technical Support (ACSTS) contract NNC05CA85C, Task 7: New ATM Requirements-Future Communications, C-Band and L-Band Communications Standard Development and was based on direction provided by FAA project-level agreements for New ATM Requirements-Future Communications. Task 7 included two subtasks. Subtask 7-1 addressed C-band (5091- to 5150-MHz) airport surface data communications standards development, systems engineering, test bed and prototype development, and tests and demonstrations to establish operational capability for the Aeronautical Mobile Airport Communications System (AeroMACS). Subtask 7-2 focused on systems engineering and development support of the L-band digital aeronautical communications system (L-DACS). Subtask 7-1 consisted of two phases. Phase I included development of AeroMACS concepts of use, requirements, architecture, and initial high-level safety risk assessment. Phase II builds on Phase I results and is presented in two volumes. Volume I (this document) is devoted to concepts of use, system requirements, and architecture, including AeroMACS design considerations. Volume II describes an AeroMACS prototype evaluation and presents final AeroMACS recommendations. This report also describes airport categorization and channelization methodologies. The purposes of the airport categorization task were (1) to facilitate initial AeroMACS architecture designs and enable budgetary projections by creating a set of airport categories based on common airport characteristics and design objectives, and (2) to offer high-level guidance to potential AeroMACS technology and policy development sponsors and service providers. A channelization plan methodology was developed because a common global methodology is needed to assure seamless interoperability among diverse AeroMACS services potentially supplied by multiple service providers.

Pairwise Trajectory Management (PTM): Concept Description and Documentation

Science.gov (United States)

Jones, Kenneth M.; Graff, Thomas J.; Carreno, Victor; Chartrand, Ryan C.; Kibler, Jennifer L.

2018-01-01

Pairwise Trajectory Management (PTM) is an Interval Management (IM) concept that utilizes airborne and ground-based capabilities to enable the implementation of airborne pairwise spacing capabilities in oceanic regions. The goal of PTM is to use airborne surveillance and tools to manage an "at or greater than" inter-aircraft spacing. Due to the accuracy of Automatic Dependent Surveillance-Broadcast (ADS-B) information and the use of airborne spacing guidance, the minimum PTM spacing distance will be less than distances a controller can support with current automation systems that support oceanic operations. Ground tools assist the controller in evaluating the traffic picture and determining appropriate PTM clearances to be issued. Avionics systems provide guidance information that allows the flight crew to conform to the PTM clearance issued by the controller. The combination of a reduced minimum distance and airborne spacing management will increase the capacity and efficiency of aircraft operations at a given altitude or volume of airspace. This document provides an overview of the proposed application, a description of several key scenarios, a high level discussion of expected air and ground equipment and procedure changes, a description of a NASA human-machine interface (HMI) prototype for the flight crew that would support PTM operations, and initial benefits analysis results. Additionally, included as appendices, are the following documents: the PTM Operational Services and Environment Definition (OSED) document and a companion "Future Considerations for the Pairwise Trajectory Management (PTM) Concept: Potential Future Updates for the PTM OSED" paper, a detailed description of the PTM algorithm and PTM Limit Mach rules, initial PTM safety requirements and safety assessment documents, a detailed description of the design, development, and initial evaluations of the proposed flight crew HMI, an overview of the methodology and results of PTM pilot training

Atlas-Based Segmentation Improves Consistency and Decreases Time Required for Contouring Postoperative Endometrial Cancer Nodal Volumes

International Nuclear Information System (INIS)

Young, Amy V.; Wortham, Angela; Wernick, Iddo; Evans, Andrew; Ennis, Ronald D.

2011-01-01

Purpose: Accurate target delineation of the nodal volumes is essential for three-dimensional conformal and intensity-modulated radiotherapy planning for endometrial cancer adjuvant therapy. We hypothesized that atlas-based segmentation ('autocontouring') would lead to time savings and more consistent contours among physicians. Methods and Materials: A reference anatomy atlas was constructed using the data from 15 postoperative endometrial cancer patients by contouring the pelvic nodal clinical target volume on the simulation computed tomography scan according to the Radiation Therapy Oncology Group 0418 trial using commercially available software. On the simulation computed tomography scans from 10 additional endometrial cancer patients, the nodal clinical target volume autocontours were generated. Three radiation oncologists corrected the autocontours and delineated the manual nodal contours under timed conditions while unaware of the other contours. The time difference was determined, and the overlap of the contours was calculated using Dice's coefficient. Results: For all physicians, manual contouring of the pelvic nodal target volumes and editing the autocontours required a mean ± standard deviation of 32 ± 9 vs. 23 ± 7 minutes, respectively (p = .000001), a 26% time savings. For each physician, the time required to delineate the manual contours vs. correcting the autocontours was 30 ± 3 vs. 21 ± 5 min (p = .003), 39 ± 12 vs. 30 ± 5 min (p = .055), and 29 ± 5 vs. 20 ± 5 min (p = .0002). The mean overlap increased from manual contouring (0.77) to correcting the autocontours (0.79; p = .038). Conclusion: The results of our study have shown that autocontouring leads to increased consistency and time savings when contouring the nodal target volumes for adjuvant treatment of endometrial cancer, although the autocontours still required careful editing to ensure that the lymph nodes at risk of recurrence are properly included in the target volume.

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)

Savannah River Site Environmental Monitoring Plan. Volume 1, Section 1000 Addendum: Revision 3

International Nuclear Information System (INIS)

Jannik, G.T.

1994-01-01

This document -- the Savannah River Site Environmental Monitoring Plan (SRS EM Plan) -- has been prepared according to guidance contained in the DOE 5400 Series orders, in 10 CFR 834, and in DOE/EH-0173T, Environmental Regulatory Guide for Radiological Effluent Monitoring and environmental Surveillance [DOE, 1991]. The SRS EM Plan's purpose is to define the criteria, regulations, and guideline requirements with which SRS will comply. These criteria and requirements are applicable to environmental monitoring activities performed in support of the SRS Environmental Monitoring Program (SRS EM Program), WSRC-3Q1-2, Volume 1, Section 1100. They are not applicable to monitoring activities utilized exclusively for process monitoring/control. The environmental monitoring program requirements documented in the SRS EM Plan incorporate all applicable should requirements of DOE/EH-0173T and expand upon them to include nonradiological environmental monitoring program requirements

LLCEDATA and LLCECALC for Windows version 1.0, Volume 3: Software verification and validation

International Nuclear Information System (INIS)

McFadden, J.G.

1998-01-01

LLCEDATA and LLCECALC for Windows are user-friendly computer software programs that work together to determine the proper waste designation, handling, and disposition requirements for Long Length Contaminated Equipment (LLCE). LLCEDATA reads from a variety of data bases to produce an equipment data file(EDF) that represents a snapshot of both the LLCE and the tank from which it originates. LLCECALC reads the EDF and the gamma assay file (AV2) that is produced by the flexible Receiver Gamma Energy Analysis System. LLCECALC performs corrections to the AV2 file as it is being read and characterizes the LLCE. Both programs produce a variety of reports, including a characterization report and a status report. The status report documents each action taken by the user, LLCEDATA, and LLCECALC. Documentation for LLCEDATA and LLCECALC for Windows is available in three volumes. Volume 1 is a user's manual, which is intended as a quick reference for both LLCEDATA and LLCECALC. Volume 2 is a technical manual, which discusses system limitations and provides recommendations to the LLCE process. Volume 3 documents LLCEDATA and LLCECALC's verification and validation. Two of the three installation test cases, from Volume 1, are independently confirmed. Data bases used in LLCEDATA are verified and referenced. Both phases of LLCECALC process gamma and characterization, are extensively tested to verify that the methodology and algorithms used are correct

No-migration variance petition: Draft. Volume 4, Appendices DIF, GAS, GCR (Volume 1)

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-05-31

The Department of Energy is responsible for the disposition of transuranic (TRU) waste generated by national defense-related activities. Approximately 2.6 million cubic feet of the se waste have been generated and are stored at various facilities across the country. The Waste Isolation Pilot Plant (WIPP), was sited and constructed to meet stringent disposal requirements. In order to permanently dispose of TRU waste, the DOE has elected to petition the US EPA for a variance from the Land Disposal Restrictions of RCRA. This document fulfills the reporting requirements for the petition. This report is volume 4 of the petition which presents details about the transport characteristics across drum filter vents and polymer bags; gas generation reactions and rates during long-term WIPP operation; and geological characterization of the WIPP site.

No-migration variance petition: Draft. Volume 4, Appendices DIF, GAS, GCR (Volume 1)

International Nuclear Information System (INIS)

1995-01-01

The Department of Energy is responsible for the disposition of transuranic (TRU) waste generated by national defense-related activities. Approximately 2.6 million cubic feet of the se waste have been generated and are stored at various facilities across the country. The Waste Isolation Pilot Plant (WIPP), was sited and constructed to meet stringent disposal requirements. In order to permanently dispose of TRU waste, the DOE has elected to petition the US EPA for a variance from the Land Disposal Restrictions of RCRA. This document fulfills the reporting requirements for the petition. This report is volume 4 of the petition which presents details about the transport characteristics across drum filter vents and polymer bags; gas generation reactions and rates during long-term WIPP operation; and geological characterization of the WIPP site

Response to comments background document for the Third Third land-disposal restrictions proposed rule November 22, 1989 (54 FR 48372). Volume 2-2. Capacity-related comments

International Nuclear Information System (INIS)

1990-01-01

On November 22, 1989, the Environmental Protection Agency (EPA, the Agency) proposed a rule to prohibit the land disposal of the final third of the schedule of restricted hazardous wastes, known as the Third Third (see 54 Federal Register 48372). The proposal outlined treatment standards and effective dates of prohibition for these wastes as well as for some First and Second Third soft hammer wastes, characteristic wastes, certain waste groups (e.g., multi-source leachate, radioactive mixed waste), and newly listed wastes. The proposed rule was issued pursuant to the 1984 Hazardous and Solid Waste Amendments (HSWA) to the Resource Conservation and Recovery Act (RCRA). The Agency requested public comment on the proposal. The regulated community, environmental organizations, trade associations, State and Federal agencies, and concerned citizens submitted over 300 written letters on the proposed rule. EPA developed three volumes of a comment response document. This document (Volume 2 of 3) presents a summary of and responses to capacity-related comments received by the EPA docket clerk in response to the proposed rule. The comments have been divided into 17 chapters, each addressing specific comment categories. This volume contains Chapters 8-12. These chapters discuss mercury wastes, other metals, F, K, U, and P wastes, KO48-KO52 wastes, and deepwell injected wastes

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.

Large Scale Document Inversion using a Multi-threaded Computing System.

Science.gov (United States)

Jung, Sungbo; Chang, Dar-Jen; Park, Juw Won

2017-06-01

Current microprocessor architecture is moving towards multi-core/multi-threaded systems. This trend has led to a surge of interest in using multi-threaded computing devices, such as the Graphics Processing Unit (GPU), for general purpose computing. We can utilize the GPU in computation as a massive parallel coprocessor because the GPU consists of multiple cores. The GPU is also an affordable, attractive, and user-programmable commodity. Nowadays a lot of information has been flooded into the digital domain around the world. Huge volume of data, such as digital libraries, social networking services, e-commerce product data, and reviews, etc., is produced or collected every moment with dramatic growth in size. Although the inverted index is a useful data structure that can be used for full text searches or document retrieval, a large number of documents will require a tremendous amount of time to create the index. The performance of document inversion can be improved by multi-thread or multi-core GPU. Our approach is to implement a linear-time, hash-based, single program multiple data (SPMD), document inversion algorithm on the NVIDIA GPU/CUDA programming platform utilizing the huge computational power of the GPU, to develop high performance solutions for document indexing. Our proposed parallel document inversion system shows 2-3 times faster performance than a sequential system on two different test datasets from PubMed abstract and e-commerce product reviews. •Information systems➝Information retrieval • Computing methodologies➝Massively parallel and high-performance simulations.

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.''

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)

Tank Monitoring and Document control System (TMACS) As Built Software Design Document

International Nuclear Information System (INIS)

GLASSCOCK, J.A.

2000-01-01

This document describes the software design for the Tank Monitor and Control System (TMACS). This document captures the existing as-built design of TMACS as of November 1999. It will be used as a reference document to the system maintainers who will be maintaining and modifying the TMACS functions as necessary. The heart of the TMACS system is the ''point-processing'' functionality where a sample value is received from the field sensors and the value is analyzed, logged, or alarmed as required. This Software Design Document focuses on the point-processing functions

Documentation and archiving of the Space Shuttle wind tunnel test data base. Volume 1: Background and description

Science.gov (United States)

Romere, Paul O.; Brown, Steve Wesley

1995-01-01

Development of the space shuttle necessitated an extensive wind tunnel test program, with the cooperation of all the major wind tunnels in the United States. The result was approximately 100,000 hours of space shuttle wind tunnel testing conducted for aerodynamics, heat transfer, and structural dynamics. The test results were converted into Chrysler DATAMAN computer program format to facilitate use by analysts, a very cost effective method of collecting the wind tunnel test results from many test facilities into one centralized location. This report provides final documentation of the space shuttle wind tunnel program. The two-volume set covers evolution of space shuttle aerodynamic configurations and gives wind tunnel test data, titles of wind tunnel data reports, sample data sets, and instructions for accessing the digital data base.

CASK/MSC/WP PREPARATION SYSTEM DESCRIPTION DOCUMENT

International Nuclear Information System (INIS)

S. Drummond

2005-01-01

The purpose of this system description document (SDD) is to establish requirements that drive the design of the Cask/MSC/WP preparation 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 and 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. This 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. This SDD addresses the ''Project Requirements Document'' (PRD) (Canori and Leitner 2003 [DIRS 166275]) requirements. Additional PRD requirements may be cited, as applicable, to drive the design of specific aspects of the system, with justifications provided in the basis. Functional and operational requirements applicable to this system are obtained from the ''Project Functional and Operational Requirements'' (F and OR) (Curry 2004 [DIRS 170557]) document. Other requirements to support the design process have been taken from higher-level requirements documents such as the ''Project Design Criteria Document'' (PDC) (BSC 2004 [DIRS 171599]) and the preclosure safety analyses

Community Documentation Centre on Industrial Risk. Bulletin no. 8

International Nuclear Information System (INIS)

Masera, M.; Rasmussen, K.

