Mine-by experiment final design report

International Nuclear Information System (INIS)

Read, R.S.; Martin, C.D.

1991-12-01

The Underground Research Laboratory (URL) Mine-by Experiment is designed to provide information on rock mass response to excavation that will be used to assess important aspects of the design of a nuclear fuel waste disposal vault in a granitic pluton. The final experiment design is the result of a multidisciplinary approach, drawing on experience gained at other sites as well as the URL, and using both internal expertise and the external consultants. The final experiment design, including details on characterization, construction, instrumentation, and numerical modelling, is presented along with final design drawings

Nevada State plan; final approval determination. Occupational Safety and Health Administration (OSHA), U.S. Department of Labor. Final State plan approval--Nevada.

Science.gov (United States)

2000-04-18

This document amends OSHA's regulations to reflect the Assistant Secretary's decision granting final approval to the Nevada State plan. As a result of this affirmative determination under section 18(e) of the Occupational Safety and Health Act of 1970, Federal OSHA's standards and enforcement authority no longer apply to occupational safety and health issues covered by the Nevada plan, and authority for Federal concurrent jurisdiction is relinquished. Federal enforcement jurisdiction is retained over any private sector maritime employment, private sector employers on Indian land, and any contractors or subcontractors on any Federal establishment where the land is exclusive Federal jurisdiction. Federal jurisdiction remains in effect with respect to Federal government employers and employees. Federal OSHA will also retain authority for coverage of the United States Postal Service (USPS), including USPS employees, contract employees, and contractor-operated facilities engaged in USPS mail operations.

78 FR 16601 - List of Approved Spent Fuel Storage Casks: MAGNASTOR® System

Science.gov (United States)

2013-03-18

... Storage Casks: MAGNASTOR[supreg] System AGENCY: Nuclear Regulatory Commission. ACTION: Direct final rule... (MAGNASTOR[supreg]) System listing within the ``List of Approved Spent Fuel Storage Casks'' to include... for the MAGNASTOR[supreg] System cask design within the list of approved spent fuel storage casks that...

Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 2002 ed

International Nuclear Information System (INIS)

2002-08-01

The current edition of the transport Regulations was published in 1996 and is more commonly referred to as 'ST-1'. Earlier Editions were known as Safety Series No. 6. The latest English reprint (2000) is now identified as TS-R-1 (ST-1, Revised). The transport Regulations elaborate requirements for the design, fabrication and maintenance of packaging as well as those for preparation, consigning, handling, carriage, storage in transit and receipt of the packages at final destination. Approval issued in the form of certificates is required for the design or shipment of packages. This report supersedes IAEA-TECDOC-1237 Directory of National Competent Authorities' Approval Certificates for Package Design, Special Form Material and Shipment of Radioactive Material, 2001 Edition. It is distributed worldwide to the IAEA Member States' competent authorities for transport, and other entities who have requested copies. Electronic copies of the main data file are provided to registered users of the PACKTRAM database. The information contained in this report is given in six tables. In each of these, information is presented in alphabetical order based on the certificate number. Tables 1 to 4 present administrative data including issue and expiry dates, package identification, package serial numbers, modes for which the package/shipment is approved and the edition of the IAEA Transport Safety Regulations on which the approval has been based. The technical information on package mass, authorized contents, and detailed and general description of the package are contained in Table 5. Table 6 shows the certificates reported to the Secretariat by each participating Member State

Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 2001 edition

International Nuclear Information System (INIS)

2001-08-01

The current edition of the transport Regulations was published in 1996 and is more commonly referred to as 'ST-1'. Earlier Editions were known as Safety Series No. 6. The latest English reprint (2000) is now identified as TS-R-1 (ST-1, Revised). The transport Regulations elaborate requirements for the design, fabrication and maintenance of packaging as well as those for preparation, consigning, handling, carriage, storage in transit and receipt of the packages at final destination. Approval issued in the form of certificates is required for the design or shipment of packages. This report supersedes IAEA-TECDOC-1171 D irectory of National Competent Authorities' Approval Certificates for Package Design, Special Form Material and Shipment of Radioactive Material, 2000 Edition . It is distributed worldwide to the IAEA Member States' competent authorities for transport, and other entities who have requested copies. Electronic copies of the main data file are provided to registered users of the PACKTRAM database. The information contained in this report is given in six tables. In each of these, information is presented in alphabetical order based on the certificate number. Tables 1 to 4 present administrative data including issue and expiry dates, package identification, package serial numbers, modes for which the package/shipment is approved and the edition of the IAEA Transport Safety Regulations on which the approval has been based. The technical information on package mass, authorized contents, and detailed and general description of the package are contained in Table 5. Table 6 shows the certificates reported to the Secretariat by each participating Member State

California Air Quality State Implementation Plans; Final Approval; Butte County Air Quality Management District; Stationary Source Permits

Science.gov (United States)

EPA is taking final action to approve a revision to the Butte County Air Quality Management District (BCAQMD) portion of the California State Implementation Plan (SIP). This revision concerns the District's New Source Review (NSR) permitting program.

76 FR 52997 - Public Company Accounting Oversight Board; Order Approving Proposed Board Funding Final Rules for...

Science.gov (United States)

2011-08-24

... Accounting Oversight Board; Order Approving Proposed Board Funding Final Rules for Allocation of the Board's... August 18, 2011. I. Introduction On June 21, 2011, the Public Company Accounting Oversight Board (the... public accounting firm, in amounts that are sufficient to cover the costs of processing and reviewing...

Applications for approval to market a new drug; complete response letter; amendments to unapproved applications. Final rule.

Science.gov (United States)

2008-07-10

The Food and Drug Administration (FDA) is amending its regulations on new drug applications (NDAs) and abbreviated new drug applications (ANDAs) for approval to market new drugs and generic drugs (drugs for which approval is sought in an ANDA). The final rule discontinues FDA's use of approvable letters and not approvable letters when taking action on marketing applications. Instead, we will send applicants a complete response letter to indicate that the review cycle for an application is complete and that the application is not ready for approval. We are also revising the regulations on extending the review cycle due to the submission of an amendment to an unapproved application and starting a new review cycle after the resubmission of an application following receipt of a complete response letter. In addition, we are adding to the regulations on biologics license applications (BLAs) provisions on the issuance of complete response letters to BLA applicants. We are taking these actions to implement the user fee performance goals referenced in the Prescription Drug User Fee Amendments of 2002 (PDUFA III) that address procedures and establish target timeframes for reviewing human drug applications.

Premarket Approval (PMA) Summary Review Memos for 180-Day Design Changes

Data.gov (United States)

U.S. Department of Health & Human Services — A 180-day supplement is a request for a significant change in components, materials, design, specification, software, color additive, and labeling to an approved...

40 CFR 125.99 - What are approved design and construction technologies?

Science.gov (United States)

2010-07-01

... construction technologies? 125.99 Section 125.99 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY...) of the Act § 125.99 What are approved design and construction technologies? (a) The following....99 was suspended. ...

Hyapproval : final handbook for approval of hydrogen refuelling stations

NARCIS (Netherlands)

Wurster, R.; Landinger, H.; Machens, C.; Allidières, L.; Molag, M.; Barron, J.; Reijalt, M.; Hill, H.J.

2006-01-01

HyApproval is an EC co-financed Specific Targeted Research Project (STREP) to develop a Handbook facilitating the approval of Hydrogen Refuelling Stations (HRS). The project, started in October 2005, will be performed over 24 months by a balanced partnership including 25 partners from industry, SMEs

Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 1992 ed

International Nuclear Information System (INIS)

1992-08-01

Being in a unique position to facilitate information exchange, the Secretariat of the International Atomic Energy Agency was requested by its Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM) to collate package approval data and publish periodical reports thereon. A database was implemented on the mainframe computer in the mid-1980s but this was soon adapted for use on a personal computer. A fully menu-driven system programme was designed that allows both contributing Member States and the Secretariat more flexibility in data processing and reporting. Complete documentation is available in the form of a user guide. The cut-off date used for this report is 31 August 1992. This report supersedes IAEA-TECDOC-617 ''Directory of National Competent Authorities' Approval Certificates for Package Design, Special Form Material and Shipment of Radioactive Material, 1991 Edition''. The information contained in this report is given in six tables. In each of these, information is presented in alphabetical order based on the certificate number. The certificate number is identical with the competent authority identification mark. It is composed of the issuing Member State's international vehicle registration identification (VRI) code, followed by a slash, then a unique number specific to a particular design or shipment that is assigned by the competent authority, another slash and finally a code identifying the type of package involved. ''-85'' is appended to those certificates that were approved on the basis of the 1985 Edition of Safety Series No. 6. Tables 1 to 4 present administrative data including issue and expiry dates, package identification, package serial numbers, modes for which the package/shipment is approved and the edition of Safety Series No. 6 on which the approval has been based. The technical information on package mass, authorized contents, and detailed and general description of the package are contained in Table 5. Table 6

76 FR 14437 - Economic Simplified Boiling Water Reactor Standard Design: GE Hitachi Nuclear Energy; Issuance of...

Science.gov (United States)

2011-03-16

... NUCLEAR REGULATORY COMMISSION [NRC-2011-0055] Economic Simplified Boiling Water Reactor Standard Design: GE Hitachi Nuclear Energy; Issuance of Final Design Approval The U.S. Nuclear Regulatory Commission has issued a final design approval (FDA) to GE Hitachi Nuclear Energy (GEH) for the economic...

Effective Date of Requirement for Premarket Approval for Surgical Mesh for Transvaginal Pelvic Organ Prolapse Repair. Final order.

Science.gov (United States)

2016-01-05

The Food and Drug Administration (FDA or the Agency) is issuing a final order to require the filing of a premarket approval application (PMA) or notice of completion of a product development protocol (PDP) for surgical mesh for transvaginal pelvic organ prolapse (POP) repair.

Safety review and approval process for the TFTR

International Nuclear Information System (INIS)

Levine, J.D.; Howe, H.J.; Howe, K.E.

1983-01-01

The design, construction, and operation of the Tokamak Fusion Test Reactor (TFTR) has undergone an extensive safety and enviromental analysis involving Princeton Plasma Physics Laboratory (PPPL), the U.S. Department of Energy (DOE), the Ebasco/Grumman Industrial Subcontractor Team, and other organizations. This analysis, which is continuing during the TFTR operational phase, has been facilitated by the preparation, review and approval of several documents, including an Environmental Statement (Draft and Final), a Preliminary Safety Analysis Report (PSAR), a Final Safety Analysis Report (FSAR), Operations Safety Requirements (OSRs) and Safety Requirements (SRs), and various Operating and Maintenance Manuals. Through TFTR Safety Group participation in formal system design evaluations, change control boards, and reviews of project procurement and installation documentation, the TFTR Management Configuration Control System assures that all aspects of the project, including proposed design, installation and operational changes, receive prompt and thorough safety analyses. These efforts will continue as the TFTR Program moves into the neutral beam and D-T operational phases. The safety review and approval experience that has been acquired on the TFTR Project should serve as a foundation for similar efforts on future fusion devices

Safety regulation for the design approval of special form radioactive sources

International Nuclear Information System (INIS)

Cho, Woon-Kap

2009-01-01

Several kinds of special form radioactive sources for industrial, medical applications are being produced in Korea. Special form radioactive sources should meet strict safety requirements specified in the domestic safety regulations and the design of the sources should be certified by the regulatory authority, the Ministry of Education, Science and Technology (MEST). Several safety tests such as impact, percussion, heating, and leak tests are performed on the sources according to the domestic regulations and the international safety standards such as ANSI N542-1977 and ISO 2919-1999(E). As a regulatory expert body, Korea Institute of Nuclear Safety (KINS) assesses various types of application documents, such as safety analysis report, quality assurance program, and other documents evidencing fulfillment of requirements for design approval of the special form radioactive sources, submitted by a legal person who intends to produce special form radioactive sources and then reports the assessment result to MEST. A design approval certificate is issued to the applicant by MEST on the basis of a technical evaluation report presented by KINS.

14 CFR 21.621 - Issuance of letters of TSO design approval: import articles.

Science.gov (United States)

2010-01-01

... performance standards of the State of Design and any other performance standards the FAA may prescribe to... to the FAA one copy of the technical data required in the applicable performance standard through its State of Design. (b) The FAA issues the letter of TSO design approval that lists any deviation granted...

Procedure for getting safety classed concrete structures approved by Finnish Radiation and Nuclear Safety Authority

International Nuclear Information System (INIS)

Halme, Ville-Juhani

2015-01-01

Posiva is preparing geological final disposal in the Finnish bedrock in Olkiluoto, Eurajoki. The final disposal facility includes encapsulation plant and underground repository. Most of the main civil structures are concrete structures. STUK is the supervising authority in civil structures. The National Building Code of Finland and STUK's Regulatory Guide on nuclear safety (YVL) are the most important instructions when constructing concrete structures into nuclear installation. Posiva has classified concrete structures in two classes according STUK's YVL-guidance: EYT (non-nuclear) and Safety Class 3 (SC 3, nuclear safety significance). When building SC 3 concrete structures, specific protocol must be followed. Protocol includes planned routines for design, construction, supervision, quality control (QC) and quality assurance (QA) activities. Documents relating concrete structures must be approved by Posiva and STUK before construction work. After structures have been designed and actual building is ongoing, there are two main steps. Before concreting, readiness inspection for concreting must be arranged. Readiness inspection will be arranged according to a specific plan and the date must be informed to STUK. After establishing readiness for concreting, casting work can begin. Once concrete structures are done, inspected and approved, final documentation according to a quality control plan will be reviewed by Posiva. After Posiva's approval, final documentation will be sent for STUK's approval. In the end STUK will give the permission for commissioning of the concrete structures after approved commissioning inspection. The document is made up of an abstract and a poster

California State Implementation Plan; Final Approval of Revision; Yolo-Solano Air Quality Management District; Reasonably Available Control Technology Requirements for 1997 8-hour Ozone NAAQS

Science.gov (United States)

EPA is taking final action to approve a revision to the Yolo-Solano Air Quality Management District (YSAQMD) portion of the California SIP concerning YSAQMD regarding RACT)requirements the 1997 8-hour ozone NAAQS and approve negative declarations into SIP.

MINIMARS conceptual design: Final report

International Nuclear Information System (INIS)

Lee, J.D.

1986-09-01

This volume contains the following sections: (1) fueling systems; (2) blanket; (3) alternative blanket concepts; (4) halo scraper/direct converter system study and final conceptual design; (5) heat-transport and power-conversion systems; (6) tritium systems; (7) minimars air detritiation system; (8) appropriate radiological safety design criteria; and (9) cost estimate

Rock quality designation of the hydraulic properties in the near field of a final repository for spent nuclear fuel

International Nuclear Information System (INIS)

Carlsson, Hans; Carlsson, Leif; Pusch, Roland

1989-06-01

Quality assurance of a final repository for spent nuclear fuel requires detailed information on the characteristics of the rock, backfill, canisters and the waste itself. Furthermore, and of fundamental importance, is the knowledge of the behaviour of the integrated system of the waste and the different barriers. The in-situ characteristics of the rock must therefore be assessed and their influence on and interactions with the remaining barriers must be predicted and verified. A rock quality designation process of the hydraulic properties in the near-field is out-lined both for the KBS-3 system as well as for the WP-cave system. The process, once updated and approved, will be included in a Quality Assurance Program for the final repository for spent nuclear fuel. Some of the available methods for the near-field designation process are presented as well as techniques that need further development or are not developed at all. Finally, a presentation is given of a generic designation process of the KBS-3 and WP-cave repository systems in the previously investigated area in Central Sweden, where the final repository for reactor waste, SFR, is located. Geological and hydrogeological data are here at hand and it is therefore possible to carry out a simulation of how the designation process would be accomplished. (authors) (72 figs., 12 tabs., 43 refs.)

Final amplifier design and mercury

International Nuclear Information System (INIS)

Rose, E.A.; Hanson, D.E.

1991-01-01

The final amplifier for the Mercury KrF excimer facility is being designed. The design exercise involves extensive modeling to predict amplifier performance. Models of the pulsed-power system, including a Child-Langmuir diode with closure, electron-beam energy deposition, KrF laser kinetics, amplified spontaneous emission (ASE), a time-dependent laser extraction in the presence of ASE are presented as a design package. The design exercise indicates that the energy objective of Phase I -- 100 joules -- will be met

Final Approval of California Air Plan Revision; Antelope Valley Air Quality Management District; VOCs From Motor Vehicle Assembly Coating Operations

Science.gov (United States)

EPA is taking final action to approve a revision to the Antelope Valley Air Quality Management District (AVAQMD) portion of the California SIP concerning the emissions of volatile organic compounds (VOCs) from motor vehicle assembly coating operations.

Medicaid program; Medicaid Management Information Systems; conditions of approval and reapproval and procedures for reduction of Federal financial participation--HCFA. Final rule.

Science.gov (United States)

1985-07-30

This final rule provides the additional requirements to the conditions and procedures for initial approval and reapproval of Medicaid Management Information Systems (MMIS) that were added by section 1903(r) of the Social Security Act (as amended by section 901 of the Mental Health Systems Act of 1980, Pub. L. 96-398). These provisions are intended to improve States' MMIS, ensure efficient system operations, and make the procedures for detection of fraud, waste, and abuse more effective. In addition, this final rule specifies the procedures we follow in reducing the level of Federal financial participation in State administrative expenditures if a State fails to meet the conditions for initial operation, initial approval, or reapproval of an MMIS.

75 FR 53727 - Self-Regulatory Organizations; NASDAQ OMX PHLX, Inc.; Order Approving Proposed Rule Change, as...

Science.gov (United States)

2010-09-01

... underwritings; (ii) supervision of market making commitments; (iii) final approval of advertisements as these... designed to prevent fraudulent and manipulative acts and practices, to promote just and equitable...

The completed design of the SLC Final Focus System

International Nuclear Information System (INIS)

Murray, J.J.; Brown, K.L.; Fieguth, T.