1993-01-01

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

Community Documentation Centre on Industrial Risk. Bulletin no. 4

International Nuclear Information System (INIS)

Gow, H.B.F.

1991-01-01

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

Community Documentation Centre on Industrial Risk. Bulletin no. 10

International Nuclear Information System (INIS)

Perschke, A.; Kirchsteiger, C.

1996-01-01

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

Community Documentation Centre on Industrial Risk. Bulletin no. 5

International Nuclear Information System (INIS)

Gow, H.B.F.

1991-11-01

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

Community Documentation Centre on Industrial Risk. Bulletin no. 7

International Nuclear Information System (INIS)

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

1993-04-01

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

Community Documentation Centre on Industrial Risk. Bulletin no. 9

International Nuclear Information System (INIS)

Perschke, A.

1995-01-01

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

Community Documentation Centre on Industrial Risk. Bulletin no. 6

International Nuclear Information System (INIS)

Gow, H.B.F.

1992-06-01

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

Community Documentation Centre on Industrial Risk. Bulletin no. 11

International Nuclear Information System (INIS)

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

1997-01-01

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

Environmental resource document for the Idaho National Engineering Laboratory. Volume 1

Energy Technology Data Exchange (ETDEWEB)

Irving, J.S.

1993-07-01

This document contains information related to the environmental characterization of the Idaho National Engineering Laboratory (INEL). The INEL is a major US Department of Energy facility in southeastern Idaho dedicated to nuclear research, waste management, environmental restoration, and other activities related to the development of technology. Environmental information covered in this document includes land, air, water, and ecological resources; socioeconomic characteristics and land use; and cultural, aesthetic, and scenic resources.

Environmental resource document for the Idaho National Engineering Laboratory. Volume 2

Energy Technology Data Exchange (ETDEWEB)

Irving, J.S.

1993-07-01

This document contains information related to the environmental characterization of the Idaho National Engineering Laboratory (INEL). The INEL is a major US Department of Energy facility in southeastern Idaho dedicated to nuclear research, waste management, environmental restoration, and other activities related to the development of technology. Environmental information covered in this document includes land, air, water, and ecological resources; socioeconomic characteristics and land use; and cultural, aesthetic, and scenic resources.

SNF AGING SYSTEM DESCRIPTION DOCUMENT

Energy Technology Data Exchange (ETDEWEB)

L.L. Swanson

2005-04-06

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&OR) (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

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

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

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

Information architecture. Volume 2, Part 1: Baseline analysis summary

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-12-01

The Department of Energy (DOE) Information Architecture, Volume 2, Baseline Analysis, is a collaborative and logical next-step effort in the processes required to produce a Departmentwide information architecture. The baseline analysis serves a diverse audience of program management and technical personnel and provides an organized way to examine the Department`s existing or de facto information architecture. A companion document to Volume 1, The Foundations, it furnishes the rationale for establishing a Departmentwide information architecture. This volume, consisting of the Baseline Analysis Summary (part 1), Baseline Analysis (part 2), and Reference Data (part 3), is of interest to readers who wish to understand how the Department`s current information architecture technologies are employed. The analysis identifies how and where current technologies support business areas, programs, sites, and corporate systems.

Title list of documents made publicly available. Volume 17, No. 1

International Nuclear Information System (INIS)

1995-03-01

This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. The following indexes are included: Personal author, corporate source, report number, and cross reference of enclosures to principal documents

Title list of documents made publicly available. Volume 17, No. 10

International Nuclear Information System (INIS)

1995-12-01

This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. The following indexes are included: Personal Author, Corporate Source, Report Number, and Cross Reference of Enclosures to Principal Documents

Title list of documents made publicly available. Volume 17, No. 10

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-12-01

This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. The following indexes are included: Personal Author, Corporate Source, Report Number, and Cross Reference of Enclosures to Principal Documents.

Title list of documents made publicly available. Volume 17, No. 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-03-01

This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. The following indexes are included: Personal author, corporate source, report number, and cross reference of enclosures to principal documents.

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.

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

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.

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

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.

CASK/MSC/WP PREPARATION SYSTEM DESCRIPTION DOCUMENT

Energy Technology Data Exchange (ETDEWEB)

S. Drummond

2005-04-12

The purpose of this system description document (SDD) is to establish requirements that drive the design of the Cask/MSC/WP preparation 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 and 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. This 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. This SDD addresses the ''Project Requirements Document'' (PRD) (Canori and Leitner 2003 [DIRS 166275]) requirements. Additional PRD requirements may be cited, as applicable, to drive the design of specific aspects of the system, with justifications provided in the basis. Functional and operational requirements applicable to this system are obtained from the ''Project Functional and Operational Requirements'' (F&OR) (Curry 2004 [DIRS 170557]) document. Other requirements to support the design process have been taken from higher-level requirements documents such as the ''Project Design Criteria Document'' (PDC) (BSC 2004 [DIRS 171599]) and the preclosure safety analyses.

Design requirements for SRB production control system. Volume 3: Package evaluation, modification and hardware

Science.gov (United States)

1981-01-01

The software package evaluation was designed to analyze commercially available, field-proven, production control or manufacturing resource planning management technology and software package. The analysis was conducted by comparing SRB production control software requirements and conceptual system design to software package capabilities. The methodology of evaluation and the findings at each stage of evaluation are described. Topics covered include: vendor listing; request for information (RFI) document; RFI response rate and quality; RFI evaluation process; and capabilities versus requirements.

Tank Monitoring and Document control System (TMACS) As Built Software Design Document

Energy Technology Data Exchange (ETDEWEB)

GLASSCOCK, J.A.

2000-01-27

This document describes the software design for the Tank Monitor and Control System (TMACS). This document captures the existing as-built design of TMACS as of November 1999. It will be used as a reference document to the system maintainers who will be maintaining and modifying the TMACS functions as necessary. The heart of the TMACS system is the ''point-processing'' functionality where a sample value is received from the field sensors and the value is analyzed, logged, or alarmed as required. This Software Design Document focuses on the point-processing functions.

National Childcare Consumer Study: 1975. Volume IV: Supplemental Documentation.

Science.gov (United States)

Unco, Inc., Washington, DC.

This document is the fourth and final report of a study sponsored by the Office of Child Development of the U.S. Department of Health, Education and Welfare to determine patterns of child care usage and related consumer preferences, attitudes and opinions about child care. The study was based on 4609 personal interviews conducted in 1975 from a…

Monitored Natural Attenuation of Inorganic Contaminants in Ground Water Volume 3 Assessment for Radionuclides IncludingTritium, Radon, Strontium, Technetium, Uranium, Iodine, Radium, Thorium, Cesium, and Plutonium-Americium

Science.gov (United States)

The current document represents the third volume of a set of three volumes that address the technical basis and requirements for assessing the potential applicability of MNA as part of a ground-water remedy for plumes with nonradionuclide and/or radionuclide inorganic contamina...

Monitored Attenuation of Inorganic Contaminants in Ground Water Volume 2 – Assessment for Non-Radionuclides Including Arsenic, Cadmium, Chromium, Copper, Lead, Nickel, Nitrate, Perchlorate, and Selenium

Science.gov (United States)

This document represents the second volume of a set of three volumes that address the technical basis and requirements for assessing the potential applicability of MNA as part of a ground-water remedy for plumes with non-radionuclide and/or radionuclide inorganic contaminants. V...

Large Scale Document Inversion using a Multi-threaded Computing System

Science.gov (United States)

Jung, Sungbo; Chang, Dar-Jen; Park, Juw Won

2018-01-01

Current microprocessor architecture is moving towards multi-core/multi-threaded systems. This trend has led to a surge of interest in using multi-threaded computing devices, such as the Graphics Processing Unit (GPU), for general purpose computing. We can utilize the GPU in computation as a massive parallel coprocessor because the GPU consists of multiple cores. The GPU is also an affordable, attractive, and user-programmable commodity. Nowadays a lot of information has been flooded into the digital domain around the world. Huge volume of data, such as digital libraries, social networking services, e-commerce product data, and reviews, etc., is produced or collected every moment with dramatic growth in size. Although the inverted index is a useful data structure that can be used for full text searches or document retrieval, a large number of documents will require a tremendous amount of time to create the index. The performance of document inversion can be improved by multi-thread or multi-core GPU. Our approach is to implement a linear-time, hash-based, single program multiple data (SPMD), document inversion algorithm on the NVIDIA GPU/CUDA programming platform utilizing the huge computational power of the GPU, to develop high performance solutions for document indexing. Our proposed parallel document inversion system shows 2-3 times faster performance than a sequential system on two different test datasets from PubMed abstract and e-commerce product reviews. CCS Concepts •Information systems➝Information retrieval • Computing methodologies➝Massively parallel and high-performance simulations.

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...

Implementing US Department of Energy lessons learned programs. Volume 2

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-08-01

The DOE Lessons Learned Handbook is a two-volume publication developed to supplement the DOE Lessons Learned Standard (DOE-STD-7501-95) with information that will organizations in developing or improving their lessons learned programs. Volume 1 includes greater detail than the Standard in areas such as identification and documentation of lessons learned; it also contains sections on specific processes such as training and performance measurement. Volume 2 (this document) contains examples of program documents developed by existing lessons learned programs as well as communications material, functional categories, transmittal documents, sources of professional and industry lessons learned, and frequently asked questions about the Lessons Learned List Service.

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)

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.

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

Documentation control process of Brazilian multipurpose reactor: conceptual design and basic design

International Nuclear Information System (INIS)

Kibrit, Eduardo; Prates, Jose Eduardo; Longo, Guilherme Carneiro; Salvetti, Tereza Cristina

2015-01-01

Established in the scope of Plan of Action of the Ministry of Science, Technology and Innovation (PACTI/MCTI) in 2007, the construction of the Brazilian Multipurpose Reactor (RMB) is on the way. This type of reactor has a broad spectrum of applications in the nuclear field and related technologies such as the radioisotopes used as supplies in the production of radiopharmaceuticals, with very much benefit to the Brazilian society being, therefore, the main goal of the Project. RMB Project consists of the following stages: site selection and site evaluation; design (conceptual design, basic design, detailed design and experimental design); construction (procurement, manufacturing; civil construction; electromechanical construction and assembling); commissioning; operation and decommissioning. Each stage requires adaptation of human resources for the stage schedule execution. The implementation of a project of this magnitude requires a complex project management, which covers not only technical, but also administrative areas. Licensing, financial resources, quality and document control systems, engineering are some of the areas involved in project success. The development of the conceptual and basic designs involved the participation of three main engineering companies. INTERTECHNE Consultores S.A. was in charge of conceptual and basic designs for conventional systems of buildings and infrastructure. INVAP S.E. was responsible for preparing the basic design of the reactor core and annexes. MRS Estudos Ambientais Ltda. has prepared documents for environmental licensing. This paper describes the procedures used during conceptual and basic design stages to control design documentation and flow of this documentation, involving the analysis and incorporation of comments from experts, control and storage of a volume of approximately 15,000 documents. (author)

Documentation control process of Brazilian multipurpose reactor: conceptual design and basic design

Energy Technology Data Exchange (ETDEWEB)

Kibrit, Eduardo; Prates, Jose Eduardo; Longo, Guilherme Carneiro; Salvetti, Tereza Cristina, E-mail: ekibrit@ipen.br, E-mail: jeprates@ipen.br, E-mail: glongo@ipen.br, E-mail: salvetti@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2015-07-01

Established in the scope of Plan of Action of the Ministry of Science, Technology and Innovation (PACTI/MCTI) in 2007, the construction of the Brazilian Multipurpose Reactor (RMB) is on the way. This type of reactor has a broad spectrum of applications in the nuclear field and related technologies such as the radioisotopes used as supplies in the production of radiopharmaceuticals, with very much benefit to the Brazilian society being, therefore, the main goal of the Project. RMB Project consists of the following stages: site selection and site evaluation; design (conceptual design, basic design, detailed design and experimental design); construction (procurement, manufacturing; civil construction; electromechanical construction and assembling); commissioning; operation and decommissioning. Each stage requires adaptation of human resources for the stage schedule execution. The implementation of a project of this magnitude requires a complex project management, which covers not only technical, but also administrative areas. Licensing, financial resources, quality and document control systems, engineering are some of the areas involved in project success. The development of the conceptual and basic designs involved the participation of three main engineering companies. INTERTECHNE Consultores S.A. was in charge of conceptual and basic designs for conventional systems of buildings and infrastructure. INVAP S.E. was responsible for preparing the basic design of the reactor core and annexes. MRS Estudos Ambientais Ltda. has prepared documents for environmental licensing. This paper describes the procedures used during conceptual and basic design stages to control design documentation and flow of this documentation, involving the analysis and incorporation of comments from experts, control and storage of a volume of approximately 15,000 documents. (author)

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)

GENII: The Hanford Environmental Radiation Dosimetry Software System: Volume 1, Conceptual representation

Energy Technology Data Exchange (ETDEWEB)

Napier, B.A.; Peloquin, R.A.; Strenge, D.L.; Ramsdell, J.V.

1988-12-01

The Hanford Environmental Dosimetry Upgrade Project was undertaken to incorporate the internal dosimetry models recommended by the International Commission on Radiological Protection (ICRP) in updated versions of the environmental pathway analysis models used at Hanford. The resulting second generation of Hanford environmental dosimetry computer codes is compiled in the Hanford Environmental Dosimetry System (Generation II, or GENII). The purpose of this coupled system of computer codes is to analyze environmental contamination resulting from acute or chronic releases to, or initial contamination of, air, water, or soil. This is accomplished by calculating radiation doses to individuals or populations. GENII is described in three volumes of documentation. The first volume describes the theoretical considerations of the system. The second volume is a Users' Manual, providing code structure, users' instructions, required system configurations, and QA-related topics. The third volume is a Code Maintenance Manual for the user who requires knowledge of code detail. It includes code logic diagrams, global dictionary, worksheets, example hand calculations, and listings of the code and its associated data libraries. 72 refs., 15 figs., 34 tabs.