1987-02-01

The design of the SLC Final Focus System has evolved from its initial conceptual design into its final form. This final design is described including a review of the critical decisions influencing the adoption of particular features. The creation of a feasible design has required that these decisions be tempered by practical considerations such as site constraints, correction of optical errors caused by imperfections, and accommodations requested by engineers and particle detector physicists. As this is the first such system to be built, it is hoped that the experience gained will be useful for the design of future systems

Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 1991 edition

International Nuclear Information System (INIS)

1991-08-01

The format of this report is a result of recommendations made by the Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM) at its 6th meeting in November 1987. The database was at that time maintained on the main frame and it was felt that adapting it for use on a personal computer would allow more flexibility in data processing and reporting. This document supersedes TECDOC-552 ''Directory of National Competent Authorities' Approval Certificates for Package Design and Shipment of Radioactive Material 1990 Edition''. Since publication of TECDOC-552, some modifications affecting the structure of the database and reporting formats were undertaken. These are fully described in ''Working Material: The PACKTRAM Database National Competent Authority Package Approval Certificates, User Guide Rev. 1'', which was released in early 1991. The present report is contained in five tables. In each of these, information is presented in alphabetical order based on the certificate number. This is composed of the issuing Member State's VRI code, followed by a slash, then a three- or four-digit number, another slash and finally a code identifying the type of package involved. ''-85'' is appended to those certificates that were approved on the basis of the 1985 Edition of Safety Series No. 6. Tables 1 to 4 present administrative data including issue and expire, dates, package identification, package serial numbers, modes for which the package/shipment is approved and the edition of Safety Series No. 6 on which the approval has been based. The technical information on package mass, authorized contents, and detailed and general description of the package are contained in Table. 5

Regulatory issues resolved through design certification on the System 80+trademark standard plant design

International Nuclear Information System (INIS)

Ritterbusch, S.E.; Brinkman, C.B.

1996-01-01

The US Nuclear Regulatory Commission (NRC) has completed its review of the System 80+trademark Standard Plant Design, approving advanced design features and closing severe accident licensing issues. Final Design Approval was granted in July 1994. The NRC review was extensive, requiring written responses to over 4,950 questions and formal printing of over 50,000 Safety Analysis Report pages. New safety issues never before addressed in a regulatory atmosphere had to be resolved with detailed analysis and evaluation of design features. the System 80+ review demonstrated that regulatory issues can be firmly resolved only through presentation of a detailed design and completion of a comprehensive regulatory review

Final Exam Weighting as Part of Course Design

Science.gov (United States)

Franke, Matthew

2018-01-01

The weighting of a final exam or a final assignment is an essential part of course design that is rarely discussed in pedagogical literature. Depending on the weighting, a final exam or assignment may provide unequal benefits to students depending on their prior performance in the class. Consequently, uncritical grade weighting can discount…

75 FR 12090 - Approval and Promulgation of Implementation Plans and Designation of Areas for Air Quality...

Science.gov (United States)

2010-03-12

... proposes to approve a request from the State of Indiana to redesignate Lake and Porter Counties to... (SIP), the State's plan for maintaining the eight-hour ozone standard through 2020 in Lake and Porter... inventories for Lake and Porter Counties as a revision of the Indiana SIP. Finally, EPA proposes to find...

Permanent certification program for health information technology; revisions to ONC-Approved Accreditor processes. Final rule.

Science.gov (United States)

2011-11-25

Under the authority granted to the National Coordinator for Health Information Technology by section 3001(c)(5) of the Public Health Service Act (PHSA) as added by the Health Information Technology for Economic and Clinical Health (HITECH) Act, this final rule establishes a process for addressing instances where the ONC-Approved Accreditor (ONC-AA) engages in improper conduct or does not perform its responsibilities under the permanent certification program. This rule also addresses the status of ONC-Authorized Certification Bodies (ONC-ACBs) in instances where there may be a change in the accreditation organization serving as the ONC-AA and clarifies the responsibilities of the new ONC-AA.

7 CFR 800.147 - Maintenance and retention of records on delegations, designations, contracts, and approval of...

Science.gov (United States)

2010-01-01

... 7 Agriculture 7 2010-01-01 2010-01-01 false Maintenance and retention of records on delegations, designations, contracts, and approval of scale testing organizations. 800.147 Section 800.147 Agriculture... and Forms (general) § 800.147 Maintenance and retention of records on delegations, designations...

A Novel Final Focus Design for Future Linear Colliders

Energy Technology Data Exchange (ETDEWEB)

Seryi, Andrei

2000-05-30

The length, complexity and cost of the present Final Focus designs for linear colliders grows very quickly with the beam energy. In this letter, a novel final focus system is presented and compared with the one proposed for NLC. This new design is simpler, shorter and cheaper, with comparable bandwidth, tolerances and tunability. Moreover, the length scales slower than linearly with energy allowing for a more flexible design which is applicable over a much larger energy range.

General method for final focus system design for circular colliders

Directory of Open Access Journals (Sweden)

Riccardo de Maria

2008-03-01

Full Text Available Colliders use final focus systems to reduce the transverse beam sizes at the interaction point in order to increase collision event rates. The maximum focal strength (gradient of the quadrupoles, and the maximum beam size in them, together limit the beam size reduction that is possible. The goal of a final focus system design is to find the best compromise between quadrupole aperture and quadrupole gradient, for the magnet technology that is used. This paper develops a design method that identifies the intrinsic limitations of a final focus system, validates the results of the method against realistic designs, and reports its application to the upgrade of the Large Hadron Collider final focus.

Design and approval of EPS diesel systems in German NPP

Energy Technology Data Exchange (ETDEWEB)

Kollmer, A.A., E-mail: anton.kollmer@tuev-sued.de [TUV SUD Industrie Service GmbH, Munich (Germany)

2014-07-01

Not at least because of 'Fukushima accident', Emergency power supply (EPS) systems with diesel engines are regarded as higher safety-important as 20 years ago. This presentation shows the design and approval of the emergency power facilities of the German nuclear power plants. It deals with the essential details e. g.: EPS Diesel integration to main power grid of the German BWR and PWR; Procedure for 'Loss of off-site power (LOOP)-Design'; Design robustness of AC Power Supply (Design requirements: independent redundancies, airplane crash, explosion pressure wave, earth-quake); Cooling systems (chilled by river water, air, well water, stored water volume); Layout of the stationary emergency Diesel generator (fuel supply, starting system); Layout of the bunkered EDG with directly driven emergency feed water pump; Robustness of AC power supply beyond design; Layout of mobile chilling equipment for diesel engines; Layout of mobile Diesel gen-sets (200 kVA and 1250 kVA); German Requirements of KTA 3702 versus US-IEE 323; Construction, Materials and Testing of EDG; Maintenance (in-service inspections, operation, Repair); Lessons learned (e. g. crank house cracks, start failure due to too much oil in the combustion chamber) (author)

Spent Nuclear Fuel (SNF) Cold Vacuum Drying (CVD) Facility Operations Manual; FINAL

International Nuclear Information System (INIS)

IRWIN, J.J.

1999-01-01

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-553, Spent Nuclear Fuel Project Final Safety Analysis Report Annex B-Cold Vacuum Drying Facility. The HNF-SD-SNF-DRD-002, 1999, Cold Vacuum Drying Facility Design Requirements, Rev. 4, and the CVDF Final Design Report. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence and references to the CVDF System Design Descriptions (SDDs). This manual has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

Summary of the ITER final design report. July 2001

International Nuclear Information System (INIS)

2001-01-01

This document is a summary of the ITER final design report foreseen during the current, Engineering Design Activities (EDA), phase of the ITER project. The report presents the results of collaborative design and supporting technical work undertaken by the ITER Joint Central team (JCT) and the Home Teams (HT) of the parties to the agreement on co-operation in the Engineering Design Activities for ITER (the ITER EDA Agreement). This report marks the achievement of the full technical scope of activities indicated in the ITER EDA Agreement, with a final design which meets the programmatic objective defined in the Agreement and satisfies detailed scientific, technical and costing objectives set by ITER Council in 1998

UMTRA project: Canonsburg final design

International Nuclear Information System (INIS)

Thiers, G.R.; Guros, F.B.; Smith, E.S.

1984-01-01

Final design for on-site stabilization of over 300,000 cubic yards of abandoned mill tailings in Canonsburg, Pennsylvania, is being completed this Fall. This paper describes design criteria, design procedures, and difficulties encountered for the following required elements: 1. Encapsulation cell; 2. Durability of erosion protection material; 3. Flood control berm; 4. Sedimentation pond; 5. Wastewater treatment plant. The 70,000 cubic yards of the tailings for which radiation levels exceed 100 picocuries per gram will be placed on a 2-ft-thick compacted clay liner and encased by a 3-ft-thick compacted clay cover. The remaining tailings will be covered with at least two feet of clay to prevent radon escape and to reduce rainfall infiltration. Erosion protection will be provided for the encapsulation cell, the drainage swales, and from potential meandering of nearby Chartiers Creek

75 FR 50711 - Approval and Promulgation of Air Quality Implementation Plans; Ohio; Final Approval and...

Science.gov (United States)

2010-08-17

... operations under OAC 3745-21-09(U)(2)(f). For administrative convenience, in a separate rulemaking published... conditional approval of portions of OAC rule 3745-21-09. You can learn more information about the rule... implementing a Federal Standard. National Technology Transfer Advancement Act In reviewing state submissions...

78 FR 45152 - Approval and Promulgation of Implementation Plans and Designation of Areas; North Carolina...

Science.gov (United States)

2013-07-26

... North Carolina SIP meets the requirements of section 182(b)(5) applicable for purposes of redesignation...] Approval and Promulgation of Implementation Plans and Designation of Areas; North Carolina; Redesignation... supplemented on March 28, 2013, the State of North Carolina, through the North Carolina Department of...

A RECIPE FOR LINEAR COLLIDER FINAL FOCUS SYSTEM DESIGN

International Nuclear Information System (INIS)

Seryi, Andrei

2003-01-01

The design of Final Focus systems for linear colliders is challenging because of the large demagnifications needed to produce nanometer-sized beams at the interaction point. Simple first- and second-order matrix matching have proven insufficient for this task, and minimization of third- and higher-order aberrations is essential. An appropriate strategy is required for the latter to be successful. A recipe for Final Focus design, and a set of computational tools used to implement this approach, are described herein. An example of the use of this procedure is given

Final Exam Weighting as Part of Course Design

Directory of Open Access Journals (Sweden)

Matthew Franke

2018-03-01

Full Text Available The weighting of a final exam or a final assignment is an essential part of course design that is rarely discussed in pedagogical literature. Depending on the weighting, a final exam or assignment may provide unequal benefits to students depending on their prior performance in the class. Consequently, uncritical grade weighting can discount student learning, by ensuring that improved mastery of material at the semester’s end is not reflected in the course grade. Problems related to several common final exam weights are explored, as are potential solutions to unequal student outcomes made possible by uncritical grade weighting. Ultimately, this essay argues that choosing a weight for a final exam or a final assignment determines what types of student success ought to be possible in the class; therefore, instructors should assign exam weights intentionally, being fully aware of the potential benefits and problems of the weights that they choose.

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

International Nuclear Information System (INIS)

Komann, Steffen; Groeke, Carsten; Droste, Bernhard

2013-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2013-07-01

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

Judicial problems in connection with preliminary decision and construction design approval in nuclear licensing procedures

International Nuclear Information System (INIS)

Schmieder, K.

1977-01-01

Standardization in nuclear engineering makes two demands on a legal instrument which is to make this standardization possible and which is to promote standardization in the nuclear licensing practice: On the basis of just one licence for a constructional part or a component, its applicability in any number of subsequent facility licensing procedures has to be warranted, and by virtue of its binding effect, standardization has to create a sufficiently big confidence protection with manufacturers, constructioneers and operators to offer sufficiently effective incentives for standardization. The nuclear preliminary decision pursuant to section 7 a of the Atomic Energy Act in the form of the component preliminary decision appears to be unsuitable as a legal instrument for standardization, as the preliminary decision refers exclusively to the construction of a concrete facility. For standardization in reactor engineering, the construction design approval appears to be basically the proper legal instrument on account of its legal structure as well as its economic effect. Its binding effect encouters a limitation with regard to third parties in so far that this limitation could question again the binding effect in a subsequent site-dependent nuclear licence procedure. The legal structure of the extent of the binding effect, which is decisive for the suitability of the construction design approval, lies with the legislator. The following questions have to be regulated: Ought the applicant to have a legal claim on the granting of a construction design approval, or ought it to be at the discretion of the authorities, and secondly, the extent of the binding effect in terms of time on the basis of the fixation of a time limit, or on the basis of the possibility of subsequent conditions to be imposed, or the revocation. (orig./HP) [de

REVIEW OF NRC APPROVED DIGITAL CONTROL SYSTEMS ANALYSIS

International Nuclear Information System (INIS)

Markman, D.W.

1999-01-01

Preliminary design concepts for the proposed Subsurface Repository at Yucca Mountain indicate extensive reliance on modern, computer-based, digital control technologies. The purpose of this analysis is to investigate the degree to which the U. S. Nuclear Regulatory Commission (NRC) has accepted and approved the use of digital control technology for safety-related applications within the nuclear power industry. This analysis reviews cases of existing digitally-based control systems that have been approved by the NRC. These cases can serve as precedence for using similar types of digitally-based control technologies within the Subsurface Repository. While it is anticipated that the Yucca Mountain Project (YMP) will not contain control systems as complex as those required for a nuclear power plant, the review of these existing NRC approved applications will provide the YMP with valuable insight into the NRCs review process and design expectations for safety-related digital control systems. According to the YMP Compliance Program Guidance, portions of various NUREGS, Regulatory Guidelines, and nuclear IEEE standards the nuclear power plant safety related concept would be applied to some of the designs on a case-by-case basis. This analysis will consider key design methods, capabilities, successes, and important limitations or problems of selected control systems that have been approved for use in the Nuclear Power industry. An additional purpose of this analysis is to provide background information in support of further development of design criteria for the YMP. The scope and primary objectives of this analysis are to: (1) Identify and research the extent and precedence of digital control and remotely operated systems approved by the NRC for the nuclear power industry. Help provide a basis for using and relying on digital technologies for nuclear related safety critical applications. (2) Identify the basic control architecture and methods of key digital control

77 FR 35862 - Approval and Promulgation of Implementation Plans; State of Florida: New Source; Review...

Science.gov (United States)

2012-06-15

...: Final rule. SUMMARY: EPA is taking final action to approve changes to the Florida State Implementation... taking final action to approve changes to the Florida SIP such that it is consistent with federal.... EPA notes that Florida's October 19, 2007, SIP submission makes clarifying changes to rule 62-212.400...

Final Design Report for the RH LLW Disposal Facility (RDF) Project, Revision 3

International Nuclear Information System (INIS)

Austad, Stephanie Lee

2015-01-01

The RH LLW Disposal Facility (RDF) Project was designed by AREVA Federal Services (AFS) and the design process was managed by Battelle Energy Alliance (BEA) for the Department of Energy (DOE). The final design report for the RH LLW Disposal Facility Project is a compilation of the documents and deliverables included in the facility final design.

Final design of the beam source for the MITICA injector

Energy Technology Data Exchange (ETDEWEB)

Marcuzzi, D., E-mail: diego.marcuzzi@igi.cnr.it; Agostinetti, P.; Dalla Palma, M.; De Muri, M.; Chitarin, G.; Gambetta, G.; Marconato, N.; Pasqualotto, R.; Pavei, M.; Pilan, N.; Rizzolo, A.; Serianni, G.; Toigo, V.; Trevisan, L.; Visentin, M.; Zaccaria, P.; Zaupa, M. [Consorzio RFX, Corso Stati Uniti, 4, I-35127 Padova (Italy); Boilson, D.; Graceffa, J.; Hemsworth, R. S. [ITER Organization, Route de Vinon-sur-Verdon, 13067 St Paul Lez Durance (France); and others

2016-02-15

The megavolt ITER injector and concept advancement experiment is the prototype and the test bed of the ITER heating and current drive neutral beam injectors, currently in the final design phase, in view of the installation in Padova Research on Injector Megavolt Accelerated facility in Padova, Italy. The beam source is the key component of the system, as its goal is the generation of the 1 MeV accelerated beam of deuterium or hydrogen negative ions. This paper presents the highlights of the latest developments for the finalization of the MITICA beam source design, together with a description of the most recent analyses and R&D activities carried out in support of the design.

K Basin sludge packaging design criteria (PDC) and safety analysis report for packaging (SARP) approval plan

International Nuclear Information System (INIS)

Brisbin, S.A.

1996-01-01

This document delineates the plan for preparation, review, and approval of the Packaging Design Crieteria for the K Basin Sludge Transportation System and the Associated on-site Safety Analysis Report for Packaging. The transportation system addressed in the subject documents will be used to transport sludge from the K Basins using bulk packaging

Safety-evaluation report related to the final design of the Standard Nuclear Steam Supply Reference System - CESSAR System 80. Docket No. STN 50-470

International Nuclear Information System (INIS)

1983-03-01

Supplement No. 1 to the Safety Evaluation Report for the application filed by Combustion Engineering, Inc. for a Final Design Approval for the Combustion Engineering Standard Safety Analysis Report (STN 50-470) has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. The purpose of this supplement is to update the Safety Evaluation by providing: (1) the evaluation of additional information submitted by the applicant since the Safety Evaluation Report was issued, (2) the evaluation of the matters the staff had under review when the Safety Evaluation Report was issued, and (3) the response to comments made by the Advisory Committee on Reactor Safeguards

Mod-5A wind turbine generator program design report. Volume 3: Final design and system description, book 2

Science.gov (United States)

1984-01-01

The design, development and analysis of the 7.3MW MOD-5A wind turbine generator is documented. The report is divided into four volumes: Volume 1 summarizes the entire MOD-5A program, Volume 2 discusses the conceptual and preliminary design phases, Volume 3 describes the final design of the MOD-5A, and Volume 4 contains the drawings and specifications developed for the final design. Volume 3, book 2 describes the performance and characteristics of the MOD-5A wind turbine generator in its final configuration. The subsystem for power generation, control, and instrumentation subsystems is described in detail. The manufacturing and construction plans, and the preparation of a potential site on Oahu, Hawaii, are documented. The quality assurance and safety plan, and analyses of failure modes and effects, and reliability, availability and maintainability are presented.

Status of system 80+ design certification

International Nuclear Information System (INIS)

Matzie, R.A.