GENII: The Hanford Environmental Radiation Dosimetry Software System: Volume 1, Conceptual representation

International Nuclear Information System (INIS)

Napier, B.A.; Peloquin, R.A.; Strenge, D.L.; Ramsdell, J.V.

1988-12-01

The Hanford Environmental Dosimetry Upgrade Project was undertaken to incorporate the internal dosimetry models recommended by the International Commission on Radiological Protection (ICRP) in updated versions of the environmental pathway analysis models used at Hanford. The resulting second generation of Hanford environmental dosimetry computer codes is compiled in the Hanford Environmental Dosimetry System (Generation II, or GENII). The purpose of this coupled system of computer codes is to analyze environmental contamination resulting from acute or chronic releases to, or initial contamination of, air, water, or soil. This is accomplished by calculating radiation doses to individuals or populations. GENII is described in three volumes of documentation. The first volume describes the theoretical considerations of the system. The second volume is a Users' Manual, providing code structure, users' instructions, required system configurations, and QA-related topics. The third volume is a Code Maintenance Manual for the user who requires knowledge of code detail. It includes code logic diagrams, global dictionary, worksheets, example hand calculations, and listings of the code and its associated data libraries. 72 refs., 15 figs., 34 tabs

Repository-based software engineering program: Concept document

Science.gov (United States)

1992-01-01

This document provides the context for Repository-Based Software Engineering's (RBSE's) evolving functional and operational product requirements, and it is the parent document for development of detailed technical and management plans. When furnished, requirements documents will serve as the governing RBSE product specification. The RBSE Program Management Plan will define resources, schedules, and technical and organizational approaches to fulfilling the goals and objectives of this concept. The purpose of this document is to provide a concise overview of RBSE, describe the rationale for the RBSE Program, and define a clear, common vision for RBSE team members and customers. The document also provides the foundation for developing RBSE user and system requirements and a corresponding Program Management Plan. The concept is used to express the program mission to RBSE users and managers and to provide an exhibit for community review.

Probabilistic Requirements (Partial) Verification Methods Best Practices Improvement. Variables Acceptance Sampling Calculators: Derivations and Verification of Plans. Volume 1

Science.gov (United States)

Johnson, Kenneth L.; White, K, Preston, Jr.

2012-01-01

The NASA Engineering and Safety Center was requested to improve on the Best Practices document produced for the NESC assessment, Verification of Probabilistic Requirements for the Constellation Program, by giving a recommended procedure for using acceptance sampling by variables techniques. This recommended procedure would be used as an alternative to the potentially resource-intensive acceptance sampling by attributes method given in the document. This document contains the outcome of the assessment.

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.

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

Probabilistic Requirements (Partial) Verification Methods Best Practices Improvement. Variables Acceptance Sampling Calculators: Empirical Testing. Volume 2

Science.gov (United States)

Johnson, Kenneth L.; White, K. Preston, Jr.

2012-01-01

The NASA Engineering and Safety Center was requested to improve on the Best Practices document produced for the NESC assessment, Verification of Probabilistic Requirements for the Constellation Program, by giving a recommended procedure for using acceptance sampling by variables techniques as an alternative to the potentially resource-intensive acceptance sampling by attributes method given in the document. In this paper, the results of empirical tests intended to assess the accuracy of acceptance sampling plan calculators implemented for six variable distributions are presented.

Title list of documents made publicly available. Volume 16, Number 5

Energy Technology Data Exchange (ETDEWEB)

1994-07-01

The Title List of Documents Made Publicly Available contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index.

Title list of documents made publicly available. Volume 16, Number 5

International Nuclear Information System (INIS)

1994-07-01

The Title List of Documents Made Publicly Available contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

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.

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

Dynamic (G2) Model Design Document, 24590-WTP-MDD-PR-01-002, Rev. 12

Energy Technology Data Exchange (ETDEWEB)

Deng, Yueying; Kruger, Albert A.

2013-12-16

The Hanford Tank Waste Treatment and Immobilization Plant (WTP) Statement of Work (Department of Energy Contract DE-AC27-01RV14136, Section C) requires the contractor to develop and use process models for flowsheet analyses and pre-operational planning assessments. The Dynamic (G2) Flowsheet is a discrete-time process model that enables the project to evaluate impacts to throughput from eventdriven activities such as pumping, sampling, storage, recycle, separation, and chemical reactions. The model is developed by the Process Engineering (PE) department, and is based on the Flowsheet Bases, Assumptions, and Requirements Document (24590-WTP-RPT-PT-02-005), commonly called the BARD. The terminologies of Dynamic (G2) Flowsheet and Dynamic (G2) Model are interchangeable in this document. The foundation of this model is a dynamic material balance governed by prescribed initial conditions, boundary conditions, and operating logic. The dynamic material balance is achieved by tracking the storage and material flows within the plant as time increments. The initial conditions include a feed vector that represents the waste compositions and delivery sequence of the Tank Farm batches, and volumes and concentrations of solutions in process equipment before startup. The boundary conditions are the physical limits of the flowsheet design, such as piping, volumes, flowrates, operation efficiencies, and physical and chemical environments that impact separations, phase equilibriums, and reaction extents. The operating logic represents the rules and strategies of running the plant.

Uranium milling: Draft generic environmental impact statement: Volume 2, Appendices

International Nuclear Information System (INIS)

1979-04-01

This volume contains appendices supporting the discussions in Volume 1. In some cases, the appendices expound upon arguments developed in the main document; in other cases, supplementary material considered to be relevant but not presented in Volume 1 is included. A third category encompasses reprinting of pertinent documents felt to be necessary for a comprehensive presentation of the current situation, e.g., Public Law 95-604

Proposed Site Treatment Plan (PSTP). Volumes 1 and 2 and Reference Document

Energy Technology Data Exchange (ETDEWEB)

Helmich, E.; Noller, D.K.; Wierzbicki, K.S.; Bailey, L.L.

1994-12-22

The Compliance Plan Volume provides overall schedules with target dates for achieving compliance with the land disposal restrictions (LDR) and contains procedures to establish milestones to be enforced under the Order. Information regarding the technical evaluation of treatment options for SRS mixed wastes is contained in the Background Volume and is provided for informational purposes only.

Federal Logistics Information System (FLIS) Procedures Manual. Volume 8. Document Identifier Code Input/Output Formats (Fixed Length)

Science.gov (United States)

1994-07-01

REQUIRED MIX OF SEGMENTS OR INDIVIDUAL DATA ELEMENTS TO BE EXTRACTED. IN SEGMENT R ON AN INTERROGATION TRANSACTION (LTI), DATA RECORD NUMBER (DRN 0950) ONLY...and zation and Marketing input DICs. insert the Continuation Indicator Code (DRN 8555) in position 80 of this record. Maximum of OF The assigned NSN...for Procurement KFR, File Data Minus Security Classified Characteristics Data KFC 8.5-2 DoD 4100.39-M Volume 8 CHAPTER 5 ALPHABETIC INDEX OF DIC

Title list of documents made publicly available. Volume 17, No. 5

International Nuclear Information System (INIS)

1995-07-01

The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (3) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

Title list of documents made publicly available. Volume 17, No. 7

International Nuclear Information System (INIS)

1995-09-01

The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

Title list of documents made publicly available. Volume 17, No. 5

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-07-01

The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (3) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index.

Title list of documents made publicly available. Volume 17, No. 7

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-09-01

The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index.

Quality assurance program manual for nuclear power plants. Volume I. Policies

International Nuclear Information System (INIS)

1976-01-01

The Consumers Power Company Quality Assurance Program Manual for Nuclear Power Plants consists of policies and procedures which comply with current NRC regulatory requirements and industry codes and standards in effect during the design, procurement, construction, testing, operation, refueling, maintenance, repair and modification activities associated with nuclear power plants. Specific NRC and industry documents that contain the requirements, including the issue dates in effect, are identified in each nuclear power plant's Safety Analysis Report. The requirements established by these documents form the basis for the Consumer Power Quality Assurance Program, which is implemented to control those structures, systems, components and operational safety actions listed in each nuclear power plant's Quality List (Q-List). As additional and revised requirements are issued by the NRC and professional organizations involved in nuclear activities, they will be reviewed for their impact on this manual, and changes will be made where considered necessary. CP Co 1--Consumers Power Company QA Program Topical Report is Volume I of this manual and contains Quality Assurance Program Policies applicable during all phases of nuclear power plant design, construction and operation

Finnish participation in the European utility requirements work

International Nuclear Information System (INIS)

Patrakka, E.

2000-01-01

The Finnish participation in the EUR process started already in April 1994 when IVO (Imatran Voima Oy presently Fortum Oyj) and TVO (Teollisuuden Voima Oy) were asked to comment EUR Volume 1 and 2 Revision A in April 1994. A formal application for the Finnish membership in the EUR organisation was sent on 20 November 1995, and Finland was accepted as an associated member on the next day. The Finnish representatives in the various EUR bodies were appointed in March 1996, at which time the formal participation in these bodies commenced. On 7 November 1996, EUR Steering Committee approved a full membership of IVO and TVO that are joint EUR members representing Finland together. A major Finnish contribution was made in 1997 when IVO and TVO performed a comparison between the EUR document and YVL guides. The period of the Finnish membership has been characterised by the compilation of EUR Volume 3 subsets, in which process IVO/Fortum and TVO have been actively participating. From the Finnish point of view, the EUR work can also be seen as a part of getting prepared to proceed with a possible new NPP project. The EUR document is a substantial aid when preparing the technical specifications for a NPP bid inquiry. The information received in connection with the detailed assessment work for Volume 3 subsets is very valuable when considering the feasibility of NPP concepts. In addition. the experiences gained in the Volume 3 activities enable to develop even better requirements that are manifested by Revision C of Volumes 1 and 2. (author)

Taking advantage of continuity of care documents to populate a research repository.

Science.gov (United States)

Klann, Jeffrey G; Mendis, Michael; Phillips, Lori C; Goodson, Alyssa P; Rocha, Beatriz H; Goldberg, Howard S; Wattanasin, Nich; Murphy, Shawn N

2015-03-01

Clinical data warehouses have accelerated clinical research, but even with available open source tools, there is a high barrier to entry due to the complexity of normalizing and importing data. The Office of the National Coordinator for Health Information Technology's Meaningful Use Incentive Program now requires that electronic health record systems produce standardized consolidated clinical document architecture (C-CDA) documents. Here, we leverage this data source to create a low volume standards based import pipeline for the Informatics for Integrating Biology and the Bedside (i2b2) clinical research platform. We validate this approach by creating a small repository at Partners Healthcare automatically from C-CDA documents. We designed an i2b2 extension to import C-CDAs into i2b2. It is extensible to other sites with variances in C-CDA format without requiring custom code. We also designed new ontology structures for querying the imported data. We implemented our methodology at Partners Healthcare, where we developed an adapter to retrieve C-CDAs from Enterprise Services. Our current implementation supports demographics, encounters, problems, and medications. We imported approximately 17 000 clinical observations on 145 patients into i2b2 in about 24 min. We were able to perform i2b2 cohort finding queries and view patient information through SMART apps on the imported data. This low volume import approach can serve small practices with local access to C-CDAs and will allow patient registries to import patient supplied C-CDAs. These components will soon be available open source on the i2b2 wiki. Our approach will lower barriers to entry in implementing i2b2 where informatics expertise or data access are limited. © The Author 2014. Published by Oxford University Press on behalf of the American Medical Informatics Association. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

Draft no-migration variance petition. Volume 1

International Nuclear Information System (INIS)

1995-01-01

The Department of Energy is responsible for the disposition of transuranic (TRU) waste generated by national defense-related activities. Approximately 2,6 million cubic feet of these waste have been generated and are stored at various facilities across the country. The Waste Isolation Pilot Plant (WIPP), was sited and constructed to meet stringent disposal requirements. In order to permanently dispose of TRU waste, the DOE has elected to petition the US EPA for a variance from the Land Disposal Restrictions of RCRA. This document fulfills the reporting requirements for the petition. This report is Volume 1 which discusses the regulatory frame work, site characterization, facility description, waste description, environmental impact analysis, monitoring, quality assurance, long-term compliance analysis, and regulatory compliance assessment

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

Advanced transportation system studies technical area 3: Alternate propulsion subsystem concepts, volume 2

Science.gov (United States)

Levak, Daniel

1993-01-01

The Alternate Propulsion Subsystem Concepts contract had five tasks defined for the first year. The tasks were: F-1A Restart Study, J-2S Restart Study, Propulsion Database Development, Space Shuttle Main Engine (SSME) Upper Stage Use, and CER's for Liquid Propellant Rocket Engines. The detailed study results, with the data to support the conclusions from various analyses, are being reported as a series of five separate Final Task Reports. Consequently, this volume only reports the required programmatic information concerning Computer Aided Design Documentation, and New Technology Reports. A detailed Executive Summary, covering all the tasks, is also available as Volume 1.