1992-01-01

This paper reports that 1991 was a year of great progress in the design certification process for ABB Combustion Engineering Nuclear Power's 1300 MWe evolutionary advanced light water reactor (ALWR) plant, System 80+. As the next generation of nuclear power plants move toward final design approval by the U.S. Nuclear Regulatory Commission (NRC), elements of the design process that emphasize operation and maintenance have become the focus. For System 80+, licensing under the new design certification process is now concentrated on operational support, human engineering, plant layout, and computer-aided engineering

Guidance for package approvals in the United Kingdom

International Nuclear Information System (INIS)

Morgan-Warren, E.J.

2004-01-01

Approval is required under the transport regulations for a wide range of package designs and operations, and applications for competent authority approval and validation are received from many sources, both in the UK and overseas. To assist package designers and applicants for approval, and to promote consistency in applications and their assessment, the UK Department for Transport issues guidance on the interpretation of the transport regulations and the requirements of an application for approval and its supporting safety case. The general guidance document, known as the Guide to an Application for UK Competent Authority Approval of Radioactive Material in Transport, has been issued for many years and updated to encompass the provisions of each successive edition of the IAEA transport regulations. The guide has been referred to in a number of international fora, including PATRAM, and was cited as a 'good practice' in the report of the IAEA TRANSAS appraisal of the UK in 2002. Specialist guides include the Guide to the Suitability of Elastomeric Seal Materials, which is the subject of a separate paper in this conference, and the Guide to the Approval of Freight Containers as Types IP-2 and IP-3 Packages. This paper discusses the guidance material and summarises the administrative and technical information required in support of applications for approval of package designs, special form and low-dispersible radioactive materials, shipments, special arrangements, modifications and validations. (author)

Final safety evaluation report related to the certification of the System 80+ design (Docket No. 52-002). Volume 1, Chapters 1--14

International Nuclear Information System (INIS)

1994-08-01

This final safety evaluation report (FSER) documents the technical review of the System 80+ standard design by the US Nuclear Regulatory Commission (NRC) staff. The application for the System 80+ design was submitted by Combustion Engineering, Inc., now Asea Brown Boveri-Combustion Engineering (ABB-CE) as an application for design approval and subsequent design certification pursuant to 10 CFR section 52.45. System 80+ is a pressurized water reactor with a rated power of 3914 megawatts thermal (MWt) and a design power of 3992 MWt at which accidents are analyzed. Many features of the System 80+ are similar to those of Abb-CE's System 80 design from which it evolved. Unique features of the System 80+ design included: a large spherical, steel containment; an in-containment refueling water storage tank; a reactor cavity flooding system, hydrogen ignitors, and a safety depressurization system for severe accident mitigation; a combustion gas turbine for an alternate ac source; and an advanced digitally based control room. On the basis of its evaluation and independent analyses, the NRC staff concludes that ABB-CE's application for design certification meets the requirements of Subpart B of 10 CFR Part 52 that are applicable and technically relevant to the System 80+ standard design. This document, Volume 1, contains Chapters 1 through 14 of this report

Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 2003 ed

International Nuclear Information System (INIS)

2003-10-01

This is the fourteenth annual report being published by the Secretariat of the International Atomic Energy Agency since implementing its database on package approval certificates (PACKTRAM) at the recommendation of the Transport Safety Standards Committee (TRANSSC). It supersedes IAEA-TECDOC-1302 'Directory of National Competent Authorities' Approval Certificates for Package Design, Special Form Material and Shipment of Radioactive Material, 2002 Edition'. Through the database, the Secretariat collects administrative and technical information provided by the issuing competent authority about package approval certificates. Such data are used mainly by national competent authorities and port and customs officials to assist in regulating radioactive material movements in their country, and also by manufacturers and shippers of radioactive material. The database carries information on extant certificates and those that expired within the last complete calendar year. The PACKTRAM database only contains information that has been provided to the IAEA. The data are not complete nor guaranteed to be accurate. If detailed information is required, the original package approval certificates must be consulted. If information is required about package approval certificates that are not contained in the database, the issuing competent authority must be consulted

Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 2003 ed

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-10-01

This is the fourteenth annual report being published by the Secretariat of the International Atomic Energy Agency since implementing its database on package approval certificates (PACKTRAM) at the recommendation of the Transport Safety Standards Committee (TRANSSC). It supersedes IAEA-TECDOC-1302 'Directory of National Competent Authorities' Approval Certificates for Package Design, Special Form Material and Shipment of Radioactive Material, 2002 Edition'. Through the database, the Secretariat collects administrative and technical information provided by the issuing competent authority about package approval certificates. Such data are used mainly by national competent authorities and port and customs officials to assist in regulating radioactive material movements in their country, and also by manufacturers and shippers of radioactive material. The database carries information on extant certificates and those that expired within the last complete calendar year. The PACKTRAM database only contains information that has been provided to the IAEA. The data are not complete nor guaranteed to be accurate. If detailed information is required, the original package approval certificates must be consulted. If information is required about package approval certificates that are not contained in the database, the issuing competent authority must be consulted.

Directory of national competent authorities' approval certificates for package design and shipment of radioactive material

International Nuclear Information System (INIS)

1990-04-01

The authorization of packages and shipments of radioactive materials are issued in the form of certificates by the national competent authority of the IAEA Member State in which the package is designed or from which a shipment originates, and may be validated or endorsed by the corresponding authority of other Member States as the need arises. This directory summarizes in tabular form the key information on existing package approval certificates contained in PACKTRAM database. 5 tabs

42 CFR 137.365 - What is the procedure for the Secretary's review and approval of project planning and design...

Science.gov (United States)

2010-10-01

... SERVICE, DEPARTMENT OF HEALTH AND HUMAN SERVICES TRIBAL SELF-GOVERNANCE Construction Roles of the...-Governance Tribe? (a) The Secretary shall review and approve planning documents to ensure compliance with... design documents for general compliance with requirements of the construction project agreement. (b) The...

8 CFR 207.6 - Control over approved refugee numbers.

Science.gov (United States)

2010-01-01

... 8 Aliens and Nationality 1 2010-01-01 2010-01-01 false Control over approved refugee numbers. 207... ADMISSION OF REFUGEES § 207.6 Control over approved refugee numbers. Current numerical accounting of approved refugees is maintained for each special group designated by the President. As refugee status is...

Final safety evaluation report related to the certification of the System 80{sup +} design (Docket No. 52-002). Volume 1, Chapters 1--14

Energy Technology Data Exchange (ETDEWEB)

1994-08-01

This final safety evaluation report (FSER) documents the technical review of the System 80+ standard design by the US Nuclear Regulatory Commission (NRC) staff. The application for the System 80+ design was submitted by Combustion Engineering, Inc., now Asea Brown Boveri-Combustion Engineering (ABB-CE) as an application for design approval and subsequent design certification pursuant to 10 CFR {section} 52.45. System 80+ is a pressurized water reactor with a rated power of 3914 megawatts thermal (MWt) and a design power of 3992 MWt at which accidents are analyzed. Many features of the System 80+ are similar to those of Abb-CE`s System 80 design from which it evolved. Unique features of the System 80+ design included: a large spherical, steel containment; an in-containment refueling water storage tank; a reactor cavity flooding system, hydrogen ignitors, and a safety depressurization system for severe accident mitigation; a combustion gas turbine for an alternate ac source; and an advanced digitally based control room. On the basis of its evaluation and independent analyses, the NRC staff concludes that ABB-CE`s application for design certification meets the requirements of Subpart B of 10 CFR Part 52 that are applicable and technically relevant to the System 80+ standard design. This document, Volume 1, contains Chapters 1 through 14 of this report.

Final design review report for K basin dose reduction project

International Nuclear Information System (INIS)

Blackburn, L.D.

1996-01-01

The strategy for reducing radiation dose originating from radionuclides absorbed in the K East Basin concrete is to raise the pool water level to provide additional shielding. This report documents a final design review for cleaning/coating basin walls and modifying other basin components where appropriate. The conclusion of this review was that the documents developed constitute an acceptable design for the Dose Reduction Project

Final safety evaluation report related to the certification of the System 80+ design (Docket No. 52-002). Volume 2, Chapters 15--22 and appendices

International Nuclear Information System (INIS)

1994-08-01

This final safety evaluation report (FSER) documents the technical review of the System 80+ standard design by the US Nuclear Regulatory Commission (NRC) staff. The application for the system 80+ design was submitted by Combustion Engineering, Inc., now Asea Brown Boveri-Combustion Engineering (ABB-CE) as an application for design approval and subsequent design certification pursuant to 10 CFR section 52.45. System 80+ is a pressurized water reactor with a rated power of 3914 megawatts thermal (MWt) and a design power of 3992 MWt at which accidents are analyzed. Many features of the System 80+ are similar to those of ABB-CE's System 80 design from which it evolved. Unique features of the System 80+ design include: a large spherical, steel containment; an in-containment refueling water storage tank; a reactor cavity flooding system, hydrogen ignitors and a safety depressurization system for severe accident mitigation; a combustion gas turbine for an alternate ac source; and an advanced digitally based control room. On the basis of its evaluation and independent analyses, the NRC staff concludes that ABB-CE's application for design certification meets the requirements of Subpart B of 10 CFR Part 52 that are applicable and technically relevant to the System 80+ standard design. This document, Volume 2, contains Chapters 15 through 22 and Appendices A through E

Final design of kaon beam K2 at KEK

International Nuclear Information System (INIS)

Kurokawa, Shin-ichi; Yamamoto, Akira.

1977-09-01

Final design of the 2.3 GeV/c kaon beam K2 is given. The K2 beam starts from the production target in slow extracted beam. Momentum range is 1 GeV/c through 2.3 GeV/c. Nominal total beam length is 27.9 m and solid-angle momentum acceptance is 6.25 msr%ΔP/P. Using a platinum target of diameter 3 mm and length 6 cm, 2.0 GeV/c beam fluxes of 1.0 x 10 6 K + and 5.2 x 10 5 K - per 10 12 13 GeV/c incident protons are expected at the final focus. (auth.)

Final design of the neutral beam lines for the Tokamak Fusion Test Reactor

International Nuclear Information System (INIS)

Pittenger, L.C.; Valby, L.E.; Stone, R.R.; Pedrotti, L.R.; Denhoy, B.; Yoard, R.

1979-01-01

Final design of the neutral beam lines for TFTR has been completed. A prototype has been assembled at Lawrence Berkeley Laboratory and is undergoing testing as part of the Neutral Beam System Test Facility (NBSTF). The final neutral beam line (NBL) configuration differs in several details from that previously reported upon; certain components have been added; and testing of the cryopump system has led to some design simplification. It is these developments which are reported herein

Final safety evaluation report related to the certification of the System 80{sup +} design (Docket No. 52-002). Volume 2, Chapters 15--22 and appendices

Energy Technology Data Exchange (ETDEWEB)

1994-08-01

This final safety evaluation report (FSER) documents the technical review of the System 80+ standard design by the US Nuclear Regulatory Commission (NRC) staff. The application for the system 80+ design was submitted by Combustion Engineering, Inc., now Asea Brown Boveri-Combustion Engineering (ABB-CE) as an application for design approval and subsequent design certification pursuant to 10 CFR {section} 52.45. System 80+ is a pressurized water reactor with a rated power of 3914 megawatts thermal (MWt) and a design power of 3992 MWt at which accidents are analyzed. Many features of the System 80+ are similar to those of ABB-CE`s System 80 design from which it evolved. Unique features of the System 80+ design include: a large spherical, steel containment; an in-containment refueling water storage tank; a reactor cavity flooding system, hydrogen ignitors and a safety depressurization system for severe accident mitigation; a combustion gas turbine for an alternate ac source; and an advanced digitally based control room. On the basis of its evaluation and independent analyses, the NRC staff concludes that ABB-CE`s application for design certification meets the requirements of Subpart B of 10 CFR Part 52 that are applicable and technically relevant to the System 80+ standard design. This document, Volume 2, contains Chapters 15 through 22 and Appendices A through E.

78 FR 28503 - Approval and Promulgation of Air Quality Implementation Plans; Indiana; Lake and Porter Counties...

Science.gov (United States)

2013-05-15

...: FRL-9812-4] Approval and Promulgation of Air Quality Implementation Plans; Indiana; Lake and Porter...). ACTION: Direct final rule. SUMMARY: EPA is approving Indiana's request to revise the Lake and Porter... approving new MOVES2010a-based budgets for the Lake and Porter County, Indiana 1997 8-hour ozone maintenance...

Final analysis and design of a thermal protection system for 8-foot HTST combustor

Science.gov (United States)

Moskowitz, S.

1973-01-01

The cylindrical shell combustor with T-bar supports in the 8-foot HTST at the NASA-Langley Research Center encountered vibratory fatigue cracking over a period of 50-250 tunnel tests within a limited range of the required operating envelope. A preliminary design study provided several suitable thermal protection system designs for the combustor, one of which was a two-pass regenerative type air-cooled omega-shaped segment liner. A final design layout of the omega segment liner was prepared and analyzed for steady-state and transient conditions. The design of a support system for the fuel spray bar assembly was also included. Detail drawings suitable for fabrication purposes were also prepared. Liner design problems defined during the preliminary study included (1) the ingress of gas into the attachment bulb section of the omega segment, (2) the large thermal gradient along the leg of the omega bulb attachment section and, (3) the local peak metal temperature at the radius between the liner ID and the leg of the bulb attachment. These were resolved during the final design task. Analyses of the final design of the omega segment liner indicated that all design goals were met and the design provided the capability of operating over the required test envelope with a life expectancy substantially above the goal of 1500 cycles.

77 FR 62433 - Hazard Communication Standard; Approval of Information Collection Requirements

Science.gov (United States)

2012-10-15

... safety data sheets (SDSs). The final standard harmonizes the U.S. system with international norms and as.... ACTION: Final rule; notice of the Office of Management and Budget's (OMB) approval of information... FURTHER INFORMATION CONTACT: Theda Kenney or Todd Owen, Directorate of Standards and Guidance, OSHA, U.S...

A conceptual design of Final Focus Systems for linear colliders

International Nuclear Information System (INIS)

Brown, K.L.

1987-06-01

Linear colliders are a relatively recent development in the evolution of particle accelerators. This report discusses some of the approaches that have been considered for the design of Final Focus Systems to demagnify the beam exiting from a linac to the small size suitable for collisions at the interaction point. The system receiving the most attention is the one adopted for the SLAC Linear Collider. However, the theory and optical techniques discussed should be applicable to the design efforts for future machines

Schedules of Controlled Substances: Placement of FDA-Approved Products of Oral Solutions Containing Dronabinol [(-)-delta-9-transtetrahydrocannabinol (delta-9-THC)] in Schedule II. Interim final rule, with request for comments.

Science.gov (United States)

2017-03-23

On July 1, 2016, the U.S. Food and Drug Administration (FDA) approved a new drug application for Syndros, a drug product consisting of dronabinol [(-)-delta-9-trans-tetrahydrocannabinol (delta-9-THC)] oral solution. Thereafter, the Department of Health and Human Services (HHS) provided the Drug Enforcement Administration (DEA) with a scheduling recommendation that would result in Syndros (and other oral solutions containing dronabinol) being placed in schedule II of the Controlled Substances Act (CSA). In accordance with the CSA, as revised by the Improving Regulatory Transparency for New Medical Therapies Act, DEA is hereby issuing an interim final rule placing FDA-approved products of oral solutions containing dronabinol in schedule II of the CSA.

Report of the Design Approval and the Safety Issues of the Ion Accelerator for Manufacturing

Energy Technology Data Exchange (ETDEWEB)

Min, Yi Sub; Lee, Chan Young [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2013-05-15

The application of ion implantation technology has been extended to the field of semiconductor, as well as of metals, ceramics and polymers. A change in the characteristics of the surface that is required in industries is various. To manufacture these devices which are by requirements of industrial, anyone must be licensed by nuclear law; producing permit. And that device must be certified to safety through the design approval. For the first time in domestic, Korea Multipurpose Accelerator Complex (KOMAC) has finished the producing facility inspection as well as the producing permit in August 2012 that can produce four types of radiation generator(RG)

HyApproval - Handbook for the approval of hydrogen refuelling stations - First preliminary achievements

Energy Technology Data Exchange (ETDEWEB)

Wurster, R.; Vandendungen, G.; Guichard, J.; Molag, M.; Barron, J.; Reijalt, M.; Hill, H.J.; Landinger, H.

2007-05-15

The EU-funded project HyApproval [www.hyapproval.org] aims at developing a universal Handbook to facilitate the approval process of Hydrogen Refuelling Stations (HRS) in Europe. The main goal of the HyApproval partnership with 22 partners from Europe and one each from China, Japan and the USA is to provide a Handbook of technical and regulatory requirements to assist authorisation officials, companies and organisations in the safe implementation and operation of HRS. Achievements during the first 15 months: analyses of HRS technology concepts and of equipment and safety distances/ Intermediate Design Paper/ Regulations, Codes and Standards (RCS) review and comparison/ first Handbook draft and first review sessions with HySafe experts/ safety matrix/ identification of accident scenarios/ agreement on safety documentation/ critical review of reliability data from collections and risk studies/ risk assessment (RA) criteria definition and RA/ matrix of acceptability and awareness levels/ database of Fire Associations and First Responders/ calendar of hydrogen events/ general description of CGH{sub 2} interfaces. (au)

Request for approval, vented container annual release fraction; FINAL

International Nuclear Information System (INIS)

HILL, J.S.

1999-01-01

In accordance with the approval conditions for Modification to the Central Waste Complex (CWC) Radioactive Air Emissions Notice of Construction (NOC). dated August 24,1998, a new release fraction has been developed for submittal to the Washington State Department of Health (WDOH). The proposed annual release fraction of 2.50 E-14 is proposed for use in future NOCs involving the storage and handling operations associated with vented containers on the Hanford Site. The proposed annual release fraction was the largest release fraction calculated from alpha measurements of the NucFil filters from 10 vented containers consisting of nine 55-gallon drums and one burial box with dimensions of 9.3 x 5.7 x 6.4 feet. An annual release fraction of 2.0 E-09 was used in the modification to the CWC radioactive air emissions NOC. This study confirmed that the release fraction used in the CWC radioactive air emissions NOC was conservative

SIAM Conference on Geometric Design and Computing. Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

None

2002-03-11

The SIAM Conference on Geometric Design and Computing attracted 164 domestic and international researchers, from academia, industry, and government. It provided a stimulating forum in which to learn about the latest developments, to discuss exciting new research directions, and to forge stronger ties between theory and applications. Final Report

A drug's life: the pathway to drug approval.