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)

Site Environmental Report for 2002, Volume 1

Energy Technology Data Exchange (ETDEWEB)

Pauer, Ron

2003-07-01

Each year, Ernest Orlando Lawrence Berkeley National Laboratory prepares an integrated report on its environmental programs to satisfy the requirements of United States Department of Energy Order 231.1. The ''Site Environmental Report for 2002'' summarizes Berkeley Lab's compliance with environmental standards and requirements, characterizes environmental management efforts through surveillance and monitoring activities, and highlights significant programs and efforts for calendar year 2002. Throughout this report, Ernest Orlando Lawrence Berkeley National Laboratory is referred to as ''Berkeley Lab,'' ''the Laboratory,'' ''Lawrence Berkeley National Laboratory,'' and ''LBNL.'' The report is separated into two volumes. Volume I contains a general overview of the Laboratory, the status of environmental programs, and summarized results from surveillance and monitoring activities. Volume II contains individual data results from the monitoring programs. This year, the ''Site Environmental Report'' was distributed on a CD in PDF format that includes Volume I, Volume II, and related documents. The report is also available on the Web at http://www.lbl.gov/ehs/esg/. The report follows the Laboratory's policy of using the International System of Units (SI), also known as the metric system of measurements. Whenever possible, results are additionally reported using the more conventional (non-SI) system of measurements because this system is referenced by some current regulatory standards and is more familiar to some readers. The tables included at the end of the Glossary are intended to help readers understand the various prefixes used with SI units of measurement and convert these units from one system to the other.

Regulatory systems-based licensing guidance documentation

International Nuclear Information System (INIS)

Delligatti, M.S.

1991-01-01

The US Nuclear Regulatory Commission (NRC) has developed a series of licensing guidance documents based on the regulatory requirements in Part 60 of Title 10 of the Code of Federal Regulations (10 CFR Part 60). This regulatory systems-based approach to licensing guidance documentation relies on the definition of the high-level waste repository in 10 CFR Part 60. A document which is important for the frame-work it gives to other programmatic licensing guidance is the Draft Regulatory Guide open-quotes Format and Content for the License Application for the High-Level Waste Repositoryclose quotes (FCRG). The FCRG describes a format and content acceptable to NRC for a high-level waste repository license application pursuant to the requirements of 10 CFR Part 60. Other licensing guidance documents will be compatible with the FCRG

1991 SOLAR WORLD CONGRESS - VOLUME 1, PART I

Science.gov (United States)

The four-volume proceedings document the 1991 Solar World Congress (the biennial congress of the International Solar Energy Society) in Denver, CO, August 19-23, 1991. Volume 1 is dedicated to solar electricity, biofuels, and renewable resources. Volume 2 contains papers on activ...

Report of the US Nuclear Regulatory Commission Piping Review Committee. Volume 5. Summary - Piping Review Committee conclusions and recommendations

International Nuclear Information System (INIS)

1985-04-01

This document summarizes a comprehensive review of NRC requirements for Nuclear Piping by the US NRC Piping Review Committee. Four topical areas, addressed in greater detail in Volumes 1 through 4 of this report, are included: (1) Stress Corrosion Cracking in Piping of Boiling Water Reactor Plants; (2) Evaluation of Seismic Design; (3) Evaluation of Potential for Pipe Breaks; and (4) Evaluation of Other Dynamic Loads and Load Combinations. This volume summarizes the major issues, reviews the interfaces, and presents the Committee's conclusions and recommendations for updating NRC requirements on these issues. This report also suggests research or other work that may be required to respond to issues not amenable to resolution at this time

DOE evaluation document for DOT 7A Type A packaging

International Nuclear Information System (INIS)

Edling, D.A.; Hopkins, D.R.; Williams, R.L.

1987-03-01

This document is a support document for the ''DOE Evaluation Document for DOT 7A Type A Packaging,'' MLM-3245, March 1987. Provided herein are details concerning the performance requirements specified in 178.350 Specification 7A, General Packaging, Type A. MLM-3245 references appropriate sections in this document. This document does not by itself meet the documentation requirements specified in 49 CFR 173.415 and has compliance value only when used in conjunction with MLM-3245

SANSMIC design document.

Energy Technology Data Exchange (ETDEWEB)

Weber, Paula D. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Rudeen, David Keith [GRAM, Inc., Albuquerque, NM (United States)

2015-07-01

The United States Strategic Petroleum Reserve (SPR) maintains an underground storage system consisting of caverns that were leached or solution mined in four salt domes located near the Gulf of Mexico in Texas and Louisiana. The SPR comprises more than 60 active caverns containing approximately 700 million barrels of crude oil. Sandia National Labo- ratories (SNL) is the geotechnical advisor to the SPR. As the most pressing need at the inception of the SPR was to create and fill storage volume with oil, the decision was made to leach the caverns and fill them simultaneously (leach-fill). Therefore, A.J. Russo developed SANSMIC in the early 1980s which allows for a transient oil-brine interface (OBI) making it possible to model leach-fill and withdrawal operations. As the majority of caverns are currently filled to storage capacity, the primary uses of SANSMIC at this time are related to the effects of small and large withdrawals, expansion of existing caverns, and projecting future pillar to diameter ratios. SANSMIC was identified by SNL as a priority candidate for qualification. This report continues the quality assurance (QA) process by documenting the "as built" mathematical and numerical models that comprise this document. The pro- gram flow is outlined and the models are discussed in detail. Code features that were added later or were not documented previously have been expounded. No changes in the code's physics have occurred since the original documentation (Russo, 1981, 1983) although recent experiments may yield improvements to the temperature and plume methods in the future.

Fuel Handling Facility Description Document

International Nuclear Information System (INIS)

M.A. LaFountain

2005-01-01

The purpose of the facility description document (FDD) is to establish the requirements and their bases that drive the design of the Fuel Handling Facility (FHF) to allow the design effort to proceed to license application. This FDD is a living document that will be revised at strategic points as the design matures. It identifies the requirements and describes the facility design as it currently exists, with emphasis on design attributes provided to meet the requirements. This FDD was developed as an engineering tool for design control. Accordingly, the primary audience and users are design engineers. It leads the design process with regard to the flow down of upper tier requirements onto the facility. Knowledge of these requirements is essential to performing the design process. It trails the design with regard to the description of the facility. This description is a reflection of the results of the design process to date

242-A Campaign 94-1 post run document

International Nuclear Information System (INIS)

Guthrie, M.D.

1994-01-01

The purpose of this post-run document is to summarize the results of 242-A Evaporator Campaign 94-1 as required. Campaign 94-1 represents the first Evaporator operation since 1989, following completion of the B-534 upgrades and Liquid Effluent Retention Facility (LERF) construction. The purpose of Campaign 94-1 was to concentrate dilute waste from TK-102-AW, TK-106-AW, and TK-103-AP. From an available 2.87 million gallon feedstock of dilute waste contained in 102-AW, 106-AW and 103-AP, an overall Waste Volume Reduction (WVR) of 2.39 million gallons (83% WVRF) was achieved. At the completion of the campaign, approximately 477,000 gallons of dilute double-shell slurry feed (DDSSF) was produced with a SpG. of 1.25--1.30. Total process condensate discharged to LERF was 3.09 million gallons, achieving a condensate/WVR ratio of 1.29. Throughput for Campaign 94-1 was 5.27 million gallons. Total steam condensate and cooling water discharge to B-pond was 4.7 and 216 million gallons respectively. The evaporator operated approximately 43 days of the 60 day campaign for a total operating efficiency of 73%. Campaign 94-1 was completed without any discharge limit, Operating Specification Document, or Operational Safety Requirement violations. Major problems encountered during the run included the following: (1) high CA1 deentrainment pad dP's caused by foaming, (2) condensate pump P-C100 failure, and (3) ion exchange column dP's and efficiency

1995 Solid Waste 30-year volume summary

International Nuclear Information System (INIS)

Valero, O.J.; DeForest, T.J.; Templeton, K.J.

1995-06-01

This document, prepared by Pacific Northwest Laboratory (PNL) under the direction of Westinghouse Hanford Company (WHC), provides a description of the annual low-level mixed waste (LLMW) and transuranic/transuranic mixed solid waste (TRU-TRUM) volumes expected to be managed by Hanford's Solid Waste Central Waste Complex (CWC) over the next 30 years. The waste generation sources and waste categories are also described. This document is intended to be used as a reference for short- and long-term planning of the Hanford treatment, storage, and disposal (TSD) activities over the next several decades. By estimating the waste volumes that will be generated in the future, facility planners can determine the timing of key waste management activities, evaluate alternative treatment strategies, and plan storage and disposal capacities. In addition, this document can be used by other waste sites and the general public to gain a better understanding of the types and volumes of waste that will be managed at Hanford

1995 Solid Waste 30-year volume summary

Energy Technology Data Exchange (ETDEWEB)

Valero, O.J. [Westinghouse Hanford Co., Richland, WA (United States); DeForest, T.J.; Templeton, K.J. [Pacific Northwest Lab., Richland, WA (United States)

1995-06-01

This document, prepared by Pacific Northwest Laboratory (PNL) under the direction of Westinghouse Hanford Company (WHC), provides a description of the annual low-level mixed waste (LLMW) and transuranic/transuranic mixed solid waste (TRU-TRUM) volumes expected to be managed by Hanford`s Solid Waste Central Waste Complex (CWC) over the next 30 years. The waste generation sources and waste categories are also described. This document is intended to be used as a reference for short- and long-term planning of the Hanford treatment, storage, and disposal (TSD) activities over the next several decades. By estimating the waste volumes that will be generated in the future, facility planners can determine the timing of key waste management activities, evaluate alternative treatment strategies, and plan storage and disposal capacities. In addition, this document can be used by other waste sites and the general public to gain a better understanding of the types and volumes of waste that will be managed at Hanford.

Data collection system. Volume 1, Overview and operators manual; Volume 2, Maintenance manual; Appendices

Energy Technology Data Exchange (ETDEWEB)

Caudell, R.B.; Bauder, M.E.; Boyer, W.B.; French, R.E.; Isidoro, R.J.; Kaestner, P.C.; Perkins, W.G.

1993-09-01

Sandia National Laboratories (SNL) Instrumentation Development Department was tasked by the Defense Nuclear Agency (DNA) to record data on Tektronix RTD720 Digitizers on the HUNTERS TROPHY field test conducted at the Nevada Test Site (NTS) on September 18, 1992. This report contains a overview and description of the computer hardware and software that was used to acquire, reduce, and display the data. The document is divided into two volumes: an overview and operators manual (Volume 1) and a maintenance manual (Volume 2).

GENII: The Hanford Environmental Radiation Dosimetry Software System: Volume 2, Users' manual: Hanford Environmental Dosimetry Upgrade Project

International Nuclear Information System (INIS)

Napier, B.A.; Peloquin, R.A.; Strenge, D.L.; Ramsdell, J.V.

1988-11-01

The Hanford Environmental Dosimetry Upgrade Project was undertaken to incorporate the internal dosimetry models recommended by the International Commission on Radiological Protection (ICRP) in updated versions of the environmental pathway analysis models used at Hanford. The resulting second generation of Hanford environmental dosimetry computer codes is compiled in the Hanford Environmental Dosimetry System (Generation II, or GENII). The purpose of this coupled system of computer codes is to analyze environmental contamination of, air, water, or soil. This is accomplished by calculating radiation doses to individuals or populations. GENII is described in three volumes of documentation. This second volume is a Users' Manual, providing code structure, users' instructions, required system configurations, and QA-related topics. The first volume describes the theoretical considerations of the system. The third volume is a Code Maintenance Manual for the user who requires knowledge of code detail. It includes logic diagrams, global dictionary, worksheets, example hand calculations, and listings of the code and its associated data libraries. 27 refs., 17 figs., 23 tabs

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).

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)

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.

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

SCALE-4 analysis of pressurized water reactor critical configurations. Volume 1: Summary

International Nuclear Information System (INIS)

DeHart, M.D.

1995-03-01

The requirements of ANSI/ANS 8.1 specify that calculational methods for away-from-reactor criticality safety analyses be validated against experimental measurements. If credit is to be taken for the reduced reactivity of burned or spent fuel relative to its original fresh composition, it is necessary to benchmark computational methods used in determining such reactivity worth against spent fuel reactivity measurements. This report summarizes a portion of the ongoing effort to benchmark away-from-reactor criticality analysis methods using critical configurations from commercial pressurized water reactors (PWR). The analysis methodology utilized for all calculations in this report is based on the modules and data associated with the SCALE-4 code system. Each of the five volumes comprising this report provides an overview of the methodology applied. Subsequent volumes also describe in detail the approach taken in performing criticality calculations for these PWR configurations: Volume 2 describes criticality calculations for the Tennessee Valley Authority's Sequoyah Unit 2 reactor for Cycle 3; Volume 3 documents the analysis of Virginia Power's Surry Unit 1 reactor for the Cycle 2 core; Volume 4 documents the calculations performed based on GPU Nuclear Corporation's Three Mile Island Unit 1 Cycle 5 core; and, lastly, Volume 5 describes the analysis of Virginia Power's North Anna Unit 1 Cycle 5 core. Each of the reactor-specific volumes provides the details of calculations performed to determine the effective multiplication factor for each reactor core for one or more critical configurations using the SCALE-4 system; these results are summarized in this volume. Differences between the core designs and their possible impact on the criticality calculations are also discussed. Finally, results are presented for additional analyses performed to verify that solutions were sufficiently converged

FLAMMABLE GAS TECHNICAL BASIS DOCUMENT

Energy Technology Data Exchange (ETDEWEB)

KRIPPS, L.J.

2005-02-18

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

The environmental impact statement for the Nevada Test Site and off-site locations in the State of Nevada. Volume 1, Appendices A-F

International Nuclear Information System (INIS)

1996-01-01

This volume contains appendices to the named document. The Appendices are entitled (A) Description of Projects and Activities, (2) Federal Register Notice, (C) Relevant Regulatory Requirements, (D) Distribution Lists, (E) Impact Assessment Methods, and (F) Project-Specific Environmental Analysis

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.

The significance of radiological control documentation in litigation

International Nuclear Information System (INIS)

Lodde, G.M.; Murphy, T.D.

1988-01-01

Commercial nuclear facilities accumulate radiological control program data and documents generated and retained pursuant to regulatory, license, and technical specification requirements. During and following the Three Mile Island Unit 2 (TMI-2) accident, many documents were produced that would not normally have been produced. Shortly after the accident, the US Nuclear Regulatory Commission (NRC) issued an order requiring the retention of all data, including documentary material and physical samples relating to the TMI-2 accident (44 Fed. Reg. 30788, May 29, 1979). Three years later, the NRC vacated the requirement to retain catalogued physical samples, provided the radioactivity data had been properly recorded, allowing disposal of many samples. After the TMI-2 accident, GPU Nuclear Corporation (GPU) designed and implemented an effective and efficient record management program for TMI. This Computer-Assisted Records and Information Retrieval System (CARIRS) was developed to assess the official record for TMI, which is maintained as a microform. GPU also retains hard copies of selected radiological control documents for potential litigation. This paper describes the use of radiological control documentation in the postaccident litigation and the magnitude of document production required to support that litigation

Spent Nuclear Fuel Project document control and Records Management Program Description

International Nuclear Information System (INIS)

MARTIN, B.M.

2000-01-01

The Spent Nuclear Fuel (SNF) Project document control and records management program, as defined within this document, is based on a broad spectrum of regulatory requirements, Department of Energy (DOE) and Project Hanford and SNF Project-specific direction and guidance. The SNF Project Execution Plan, HNF-3552, requires the control of documents and management of records under the auspices of configuration control, conduct of operations, training, quality assurance, work control, records management, data management, engineering and design control, operational readiness review, and project management and turnover. Implementation of the controls, systems, and processes necessary to ensure compliance with applicable requirements is facilitated through plans, directives, and procedures within the Project Hanford Management System (PHMS) and the SNF Project internal technical and administrative procedures systems. The documents cited within this document are those which directly establish or define the SNF Project document control and records management program. There are many peripheral documents that establish requirements and provide direction pertinent to managing specific types of documents that, for the sake of brevity and clarity, are not cited within this document

Terminologie de Base de la Documentation. (Basic Terminology of Documentation).

Science.gov (United States)

Commission des Communautes Europeennes (Luxembourg). Bureau de Terminologie.

This glossary is designed to aid non-specialists whose activities require that they have some familiarity with the terminology of the modern methods of documentation. Definitions have been assembled from various dictionaries, manuals, etc., with particular attention being given to the publications of UNESCO and the International Standards…

Embedding the shapes of regions of interest into a Clinical Document Architecture document.

Science.gov (United States)

Minh, Nguyen Hai; Yi, Byoung-Kee; Kim, Il Kon; Song, Joon Hyun; Binh, Pham Viet

2015-03-01

Sharing a medical image visually annotated by a region of interest with a remotely located specialist for consultation is a good practice. It may, however, require a special-purpose (and most likely expensive) system to send and view them, which is an unfeasible solution in developing countries such as Vietnam. In this study, we design and implement interoperable methods based on the HL7 Clinical Document Architecture and the eXtensible Markup Language Stylesheet Language for Transformation standards to seamlessly exchange and visually present the shapes of regions of interest using web browsers. We also propose a new integration architecture for a Clinical Document Architecture generator that enables embedding of regions of interest and simultaneous auto-generation of corresponding style sheets. Using the Clinical Document Architecture document and style sheet, a sender can transmit clinical documents and medical images together with coordinate values of regions of interest to recipients. Recipients can easily view the documents and display embedded regions of interest by rendering them in their web browser of choice. © The Author(s) 2014.

Geostatistical approach for assessing soil volumes requiring remediation: validation using lead-polluted soils underlying a former smelting works.

Science.gov (United States)

Demougeot-Renard, Helene; De Fouquet, Chantal

2004-10-01

Assessing the volume of soil requiring remediation and the accuracy of this assessment constitutes an essential step in polluted site management. If this remediation volume is not properly assessed, misclassification may lead both to environmental risks (polluted soils may not be remediated) and financial risks (unexpected discovery of polluted soils may generate additional remediation costs). To minimize such risks, this paper proposes a geostatistical methodology based on stochastic simulations that allows the remediation volume and the uncertainty to be assessed using investigation data. The methodology thoroughly reproduces the conditions in which the soils are classified and extracted at the remediation stage. The validity of the approach is tested by applying it on the data collected during the investigation phase of a former lead smelting works and by comparing the results with the volume that has actually been remediated. This real remediated volume was composed of all the remediation units that were classified as polluted after systematic sampling and analysis during clean-up stage. The volume estimated from the 75 samples collected during site investigation slightly overestimates (5.3% relative error) the remediated volume deduced from 212 remediation units. Furthermore, the real volume falls within the range of uncertainty predicted using the proposed methodology.

IDC System Specification Document Version 1.1.

Energy Technology Data Exchange (ETDEWEB)

Harris, James M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Lober, Randall R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2015-02-01

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 V1.1 2/2015 IDC Reengineering Project Team Iteration I2 Review Comments M. Harris

IDC Re-Engineering Phase 2 System Specification Document Version 1.5

Energy Technology Data Exchange (ETDEWEB)

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

2017-01-01

This document contains the system specifications derived to satisfy the system requirements found in the IDC System Requirements Document for the IDC Re-Engineering Phase 2 project. This System Specification Document (SSD) defines waveform data processing requirements for the International Data Centre (IDC) of the Comprehensive Nuclear Test Ban Treaty Organization (CTBTO). 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 does include requirements for the dissemination of radionuclide data and products.

Leak testing plan for the Oak Ridge National Laboratory liquid low-level waste systems (active tanks): Revision 2. Volume 1: Regulatory background and plan approach; Volume 2: Methods, protocols, and schedules; Volume 3: Evaluation of the ORNL/LT-823DP differential pressure leak detection method; Appendix to Revision 2: DOE/EPA/TDEC correspondence

Energy Technology Data Exchange (ETDEWEB)

Douglas, D.G.; Wise, R.F.; Starr, J.W.; Maresca, J.W. Jr. [Vista Research, Inc., Mountain View, CA (United States)

1994-11-01

This document, the Leak Testing Plan for the Oak Ridge National Laboratory Liquid Low-Level Waste System (Active Tanks), comprises three volumes. The first two volumes address the component-based leak testing plan for the liquid low-level waste system at Oak Ridge, while the third volume describes the performance evaluation of the leak detection method that will be used to test this system. Volume 1, describes that portion of the liquid low-level waste system at that will be tested; it provides the regulatory background, especially in terms of the requirements stipulated in the Federal Facilities Agreement, upon which the leak testing plan is based. Volume 1 also describes the foundation of the plan, portions of which were abstracted from existing federal documents that regulate the petroleum and hazardous chemicals industries. Finally, Volume 1 gives an overview the plan, describing the methods that will be used to test the four classes of components in the liquid low-level waste system. Volume 2 takes the general information on component classes and leak detection methods presented in Volume 1 and shows how it applies particularly to each of the individual components. A complete test plan for each of the components is presented, with emphasis placed on the methods designated for testing tanks. The protocol for testing tank systems is described, and general leak testing schedules are presented. Volume 3 describes the results of a performance evaluation completed for the leak testing method that will be used to test the small tanks at the facility (those less than 3,000 gal in capacity). Some of the details described in Volumes 1 and 2 are expected to change as additional information is obtained, as the viability of candidate release detection methods is proven in the Oak Ridge environment, and as the testing program evolves.

Leak testing plan for the Oak Ridge National Laboratory liquid low-level waste systems (active tanks): Revision 2. Volume 1: Regulatory background and plan approach; Volume 2: Methods, protocols, and schedules; Volume 3: Evaluation of the ORNL/LT-823DP differential pressure leak detection method; Appendix to Revision 2: DOE/EPA/TDEC correspondence

International Nuclear Information System (INIS)

Douglas, D.G.; Wise, R.F.; Starr, J.W.; Maresca, J.W. Jr.

1994-11-01

This document, the Leak Testing Plan for the Oak Ridge National Laboratory Liquid Low-Level Waste System (Active Tanks), comprises three volumes. The first two volumes address the component-based leak testing plan for the liquid low-level waste system at Oak Ridge, while the third volume describes the performance evaluation of the leak detection method that will be used to test this system. Volume 1, describes that portion of the liquid low-level waste system at that will be tested; it provides the regulatory background, especially in terms of the requirements stipulated in the Federal Facilities Agreement, upon which the leak testing plan is based. Volume 1 also describes the foundation of the plan, portions of which were abstracted from existing federal documents that regulate the petroleum and hazardous chemicals industries. Finally, Volume 1 gives an overview the plan, describing the methods that will be used to test the four classes of components in the liquid low-level waste system. Volume 2 takes the general information on component classes and leak detection methods presented in Volume 1 and shows how it applies particularly to each of the individual components. A complete test plan for each of the components is presented, with emphasis placed on the methods designated for testing tanks. The protocol for testing tank systems is described, and general leak testing schedules are presented. Volume 3 describes the results of a performance evaluation completed for the leak testing method that will be used to test the small tanks at the facility (those less than 3,000 gal in capacity). Some of the details described in Volumes 1 and 2 are expected to change as additional information is obtained, as the viability of candidate release detection methods is proven in the Oak Ridge environment, and as the testing program evolves

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)

Evaluation of automated decisionmaking methodologies and development of an integrated robotic system simulation, volume 2, part 1. Appendix A: Software documentation

Science.gov (United States)

Lowrie, J. W.; Fermelia, A. J.; Haley, D. C.; Gremban, K. D.; Vanbaalen, J.; Walsh, R. W.

1982-01-01

Documentation of the preliminary software developed as a framework for a generalized integrated robotic system simulation is presented. The program structure is composed of three major functions controlled by a program executive. The three major functions are: system definition, analysis tools, and post processing. The system definition function handles user input of system parameters and definition of the manipulator configuration. The analysis tools function handles the computational requirements of the program. The post processing function allows for more detailed study of the results of analysis tool function executions. Also documented is the manipulator joint model software to be used as the basis of the manipulator simulation which will be part of the analysis tools capability.

Mod-5A Wind Turbine Generator Program Design Report. Volume 2: Conceptual and Preliminary Design, Book 1

Science.gov (United States)

1984-01-01

The design, development and analysis of the 7.3 MW MOD-5A wind turbine generator is documented. There are four volumes. In Volume 2, book 1 the requirements and criteria for the design are presented. The conceptual design studies, which defined a baseline configuration and determined the weights, costs and sizes of each subsystem, are described. The development and optimization of the wind turbine generator are presented through the description of the ten intermediate configurations between the conceptual and final designs. Analyses of the system's load and dynamics are presented.

Documentation and dissemination of agricultural Research results in ...

African Journals Online (AJOL)

A study was conducted to find out the volume of documented vis a vis generated agricultural research information over a 10-year period and to identify existing avenues for disseminating generated research information to the target population. A questionnaire survey was conducted between December 1996 and February ...

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...

Development of an Inline Dry Power Inhaler That Requires Low Air Volume.

Science.gov (United States)

Farkas, Dale; Hindle, Michael; Longest, P Worth

2017-12-20

Inline dry powder inhalers (DPIs) are actuated by an external air source and have distinct advantages for delivering aerosols to infants and children, and to individuals with compromised lung function or who require ventilator support. However, current inline DPIs either perform poorly, are difficult to operate, and/or require large volumes (∼1 L) of air. The objective of this study was to develop and characterize a new inline DPI for aerosolizing spray-dried formulations with powder masses of 10 mg and higher using a dispersion air volume of 10 mL per actuation that is easy to load (capsule-based) and operate. Primary features of the new low air volume (LV) DPIs are fixed hollow capillaries that both pierce the capsule and provide a continuous flow path for air and aerosol passing through the device. Two different configurations were evaluated, which were a straight-through (ST) device, with the inlet and outlet capillaries on opposite ends of the capsule, and a single-sided (SS) device, with both the inlet and outlet capillaries on the same side of the capsule. The devices were operated with five actuations of a 10 mL air syringe using an albuterol sulfate (AS) excipient-enhanced growth (EEG) formulation. Device emptying and aerosol characteristics were evaluated for multiple device outlet configurations. Each device had specific advantages. The best case ST device produced the smallest aerosol [mean mass median aerodynamic diameter (MMAD) = 1.57 μm; fine particle fraction <5 μm (FPF <5μm ) = 95.2%)] but the mean emitted dose (ED) was 61.9%. The best case SS device improved ED (84.8%), but produced a larger aerosol (MMAD = 2.13 μm; FPF <5μm  = 89.3%) that was marginally higher than the initial deaggregation target. The new LV-DPIs produced an acceptable high-quality aerosol with only 10 mL of dispersion air per actuation and were easy to load and operate. This performance should enable application in high and low flow

Nuclear regulatory legislation, 104th Congress, Volume 1, No. 4

International Nuclear Information System (INIS)

1997-12-01

This document is the first of two volumes compiling statutes and material pertaining to nuclear regulatory legislation through the 104th Congress, 2nd Session. It is intended for use as a U.S. Nuclear Regulatory Commission (NRC) internal resource document. Legislative information reproduced in this document includes portions of the Atomic Energy Act, Energy Reorganization Act, Low-Level Radioactive Waste Policy Amendments Act, and Nuclear Waste Policy Act. Other information included in this volume pertains to NRC user fees, NRC authorizations, the Inspector General Act, and the Administrative Procedure Act

Nuclear regulatory legislation, 104th Congress, Volume 1, No. 4

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-12-01

This document is the first of two volumes compiling statutes and material pertaining to nuclear regulatory legislation through the 104th Congress, 2nd Session. It is intended for use as a U.S. Nuclear Regulatory Commission (NRC) internal resource document. Legislative information reproduced in this document includes portions of the Atomic Energy Act, Energy Reorganization Act, Low-Level Radioactive Waste Policy Amendments Act, and Nuclear Waste Policy Act. Other information included in this volume pertains to NRC user fees, NRC authorizations, the Inspector General Act, and the Administrative Procedure Act.

200 Area TEDF interface control document

Energy Technology Data Exchange (ETDEWEB)

Brown, M.J.; Hildebrand, R.A.