Science.gov (United States)

Keng, Michael K; Wenzell, Candice M; Sekeres, Mikkael A

2013-10-01

In the United States, drugs and medical devices are regulated by the US Food and Drug Administration (FDA). A drug must undergo rigorous testing prior to marketing to and medical use by the general public. The FDA grants marketing approval for drug products based on a comprehensive review of safety and efficacy data. This review article explains the history behind the establishment of the FDA and examines the historical legislation and approval processes for drugs, specifically in the fields of medical oncology and hematology. The agents imatinib (Gleevec, Novartis) and decitabine (Dacogen, Eisai) are used to illustrate both the current FDA regulatory process-specifically the orphan drug designation and accelerated approval process-and why decitabine failed to gain an indication for acute myeloid leukemia. The purpose and construct of the Oncologic Drugs Advisory Committee are also discussed, along with examples of 2 renal cell cancer drugs-axitinib (Inlyta, Pfizer) and tivozanib-that used progression-free survival as an endpoint. Regulatory approval of oncology drugs is the cornerstone of the development of new treatment agents and modalities, which lead to improvements in the standard of cancer care. The future landscape of drug development and regulatory approval will be influenced by the new breakthrough therapy designation, and choice of drug will be guided by genomic insights.

77 FR 31727 - Approval and Promulgation of Air Quality Implementation Plans; Illinois; Small Container...

Science.gov (United States)

2012-05-30

... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 52 [EPA-R05-OAR-2012-0073; FRL 9677-3] Approval and Promulgation of Air Quality Implementation Plans; Illinois; Small Container Exemption From VOC Coating Rules...), direct final rule approving a revision to the Illinois SIP that added a ``small container exemption'' for...

Reference Design of the Mu2e Detector Solenoid

CERN Document Server

Feher, S; Brandt,, J; Cheban, S; Coleman, R; Dhanaraj, N; Fang, I; Lamm, M; Lombardo, V; Lopes, M; Miller, J; Ostojic, R ,; Orris, D; Page, T; Peterson, T; Tang, Z; Wands, R

2014-01-01

The Mu2e experiment at Fermilab has been approved by the Department of Energy to proceed developing the preliminary design. Integral to the success of Mu2e is the superconducting solenoid system. One of the three major solenoids is the Detector Solenoid that houses the stopping target and the detectors. The goal of the Detector Solenoid team is to produce detailed design specifications that are sufficient for vendors to produce the final design drawings, tooling and fabrication procedures and proceed to production. In this paper we summarize the Reference Design of the Detector Solenoid.

5 CFR 7401.102 - Prior approval for outside employment.

Science.gov (United States)

2010-01-01

... STANDARDS OF ETHICAL CONDUCT FOR EMPLOYEES OF THE MERIT SYSTEMS PROTECTION BOARD § 7401.102 Prior approval... written approval from the employee's supervisor and the concurrence of the Designated Agency Ethics... name of the employer or organization; (ii) The nature of the legal activity or other work to be...

Passive solar commercial buildings: design assistance and demonstration program. Phase 1. Final report

Energy Technology Data Exchange (ETDEWEB)

None

1981-01-26

The final design of the Mount Airy Public Library is given. Incremental passive design costs are discussed. Performance and economic analyses are made and the results reported. The design process is thoroughly documented. Considerations discussed are: (1) building energy needs; (2) site energy potentials, (3) matching energy needs with site energy potentials, (4) design indicators for best strategies and concepts, (5) schematic design alternatives, (6) performance testing of the alternatives, (7) design selection, and (8) design development. Weather data and Duke Power electric rates are included. (LEW)

76 FR 36875 - Approval and Promulgation of Implementation Plans; South Carolina: Prevention of Significant...

Science.gov (United States)

2011-06-23

... requirements pertaining to NO X as an ozone precursor into the South Carolina SIP. b. NSR PM2.5 Rule With...-0958-201119; FRL-9322- 6] Approval and Promulgation of Implementation Plans; South Carolina: Prevention.... SUMMARY: EPA is taking final action to approve three revisions to the South Carolina State Implementation...

Sixty-five-year old final clarifier performance rivals that of modern designs.

Science.gov (United States)

Barnard, James L; Kunetz, Thomas E; Sobanski, Joseph P

2008-01-01

The Stickney plant of the Metropolitan Wastewater Reclamation District of Greater Chicago (MWRDGC), one of the largest wastewater treatment plants in the world, treats an average dry weather flow of 22 m3/s and a sustained wet weather flow of 52 m3/s that can peak to 63 m3/s. Most of the inner city of Chicago has combined sewers, and in order to reduce pollution through combined sewer overflows (CSO), the 175 km Tunnel and Reservoir Plan (TARP) tunnels, up to 9.1 m in diameter, were constructed to receive and convey CSO to a reservoir from where it will be pumped to the Stickney treatment plant. Pumping back storm flows will result in sustained wet weather flows over periods of weeks. Much of the success of the plant will depend on the ability of 96 circular final clarifiers to produce an effluent of acceptable quality. The nitrifying activated sludge plant is arranged in a plug-flow configuration, and some denitrification takes place as a result of the high oxygen demand in the first pass of the four-pass aeration basins that have a length to width ratio of 18:1. The SVI of the mixed liquor varies between 60 and 80 ml/g. The final clarifiers, which were designed by the District's design office in 1938, have functioned for more than 65 years without major changes and are still producing very high-quality effluent. This paper will discuss the design and operation of these final clarifiers and compare the design with more modern design practices. (c) IWA Publishing 2008.

Preliminary Design Progress of the HCCR TBM for ITER testing

Energy Technology Data Exchange (ETDEWEB)

Lee, Dong Won; Park, Sung Dae; Kim, Dong Jun; Jin, Hyung Gon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Ahn, Mu-Young [National Fusion Research Institute, Daejeon (Korea, Republic of)

2016-10-15

Korea has designed a helium cooled ceramic reflector (HCCR) test blanket module (TBM) including the TBM-shield, which is called the TBM-set, to be tested in ITER, a Nuclear Facility INB-174. Through the conceptual design review (CDR), its design integrity was successfully demonstrated at the conceptual design level at various loads. After CD approval, preliminary design (PD) was started and the progress is introduced in the present study. After PD review and approval, final design and then fabrication will be started. The main purpose of PD is to design the TBM-set according to the fabrication aspect and more detailed design for interfaces with ITER machine, such as installed TBM port plug and frame. With these considering, PD of TBM-set was started. PD for HCCR TBM has been performed (so far v0.24) from the CD model. FW, BZ, SW, TES/NAS, BM, and connecting support design were performed through the analyses, if necessary. The manufacturability was the main concern for PD model development. Thermal hydraulic analysis will be performed to evaluate the temperature and pressure drop in TBM-set. The structural integrity of TBM-set will be confirmed with combined various loads condition.

46 CFR 160.077-6 - Approval procedures.

Science.gov (United States)

2010-10-01

... Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) EQUIPMENT, CONSTRUCTION, AND MATERIALS... to the particular design or that by design or construction the PFD cannot fail the test. (c) Alternative Requirements. A PFD that does not meet requirements in this subpart may still be approved if the...

How does sustainability certification affect the design process? Mapping final design projects at an architectural office

DEFF Research Database (Denmark)

Landgren, Mathilde; Jensen, Lotte Bjerregaard

2017-01-01

process and informing the industry of them. This has led to optimised design processes such as Integrated Energy Design, in which many decisions related to energy consumption and indoor climate are made in the early design stages. The current tendency is to use an expanded notion of sustainability......, derived from the sustainability certification system itself, and to apply it even in the early design process. This perspective emphasises all phases of the life cycle of a building. The goal of the present study was to map how a Danish architectural office approached sustainability in the projects......The context of the study is the very strict regulation of energy consumption for operating buildings in Denmark. It is difficult to meet the requirements by system optimisation in the final design phase, so recent research has focused on ways of meeting the target by adapting the whole design...

2016 in review: FDA approvals of new molecular entities.

Science.gov (United States)

Griesenauer, Rebekah H; Kinch, Michael S

2017-11-01

An overview of drugs approved by FDA in 2016 reveals dramatic disruptions in long-term trends. The number of new molecular entities (NMEs) dropped, reflecting the lowest rate of small-molecule approvals observed in almost five decades. In addition, the pace of industry consolidation slowed substantially. The impact of mergers and acquisitions decreased the total number of organizations with past approval experience and continued research and development (R&D) activities to 102, divided evenly between more established pharmaceutical and newer biotechnology companies. Despite these substantial differences, the industry continued to pursue regulatory incentives, as evidenced by a continued increase in the fraction of NMEs approved using an orphan or priority designation, and almost all oncology drugs approved in 2016 utilized these mechanisms. Copyright © 2017 Elsevier Ltd. All rights reserved.

Final turbine and test facility design report Alden/NREC fish friendly turbine

Energy Technology Data Exchange (ETDEWEB)

Cook, Thomas C. [Alden Research Lab., Holden, MA (United States); Cain, Stuart A. [Alden Research Lab., Holden, MA (United States); Fetfatsidis, Paul [Alden Research Lab., Holden, MA (United States); Hecker, George E. [Alden Research Lab., Holden, MA (United States); Stacy, Philip S. [Alden Research Lab., Holden, MA (United States)

2000-09-01

The final report provides an overview of the Alden/NREC Fish Friendly turbine design phase, turbine test plan, preliminary test results, costs, schedule, and a hypothetical application at a real world project.

78 FR 52429 - New Animal Drugs; Withdrawal of Approval of New Animal Drug Applications; Diethylcarbamazine...

Science.gov (United States)

2013-08-23

... 558 [Docket No. FDA-2013-N-0839] New Animal Drugs; Withdrawal of Approval of New Animal Drug...: Final rule. SUMMARY: The Food and Drug Administration (FDA) is amending the animal drug regulations to reflect the withdrawal of approval of three new animal drug applications (NADAs) at the sponsors' request...

78 FR 26301 - Approval and Promulgation of Air Quality Implementation Plans; Illinois; Consumer Products and...

Science.gov (United States)

2013-05-06

... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 52 [EPA-R05-OAR-2010-0394; EPA-R05-OAR-2012-0786; FRL-9786-1] Approval and Promulgation of Air Quality Implementation Plans; Illinois; Consumer Products and... consumer products categories into the State's SIP. Finally, EPA is proposing to approve language to clarify...

78 FR 69773 - Approval and Promulgation of Implementation Plans; Texas; Control of Air Pollution by Permits for...

Science.gov (United States)

2013-11-21

...EPA is taking a direct final action to approve portions of two revisions to the Texas State Implementation Plan (SIP) concerning the Permits for Specific Designated Facilities Program, also referred to as the FutureGen Program. EPA has determined that the portions of these SIP revisions specific to the FutureGen Program submitted on March 9, 2006 and July 2, 2010, comply with the Clean Air Act and EPA regulations and are consistent with EPA policies. This action is being taken under section 110 and parts C and D of the Act.

Schedules of Controlled Substances: Placement of FDA-Approved Products of Oral Solutions Containing Dronabinol [(-)-delta-9-trans-

Science.gov (United States)

2017-11-22

This final rule adopts without changes an interim final rule with request for comments published in the Federal Register on March 23, 2017. On July 1, 2016, the U.S. Food and Drug Administration (FDA) approved a new drug application for Syndros, a drug product consisting of dronabinol [(-)-delta-9-trans-tetrahydrocannabinol (delta-9-THC)] oral solution. The Drug Enforcement Administration (DEA) maintains FDA-approved products of oral solutions containing dronabinol in schedule II of the Controlled Substances Act.

78 FR 63937 - Approval and Promulgation of Implementation Plans; Approval and Promulgation of State Air Quality...

Science.gov (United States)

2013-10-25

... Quality Plans for Designated Facilities and Pollutants, State of Iowa; Control of Emissions From Existing Hospital/ Medical/Infectious Waste Incinerator Units, Negative Declaration and 111(d) Plan Rescission... existing state air quality rules, approve an exemption from constructing permitting for engines used in...

78 FR 63887 - Approval and Promulgation of Implementation Plans; Approval and Promulgation of State Air Quality...

Science.gov (United States)

2013-10-25

... Quality Plans for Designated Facilities and Pollutants, State of Iowa; Control of Emissions From Existing Hospital/ Medical/Infectious Waste Incinerator Units, Negative Declaration and 111(d) Plan Rescission... quality rules, approve an exemption from constructing permitting for engines used in periodic pipeline...

75 FR 68429 - Cranes and Derricks in Construction; Approval of Information Collection Requirements

Science.gov (United States)

2010-11-08

.... OSHA-2007-0066] RIN 1218-AC01 Cranes and Derricks in Construction; Approval of Information Collection... requirements. SUMMARY: On August 9, 2010, OSHA published a final rule revising the Cranes and Derricks Standard... necessary to protect employees during the use of cranes and derricks in construction. That final standard...

Template for letter of approval by Research Supervisor

International Development Research Centre (IDRC) Digital Library (Canada)

Liliane Castets-Poupart

a) the approval of the candidate's final version of their research proposal (not just the research topic) by the research supervisor; b) the list of courses already completed and still to be completed by the candidate in the master's/PhD program; c) confirmation that all courses will be completed, and, for PhD candidates,.

Transmission service charges: cost allocation and rate design

International Nuclear Information System (INIS)

Poray, A. T.

2000-01-01

The application of the Ontario Hydro Networks Company (OHNC) to the Ontario Energy Board to seek approval for cost allocation and rate design methodology to recover revenue requirements for the provision of transmission services in Ontario are summarized. Insights that led to the arguments made in support of the application are also described. The paper contains an overview of plans for the operation of the transmission system, the agreement between Ontario Hydro Services Company (OHSC) and the Independent Market Operator (IMO), the stakeholder consultation process by OHNC to develop the transmission cost allocation and rate design methodology, a discussion of the major rate design issues, a summary of stakeholder opinions and a summary of OHNC's final proposal for transmission pricing. Public hearings on the OHNC application were held between February 16 and March 20, 2000. Final decision by the OEB is expected sometime in May 2000

Inertial confinement fusion driver enhancements: Final focusing systems and compact heavy-ion driver designs

International Nuclear Information System (INIS)

Bieri, R.L.

1991-01-01

Required elements of an inertial confinement fusion power plant are modeled and discussed. A detailed analysis of two critical elements of candidate drivers is done, and new component designs are proposed to increase the credibility and feasibility of each driver system. An analysis of neutron damage to the final elements of a laser focusing system is presented, and multilayer -- dielectric mirrors are shown to have damage lifetimes which axe too short to be useful in a commercial power plant. A new final-focusing system using grazing incidence metal mirrors to protect sensitive laser optics is designed and shown to be effective in extending the lifetime of the final focusing system. The reflectivities and damage limits of grazing incidence metal mirrors are examined in detail, and the required mirror sizes are shown to be compatible with the beam sizes and illumination geometries currently envisioned for laser drivers. A detailed design and analysis is also done for compact arrays of superconducting magnetic quadrupoles, which are needed in a multi-beam heavy-ion driver. The new array model is developed in more detail than some previous conceptual designs and models arrays which are more compact than arrays scaled from existing single -- quadrupole designs. The improved integrated model for compact arrays is used to compare the effects of various quadrupole array design choices on the size and cost of a heavy-ion driver. Array design choices which significantly affect the cost of a heavy-ion driver include the choice of superconducting material and the thickness of the collar used to support the winding stresses. The effect of these array design choices on driver size and cost is examined and the array model is used to estimate driver cost savings and performance improvements attainable with aggressive quadrupole array designs with high-performance superconductors

Development of the ITER Continuous External Rogowski: From conceptual design to final design

Energy Technology Data Exchange (ETDEWEB)

Moreau, Philippe, E-mail: philippe.jacques.moreau@cea.fr [CEA, IRFM, F-13108 Saint-Paul-lez-Durance (France); Spuig, Pascal; Le-luyer, Alain; Malard, Philippe; Cantone, Bruno; Pastor, Patrick; Saint-Laurent, François [CEA, IRFM, F-13108 Saint-Paul-lez-Durance (France); Vayakis, George; Delhom, Dominique [ITER Organization, Route de Vinon-sur-Verdon, CS 90 046, 13067 St. Paul Lez Durance Cedex (France); Arshad, Shakeib [Fusion for Energy, Josep Pla 2, Torres Diagonal Litoral B3, 08019 Barcelona (Spain); Lister, Jonathan; Toussaint, Matthieu; Marmillod, Philippe; Testa, Duccio; Schlatter, Christian [Ecole polytechnique fédérale de Lausanne, Centre de Recherches en Physique des Plasmas, 1015 Lausanne (Switzerland); Peruzzo, Simone [Consorzio RFX, C.so Stati Uniti 4, 35127 Padova (Italy)

2015-10-15

Highlights: • ITER Continuous External Rogowskis are designed for plasma current measurement. • CER are located in the casing of Toroidal Field Coils and will operate at 4.5 K. • The design of the sensors has been completed and validated through prototypes. • Detailed assembly procedure inside the toroidal field coil casing has been defined. • The CER has passed all the ITER and F4E design review procedures. - Abstract: In ITER, an accurate measurement of plasma current, with high reliability, is mandatory as this parameter is used to demonstrate licensing compliance with regulatory limits. For that purpose, several independent measurements based on magnetic diagnostics have been proposed. Rogowski coils are standard inductive sensors for current measurement in many applications. In ITER, three continuous external Rogowski coils are to be installed in the casing of the toroidal field coils. These sensors are remarkable from several points of view: overall length is about 40 m, high sensitivity needed, located in the toroidal field coil casing at 4.5 K and complex 3D routing with tight bending radius of 50 mm. Since 2005 an extensive work has been carried out to develop and analyze several design options complying with ITER specifications. Prototypes of a selected continuous external Rogowski design were built and tested successfully in terms of electrical, thermal, mechanical and vacuum characteristics. Finally a detailed assembly procedure inside the toroidal field coil casing has been defined according to the coil manufacturing and assembly constraints.