1994-11-15

Because the TEDF does not have any treatment or retention capacity, strict control at the generator interface is essential to operate the TEDF in compliance with good engineering practices, Hanford site requirements, and the 216 Discharge Permit. The information in the Interface Control Document (ICD) forms the basis of understanding between all parties involved in the TEDF; DOE, WHC, and the generating facilities. The ICD defines the controlling document hierarchy; LEF, and generator responsibilities; monitoring and sampling requirements; and specifies the TEDF/Generator Interface points.

200 Area TEDF interface control document

International Nuclear Information System (INIS)

Brown, M.J.; Hildebrand, R.A.

1994-01-01

Because the TEDF does not have any treatment or retention capacity, strict control at the generator interface is essential to operate the TEDF in compliance with good engineering practices, Hanford site requirements, and the 216 Discharge Permit. The information in the Interface Control Document (ICD) forms the basis of understanding between all parties involved in the TEDF; DOE, WHC, and the generating facilities. The ICD defines the controlling document hierarchy; LEF, and generator responsibilities; monitoring and sampling requirements; and specifies the TEDF/Generator Interface points

Solid waste 30-year volume summary

International Nuclear Information System (INIS)

Valero, O.J.; Armacost, L.L.; DeForest, T.J.; Templeton, K.J.; Williams, N.C.

1994-06-01

A 30-year forecast of the solid waste volumes to be generated or received at the US Department of Energy Hanford Site is described in this report. The volumes described are low-level mixed waste (LLMW) and transuranic/transuranic mixed (TRU/TRUM) waste that will require treatment, storage, and disposal at Hanford's Solid Waste Operations Complex (SWOC) during the 30-year period from FY 1994 through FY 2023. The data used to complete this document were collected from onsite and offsite waste generators who currently, or are planning to, ship solid wastes to the Hanford Site. An analysis of the data suggests that over 300,000 m 3 of LLMW and TRU/TRUM waste will be managed at Hanford's SWOC over the next 30 years. An extensive effort was made this year to collect this information. The 1993 solid waste forecast was used as a starting point, which identified approximately 100,000 m 3 of LLMW and TRU/TRUM waste to be sent to the SWOC. After analyzing the forecast waste volume, it was determined that additional waste was expected from the tank waste remediation system (TWRS), onsite decontamination and decommissioning (D ampersand D) activities, and onsite remedial action (RA) activities. Data presented in this report establish a starting point for solid waste management planning. It is recognized that forecast estimates will vary (typically increasing) as facility planning and missions continue to change and become better defined, but the information presented still provides useful insight into Hanford's future solid waste management requirements

Document organization by means of graphs

Directory of Open Access Journals (Sweden)

Santa Vallejo Figueroa

2016-12-01

Full Text Available Nowadays documents are the main way to represent information and knowledge in several domains. Continuously users store documents in hard disk or online media according to some personal organization based on topics, but such documents can contain one or more topics. This situation makes hard to access documents when is required. The current search engines are based on the name of file or content, but where the desired term or terms must match exactly as are in the content. In this paper, a method for organize documents by means of graphs is proposed, taking into account the topics of the documents. For this a graph for each document is generated taking into account synonyms, semantic related terms, hyponyms, and hypernyms of nouns and verbs contained in documents. The proposal have been compares against Google Desktop and LogicalDoc with interesting results.

Research on Generating Method of Embedded Software Test Document Based on Dynamic Model

Science.gov (United States)

Qu, MingCheng; Wu, XiangHu; Tao, YongChao; Liu, Ying

2018-03-01

This paper provides a dynamic model-based test document generation method for embedded software that provides automatic generation of two documents: test requirements specification documentation and configuration item test documentation. This method enables dynamic test requirements to be implemented in dynamic models, enabling dynamic test demand tracking to be easily generated; able to automatically generate standardized, standardized test requirements and test documentation, improved document-related content inconsistency and lack of integrity And other issues, improve the efficiency.

Guidelines for upgrading of low volume roads

CSIR Research Space (South Africa)

Division of Roads

1993-03-01

Full Text Available The purpose of this manual is to provide guidelines on the upgrading of gravel low volume roads to roads and maintenance personnel of road authorities of all sizes. Low volume is, for the purpose of this document, defined to be less than 500...

Technical Basis Document (TBD) and user guides

International Nuclear Information System (INIS)

Chiaro, P.J. Jr.

1998-09-01

A Technical Basis Document (TBD) should provide the background information for establishment of an instrument's operational requirements. Due to the amount and location of DOE facilities, no one set of requirements is possible. Operational requirements will vary based on the local environments and missions at each facility. Environmental conditions that can affect an instrument's operations are ambient temperature, humidity, and radio frequency, and to a lesser extent, magnetic fields, and interfering ionizing radiations. Consideration should also be made regarding how an instrument is to be used. If an instrument will be transported around the facility, vibration and shock can cause problems if they are not addressed in the TBD. This document provides guidance for the development of a TBD. This document applies to radiation instruments used for personnel and equipment contamination monitoring, dose rate monitoring, and air monitoring

7 CFR 1710.407 - Loan documents.

Science.gov (United States)

2010-01-01

... 7 Agriculture 11 2010-01-01 2010-01-01 false Loan documents. 1710.407 Section 1710.407 Agriculture... GENERAL AND PRE-LOAN POLICIES AND PROCEDURES COMMON TO ELECTRIC LOANS AND GUARANTEES Application Requirements and Procedures for Loans § 1710.407 Loan documents. Following approval of a loan, RUS will forward...

Multiple sclerosis documentation system (MSDS): moving from documentation to management of MS patients.

Science.gov (United States)

Ziemssen, Tjalf; Kempcke, Raimar; Eulitz, Marco; Großmann, Lars; Suhrbier, Alexander; Thomas, Katja; Schultheiss, Thorsten

2013-09-01

The long disease duration of multiple sclerosis and the increasing therapeutic options require a individualized therapeutic approach which should be carefully documented over years of observation. To switch from MS documentation to an innovative MS management, new computer- and internet-based tools could be implemented as we could demonstrate with the novel computer-based patient management system "multiple sclerosis management system 3D" (MSDS 3D). MSDS 3D allows documentation and management of visit schedules and mandatory examinations via defined study modules by integration of data input from various sources (patients, attending physicians and MS nurses). It provides forms for the documentation of patient visits as well as clinical and diagnostic findings. Information can be collected via interactive touch screens. Specific modules allow the management of highly efficacious treatments as natalizumab or fingolimod. MSDS can be used to transfer the documented data to databases as, e.g. the registry of the German MS society or REGIMS. MSDS has already been implemented successfully in clinical practice and is currently being evaluated in a multicenter setting. High-quality management and documentation are crucial for improvements in clinical practice and research work.

System requirements and design description for the environmental requirements management interface (ERMI)

International Nuclear Information System (INIS)

Biebesheimer, E.

1997-01-01

This document describes system requirements and the design description for the Environmental Requirements Management Interface (ERMI). The ERMI database assists Tank Farm personnel with scheduling, planning, and documenting procedure compliance, performance verification, and selected corrective action tracking activities for Tank Farm S/RID requirements. The ERMI database was developed by Science Applications International Corporation (SAIC). This document was prepared by SAIC and edited by LMHC

Diversion path analysis handbook. Volume 2 (of 4 volumes). Example

International Nuclear Information System (INIS)

Goodwin, K.E.; Schleter, J.C.; Maltese, M.D.K.

1978-11-01

Volume 2 of the Handbook is divided into two parts, the workpaper documentation and the summary documentation. The former sets forth, in terms of the hypothetical process, the analysis guidelines, the information gathered, the characterization of the process, the specific diversion paths related to the process, and, finally, the results and findings of the Diversion Path Analysis (DPA). The summary documentation, made up of portions of sections already prepared for the workpapers, is a concise statement of results and recommendations for management use. Most of the details available in the workpapers are not used, or are held to a minimum, in this report. Also, some rearrangement of the excerpted sections has been made in order to permit rapid comprehension by a manager having only limited time to devote to study and review of the analysis

Delve: A Data Set Retrieval and Document Analysis System

KAUST Repository

Akujuobi, Uchenna Thankgod

2017-12-29

Academic search engines (e.g., Google scholar or Microsoft academic) provide a medium for retrieving various information on scholarly documents. However, most of these popular scholarly search engines overlook the area of data set retrieval, which should provide information on relevant data sets used for academic research. Due to the increasing volume of publications, it has become a challenging task to locate suitable data sets on a particular research area for benchmarking or evaluations. We propose Delve, a web-based system for data set retrieval and document analysis. This system is different from other scholarly search engines as it provides a medium for both data set retrieval and real time visual exploration and analysis of data sets and documents.

European Utility Requirements: leveling the European electricity producers' playing ground for new NPPs

International Nuclear Information System (INIS)

Bernard Roche

2006-01-01

Full text of publication follows: Since 1992, the European Utility Requirement (EUR) document has been developed by the major European electricity producers. The main driver to this work has been the construction of a unified European market. The electricity producers have set out design requirements adapted to this new European environment, while keeping in mind experience feedback from operating NPPs worldwide. The EUR document is now fully operational and its set of generic requirements have been recently used as bid specification in Finland and in China. The EUR document keeps developing in two directions: 1- completing the assessment of the projects that could be proposed by the vendors for the European market. Five projects have been assessed between 1999 and 2002: BWR90, EPR, EP1000, ABWR and SWR1000. Two new projects are being assessed, the Westinghouse AP1000 and the Russian VVER AES92. It is currently planned to publish these two new assessments in the first half of 2006. Others may be undertaken meanwhile. 2- revision of the generic requirements. A revision C of the volume 4 dedicated to power generation plant is being completed. It includes responses to vendors comments and feedback from the TVO call for bid for Finland 5. A revision D of the volumes 1 and 2 dedicated to nuclear islands is foreseen. The main contributions to this revision are the harmonization actions going on in Europe about nuclear safety (WENRA study on reactor safety harmonization, EC works, evolution of the IAEA guides and requirements), the harmonization works on the conditions of connection to the European HV grid as well as harmonization works on other matters, like codes and standards. This has given a unified frame in which the future nuclear plants can be designed and built. In this frame development of standards designs usable throughout Europe without major design change is possible, thus helping to increase competition, and ultimately to save investment and operating costs

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

International Nuclear Information System (INIS)

Brown, Tulanda

2003-01-01

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

Technical support document for land application of sewage sludge. Volume 1. Final report

International Nuclear Information System (INIS)

Jones, A.; Beyer, L.; Rookwood, M.; Pacenka, J.; Bergin, J.

1992-11-01

The document provides the technical background and justification for the U.S. Environmental Protection Agency's (EPA) final regulation (40 CFR Part 503) covering the land application of sewage sludge. The document summarizes current practices in land application and presents data supporting the risk assessment methodology used to derive human health and environmental risk-based limits for contaminants in land applied sewage sludge. The management practices associated with land application are outlined and the different pathways by which contaminants reach highly-exposed individuals (HEIs) through land application are discussed

Preparation of plant and system design description documents

International Nuclear Information System (INIS)

1989-01-01

This standard prescribes the purpose, scope, organization, and content of plant design requirements (PDR) documents and system design descriptions (SDDs), to provide a unified approach to their preparation and use by a project as the principal means to establish the plant design requirements and to establish, describe, and control the individual system designs from conception and throughout the lifetime of the plant. The Electric Power Research Institute's Advanced Light Water Reactor (LWR) Requirements Document should be considered for LWR plants

Documentation Panels Enhance Teacher Education Programs

Science.gov (United States)

Warash, Bobbie Gibson

2005-01-01

Documentation of children's projects is advantageous to their learning process and is also a good method for student teachers to observe the process of learning. Documentation panels are a unique way to help student teachers understand how children learn. Completing a panel requires a student teacher to think through a process. Teachers must learn…

Documentation and archiving of the Space Shuttle wind tunnel test data base. Volume 2: User's Guide to the Archived Data Base

Science.gov (United States)

Romere, Paul O.; Brown, Steve Wesley

1995-01-01

Development of the Space Shuttle necessitated an extensive wind tunnel test program, with the cooperation of all the major wind tunnels in the United States. The result was approximately 100,000 hours of Space Shuttle wind tunnel testing conducted for aerodynamics, heat transfer, and structural dynamics. The test results were converted into Chrysler DATAMAN computer program format to facilitate use by analysts, a very cost effective method of collecting the wind tunnel test results from many test facilities into one centralized location. This report provides final documentation of the Space Shuttle wind tunnel program. The two-volume set covers the evolution of Space Shuttle aerodynamic configurations and gives wind tunnel test data, titles of wind tunnel data reports, sample data sets, and instructions for accessing the digital data base.

45 CFR 641.16 - Preparation of environmental documents, generally.

Science.gov (United States)

2010-10-01

... affect climate and weather patterns; (3) May adversely affect air or water quality; (4) May affect... knowledge and expertise. (e) Type of environmental document. The type of environmental document required... bases for much of the year, and the need to obtain items or materials requiring long lead times), it may...

High integrity software for nuclear power plants: Candidate guidelines, technical basis and research needs. Main report, Volume 2

International Nuclear Information System (INIS)

Seth, S.; Bail, W.; Cleaves, D.; Cohen, H.; Hybertson, D.; Schaefer, C.; Stark, G.; Ta, A.; Ulery, B.