Newman Unit 1 advanced solar repowering advanced conceptual design. Final report

Energy Technology Data Exchange (ETDEWEB)

None

1982-04-01

The Newman Unit 1 solar repowering design is a water/steam central receiver concept supplying superheated steam. The work reported is to develop a refined baseline conceptual design that has potential for construction and operation by 1986, makes use of existing solar thermal technology, and provides the best economics for this application. Trade studies performed in the design effort are described, both for the conceptual design of the overall system and for the subsystem conceptual design. System-level functional requirements, design, operation, performance, cost, safety, environmental, institutional, and regulatory considerations are described. Subsystems described include the collector, receiver, fossil energy, electrical power generating, and master control subsystems, site and site facilities. The conceptual design, cost, and performance of each subsystem is discussed at length. A detailed economic analysis of the repowered unit is made to realistically assess the economics of the first repowered unit using present cost data for a limited production level for solar hardware. Finally, a development plan is given, including the design, procurement, construction, checkout, startup, performance validation, and commercial operation. (LEW)

13 CFR 108.140 - SBA approval of initial Management Expenses.

Science.gov (United States)

2010-01-01

... VENTURE CAPITAL (âNMVCâ) PROGRAM Qualifications for the NMVC Program Organizing A Nmvc Company § 108.140 SBA approval of initial Management Expenses. A NMVC Company must have its Management Expenses approved by SBA at the time of designation as a NMVC Company. (See § 108.520 for the definition of Management...

76 FR 76302 - Approval and Promulgation of Air Quality Implementation Plans; Indiana; Redesignation of Lake and...

Science.gov (United States)

2011-12-07

...] Approval and Promulgation of Air Quality Implementation Plans; Indiana; Redesignation of Lake and Porter...). ACTION: Final rule. SUMMARY: EPA is taking several related actions affecting Lake and Porter Counties and... redesignation of Lake and Porter Counties to attainment of the 1997 annual PM 2.5 standard. EPA is approving, as...

Experimental fusion power reactor conceptual design study. Final report. Volume III

International Nuclear Information System (INIS)

Baker, C.C.

1976-12-01

This document is the final report which describes the work carried out by General Atomic Company for the Electric Power Research Institute on a conceptual design study of a fusion experimental power reactor (EPR) and an overall EPR facility. The primary objective of the two-year program was to develop a conceptual design of an EPR that operates at ignition and produces continuous net power. A conceptual design was developed for a Doublet configuration based on indications that a noncircular tokamak offers the best potential of achieving a sufficiently high effective fuel containment to provide a viable reactor concept at reasonable cost. Other objectives included the development of a planning cost estimate and schedule for the plant and the identification of critical R and D programs required to support the physics development and engineering and construction of the EPR. This volume contains the following appendices: (1) tradeoff code analysis, (2) residual mode transport, (3) blanket/first wall design evaluations, (4) shielding design evaluation, (5) toroidal coil design evaluation, (6) E-coil design evaluation, (7) F-coil design evaluation, (8) plasma recycle system design evaluation, (9) primary coolant purification design evaluation, (10) power supply system design evaluation, (11) number of coolant loops, (12) power conversion system design evaluation, and (13) maintenance methods evaluation

Final report of the ITER EDA. Final report of the ITER Engineering Design Activities. Prepared by the ITER Council

International Nuclear Information System (INIS)

2001-01-01

This is the Final Report by the ITER Council on work carried out by ITER participating countries on cooperation in the Engineering Design Activities (EDA) for the ITER. In this report the main ITER EDA technical objectives, the scope of ITER EDA, its organization and resources, engineering design of ITER tokamak and its main parameters are presented. This Report also includes safety and environmental assessments, site requirements and proposed schedule and estimates of manpower and cost as well as proposals on approaches to joint implementation of the project

Grid fault and design-basis for wind turbines - Final report

DEFF Research Database (Denmark)

Hansen, Anca Daniela; Cutululis, Nicolaos Antonio; Markou, Helen

, have been performed and compared for two cases, i.e. one when the turbine is immediately disconnected from the grid when a grid fault occurs and one when the turbine is equipped with a fault ride-through controller and therefore it is able to remain connected to the grid during the grid fault......This is the final report of a Danish research project “Grid fault and design-basis for wind turbines”. The objective of this project has been to assess and analyze the consequences of the new grid connection requirements for the fatigue and ultimate structural loads of wind turbines....... The fulfillment of the grid connection requirements poses challenges for the design of both the electrical system and the mechanical structure of wind turbines. The development of wind turbine models and novel control strategies to fulfill the TSO’s requirements are of vital importance in this design. Dynamic...

Designing with LED

OpenAIRE

Johnson, Amanda

2018-01-01

This presentation focuses on the recently adopted changes in the way highway lighting systems are designed, with emphasis on how the approved list of solid state–based luminaires is integrated into the design process. Progress made on the approved list and experiences in developing it will also be shared.

Approval of devices and facilities using ionizing radiations for medical purposes

International Nuclear Information System (INIS)

1977-01-01

This Order made by the Ministers of Health and Social Security, Agriculture and Labour amends a previous Decree of 23 April 1969 in particular concerning the classification of medical or dental radiodiagnostic devices subject to approval. The technical conditions to be complied with for such devices and facilities have also been amended. Finally, it is provided that, as regards facilities with heavy equipment subject to licensing (Act of 31 December 1970), approval is subject to compliance with the licensing conditions and is requested together with the application for a licence. (NEA) [fr

Project W-314 phase I environmental permits and approvals plan

International Nuclear Information System (INIS)

TOLLEFSON, K.S.

1999-01-01

This document describes the range of environmental actions, including required permits and other agency approvals, for Project W-314 activities in the Hanford Site's Tank Waste Remediation System. This document outlines alternative approaches to satisfying applicable environmental standards, and describes selected strategies for acquiring permits and other approvals needed for waste feed delivery to proceed. This document also includes estimated costs and schedule to obtain the required permits and approvals based on the selected strategy. It also provides estimated costs for environmental support during design and construction based on the preliminary project schedule provided

Training reactor deployment. Advanced experimental course on designing new reactor cores

International Nuclear Information System (INIS)

Skoda, Radek

2009-01-01

Czech Technical University in Prague (CTU) operating its training nuclear reactor VR1, in cooperation with the North West University of South Africa (NWU), is applying for accreditation of the experimental training course ''Advanced experimental course on designing the new reactor core'' that will guide the students, young nuclear engineering professionals, through designing, calculating, approval, and assembling a new nuclear reactor core. Students, young professionals from the South African nuclear industry, face the situation when a new nuclear reactor core is to be build from scratch. Several reactor core design options are pre-calculated. The selected design is re-calculated by the students, the result is then scrutinized by the regulator and, once all the analysis is approved, physical dismantling of the current core and assembling of the new core is done by the students, under a close supervision of the CTU staff. Finally the reactor is made critical with the new core. The presentation focuses on practical issues of such a course, desired reactor features and namely pedagogical and safety aspects. (orig.)

77 FR 429 - Clarification and Further Guidance on the Fireworks Approvals Policy

Science.gov (United States)

2012-01-05

... 173 [Docket No. PHMSA-2011-0315; Notice No. 11-13] Clarification and Further Guidance on the Fireworks... fireworks approvals applications from fireworks manufacturers or their designated agents and grant approvals only to manufacturers of fireworks devices. This clarification and additional guidance follows the...

Final design and construction issues of the TAPIRO epithermal column

International Nuclear Information System (INIS)

Burn, K.W.; Casalini, L.; Nava, E.; Tinti, R.; Martini, S.; Mondini, D.; Rosi, G.

2006-01-01

The construction of the epithermal column for clinical trials at the 5 kW fast reactor TAPIRO (ENEA, Casaccia, Italy) has been completed, the experimental bunker in the reactor hall has been designed and the beam characterisation will shortly be underway. As has been reviewed at the last two ICNCT conferences, the low power of the neuron source and the relatively distant patient position outside the reactor shield led to a column design with certain characteristics. One consequence is the employment of a collimator containing lead of high purity with the resultant problems of mechanical construction. Another is the substantial neutron leakage from the column outside the aperture into the experimental bunker. Furthermore the absence of a gamma shield has led to an electron dose to the skin. This is resolved with an electron shield of aluminium. Here the construction and final design issues are discussed and the state of the project is presented. (author)

75 FR 52860 - Final Airworthiness Design Standards for Acceptance Under the Primary Category Rule; Orlando...

Science.gov (United States)

2010-08-30

... DEPARTMENT OF TRANSPORTATION Federal Aviation Administration 14 CFR Part 21 Final Airworthiness Design Standards for Acceptance Under the Primary Category Rule; Orlando Helicopter Airways (OHA), Inc... Existence of Proposed Airworthiness Design Standards for Acceptance Under the Primary Category Rule; Orlando...

Developments in the safe design of LNG tanks

Science.gov (United States)

Fulford, N. J.; Slatter, M. D.

The objective of this paper is to discuss how the gradual development of design concepts for liquefied natural gas (LNG) storage systems has helped to enhance storage safety and economy. The experience in the UK is compared with practice in other countries with similar LNG storage requirements. Emphasis is placed on the excellent record of safety and reliability exhibited by tanks with a primary metal container designed and constructed to approved standards. The work carried out to promote the development of new materials, fire protection, and monitoring systems for use in LNG storage is also summarized, and specific examples described from British Gas experience. Finally, the trends in storage tank design world-wide and options for future design concepts are discussed, bearing in mind planned legislation and design codes governing hazardous installations.

Hawaii State Plan for Occupational Safety and Health. Final rule.

Science.gov (United States)

2012-09-21

This document announces the Occupational Safety and Health Administration's (OSHA) decision to modify the Hawaii State Plan's ``final approval'' determination under Section 18(e) of the Occupational Safety and Health Act (the Act) and to transition to ``initial approval'' status. OSHA is reinstating concurrent federal enforcement authority over occupational safety and health issues in the private sector, which have been solely covered by the Hawaii State Plan since 1984.

Experimental fusion power reactor conceptual design study. Final report. Volume II

International Nuclear Information System (INIS)

Baker, C.C.

1976-12-01

This document is the final report which describes the work carried out by General Atomic Company for the Electric Power Research Institute on a conceptual design study of a fusion experimental power reactor (EPR) and an overall EPR facility. The primary objective of the two-year program was to develop a conceptual design of an EPR that operates at ignition and produces continuous net power. A conceptual design was developed for a Doublet configuration based on indications that a noncircular tokamak offers the best potential of achieving a sufficiently high effective fuel containment to provide a viable reactor concept at reasonable cost. Other objectives included the development of a planning cost estimate and schedule for the plant and the identification of critical R and D programs required to support the physics development and engineering and construction of the EPR. This volume contains the following sections: (1) reactor components, (2) auxiliary systems, (3) operations, (4) facility design, (5) program considerations, and (6) conclusions and recommendations

Experimental and Theoretical Progress of Linear Collider Final Focus Design and ATF2 Facility

CERN Document Server

Seryi, Andrei; Zimmermann, Frank; Kubo, Kiyoshi; Kuroda, Shigeru; Okugi, Toshiyuki; Tauchi, Toshiaki; Terunuma, Nobuhiro; Urakawa, Junji; White, Glen; Woodley, Mark; Angal-Kalinin, Deepa

2014-01-01

In this brief overview we will reflect on the process of the design of the linear collider (LC) final focus (FF) optics, and will also describe the theoretical and experimental efforts on design and practical realisation of a prototype of the LC FF optics implemented in the ATF2 facility at KEK, Japan, presently being commissioned and operated.

46 CFR 163.002-9 - Approval procedure.

Science.gov (United States)

2010-10-01

... COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) EQUIPMENT, CONSTRUCTION, AND MATERIALS... designs. A pilot hoist that does not meet the materials, construction, or performance requirements of this... or in addition to the approval tests required by this subpart, show that the alternative materials...

Osiris and SOMBRERO inertial confinement fusion power plant designs. Volume 2, Designs, assessments, and comparisons, Final report

Energy Technology Data Exchange (ETDEWEB)

Meier, W.R.; Bieri, R.L.; Monsler, M.J.

1992-03-01

The primary objective of the of the IFE Reactor Design Studies was to provide the Office of Fusion Energy with an evaluation of the potential of inertial fusion for electric power production. The term reactor studies is somewhat of a misnomer since these studies included the conceptual design and analysis of all aspects of the IFE power plants: the chambers, heat transport and power conversion systems, other balance of plant facilities, target systems (including the target production, injection, and tracking systems), and the two drivers. The scope of the IFE Reactor Design Studies was quite ambitious. The majority of our effort was spent on the conceptual design of two IFE electric power plants, one using an induction linac heavy ion beam (HIB) driver and the other using a Krypton Fluoride (KrF) laser driver. After the two point designs were developed, they were assessed in terms of their (1) environmental and safety aspects; (2) reliability, availability, and maintainability; (3) technical issues and technology development requirements; and (4) economics. Finally, we compared the design features and the results of the assessments for the two designs.

Mod-5A wind turbine generator program design report. Volume 3: Final design and system description, 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. Volume 3, book 1 describes the performance and characteristics of the MOD-5A wind turbine generator in its final configuration. Each subsystem - the rotor, drivetrain, nacelle, tower and foundation is described in detail.

Design principle of TVO's final repository and preliminary adaptation to site specific conditions

International Nuclear Information System (INIS)

Salo, J-P.; Reikkola, R.

1995-01-01

Teollisuuden Voima Oy (TVO) is responsible for the management of spent fuel produced by the Olkiluoto power plant. TVO's current programme of spent fuel management is based on the guidelines and time schedule set by the Finnish Government. TVO has studied a final disposal concept in which the spent fuel bundles are encapsulated in copper canisters and emplaced in Finnish bedrock. According to the plan the final repository for spent fuel will be in operation by 2020. TVO's updated technical plans for the disposal of spent fuel together with a performance analysis (TVO-92) were submitted to the authorities in 1992. The paper describes the design principle of TVO's final repository and preliminary adaptation of the repository to site specific conditions. (author). 10 refs., 5 figs

Los Angeles-Gateway Freight Advanced Traveler Information System : final system design and architecture for FRATIS prototype.

Science.gov (United States)

2013-05-01

This Final Architecture and Design report has been prepared to describe the structure and design of all the system : components for the LA-Gateway FRATIS Demonstration Project. More specifically, this document provides: : Detailed descriptions of...

Prototypical spent nuclear fuel rod consolidation equipment: Phase 2, Final design report: Volume 1, Detailed design

International Nuclear Information System (INIS)

Blissell, W.H.; Ciez, A.P.; Goedicke, F.E.; Bessko, C.

1987-01-01

This document describes the Westinghouse Final Design for the Prototypical Spent Fuel Consolidation Equipment Demonstration Project. This design represents a fully qualified, licensable, cost effective spent fuel rod consolidation system. As a result of significant concerns raised by DOE and its Technical Review Committee during the 30% Design Review, significant changes were made to the original Preliminary Design resulting from Phase I activities. These changes focused on increased automation, end fitting removal, the rod pulling process and the need to maintain the consolidation canisters as clean as possible. As a result of these changes, the new system is greatly enhanced with a much greater probability of meeting or exceeding the project functional requirements. As a result of delays in resolving cost and contractual differences, additional bench testing was not conducted during Phase II. It is however our belief that the current design exceeds the 90% confidence level required by DOE because of the confidence gained from the Phase I tests, the additional engineering detail completed and the fact that our rod pulling tool has been demonstrated in a similar application at Oconee while our ID tube cutter is a modified (mounting method only) off-the-shelf design. 7 refs., 49 figs., 36 tabs

78 FR 52006 - 30-Day Notice of Proposed Information Collection: Final Endorsement of Credit Instrument

Science.gov (United States)

2013-08-21

... Information Collection: Final Endorsement of Credit Instrument AGENCY: Office of the Chief Information Officer... Title of Information Collection: Final Endorsement of Credit Instrument. OMB Approval Number: 2502-0016... Credit Instrument'' form is used to request to request final [[Page 52007

77 FR 15759 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2012-03-16

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort AGENCY: National Institute for Occupational Safety and Health...). ACTION: Notice. SUMMARY: HHS gives notice concerning the final effect of the HHS decision to designate a...

78 FR 21955 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2013-04-12

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort AGENCY: National Institute for Occupational Safety and Health...). ACTION: Notice. SUMMARY: HHS gives notice concerning the final effect of the HHS decision to designate a...

78 FR 70949 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2013-11-27

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort AGENCY: National Institute for Occupational Safety and Health...). ACTION: Notice. SUMMARY: HHS gives notice concerning the final effect of the HHS decision to designate a...

77 FR 60438 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2012-10-03

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort AGENCY: National Institute for Occupational Safety and Health...). ACTION: Notice. SUMMARY: HHS gives notice concerning the final effect of the HHS decision to designate a...

75 FR 27784 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2010-05-18

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort AGENCY: National Institute for Occupational Safety and Health... concerning the final effect of the decision to designate a class of employees from Lawrence Livermore...

75 FR 37812 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2010-06-30

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort AGENCY: National Institute for Occupational Safety and Health... and Human Services (HHS) gives notice concerning the final effect of the HHS decision to designate a...

77 FR 60437 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2012-10-03

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort AGENCY: National Institute for Occupational Safety and Health...). ACTION: Notice. SUMMARY: HHS gives notice concerning the final effect of the HHS decision to designate a...

77 FR 69845 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2012-11-21

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort AGENCY: National Institute for Occupational Safety and Health...). ACTION: Notice. SUMMARY: HHS gives notice concerning the final effect of the HHS decision to designate a...

78 FR 21954 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2013-04-12

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort AGENCY: National Institute for Occupational Safety and Health...). ACTION: Notice. SUMMARY: HHS gives notice concerning the final effect of the HHS decision to designate a...

Final design and performance of in situ testing in Grimsel

International Nuclear Information System (INIS)

Fuentes-Cantillana, J.L.; Garcia-SiNeriz, J.L.

1998-01-01

This report is focused on the design, engineering, and construction aspects of the in situ test carried out at the Grimsel underground laboratory in Switzerland. This reproduces the AGP-granite concept of ENRESA for HLW repositories in crystalline rock. Two heaters, similar in dimensions and weight to the canisters in the reference concept, have been placed in a horizontal drift with a 2.28-m diameter, a total test length of 17.4 m, and backfilled with a total of 115.7 † of highly-compacted bentonite blocks. The backfilled area has been closed with a concrete plug which is 2.7 m thick. More than 600 sensors have been installed in the test to monitor different parameters such as temperature, pressures, humidity, etc., within both the buffer material and the host rock. The installation was completed and commissioned in February 1997, and then the heating phase, which will last for at least 3 years, was started. During this period, the test will basically be operated in an automatic mode, controlled and monitored from Spain via modem. The report is the Final Report from AITEMIN for Phase 4 of the project and includes a description of the test configuration and layout; the design, engineering, and manufacturing aspects of the different test components and equipment; the emplacement operation; and the as built information regarding the final position of the main components and the sensors. (Author)

Design review report for the SY-101 RAPID mitigation system

International Nuclear Information System (INIS)

SCHLOSSER, R.L.