1995-06-01

The work documented in this report was performed in support of the US Nuclear Regulatory Commission to examine the technical basis for candidate guidelines that could be considered in reviewing and evaluating high integrity computer e following software development and assurance activities: Requirements specification; design; coding; verification and validation, inclukding static analysis and dynamic testing; safety analysis; operation and maintenance; configuration management; quality assurance; and planning and management. Each activity (framework element) was subdivided into technical areas (framework subelements). The report describes the development of approximately 200 candidate guidelines that span the entire ran e identification, categorization and prioritization of technical basis for those candidate guidelines; and the identification, categorization and prioritization of research needs for improving the technical basis. The report has two volumes: Volume 1, Executive Summary includes an overview of the framwork and of each framework element, the complete set of candidate guidelines, the results of the assessment of the technical basis for each candidate guideline, and a discussion of research needs that support the regulatory function; this document, Volume 2, is the main report

High integrity software for nuclear power plants: Candidate guidelines, technical basis and research needs. Main report, Volume 2

Energy Technology Data Exchange (ETDEWEB)

Seth, S.; Bail, W.; Cleaves, D.; Cohen, H.; Hybertson, D.; Schaefer, C.; Stark, G.; Ta, A.; Ulery, B. [Mitre Corp., McLean, VA (United States)

1995-06-01

The work documented in this report was performed in support of the US Nuclear Regulatory Commission to examine the technical basis for candidate guidelines that could be considered in reviewing and evaluating high integrity computer e following software development and assurance activities: Requirements specification; design; coding; verification and validation, inclukding static analysis and dynamic testing; safety analysis; operation and maintenance; configuration management; quality assurance; and planning and management. Each activity (framework element) was subdivided into technical areas (framework subelements). The report describes the development of approximately 200 candidate guidelines that span the entire ran e identification, categorization and prioritization of technical basis for those candidate guidelines; and the identification, categorization and prioritization of research needs for improving the technical basis. The report has two volumes: Volume 1, Executive Summary includes an overview of the framwork and of each framework element, the complete set of candidate guidelines, the results of the assessment of the technical basis for each candidate guideline, and a discussion of research needs that support the regulatory function; this document, Volume 2, is the main report.

Technical support document: Energy efficiency standards for consumer products: Room air conditioners, water heaters, direct heating equipment, mobile home furnaces, kitchen ranges and ovens, pool heaters, fluorescent lamp ballasts and television sets. Volume 1, Methodology

Energy Technology Data Exchange (ETDEWEB)

1993-11-01

The Energy Policy and Conservation Act (P.L. 94-163), as amended, establishes energy conservation standards for 12 of the 13 types of consumer products specifically covered by the Act. The legislation requires the Department of Energy (DOE) to consider new or amended standards for these and other types of products at specified times. DOE is currently considering amending standards for seven types of products: water heaters, direct heating equipment, mobile home furnaces, pool heaters, room air conditioners, kitchen ranges and ovens (including microwave ovens), and fluorescent light ballasts and is considering establishing standards for television sets. This Technical Support Document presents the methodology, data, and results from the analysis of the energy and economic impacts of the proposed standards. This volume presents a general description of the analytic approach, including the structure of the major models.

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.)

Definition of technology development missions for early Space Station satellite servicing. Volume 2: Technical

Science.gov (United States)

Cable, D. A.; Diewald, C. A.; Hills, T. C.; Parmentier, T. J.; Spencer, R. A.; Stone, G. E.

1984-01-01

Volume 2 contains the Technical Report of the approach and results of the Phase 2 study. The phase 2 servicing study was initiated in June 1983, and is being reported in this document. The scope of the contract was to: (1) define in detail five selected technology development missions (TDM); (2) conduct a design requirement analysis to refine definitions of satellite servicing requirements at the space station; and (3) develop a technology plan that would identify and schedule prerequisite precursor technology development, associated. STS flight experiments and space station experiments needed to provide onorbit validation of the evolving technology.

ANDRA - Referential Materials. Volume 1: Context and scope; Volume 2: Argillaceous materials; Volume 3: Cementitious materials; Volume 4: The corrosion of metallic materials

International Nuclear Information System (INIS)

2001-01-01

This huge document gathers four volumes. The first volume presents some generalities about materials used in the storage of radioactive materials (definition, design principle, current choices and corresponding storage components, general properties of materials and functions of the corresponding storage components, physical and chemical solicitations experienced by materials in a storage), and the structure and content of the other documents. The second volume addresses argillaceous materials. It presents some generalities about these materials in the context of a deep geological storage, and about their design. It presents and comments the crystalline and chemical, and physical and chemical characteristics of swelling argillaceous materials and minerals, describes how these swelling argillaceous materials are shaped and set up, presents and comments physical properties (hydraulic, mechanical and thermal properties) of these materials, comments and discusses the modelling of the geo-chemical behaviour, and their behaviour in terms of containment and transport of radionuclides. The third volume addresses cementitious materials. It presents some generalities about these materials in the context of a deep geological storage, and about their definition and specifications. It presents some more detailed generalities (cement definition and composition, hydration, microstructure of hydrated cements, adjuvants), presents and comments their physical properties (fresh concrete structure and influence of composition, main aimed properties in the hardened status, transfer, mechanical, and thermal properties, shaping and setting up of these materials, technical solutions for hydraulic works). The fourth volume addresses the corrosion of metallic materials. It presents some generalities about these materials in the context of a deep geological storage of radioactive materials. It presents metallic materials and discusses their corrosion behaviour. It describes the peculiarities

Executive overview and introduction to the SMAP information system life-cycle and documentation standards

Science.gov (United States)

1989-01-01

An overview of the five volume set of Information System Life-Cycle and Documentation Standards is provided with information on its use. The overview covers description, objectives, key definitions, structure and application of the standards, and document structure decisions. These standards were created to provide consistent NASA-wide structures for coordinating, controlling, and documenting the engineering of an information system (hardware, software, and operational procedures components) phase by phase.

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

Science.gov (United States)

1992-01-01

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

Feed tank transfer requirements

International Nuclear Information System (INIS)

Freeman-Pollard, J.R.

1998-01-01

This document presents a definition of tank turnover; DOE responsibilities; TWRS DST permitting requirements; TWRS Authorization Basis (AB) requirements; TWRS AP Tank Farm operational requirements; unreviewed safety question (USQ) requirements; records and reporting requirements, and documentation which will require revision in support of transferring a DST in AP Tank Farm to a privatization contractor for use during Phase 1B

49 CFR 237.155 - Documents and records.

Science.gov (United States)

2010-10-01

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

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

International Nuclear Information System (INIS)

1995-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-01-01

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

Preliminary evaluation of alternative waste form solidification processes. Volume II. Evaluation of the processes

International Nuclear Information System (INIS)

1980-08-01

This Volume II presents engineering feasibility evaluations of the eleven processes for solidification of nuclear high-level liquid wastes (HHLW) described in Volume I of this report. Each evaluation was based in a systematic assessment of the process in respect to six principal evaluation criteria: complexity of process; state of development; safety; process requirements; development work required; and facility requirements. The principal criteria were further subdivided into a total of 22 subcriteria, each of which was assigned a weight. Each process was then assigned a figure of merit, on a scale of 1 to 10, for each of the subcriteria. A total rating was obtained for each process by summing the products of the subcriteria ratings and the subcriteria weights. The evaluations were based on the process descriptions presented in Volume I of this report, supplemented by information obtained from the literature, including publications by the originators of the various processes. Waste form properties were, in general, not evaluated. This document describes the approach which was taken, the developent and application of the rating criteria and subcriteria, and the evaluation results. A series of appendices set forth summary descriptions of the processes and the ratings, together with the complete numerical ratings assigned; two appendices present further technical details on the rating process

Site Environmental Report for 2005 Volume I and Volume II

Energy Technology Data Exchange (ETDEWEB)

Ruggieri, Michael

2006-07-07

Each year, Ernest Orlando Lawrence Berkeley National Laboratory prepares an integrated report on its environmental programs to satisfy the requirements of United States Department of Energy Order 231.1A, ''Environment, Safety, and Health Reporting''. The ''Site Environmental Report for 2005'' summarizes Berkeley Lab's environmental management performance, presents environmental monitoring results, and describes significant programs for calendar year 2005. (Throughout this report, Ernest Orlando Lawrence Berkeley National Laboratory is referred to as ''Berkeley Lab'', ''the Laboratory'', ''Lawrence Berkeley National Laboratory'', and ''LBNL''.) The report is separated into two volumes. Volume I contains an overview of the Laboratory, the status of environmental programs, and summarized results from surveillance and monitoring activities. This year's Volume I text body is organized into an executive summary followed by six chapters. The report's structure has been reorganized this year, and it now includes a chapter devoted to environmental management system topics. Volume II contains individual data results from surveillance and monitoring activities. The ''Site Environmental Report'' is distributed by releasing it on the Web from the Berkeley Lab Environmental Services Group (ESG) home page, which is located at http://www.lbl.gov/ehs/esg/. Many of the documents cited in this report also are accessible from the ESG Web page. CD and printed copies of this Site Environmental Report are available upon request. The report follows the Laboratory's policy of using the International System of Units (SI), also known as the metric system of measurements. Whenever possible, results are also reported using the more conventional (non-SI) system of measurements, because the non-SI system is referenced by several current

Upon e-Documents: Evolution or Involution on GED Market

Directory of Open Access Journals (Sweden)

Mircea GEORGESCU

2006-01-01

Full Text Available In many organizations, vital information is trapped within individual desktops and fragmented in server silos across the enterprise. Manual, ad-hoc processes create inefficiencies, confusion and delays as employees waste time searching for important information. Organizations must find safer and easier ways to access, manage and share their content. Document and file management solutions designed to be used across the organization can help achieve these goals and reduce the total cost of managing content throughout the organization. If you decide to use an EDMS, your selection requires a careful, considered balance between your legal requirements and your technological options. The decision to use an EDMS requires significant planning and analysis. Managing documents more effectively, controlling costs associated with documents and document processes, and using resources more efficiently has become and will continue to be increasingly important to businesses and IT organizations.

Automotive Manufacturing Assessment System : Volume 1. Master Product Schedules.

Science.gov (United States)

1999-11-01

Volume I is part of a four volume set documenting areas of research resulting from the development of the Automotive Manufacturing Assessment System (AMAS) for the DOT/Transportation Systems Center. AMAS was designed to assist in the evaluation of in...

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...

Information architecture. Volume 3: Guidance

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-04-01

The purpose of this document, as presented in Volume 1, The Foundations, is to assist the Department of Energy (DOE) in developing and promulgating information architecture guidance. This guidance is aimed at increasing the development of information architecture as a Departmentwide management best practice. This document describes departmental information architecture principles and minimum design characteristics for systems and infrastructures within the DOE Information Architecture Conceptual Model, and establishes a Departmentwide standards-based architecture program. The publication of this document fulfills the commitment to address guiding principles, promote standard architectural practices, and provide technical guidance. This document guides the transition from the baseline or defacto Departmental architecture through approved information management program plans and budgets to the future vision architecture. This document also represents another major step toward establishing a well-organized, logical foundation for the DOE information architecture.

Tank Waste Remediation System Projects Document Control Plan

International Nuclear Information System (INIS)

Slater, G.D.; Halverson, T.G.

1994-01-01

The purpose of this Tank Waste Remediation System Projects Document Control Plan is to provide requirements and responsibilities for document control for the Hanford Waste Vitrification Plant (HWVP) Project and the Initial Pretreatment Module (IPM) Project

Integrity Based Access Control Model for Multilevel XML Document

Institute of Scientific and Technical Information of China (English)

HONG Fan; FENG Xue-bin; HUANO Zhi; ZHENG Ming-hui

2008-01-01

XML's increasing popularity highlights the security demand for XML documents. A mandatory access control model for XML document is presented on the basis of investigation of the function dependency of XML documents and discussion of the integrity properties of multilevel XML document. Then, the algorithms for decomposition/recovery multilevel XML document into/from single level document are given, and the manipulation rules for typical operations of XQuery and XUpdate: QUERY, INSERT,UPDATE, and REMOVE, are elaborated. The multilevel XML document access model can meet the requirement of sensitive information processing application.

Design basis document open-item resolution and reportability

International Nuclear Information System (INIS)

Gambhir, S.K.; Livingston, B.R.; Purcell, J.J.; Erickson, E.A.

1989-01-01

In the process of reconstituting the design bases for older nuclear power plants, information or references may not be available to fully define the design requirements or to document and verify the adequacy of the design. Also, information that is in conflict with other data is identified. The missing and conflicting information must be reconstituted in order to adequately document the design bases of the plant. For these operating facilities, the identification, tracking, and resolution of missing or conflicting information is very important when the reporting requirements stipulated by 10CFR21, 10CFR50.72, and 10CFR50.73 are considered. Additionally, controlled documentation (calculations, drawings, etc.) used to develop the design basis documents may contain conflicting data. In some cases, conflicts between the as-built design and licensing or design basis requirements established in specific commitments to the U.S. Nuclear Regulatory Commission may be identified. Furthermore, concerns regarding the adequacy of safety-related systems or components to perform their required function may be identified that would warrant prompt action by the licensee. The approach discussed in this paper was used by Omaha Public Power District for the ongoing design basis reconstitution effort at the Fort Calhoun nuclear plant

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

Piles, tabs and overlaps in navigation among documents

DEFF Research Database (Denmark)

Jakobsen, Mikkel Rønne; Hornbæk, Kasper

2010-01-01

Navigation among documents is a frequent, but ill supported activity. Overlapping or tabbed documents are widespread, but they offer limited visibility of their content. We explore variations on navigation support: arranging documents with tabs, as overlapping windows, and in piles. In an experim......Navigation among documents is a frequent, but ill supported activity. Overlapping or tabbed documents are widespread, but they offer limited visibility of their content. We explore variations on navigation support: arranging documents with tabs, as overlapping windows, and in piles....... In an experiment we compared 11 participants’ navigation with these variations and found strong task effects. Overall, overlapping windows were preferred and their structured layout worked well with some tasks. Surprisingly, tabbed documents were efficient in tasks requiring simply finding a document. Piled...... on document navigation and its support by piling....

Managing the consistency of distributed documents

OpenAIRE

Nentwich, C.

2005-01-01

Many businesses produce documents as part of their daily activities: software engineers produce requirements specifications, design models, source code, build scripts and more; business analysts produce glossaries, use cases, organisation charts, and domain ontology models; service providers and retailers produce catalogues, customer data, purchase orders, invoices and web pages. What these examples have in common is that the content of documents is often semantically relate...

Title list of documents made publicly available: February 1--28, 1995. Volume 17, Number 2

International Nuclear Information System (INIS)

1995-04-01

This monthly publication contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index. NRC documents that are publicly available may be examined without charge at the NRC Public Document Room (PDR)

Title list of documents made publicly available: February 1--28, 1995. Volume 17, Number 2

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-04-01

This monthly publication contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index. NRC documents that are publicly available may be examined without charge at the NRC Public Document Room (PDR).