1999-01-01

This report documents design reviews conducted of the SY-101 Respond And Pump In Days (RAPID) Mitigation System. As part of the SY-101 Surface-Level-Rise Remediation Project, the SY-101 WID Mitigation System will reduce the potential unacceptable consequences of crust growth in Tank 241-SY-101 (SY-101). Projections of the crust growth rate indicate that the waste level in the tank may reach the juncture of the primary and secondary confinement structures of the tank late in 1999. Because of this time constraint, many design activities are being conducted in parallel and design reviews were conducted for system adequacy as well as design implementation throughout the process. Design implementation, as used in this design review report, is the final component selection (e.g., which circuit breaker, valve, or thermocouple) that meets the approved design requirements, system design, and design and procurement specifications. Design implementation includes the necessary analysis, testing, verification, and qualification to demonstrate compliance with the system design and design requirements. Design implementation is outside the scope of this design review. The design activities performed prior to detailed design implementation (i.e., system mission requirements, functional design requirements, technical criteria, system conceptual design, and where design and build contracts were placed, the procurement specification) have been reviewed and are within the scope of this design review report. Detailed design implementation will be controlled, reviewed, and where appropriate, approved in accordance with Tank Waste Remediation System (TWRS) engineering procedures. Review of detailed design implementation will continue until all components necessary to perform the transfer function are installed and tested

Design review report for the SY-101 RAPID mitigation system

Energy Technology Data Exchange (ETDEWEB)

SCHLOSSER, R.L.

1999-05-24

This report documents design reviews conducted of the SY-101 Respond And Pump In Days (RAPID) Mitigation System. As part of the SY-101 Surface-Level-Rise Remediation Project, the SY-101 WID Mitigation System will reduce the potential unacceptable consequences of crust growth in Tank 241-SY-101 (SY-101). Projections of the crust growth rate indicate that the waste level in the tank may reach the juncture of the primary and secondary confinement structures of the tank late in 1999. Because of this time constraint, many design activities are being conducted in parallel and design reviews were conducted for system adequacy as well as design implementation throughout the process. Design implementation, as used in this design review report, is the final component selection (e.g., which circuit breaker, valve, or thermocouple) that meets the approved design requirements, system design, and design and procurement specifications. Design implementation includes the necessary analysis, testing, verification, and qualification to demonstrate compliance with the system design and design requirements. Design implementation is outside the scope of this design review. The design activities performed prior to detailed design implementation (i.e., system mission requirements, functional design requirements, technical criteria, system conceptual design, and where design and build contracts were placed, the procurement specification) have been reviewed and are within the scope of this design review report. Detailed design implementation will be controlled, reviewed, and where appropriate, approved in accordance with Tank Waste Remediation System (TWRS) engineering procedures. Review of detailed design implementation will continue until all components necessary to perform the transfer function are installed and tested.

76 FR 72928 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2011-11-28

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort AGENCY: National Institute for Occupational Safety and Health... concerning the final effect of the HHS decision to designate a class of employees from Vitro Manufacturing in...

76 FR 7852 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2011-02-11

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort AGENCY: National Institute for Occupational Safety and Health... concerning the final effect of the HHS decision to designate a class of employees from Texas City Chemicals...

76 FR 59701 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2011-09-27

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort AGENCY: National Institute for Occupational Safety and Health... concerning the final effect of the HHS decision to designate a class of employees from the Sandia National...

75 FR 67364 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2010-11-02

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort AGENCY: National Institute for Occupational Safety and Health... concerning the final effect of the HHS decision to designate a class of employees from the Blockson Chemical...

75 FR 51816 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2010-08-23

... Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort AGENCY...). ACTION: Notice. SUMMARY: HHS gives notice concerning the final effect of the HHS decision to designate a... Special Exposure Cohort (SEC) under the Energy Employees Occupational Illness Compensation Program Act of...

75 FR 27785 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2010-05-18

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort AGENCY: National Institute for Occupational Safety and Health... concerning the final effect of the decision to designate a class of employees from Area IV of the Santa...

Project W-521, waste feed delivery systems environmental permits and approvals plan

International Nuclear Information System (INIS)

TOLLEFSON, K.S.

1999-01-01

This document has been prepared to define the specific environmental requirements applicable to Project W-521. The document describes the permits and approvals necessary for the project to design, construct, and install planned upgrades, and provides a schedule of activities and provides cost estimates to complete the required permitting and approval activities

An ion-optical design study of a carbon-ion rotating gantry with a superconducting final bending magnet

International Nuclear Information System (INIS)

Bokor, J.; Pavlovič, M.

2016-01-01

Ion-optical designs of an isocentric ion gantry with a compact curved superconducting final bending magnet are presented. The gantry is designed for transporting carbon-therapy beams with nominal kinetic energy of 400 MeV/u, which corresponds to the penetration range of C"6"+ beam in water of about 28 cm. In contrast to other existing designs, we present a “hybrid” beam transport system containing a single superconducting element – the last bending magnet. All other elements are based on conventional warm technology. Ion-optical properties of such a hybrid system are investigated in case of transporting non-symmetric (i.e. different emittance patterns in the horizontal and vertical plane) beams. Different conditions for transporting the non-symmetric beams are analyzed aiming at finding the optimal, i.e. the most compact, gantry version. The final gantry layout is presented including a 2D parallel scanning. The ion-optical and scanning properties of the final gantry design are described, discussed and illustrated by computer simulations performed by WinAGILE.

Evaluation of regulatory processes affecting nuclear power plant early site approval and standardization

International Nuclear Information System (INIS)

1983-12-01

This report presents the results of a survey and evaluation of existing federal, state and local regulatory considerations affecting siting approval of power plants in the United States. Those factors that may impede early site approval of nuclear power plants are identified, and findings related to the removal of these impediments and the general improvement of the approval process are presented. A brief evaluation of standardization of nuclear plant design is also presented

Final design of ITER port plug test facility

Energy Technology Data Exchange (ETDEWEB)

Cerisier, Thierry, E-mail: thierry.cerisier@yahoo.fr [ITER Organization, Route de Vinon-sur-Verdon, CS 90046, St Paul-lez-Durance Cedex, 13067 (France); Levesy, Bruno [ITER Organization, Route de Vinon-sur-Verdon, CS 90046, St Paul-lez-Durance Cedex, 13067 (France); Romannikov, Alexander [Institution “Project Center ITER”, Kurchatov sq. 1, Building 3, Moscow 123182 (Russian Federation); Rumyantsev, Yuri [JSC “Cryogenmash”, Moscow reg., Balashikha 143907 (Russian Federation); Cordier, Jean-Jacques; Dammann, Alexis [ITER Organization, Route de Vinon-sur-Verdon, CS 90046, St Paul-lez-Durance Cedex, 13067 (France); Minakov, Victor; Rosales, Natalya; Mitrofanova, Elena [JSC “Cryogenmash”, Moscow reg., Balashikha 143907 (Russian Federation); Portone, Sergey; Mironova, Ekaterina [Institution “Project Center ITER”, Kurchatov sq. 1, Building 3, Moscow 123182 (Russian Federation)

2016-11-01

Highlights: • We introduce the port plug test facility (purpose and status of the design). • We present the PPTF sub-systems. • We present the environmental and functional tests. • We present the occupational and nuclear safety functions. • We conclude on the achievements and next steps. - Abstract: To achieve the overall ITER machine availability target, the availability of diagnostics and heating port plugs shall be as high as 99.5%. To fulfill this requirement, it is mandatory to test the port plugs at operating temperature before installation on the machine and after refurbishment. The ITER port plug test facility (PPTF) is composed of several test stands that can be used to test the port plugs whereas at the end of manufacturing (in a non-nuclear environment), or after refurbishment in the ITER hot cell facility. The PPTF provides the possibility to perform environmental (leak tightness, vacuum and thermo-hydraulic performances) and functional tests (radio frequency acceptance tests, behavior of the plugs’ steering mechanism and calibration of diagnostics) on upper and equatorial port plugs. The final design of the port plug test facility is described. The configuration of the standalone test stands and the integration in the hot cell facility are presented.

Final design of the generic equatorial port plug structure for ITER diagnostic systems

International Nuclear Information System (INIS)

Udintsev, V.S.; Maquet, P.; Alexandrov, E.; Casal, N.; Cuenca, D.; Drevon, J.-M.; Feder, R.; Friconneau, J.P.; Giacomin, T.; Guirao, J.; Iglesias, S.; Josseaume, F.; Levesy, B.; Loesser, D.; Ordieres, J.; Quinn, E.; Pak, S.; Penot, C.; Pitcher, C.S.; Portalès, M.

2015-01-01

The Diagnostic Generic Equatorial Port Plug (GEPP) is designed to be common to all equatorial port-based diagnostic systems. It is designed to survive throughout the lifetime of ITER for 20 years, 30,000 discharges, and 3000 disruptions. The EPP structure dimensions (without Diagnostic First Walls and Diagnostic Shield Modules) are L2.9 × W1.9 × H2.4 m"3. The length of the fully integrated EPP is 3174 mm. The weight of the EPP structure is about 15 t, whereas the total weight of the integrated EPP may be up to 45 t. The EPP structure provides a flexible platform for a variety of diagnostics. The Diagnostic Shield Module assemblies, or drawers, allow a modular approach with respect to diagnostic integration and maintenance. In the nuclear phase of ITER operations, they will be remotely inserted into the EPP structure in the Hot Cell Facility. The port plug structure must also contribute to the nuclear shielding, or plugging, of the port and further contain circulated water to allow cooling during operation and heating during bake-out. The Final Design of the GEPP has been successfully passed in late 2013 and is now heading toward manufacturing. The final design of the GEPP includes interfaces, manufacturing, R&D, operation and maintenance, load cases and analysis of failure modes.

Final design review report for K Basin Dose Reduction Project Clean and Coat Task

International Nuclear Information System (INIS)

Blackburn, L.D.

1996-02-01

The strategy for reducing radiation dose originating from radionuclides absorbed in the concrete is to raise the pool water level to provide additional shielding. The concrete walls need to be coated to prevent future radionuclide absorption into the walls. This report documents a final design review of equipment to clean and coat basin walls. The review concluded that the design presented was acceptable for release for fabrication

24 CFR 220.802 - Final insurance endorsement.

Science.gov (United States)

2010-04-01

... 24 Housing and Urban Development 2 2010-04-01 2010-04-01 false Final insurance endorsement. 220... insurance endorsement. When all advances of loan proceeds have been made, and all the terms and conditions... on the original credit instrument the total of advances he has approved for insurance and again...

Implementing Project-Based Learning (PBL) in Final Collection to Improve the Quality of Fashion Design Student

OpenAIRE

Indarti, Indarti

2016-01-01

Fashion design education is one of education that prepares students to work in fashion design field. Students research future fashion trends, sketch designs, select colors, fabrics and patterns, and give instructions on how to make the products they designed. Fashion design education not only nurture and develop student's creative skills, it also teaches essential practical skills such as production techniques and material properties, to create a final product. According to this, new educatio...

38 CFR 17.65 - Approvals and provisional approvals of community residential care facilities.

Science.gov (United States)

2010-07-01

... approvals of community residential care facilities. 17.65 Section 17.65 Pensions, Bonuses, and Veterans' Relief DEPARTMENT OF VETERANS AFFAIRS MEDICAL Community Residential Care § 17.65 Approvals and provisional approvals of community residential care facilities. (a) An approval of a facility meeting all of...

Final design of the Korean AC/DC converters for the ITER coil power supply system

Energy Technology Data Exchange (ETDEWEB)

Oh, Jong-Seok, E-mail: jsoh@nfri.re.kr [ITER Korea, National Fusion Research Institute, Daejeon 305-806 (Korea, Republic of); Choi, Jungwan; Suh, Jae-Hak; Choi, Jihyun [ITER Korea, National Fusion Research Institute, Daejeon 305-806 (Korea, Republic of); Lee, Lacksang; Kim, Changwoo; Park, Hyungjin; Jo, Seongman; Lee, Seungyun; Hwang, Kwangcheol; Liu, Hyoyol [Dawonsys Corp., Siheung 429-450 (Korea, Republic of); Hong, Ki-Don; Sim, Dong-Joon; Lee, Jang-Soo [Hyosung Corp., Gongdeok-Dong, Seoul 121-720 (Korea, Republic of); Lee, Eui-Jae; Kwon, Yang-Hae; Lee, Dae-Yeol; Ko, Ki-Won; Kim, Jong-Min [Mobiis Corp., Yangjae-dong, Seoul 137-888 (Korea, Republic of); Song, Inho [ITER Organization, Route de Vinon sur Verdon, CS 90 046, 13067 St. Paul Lez Durance Cedex (France); and others

2015-10-15

The final design of the ITER TF, CS, CC and VS AC/DC converters has been completed to implement ITER requirements following the detailed design and refinements of the preliminary design. The number of parallel thyristors and the rating of fuses are coordinated to keep those devices within the explosion limit even under most severe fault conditions. The impedance of the converter transformer has been optimized taking into account the energization inrush current, short circuit current, reactive power consumption and the available DC voltage. To ensure system integrity, AC/DC converters are mechanically divided into transformers, AC busbars, 6-pulse bridges, DC interconnecting busbars and DC reactors, and then all subsystems are decoupled by flexible links. To provide stable real time network communication down to the converters, a one GbE link is deployed between master controllers and local controllers. IEEE 1588 is implemented to the embedded controllers for precision time synchronization. This paper describes the detailed solutions implemented in the final design for the ITER AC/DC converters with R&D results of converter prototypes.

Experimental evaluation and design of unfilled and concrete-filled FRP composite piles : Task 7 : final report : thesis.

Science.gov (United States)

2015-05-01

The overall goal of this project is the experimental evaluation and design of unfilled and concrete-filled FRP composite piles for load-bearing in bridges. This report covers Task 7, Final Report - Thesis. : This final report covers Tasks 1, 2, 3, 5 ...

24 CFR 213.268 - Final insurance endorsement.

Science.gov (United States)

2010-04-01

... 24 Housing and Urban Development 2 2010-04-01 2010-04-01 false Final insurance endorsement. 213... insurance endorsement. When all advances of mortgage or loan proceeds have been made and all the terms and... indicate on the original credit instrument the total of all advances he has approved for insurance and...

77 FR 4822 - Western Hemisphere Travel Initiative: Designation of an Approved Native American Tribal Card...

Science.gov (United States)

2012-01-31

... and sea ports of entry. See 73 FR 18384 (the WHTI land and sea final rule). It amended, among other..., including a testing and auditing process to ensure that the cards are produced and issued in accordance with... auditing by CBP of the cards and program, the Secretary of DHS or the Commissioner of CBP may designate the...

Modifications of the design of the final transformer in the FFS to accommodate lower gradients in the final quadrupole triplet

International Nuclear Information System (INIS)

Murray, J.J.

1983-01-01

The final transformer of the FFS includes the soft bend magnet and two symmetric quadrupole triplets. It ends at the IP. It is a telescopic transformer (meaning that its transfer matrix is diagonal) with a magnification of -1/5 in both planes. In the current design, L*, the distance between the downstream end of Q1 and the IP, is equal to 7.25 feet (2.21 m) and space is provided upstream of Q6 to accommodate a 27 foot long soft bend magnet. Satisfaction of the foregoing conditions leads to field gradients of about 19.8 kg/cm in Q1 and Q3 and 18.1 kg/cm in Q2. It now appears that it would be very difficult to attain such gradients. For practical superconducting quad designs, meaning iron-free, 5 cm bore, two-layer windings and 4.2 0 K, experts have estimated that gradients of at least 14 kg/cm would be reasonable. This raises the question, can the final transformer in the FFS be modified to accommodate gradients of 14 kg/cm or less and if so at what price in performance

Final design of a free-piston hydraulic advanced Stirling conversion system

Science.gov (United States)

Wallace, D. A.; Noble, J. E.; Emigh, S. G.; Ross, B. A.; Lehmann, G. A.

1991-01-01

Under the US Department of Energy's (DOEs) Solar Thermal Technology Program, Sandia National Laboratories is evaluating heat engines for solar distributed receiver systems. The final design is described of an engineering prototype advanced Stirling conversion system (ASCS) with a free-piston hydraulic engine output capable of delivering about 25 kW of electric power to a utility grid. The free-piston Stirling engine has the potential for a highly reliable engine with long life because it has only a few moving parts, has noncontacting bearings, and can be hermetically sealed. The ASCS is designed to deliver maximum power per year over a range of solar input with a design life of 30 years (60,000 h). The system includes a liquid Nak pool boiler heat transport system and a free-piston Stirling engine with high-pressure hydraulic output, coupled with a bent axis variable displacement hydraulic motor and a rotary induction generator.

Final design of a free-piston hydraulic advanced Stirling conversion system

Science.gov (United States)

Wallace, D. A.; Noble, J. E.; Emigh, S. G.; Ross, B. A.; Lehmann, G. A.

Under the US Department of Energy's (DOEs) Solar Thermal Technology Program, Sandia National Laboratories is evaluating heat engines for solar distributed receiver systems. The final design is described of an engineering prototype advanced Stirling conversion system (ASCS) with a free-piston hydraulic engine output capable of delivering about 25 kW of electric power to a utility grid. The free-piston Stirling engine has the potential for a highly reliable engine with long life because it has only a few moving parts, has noncontacting bearings, and can be hermetically sealed. The ASCS is designed to deliver maximum power per year over a range of solar input with a design life of 30 years (60,000 h). The system includes a liquid Nak pool boiler heat transport system and a free-piston Stirling engine with high-pressure hydraulic output, coupled with a bent axis variable displacement hydraulic motor and a rotary induction generator.

APPROVAL OF WASTE TREATMENT AND IMMOBILIZATION PLANT CONTRACTOR-INITIATED AUTHORIZATION BASIS AMENDMENT REQUESTS (ABAR)

International Nuclear Information System (INIS)

JONES GL

2008-01-01

The objective is to describe the process used by the Office of River Protection (ORP) for evaluating and implementing Contractor-initiated changes to the Waste Treatment and Immobilization Plant (WTP) Authorization Basis (AB). The WTP Project's history has provided a unique challenge for establishing and maintaining an ORP-approved AB during design and construction. Until operations begin, the project cannot implement the classic Unreviewed Safety Question (USQ) process to determine when ORP approval of Contractor-initiated changes is required. A 'quasiUSQ' process has been implemented that defines when AB changes could occur. The three types of AB changes are (1) Limited Scope Changes, (2) Authorization Basis Deviations, and (3) Authorization Basis Amendment Request (ABAR). DOE RL/REG 97-13, 'Office of River Protection Position on Contractor-Initiated Changes to the Authorization Basis', describes the process the WTP Contractor must follow to make changes to the AB, with and without ORP approval. The process uses a 'safety evaluation' process that is similar to the USQ process but at a more qualitative level. The maturation of the WTP Contractor's facility design and activities, and other changing conditions, resulted in a process that allows the Contractor to make changes to the AB without ORP approval; however, those changes that may significantly affect nuclear safety do require ORP approval. This process balances the WTP regulatory principle of efficiency with assurance that adequate safety will not be compromised. The process has reduced the number of ABARs requiring ORP approval and reduced the potential for delays in design and procurement activities

Can an ethics officer role reduce delays in research ethics approval? A mixed-method evaluation of an improvement project

Science.gov (United States)

Dixon-Woods, Mary; Foy, Chris; Hayden, Charlotte; Al-Shahi Salman, Rustam; Tebbutt, Stephen; Schroter, Sara

2016-01-01

Objective Frustration continues to be directed at delays in gaining approvals for undertaking health research in the UK. We aimed to evaluate the impact of an ethics officer intervention on rates of favourable opinions (approval) and provisional opinions (requiring revision and resubmission) and on the time taken to reach a final opinion by research ethics committees (RECs), to characterise how the role operated in practice, and to investigate applicants' views. Design Mixed-method study involving (i) a 2-group, non-randomised before-and-after intervention study of RECs assigned an ethics officer and a matched comparator group; (ii) a process evaluation involving a survey of applicants and documentary analysis. Participants 6 RECs and 3 associated ethics officers; 18 comparator RECs; REC applicants. Results Rates of provisional and favourable opinions between ethics officer and comparator RECs did not show a statistically significant effect of the intervention (logistic regression, p=0.26 for favourable opinions and p=0.31 for provisional opinions). Mean time to reach a decision showed a non-significant reduction (ANOVA, p=0.22) from 33.3 to 32.0 days in the ethics officer RECs compared with the comparator RECs (32.6 to 32.9 days). The survey (30% response rate) indicated applicant satisfaction and also suggested that ethics officer support might be more useful before submission. Ethics officers were successful in identifying many issues with applications, but the intervention did not function exactly as designed: in 31% of applicants, no contact between the applicants and the ethics officer took place before REC review. Limitations This study was a non-randomised comparison cohort study. Some data were missing. Conclusions An ethics officer intervention, as designed and implemented in this study, did not increase the proportion of applications to RECs that were approved on first review and did not reduce the time to a committee decision. PMID:27580832

19 CFR 115.41 - Certificate of approval for containers approved after manufacture.

Science.gov (United States)

2010-04-01

... after manufacture. 115.41 Section 115.41 Customs Duties U.S. CUSTOMS AND BORDER PROTECTION, DEPARTMENT... PURSUANT TO INTERNATIONAL CUSTOMS CONVENTIONS Procedures for Approval of Containers After Manufacture § 115.41 Certificate of approval for containers approved after manufacture. The Certifying Authority shall...

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

75 FR 59717 - Agency Information Collection Activities: Announcement of Board Approval Under Delegated...

Science.gov (United States)

2010-09-28

..., New Executive Office Building, Room 10235, Washington, DC 20503. Final approval under OMB delegated... a bank shall establish and maintain written policies and procedures to prevent excessive exposure to... selecting correspondents and terminating those relationships. The policies and procedures should be reviewed...

Final design of the generic upper port plug structure for ITER diagnostic systems

Energy Technology Data Exchange (ETDEWEB)

Pak, Sunil, E-mail: paksunil@nfri.re.kr [National Fusion Research Institute, Daejeon (Korea, Republic of); Feder, Russell [Princeton Plasma Physics Laboratory, Princeton, NJ (United States); Giacomin, Thibaud; Guirao, Julio; Iglesias, Silvia; Josseaume, Fabien [ITER Organization, Route de Vinon sur Verdon, 13115 St Paul-lez-Durance (France); Kalish, Michael; Loesser, Douglas [Princeton Plasma Physics Laboratory, Princeton, NJ (United States); Maquet, Philippe [ITER Organization, Route de Vinon sur Verdon, 13115 St Paul-lez-Durance (France); Ordieres, Javier; Panizo, Marcos [NATEC, Ingenieros, Gijón (Spain); Pitcher, Spencer; Portalès, Mickael [ITER Organization, Route de Vinon sur Verdon, 13115 St Paul-lez-Durance (France); Proust, Maxime [CEA, Cadarache, St. Paul-lez-Durance (France); Ronden, Dennis [FOM Institute DIFFER, Nieuwegein (Netherlands); Serikov, Arkady [Karlsruhe Institute of Technology, Eggenstein-Leopoldshafen (Germany); Suarez, Alejandro [ITER Organization, Route de Vinon sur Verdon, 13115 St Paul-lez-Durance (France); Tanchuk, Victor [NIIEFA, St.-Petersburg (Russian Federation); Udintsev, Victor; Vacas, Christian [ITER Organization, Route de Vinon sur Verdon, 13115 St Paul-lez-Durance (France); and others

2016-01-15

The generic upper port plug (GUPP) structure in ITER is a 6 m long metal box which deploys diagnostic components into the vacuum vessel. This structure is commonly used for all the diagnostic upper ports. The final design of the GUPP structure, which has successfully passed the final design review in 2013, is described here. The diagnostic port plug is cantilevered to the vacuum vessel with a heavy payload at the front, so called the diagnostic first wall (DFW) and the diagnostic shield module (DSM). Most of electromagnetic (EM) load (∼80%) occurs in DFW/DSM. Therefore, the mounting design to transfer the EM load from DFW/DSM to the GUPP structure is challenging, which should also comply with thermal expansion and tolerance for assembly and manufacturing. Another key design parameter to be considered is the gap between the port plug and the vacuum vessel port. The gap should be large enough to accommodate the remote handling of the heavy port plug (max. 25 t), the structural deflection due to external loads and machine assembly tolerance. At the same time, the gap should be minimized to stop the neutron streaming according to the ALARA (as low as reasonably achievable) principle. With these design constraints, the GUPP structure should also provide space for diagnostic integration as much as possible. This requirement has led to the single wall structure having the gun-drilled water channels inside the structure. Furthermore, intensive efforts have been made on the manufacturing study including material selection, manufacturing codes and French regulation related to nuclear equipment and safety. All these main design and manufacturing aspects are discussed in this paper, including requirements, interfaces, loads and structural assessment and maintenance.

AP1000, a nuclear central of advanced design

International Nuclear Information System (INIS)

Hernandez M, N.; Viais J, J.

2005-01-01

The AP1000 is a design of a nuclear reactor of pressurized water (PWR) of 1000 M We with characteristic of safety in a passive way; besides presenting simplifications in the systems of the plant, the construction, the maintenance and the safety, the AP1000 is a design that uses technology endorsed by those but of 30 years of operational experience of the PWR reactors. The program AP1000 of Westinghouse is focused to the implementation of the plant to provide improvements in the economy of the same one and it is a design that is derived directly of the AP600 designs. On September 13, 2004 the US-NRC (for their initials in United States- Nuclear Regulatory Commission) approved the final design of the AP1000, now Westinghouse and the US-NRC are working on the whole in a complete program for the certification. (Author)

California; Northern Sierra Air Quality Management District; Approval of Air Plan Revisions; Wood Burning Devices

Science.gov (United States)

EPA is taking final action to approve a revision to the Northern Sierra Air Quality Management District (NSAQMD) portion of the California SIP concerning emissions of particulate matter (PM) from wood burning devices.

75 FR 45145 - Notice of Submission of Proposed Information Collection to OMB Final Endorsement of Credit...

Science.gov (United States)

2010-08-02

... Proposed Information Collection to OMB Final Endorsement of Credit Instrument (HUD Programs) AGENCY: Office... proposal. Information collected is used to request final endorsement by HUD of the credit instrument. The...: Title of Proposal: Final Endorsement of Credit Instrument. OMB Approval Number: 2502-0016. Form Numbers...

77 FR 53210 - Notice of Proposed Information Collection: Comment Request; Request for Approval of Advance of...

Science.gov (United States)

2012-08-31

... cost not paid at final endorsement, non-critical repairs and capital needs assessment. The mortgagor... Credit Examiner, Inspector, and Architect, must use information collected to approve the withdrawal of...

FINAL DESIGN REVIEW REPORT Subcritical Experiments Gen 2, 3-ft Confinement Vessel Weldment

Energy Technology Data Exchange (ETDEWEB)

Romero, Christopher [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-09-28

A Final Design Review (FDR) of the Subcritical Experiments (SCE) Gen 2, 3-ft. Confinement Vessel Weldment was held at Los Alamos National Laboratory (LANL) on September 14, 2017. The review was a focused review on changes only to the confinement vessel weldment (versus a system design review). The changes resulted from lessons-learned in fabricating and inspecting the current set of confinement vessels used for the SCE Program. The baseline 3-ft. confinement vessel weldment design has successfully been used (to date) for three (3) high explosive (HE) over-tests, two (2) fragment tests, and five (5) integral HE experiments. The design team applied lessons learned from fabrication and inspection of these vessel weldments to enhance fit-up, weldability, inspection, and fitness for service evaluations. The review team consisted of five (5) independent subject matter experts with engineering design, analysis, testing, fabrication, and inspection experience. The

National Ignition Facility subsystem design requirements final optics assembly subsystem SSDR 1.8.7

International Nuclear Information System (INIS)

Adams, C.

1996-01-01

This SSDR establishes the performance, design, development and test requirements for the Final Optic Assembly (FOA). The FOA (WBS 1.8.7) as part of the Target Experimental System (1.8) includes vacuum windows, frequency conversion crystals, focus lens, debris shields and supporting mechanical equipment

78 FR 72036 - Approval and Promulgation of Implementation Plans and Designation of Areas for Air Quality...

Science.gov (United States)

2013-12-02

... maintenance plan to the year 2025 and updating the sub-area motor vehicle emission budgets (MVEBs) for... taking? III. Why is EPA taking these actions? IV. What are the effects of these actions? V. Final Action... design values Location County Monitor ID 2008 2009 2010 2008-2010 Lincoln County Replacing Iron Station...

77 FR 16447 - Approval and Promulgation of Implementation Plans; Designation of Areas for Air Quality Planning...

Science.gov (United States)

2012-03-21

... County, Western Mojave Desert, South Coast Air Basin, Eastern Kern County, and San Diego County. DATES... April 30, 2004 final rule, we designated the Western Mojave Desert area as a moderate nonattainment area... reclassification of several areas for the 1997 8-hour ozone standard. See 75 FR 24409 (May 5, 2010). The Western...

Design and test of the final ALICE SDD CARLOS end ladder board

CERN Document Server

Antinori, S; Falchieri, D; Gabrielli, A; Gandolfi, E; Masetti, M; Tosellob, F

2007-01-01

The paper presents the design and test of the final prototype of the CARLOS (Compression And Run Length Encoding Subsystem) end ladder board that is going to be used in the ALICE experiment at CERN. This board is able to compress data coming from one Silicon Drift Detector (SDD) front-end electronics and to send them towards the data concentrator card CARLOSrx in counting room via a 800 Mb/s optical link. The board design faces several constraints, mainly size (54x49 mm) and radiation tolerance: for this reason the board contains several CERN developed ASICs. A test setup has been realized for selecting the good devices among the 500 cards already produced.

Efficient design of two-dimensional recursive digital filters. Final report

International Nuclear Information System (INIS)

Twogood, R.E.; Mitra, S.K.

1980-01-01

This report outlines the research progress during the period August 1978 to July 1979. This work can be divided into seven basic project areas. Project 1 deals with a comparative study of 2-D recursive and nonrecursive digital filters. The second project addresses a new design technique for 2-D half-plane recursive filters, and Projects 3 thru 5 deal with implementation issues. The sixth project presents our recent study of the applicability of array processors to 2-D digital signal processing. The final project involves our investigation into techniques for incorporating symmetry constraints on 2-D recursive filters in order to yield more efficient implementations

49 CFR 611.13 - Overall project ratings.

Science.gov (United States)

2010-10-01

... Transportation Other Regulations Relating to Transportation (Continued) FEDERAL TRANSIT ADMINISTRATION... to enter into preliminary engineering, final design, or FFGAs. (c) These ratings will be used to: (1) approve advancement of a proposed project into preliminary engineering and final design; (2) Approve...

Sustainability Logistics Basing - Science and Technology Objective - Demonstration; Industry Assessment and Demonstration Final Report

Science.gov (United States)

2017-08-14

TECHNICAL REPORT AD ________________ NATICK/TR-17/019 SUSTAINABILITY ...LOGISTICS BASING – SCIENCE & TECHNOLOGY OBJECTIVE – DEMONSTRATION; INDUSTRY ASSESSMENT AND DEMONSTRATION FINAL REPORT by Elizabeth D. Swisher and...Benjamin J. Campbell August 2017 Final Report December 2014 – February 2016 Approved for public release; distribution is

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.''

Final design and status of the NSLS vacuum system

International Nuclear Information System (INIS)

Schuchman, J.C.

1982-01-01

We describe the final system, as built, reasons for changes and the general status of the NSLS. The NSLS is a dedicated facility for the purpose of producing synchrotron radiation. It consists of an electron linac-booster injector system, and two storage rings, one for uv research and the other for x-ray research. (Synchrotron radiation is produced by accelerating electrons in the storage rings.) The design current and energies are 1000 ma at 700 MeV for the vuv ring and 500 ma at 2.5 GeV for the x-ray ring. A total of 44 experimental beam ports are available for use. Since each beam port may be divided into two or more experimentall beam lines, it is quite plausible to have upward of 100 simultaneously operating beam lines

FERMI(at)Elettra FEL Design Technical Optimization Final Report

International Nuclear Information System (INIS)

Fawley, William; Penn, Gregory; Allaria, Enrico; De Ninno, Giovanni; Graves, William

2006-01-01

This is the final report of the FEL Design Group for the Technical Optimization Study for the FERMI(at)ELETTRA project. The FERMI(at)ELETTRA project is based on the principle of harmonic upshifting of an initial ''seed'' signal in a single pass, FEL amplifier employing multiple undulators. There are a number of FEL physics principles which underlie this approach to obtaining short wavelength output: (1) the energy modulation of the electron beam via the resonant interaction with an external laser seed (2) the use of a chromatic dispersive section to then develop a strong density modulation with large harmonic overtones (3) the production of coherent radiation by the microbunched beam in a downstream radiator. Within the context of the FERMI project, we discuss each of these elements in turn

Design optimization of the International Linear Collider Final Focus System with a long L*

CERN Document Server

Plassard, Fabien

This Master's Thesis work has been done in the Aerospace Engineering master's programme framework and carried out at the European Organization for Nuclear Research (CERN). It was conducted under the 500 GeV e-e+ International Linear Collider (ILC) study and focused on the design and performance optimization of the Final Focus System (FFS). The purpose of the final focus system of the future linear colliders (ILC and CLIC) is to demagnify the beam to the required transverse size at the interaction point (IP). The FFS is designed for a flat-beam in a compact way based on a local chromaticity correction which corrects both horizontal and vertical chromaticities simultaneously. An alternative FFS configuration based on the traditional scheme with two dedicated chromatic correction sections for horizontal and vertical chromaticities and a long L * option has been developed. A longer free space between the last quadrupole and the IP allows to place the last quadrupole on a stable ground, with fewer engineering ...

Template for letter of approval by Research Supervisor

International Development Research Centre (IDRC) Digital Library (Canada)

Liliane Castets-Poupart

a) As research supervisor of J. Smith, I confirm that I approve and support the research proposal submitted by the candidate. b) J. Smith has successfully completed the following course(s):. STAT 890: Statistics, Survey Design and Analysis INAF 540: International Affairs Dynamics. ECON 700: Qualitative Research Data.

Requirements for US regulatory approval of the International Thermonuclear Experimental Reactor (ITER)

International Nuclear Information System (INIS)

Petti, D.A.; Haire, J.C.

1993-12-01

The International Thermonuclear Experimental Reactor (ITER) is the first fusion machine that will have sufficient decay heat and activation product inventory to pose potential nuclear safety concerns. As a result, nuclear safety and environmental issues will be much more important in the approval process for the design, siting, construction, and operation of ITER in the United States than previous fusion devices, such as the Tokamak Fusion Test Reactor. The purpose of this report is (a) to provide an overview of the regulatory approval process for a Department of Energy (DOE) nuclear facility; (b) to present the dose limits used by DOE to protect workers, the public, and the environment from the risks of exposure to radiation and hazardous materials; (c) to discuss some key nuclear safety-related issues that must be addressed early in the Engineering Design Activities (EDA) to obtain regulatory approval; and (d) to provide general guidelines to the ITER Joint Central Team (JCT) concerning the development of a regulatory framework for the ITER project

77 FR 11744 - Approval and Promulgation of Implementation Plans; Tennessee: Prevention of Significant...

Science.gov (United States)

2012-02-28

...), Air Pollution Control Division, to EPA on August 30, 2010, for parallel processing. TDEC submitted the final version of this SIP revision on January 11, 2012. The SIP revision approved by today's action...). List of Subjects in 40 CFR Part 52 Environmental protection, Air pollution control, Greenhouse gases...

77 FR 25003 - Self-Regulatory Organizations; NASDAQ OMX Phlx LLC; Order Approving Proposed Rule Change To Amend...

Science.gov (United States)

2012-04-26

...; review and endorsement of customer orders; final approval of advertising or sales literature for use by... and qualified, given the importance and complexity of the rules governing financial responsibility for...