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.

Environmental Sensitivity Index (ESI) Atlas: East Florida, maps in portable document format, Volume 1, Volume 2 (NODC Accession 0004150)

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — This data set comprises the Environmental Sensitivity Index (ESI) maps in Portable Document Format (.PDF) for the shoreline of East Florida (to encompass the coastal...

Viability Assessment Volume 2

International Nuclear Information System (INIS)

1998-01-01

This volume describes the major design features of the Monitored Geologic Repository. This document is not intended to provide an exhaustive, detailed description of the repository design. Rather, this document summarizes the major systems and primary elements of the design that are radiologically significant, and references the specific technical documents and design analyses wherein the details can be found. Not all portions of the design are at the same level of completeness. Highest priority has been given to assigning resources to advance the design of the Monitored Geologic Repository features that are important to radiological safety and/or waste isolation and for which there is no NRC licensing precedent. Those features that are important to radiological safety and/or waste isolation, but for which there is an NRC precedent, receive second priority. Systems and features that have no impact on radiological safety or waste isolation receive the lowest priority. This prioritization process, referred to as binning, is discussed in more detail in Section 2.3. Not every subject discussed in this volume is given equal treatment with regard to the level of detail provided. For example, less detail is provided for the surface facility design than for the subsurface and waste package designs. This different level of detail is intentional. Greater detail is provided for those functions, structures, systems, and components that play key roles with regard to protecting radiological health and safety and that are not common to existing nuclear facilities already licensed by NRC. A number of radiological subjects are not addressed in the VA, (e.g., environmental qualification of equipment). Environmental qualification of equipment and other radiological safety considerations will be addressed in the LA. Non-radiological safety considerations such as silica dust control and other occupational safety considerations are considered equally important but are not addressed in

An Independent Scientific Assessment of Well Stimulation in California Volume I

Energy Technology Data Exchange (ETDEWEB)

Long, Jane C.S. [California Council on Science and Technology, Sacramento, CA (United States); Feinstein, Laura C. [California Council on Science and Technology, Sacramento, CA (United States); Birkholzer, Jens [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Jordan, Preston [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Houseworth, James [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Dobson, Patrick F. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Heberger, Matthew [Pacific Inst., Oakland, CA (United States); Gautier, Donald L. [Dr. Donald Dautier, LLC., Palo Alto, CA (United States)

2015-01-01

In 2013, the California Legislature passed Senate Bill 4 (SB 4), setting the framework for regulation of well stimulation technologies in California, including hydraulic fracturing. SB 4 also requires the California Natural Resources Agency to conduct an independent scientific study of well stimulation technologies in California to assess current and potential future practices, including the likelihood that well stimulation technologies could enable extensive new petroleum production in the state, evaluate the impacts of well stimulation technologies and the gaps in data that preclude this understanding, identify risks associated with current practices, and identify alternative practices which might limit these risks. The study is issued in three volumes. This document, Volume I, provides the factual basis describing well stimulation technologies, how and where operators deploy these technologies for oil and gas production in California, and where they might enable production in the future. Volume II discusses how well stimulation affects water, the atmosphere, seismic activity, wildlife and vegetation, traffic, light and noise levels; it will also explore human health hazards, and identify data gaps and alternative practices. Volume III presents case studies to assess environmental issues and qualitative

Time-motion analysis of clinical nursing documentation during implementation of an electronic operating room management system for ophthalmic surgery.

Science.gov (United States)

Read-Brown, Sarah; Sanders, David S; Brown, Anna S; Yackel, Thomas R; Choi, Dongseok; Tu, Daniel C; Chiang, Michael F

2013-01-01

Efficiency and quality of documentation are critical in surgical settings because operating rooms are a major source of revenue, and because adverse events may have enormous consequences. Electronic health records (EHRs) have potential to impact surgical volume, quality, and documentation time. Ophthalmology is an ideal domain to examine these issues because procedures are high-throughput and demand efficient documentation. This time-motion study examines nursing documentation during implementation of an EHR operating room management system in an ophthalmology department. Key findings are: (1) EHR nursing documentation time was significantly worse during early implementation, but improved to a level near but slightly worse than paper baseline, (2) Mean documentation time varied significantly among nurses during early implementation, and (3) There was no decrease in operating room turnover time or surgical volume after implementation. These findings have important implications for ambulatory surgery departments planning EHR implementation, and for research in system design.

Environment, Health, and Safety - Construction Subcontractors Documents |

Science.gov (United States)

NREL Environment, Health, and Safety - Construction Subcontractors Documents Environment Environment, Health and Safety (EH&S) requirements are understood by construction subcontractors and with these requirements before submitting proposals and/or environment, health and safety plans for the

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.)

Regulatory Oversight Program, July 1, 1993--March 3, 1997. Volume 2: Appendices

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-12-31

On July, 1993, a Regulatory Oversight (RO) organization was established within the US DOE, Oak Ridge Operations to provide regulatory oversight of the DOE uranium enrichment facilities leased to the United States Enrichment Corporation (USEC). The purpose of the OR program was to ensure continued plant safety, safeguards and security while the plants were transitioned to regulatory oversight by the Nuclear Regulatory Commission (NRC). Volume 2 contains copies of the documents which established the relationship between NRC, DOE, USEC, and DOL (Dept of Labor) required to facilitate regulatory oversight transition.

Regulatory Oversight Program, July 1, 1993 - March 3, 1997. Volume 2: Appendices

International Nuclear Information System (INIS)

1997-01-01

On July, 1993, a Regulatory Oversight (RO) organization was established within the US DOE, Oak Ridge Operations to provide regulatory oversight of the DOE uranium enrichment facilities leased to the United States Enrichment Corporation (USEC). The purpose of the OR program was to ensure continued plant safety, safeguards and security while the plants were transitioned to regulatory oversight by the Nuclear Regulatory Commission (NRC). Volume 2 contains copies of the documents which established the relationship between NRC, DOE, USEC, and DOL (Dept of Labor) required to facilitate regulatory oversight transition

Sandia software guidelines, Volume 4: Configuration management

Energy Technology Data Exchange (ETDEWEB)

1992-06-01

This volume is one in a series of Sandia Software Guidelines for use in producing quality software within Sandia National Laboratories. This volume is based on the IEEE standard and guide for software configuration management. The basic concepts and detailed guidance on implementation of these concepts are discussed for several software project types. Example planning documents for both projects and organizations are included.

Born Broken: Fonts and Information Loss in Legacy Digital Documents

Directory of Open Access Journals (Sweden)

Geoffrey Brown

2011-03-01

Full Text Available For millions of legacy documents, correct rendering depends upon resources such as fonts that are not generally embedded within the document structure. Yet there is a significant risk of information loss due to missing or incorrectly substituted fonts. Large document collections depend on thousands of unique fonts not available on a common desktop workstation, which typically has between 100 and 200 fonts. Silent substitution of fonts, performed by applications such as Microsoft Office, can yield poorly rendered documents. In this paper we use a collection of 230,000 Word documents to assess the difficulty of matching font requirements with a database of fonts. We describe the identifying information contained in common font formats, font requirements stored in Word documents, the API provided by Windows to support font requests by applications, the documented substitution algorithms used by Windows when requested fonts are not available, and the ways in which support software might be used to control font substitution in a preservation environment.

Our Documents: A National Initiative on American History, Civics, and Service. Teacher Sourcebook, Volume II

Science.gov (United States)

Mazzenga, Maria, Ed.; McCullough, Julie, Ed.

2003-01-01

What do Matthew Brady, Carrie Chapman Catt, Ansel Adams, Orson Welles, and J. Howard Miller have to do with the 100 milestone documents? A few hints: Matthew Brady created the first photographic documentation of a war. Carrie Chapman Catt was the president of the National American Woman Suffrage Association in 1920. Orson Welles produced plays for…

Specifying semantic information on functional requirements

OpenAIRE

YAO, WUPING

2012-01-01

Requirements engineering is a challenging process in software development projects. Requirements, in general, are documented in natural language. They often have issues related to ambiguity, completeness and consistency. How to improve the quality of requirements documentation remains a classic research topic. This research aims at improving the way of editing and documenting functional requirements. We propose a meta-model to specify the semantic information of functional requirements, and d...

The Algorithm Theoretical Basis Document for Level 1A Processing

Science.gov (United States)

Jester, Peggy L.; Hancock, David W., III

2012-01-01

The first process of the Geoscience Laser Altimeter System (GLAS) Science Algorithm Software converts the Level 0 data into the Level 1A Data Products. The Level 1A Data Products are the time ordered instrument data converted from counts to engineering units. This document defines the equations that convert the raw instrument data into engineering units. Required scale factors, bias values, and coefficients are defined in this document. Additionally, required quality assurance and browse products are defined in this document.

Quality documentation challenges for veterinary clinical pathology laboratories.

Science.gov (United States)

Sacchini, Federico; Freeman, Kathleen P

2008-05-01

An increasing number of veterinary laboratories worldwide have obtained or are seeking certification based on international standards, such as the International Organization for Standardization/International Electrotechnical Commission 17025. Compliance with any certification standard or quality management system requires quality documentation, an activity that may present several unique challenges in the case of veterinary laboratories. Research specifically addressing quality documentation is conspicuously absent in the veterinary literature. This article provides an overview of the quality system documentation needed to comply with a quality management system with an emphasis on preparing written standard operating procedures specific for veterinary laboratories. In addition, the quality documentation challenges that are unique to veterinary clinical pathology laboratories are critically evaluated against the existing quality standards and discussed with respect to possible solutions and/or recommended courses of action. Documentation challenges include the establishment of quality requirements for veterinary tests, the use or modification of human analytic methods for animal samples, the limited availability of quality control materials satisfactory for veterinary clinical pathology laboratories, the limited availability of veterinary proficiency programs, and the complications in establishing species-specific reference intervals.

Title list of documents made publicly available, March 1--31, 1995: Volume 17, No. 3

International Nuclear Information System (INIS)

1995-05-01

The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index. The docketed information contained in the Title List includes the information formerly issued through the Department of Energy publication Power Reactor Docket Information, last published in January 1979. NRC documents that are publicly available may be examined without charge at the NRC Public Document Room (PDR). Duplicate copies may be obtained for a fee. Standing orders for certain categories of documents are also available. Clients may search for and order desired titles through the PDR computerized Bibliographic Retrieval System, which is accessible both at the PDR and remotely. The PDR is staffed by professional technical librarians, who provide reference assistance to users. See NOTES at the end of the preface for information about reaching the PDR. Microfiche of the docketed information listed in the Title List is available for sale on a subscription basis from the National Technical Information Service (NTIS)

Title list of documents made publicly available, March 1--31, 1995: Volume 17, No. 3

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-05-01

The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index. The docketed information contained in the Title List includes the information formerly issued through the Department of Energy publication Power Reactor Docket Information, last published in January 1979. NRC documents that are publicly available may be examined without charge at the NRC Public Document Room (PDR). Duplicate copies may be obtained for a fee. Standing orders for certain categories of documents are also available. Clients may search for and order desired titles through the PDR computerized Bibliographic Retrieval System, which is accessible both at the PDR and remotely. The PDR is staffed by professional technical librarians, who provide reference assistance to users. See NOTES at the end of the preface for information about reaching the PDR. Microfiche of the docketed information listed in the Title List is available for sale on a subscription basis from the National Technical Information Service (NTIS).

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

Volumes and doses for external radiotherapy - Definitions and recommendations; Volum og doser i ekstern straaleterapi - Definisjoner og anbefalinger

Energy Technology Data Exchange (ETDEWEB)

Levernes, Sverre (ed.)

2012-07-01

The report contains definitions of volume and dose parameters for external radiotherapy. In addition the report contains recommendations for use, documentation and minimum reporting for radiotherapy of the individual patient.(Author)

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...

Bare-Hand Volume Cracker for Raw Volume Data Analysis

Directory of Open Access Journals (Sweden)

Bireswar Laha

2016-09-01

Full Text Available Analysis of raw volume data generated from different scanning technologies faces a variety of challenges, related to search, pattern recognition, spatial understanding, quantitative estimation, and shape description. In a previous study, we found that the Volume Cracker (VC 3D interaction (3DI technique mitigated some of these problems, but this result was from a tethered glove-based system with users analyzing simulated data. Here, we redesigned the VC by using untethered bare-hand interaction with real volume datasets, with a broader aim of adoption of this technique in research labs. We developed symmetric and asymmetric interfaces for the Bare-Hand Volume Cracker (BHVC through design iterations with a biomechanics scientist. We evaluated our asymmetric BHVC technique against standard 2D and widely used 3D interaction techniques with experts analyzing scanned beetle datasets. We found that our BHVC design significantly outperformed the other two techniques. This study contributes a practical 3DI design for scientists, documents lessons learned while redesigning for bare-hand trackers, and provides evidence suggesting that 3D interaction could improve volume data analysis for a variety of visual analysis tasks. Our contribution is in the realm of 3D user interfaces tightly integrated with visualization, for improving the effectiveness of visual analysis of volume datasets. Based on our experience, we also provide some insights into hardware-agnostic principles for design of effective interaction techniques.

LHCb Online Networking Requirements

CERN Document Server

Jost, B

2003-01-01

This document describes the networking requirements of the LHCb online installation. It lists both quantitative aspects such as the number of required switch ports, as well as some qualitative features of the equipment, such as minimum buffer sizes in switches. The document comprises both the data acquisition network and the controls/general-purpose network. While the numbers represent our best current knowledge and are intended to give (in particular) network equipment manufacturers an overview of our needs, this document should not be confused with a market survey questionnaire or a formal tendering document. However the information contained in this document will be the input of any such document. A preliminary schedule for procurement and installation is also given.

Elmo Bumpy Torus proof of principle, Phase II: Title 1 report. Volume VII. Cryogenic system