Final repository for spent nuclear fuel. Underground design Simpevarp, Layout D1

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-04-15

This report is a compilation of the results of the underground design work carried out in design phase D1 of the Repository Design Project within the Deep Repository Project for the Simpevarp site. Similar reports are also being produced for the Laxemar and Forsmark sites. The design phase coincides with the initial site investigation phase. The main purpose of phase D1 is to answer the question 'Can a final repository be accommodated within the designated site', but also to test the design methodology and provide feedback to the modelling project. Design was carried out in accordance with the methodology described in UDP (Underground Design Premises), SKB R-04-60, and was based on preliminary data from various disciplines in the site modelling project. The preliminary input data used were then cross-checked against data in the final Site Descriptive Model SDM v 1.2 and significant differences were integrated in the design work. The design results from each design topic were presented by the designer at presentation meetings for SKB's design management and the reviewers engaged by SKB for the specific topic. After the presentation meeting the designer wrote up the work reports for the topic in question. The work reports were then reviewed by SKB's review team. The results of the review were compiled in a statement that was submitted to the designer to be dealt with. In the statement the designer documented which comments were dealt with and how. This report is a compilation of the entire design phase D1 for Simpevarp. The 3D layout with coordinate lists for deposition holes and tunnels that was drawn to illustrate a possible layout was used in the Preliminary safety evaluation of the Simpevarp subarea and the hydro modelling of the Open Repository, both activities within the Deep Repository Project. According to current plans for the Swedish nuclear programme, the minimum required number of canister positions in the repository is estimated to be

Design and drafting document control procedures for CPRF/ZTH experiment

International Nuclear Information System (INIS)

Pollat, L.L.; Kewish, R.W.

1989-01-01

This paper will present, in general, the control procedures for design approval, review, changes, and release of engineering documents. It will also discuss interface control for tasks so that possible design interference does not occur. A document control procedure to insure that design criteria are met and technical specifications translate into workable drawings was instituted to support the Confinement Physics Research Facility (CPRF/ZTH) construction program. Our goal, to eliminate any conflicts that might arise between various tasks as the final designs are developed, required tight control and up-to-date design information. Detailed procedure for reviews were instituted, since circumventing the process of design and drafting anywhere might have proven disastrous to the CPRF/ZTH program. Design is a process of translating technical requirements, according to established standards, into drawings that are usable for fabrication and assembly. Both the designer and engineer are responsible for adhering to standards that have been established by the Mechanical Engineering Section for the CPRF/ZTH program. 6 refs., 5 figs

A guide for approval of x-ray fluorescence analysis devices

International Nuclear Information System (INIS)

1990-01-01

This guide has been written to assist manufacturers, distributors and users of x-ray fluorescence analysis devices in the preparation of a submission to the Atomic Energy Control Board (AECB) in support of a request for approval of an x-ray fluorescence analysis device. Prior to the issuance of a Radioisotope licence authorizing the use or possession of an x-ray fluorescence analysis device in Canada, the design and construction of the device must be approved by the AECB. The AECB assessment is limited to the radiation safety aspects of use and packaging for transportation

Redfield Energy Approval

Science.gov (United States)

This September 19, 2016 letter from EPA approves the petition from Poet Biorefining-Lake Crystal, regarding non-This October 27, 2016 letter from EPA approves the petition from Redfield Energy, LLC, regarding non-grandfathered ethanol produced

Innovating by developing new uses of already-approved drugs: trends in the marketing approval of supplemental indications.

Science.gov (United States)

DiMasi, Joseph A

2013-06-01

Much of the literature on trends and factors affecting biopharmaceutical innovation has focused overwhelmingly on the development and approval of never-before approved drugs and biologics. Little attention has been paid to new uses for already-approved compounds, which can be an important form of innovation. This paper aimed to determine and analyze recent trends in the number and type of new or modified US indication approvals for drugs and biologics. We also examine regulatory approval-phase times for new-use efficacy supplements and compare them to approval-phase times for original-use approvals over the same period. We developed a data set of efficacy supplements approved by the US Food and Drug Administration (FDA) from 1998 to 2011 that includes information on the type, approval-phase time (time from submission to the FDA of an application for marketing approval to approval of the application), and FDA therapeutic-significance rating for the approved application, which we obtained from an FDA Web site. This data set was merged with a Tufts Center for the Study of Drug Development (CSDD) data set of US new drug and biologics approvals. We developed descriptive statistics on trends in the number and type of new-use efficacy supplements, on US regulatory approval-phase times for the supplements, and on original new drug and biologics approvals over the study period and for the time from original- to new-use approval. The total number of new-use efficacy-supplement approvals did not exhibit a marked trend, but the number of new pediatric-indication approvals increased substantially. Approval-phase times for new-use supplements varied by therapeutic class and FDA therapeutic-significance rating. Mean approval-phase times were highest for central nervous system compounds (13.8 months) and lowest for antineoplastics (8.9 months). The mean time from original to supplement approval was substantially longer for new pediatric indications than for other new uses. Mean

Alternate cap designs under RCRA regulations

International Nuclear Information System (INIS)

Manrod, W.E. III; Yager, R.E.; Craig, P.M.

1988-01-01

Low-level radioactive waste and mixed wastes have been disposed of in several sites in the vicinity of the Oak Ridge Y-12 Plant in Tennessee. Most of these materials have been placed in shallow land burial pits (SLB). Closure plans have been developed and approved by appropriate regulatory agencies for several of these sites. A variety of cap (final cover) designs for closure of these sites were investigated to determine their ability to inhibit infiltration of precipitation to the waste. The most effective designs are those that use synthetic materials as drainage layers and/or impermeable liners. The more complex, multi-layer systems perform no better than simpler covers and would complicate construction and increase costs. Despite the successful analytical results described in this paper, additional considerations must be factored into use of geosynthetic as well as natural materials

76 FR 49313 - Approval and Promulgation of Implementation Plans North Carolina: Prevention of Significant...

Science.gov (United States)

2011-08-10

... Code (NCAC), Subchapter 2D .0530, subsections (a), (b), (g), (i), (u), and (v) (from North Carolina's... and Promulgation of Implementation Plans North Carolina: Prevention of Significant Deterioration and...: EPA is taking final action to approve revisions to the North Carolina State Implementation Plan (SIP...

29 CFR 15.10 - Action on approved claim.

Science.gov (United States)

2010-07-01

.... (a) Payment. Payment of a claim approved under this subpart is contingent upon claimant's execution of a “Voucher for Payment Under Federal Tort Claims Act,” Standard Form 1145. When a claimant is represented by an attorney, the voucher for payment shall designate both the claimant and his or her attorney...

Preliminary design for hot dirty-gas control-valve test facility. Final report

Energy Technology Data Exchange (ETDEWEB)

1980-01-01

This report presents the results of a preliminary design and cost estimating effort for a facility for the testing of control valves in Hot Dirty Gas (HDGCV) service. This design was performed by Mittelhauser Corporation for the United States Department of Energy's Morgantown Energy Technology Center (METC). The objective of this effort was to provide METC with a feasible preliminary design for a test facility which could be used to evaluate valve designs under simulated service conditions and provide a technology data base for DOE and industry. In addition to the actual preliminary design of the test facility, final design/construction/operating schedules and a facility cost estimate were prepared to provide METC sufficient information with which to evaluate this design. The bases, assumptions, and limitations of this study effort are given. The tasks carried out were as follows: METC Facility Review, Environmental Control Study, Gas Generation Study, Metallurgy Review, Safety Review, Facility Process Design, Facility Conceptual Layout, Instrumentation Design, Cost Estimates, and Schedules. The report provides information regarding the methods of approach used in the various tasks involved in the completion of this study. Section 5.0 of this report presents the results of the study effort. The results obtained from the above-defined tasks are described briefly. The turnkey cost of the test facility is estimated to be $9,774,700 in fourth quarter 1979 dollars, and the annual operating cost is estimated to be $960,000 plus utilities costs which are not included because unit costs per utility were not available from METC.

Radiological Medical Device Innovation: Approvals via the Premarket Approval Pathway From 2000 to 2015.

Science.gov (United States)

Ghobadi, Comeron W; Hayman, Emily L; Finkle, Joshua H; Walter, Jessica R; Xu, Shuai

2017-01-01

The aim of this study was to critically assess the clinical evidence leading to radiologic medical device approvals via the premarket approval pathway from 2000 to 2015. This study used the publically available FDA premarket database for radiologic device approvals over the past 15 years (September 1, 2000, to August 31, 2015). Approval characteristics were collected for each device, and statistical analysis was performed on the data for each pivotal trial. Additionally, methodological quality of the pivotal trial was determined using the Quality Assessment of Diagnostic Accuracy Studies tool. Twenty-three class III radiologic device approvals were identified, with breast imaging accounting for 16 (70%) and computer-aided detection software accounting for 9 (39%) approvals. The median premarket approval time was 475 days (range, 180-1,116). Twenty-one devices were approved on the basis of multireader, multicenter studies, one on the basis of a randomized controlled trial, and one on the basis of a preclinical technical equivalence trial. The median number of patients per pivotal trial was 201 (range, 25-3,946). Twenty-six of the 34 pivotal trials (76%) had at least one methodologic bias. Breast imaging devices had a greater number of patients per pivotal trial (P = .009) and more prospective studies. With regard to all modalities, increased time to device approval correlated with weaker trial quality (r = 0.600, P assessing diagnostic technologies. Given that radiologic devices play a key role in modern medicine, further efforts should be made to increase transparency of clinical data leading to approval. Copyright © 2016 American College of Radiology. Published by Elsevier Inc. All rights reserved.

77 FR 25901 - Approval and Promulgation of Air Quality Implementation Plans; Maryland; Removal of the 1980...

Science.gov (United States)

2012-05-02

... email. The www.regulations.gov Web site is an ``anonymous access'' system, which means EPA will not know... annually in 1980 to less than 100,000 tons annually today. III. Final Action EPA is approving MDE's...

30 CFR 18.95 - Approval of machines constructed of components approved, accepted or certified under Bureau of...

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Approval of machines constructed of components... APPROVAL OF MINING PRODUCTS ELECTRIC MOTOR-DRIVEN MINE EQUIPMENT AND ACCESSORIES Field Approval of Electrically Operated Mining Equipment § 18.95 Approval of machines constructed of components approved...

34 CFR 35.7 - Payment of approved claims.

Science.gov (United States)

2010-07-01

... sign the voucher for payment, Standard Form 1145, before payment is made. (b) When the claimant is represented by an attorney, the voucher for payment (SF 1145) shall designate both the claimant and his... 34 Education 1 2010-07-01 2010-07-01 false Payment of approved claims. 35.7 Section 35.7 Education...

12 CFR 793.7 - Payment of approved claims.

Science.gov (United States)

2010-01-01

... voucher for payment, Standard Form 1145, before payment is made. (b) When the claimant is represented by an attorney, the voucher for payment (S.F. 1145) shall designate both the claimant and his attorney... 12 Banks and Banking 6 2010-01-01 2010-01-01 false Payment of approved claims. 793.7 Section 793.7...

77 FR 30523 - Agency Information Collection Activities; Submission to OMB for Review and Approval; Comment...

Science.gov (United States)

2012-05-23

... Activities; Submission to OMB for Review and Approval; Comment Request; RCRA Definition of Solid Waste... Recovery and Waste Management Division, Office of Resource Conservation and Recovery, (5304P... published final revisions to the definition of solid waste that exclude certain hazardous secondary...

76 FR 62806 - Agency Information Collection Activities: Announcement of Board Approval Under Delegated...

Science.gov (United States)

2011-10-11

...; and request for designation as a wholesale or limited purpose bank, 4 hours. Disclosure Requirement... request for designation as a wholesale or limited purpose bank, 1. Disclosure Requirement, public file... FEDERAL RESERVE SYSTEM Agency Information Collection Activities: Announcement of Board Approval...

Mixed waste landfill monitoring prototype test design for Los Alamos National Laboratory. Final report

International Nuclear Information System (INIS)

Keller, C.

1994-09-01

The purpose of this contract is to design the prototype tests necessary for the verification of the measurement methods proposed for the Mixed Waste Disposal Facility. The design is limited to the hydrological performance of the measurement methods. It does not include the mechanical testing of the methods proposed. The test site is to be selected and when approved, construction drawings provided. The contract also includes testing of vitrified clay pipe as the liner of choice for the passages under the landfill. The tests are to be done of both he hydrologic and the mechanical capability of the pipe. The test bed construction is to be supervised as it is being done by the construction contractor monitored by LANL. This contract does not include the logical subsequent work of performance of the measurements in the test bed. Since this contract was received by September 15, with the work to be completed by September 30, only that work possible in the short time was performed. That included the design of the test bed, the purchase of the vitrified clay pipe and the mechanical tests of the pipe, and the purchase of the SEAMIST systems for testing in the clay pipe. None of those could be delivered in time for flow tests to be done on the clay pipe. The mechanical tests were done as part of the pipe purchase and are reported here. The contract was not extended beyond September 30 for lack of funds. This report is therefore limited to the preliminary design of the test bed and to the specification of the orders for the materials. The hope is that funding will be restored to the program for the completion of the design and measurement effort

Northeast Oregon Hatchery Project, Conceptual Design Report, Final Report.

Energy Technology Data Exchange (ETDEWEB)

Watson, Montgomery (Montgomery Watson, Bellevue, WA)

1995-03-01

This report presents the results of site analysis for the Bonneville Power Administration Northeast Oregon Hatchery Project. The purpose of this project is to provide engineering services for the siting and conceptual design of hatchery facilities for the Bonneville Power Administration. The hatchery project consists of artificial production facilities for salmon and steelhead to enhance production in three adjacent tributaries to the Columbia River in northeast Oregon: the Grande Ronde, Walla Walla, and Imnaha River drainage basins. Facilities identified in the master plan include adult capture and holding facilities; spawning incubation, and early rearing facilities; full-term rearing facilities; and direct release or acclimation facilities. The evaluation includes consideration of a main production facility for one or more of the basins or several smaller satellite production facilities to be located within major subbasins. The historic and current distribution of spring and fall chinook salmon and steelhead was summarized for the Columbia River tributaries. Current and future production and release objectives were reviewed. Among the three tributaries, forty seven sites were evaluated and compared to facility requirements for water and space. Site screening was conducted to identify the sites with the most potential for facility development. Alternative sites were selected for conceptual design of each facility type. A proposed program for adult holding facilities, final rearing/acclimation, and direct release facilities was developed.

Northeast Oregon Hatchery Project conceptual design report. Final report

International Nuclear Information System (INIS)

1995-03-01

This report presents the results of site analysis for the Bonneville Power Administration Northeast Oregon Hatchery Project. The purpose of this project is to provide engineering services for the siting and conceptual design of hatchery facilities for the Bonneville Power Administration. The hatchery project consists of artificial production facilities for salmon and steelhead to enhance production in three adjacent tributaries to the Columbia River in northeast Oregon: the Grande Ronde, Walla Walla, and Imnaha River drainage basins. Facilities identified in the master plan include adult capture and holding facilities; spawning incubation, and early rearing facilities; full-term rearing facilities; and direct release or acclimation facilities. The evaluation includes consideration of a main production facility for one or more of the basins or several smaller satellite production facilities to be located within major subbasins. The historic and current distribution of spring and fall chinook salmon and steelhead was summarized for the Columbia River tributaries. Current and future production and release objectives were reviewed. Among the three tributaries, forty seven sites were evaluated and compared to facility requirements for water and space. Site screening was conducted to identify the sites with the most potential for facility development. Alternative sites were selected for conceptual design of each facility type. A proposed program for adult holding facilities, final rearing/acclimation, and direct release facilities was developed

Drugs Approved for Breast Cancer

Science.gov (United States)

... Ask about Your Treatment Research Drugs Approved for Breast Cancer This page lists cancer drugs approved by the ... are not listed here. Drugs Approved to Prevent Breast Cancer Evista (Raloxifene Hydrochloride) Raloxifene Hydrochloride Tamoxifen Citrate Drugs ...

Conceptual design of bend, compression, and final focus components of ILSE [Induction Linac System Experiment

International Nuclear Information System (INIS)

Lee, E.P.; Fong, C.; Mukherjee, S.; Thur, W.

1989-03-01

The Induction Linac System Experiment (ILSE) includes a 180/degree/ bend system, drift compression line and a final focus, which test the analogous features of a heavy ion driver for inertial fusion. These components are novel in their transport of a space-charge-dominated ion beam with large head-to-tail velocity tilt. Their conceptual design is presented, including calculations of the beam envelope, momentum dispersion, and engineering design of magnets, vacuum system, diagnostics, alignment, and support. 3 refs., 5 figs

Drugs Approved for Thyroid Cancer

Science.gov (United States)

... Ask about Your Treatment Research Drugs Approved for Thyroid Cancer This page lists cancer drugs approved by the ... that are not listed here. Drugs Approved for Thyroid Cancer Cabozantinib-S-Malate Caprelsa (Vandetanib) Cometriq (Cabozantinib-S-Malate) Doxorubicin ...

78 FR 26258 - Approval and Promulgation of Air Quality Implementation Plans; Illinois; Consumer Products and...

Science.gov (United States)

2013-05-06

... adopt these VOC limits to create more consistency in regional and national markets for consumer products... organic compound (VOC) content limits and associated provisions for additional consumer products categories into the state's SIP. Finally, EPA is approving language to clarify VOC limit applicability for...

Excipients and their role in approved injectable products: current usage and future directions.

Science.gov (United States)

Nema, Sandeep; Brendel, Ronald J

2011-01-01

This review article is a current survey of excipients used in approved injectable products. Information provided includes concentration ranges, function, frequency of use, and role in dosage form. This article is an update of a paper published more than a decade ago (reference 11). Since then many new products have been approved. Safety concerning excipients has evolved as the scientific community continues to learn about their usage. New excipients are being used in early phases of clinical trials to support novel therapeutic entities like RNAi, aptamers, anti-sense, fusion proteins, monoclonal antibodies, and variant scaffolds. Because these excipients are not inert, various pharmacopoeias are responding with monographs or informational chapters addressing excipient functionality. The final sections of this article discuss new excipients, serving specific needs that traditional excipients are unable to provide and for which safety studies are necessary to support a novel excipient for marketing applications. Excipients are added to parenteral dosage forms to serve a variety of functions including stabilization and as vehicles. This review article is a survey of excipients used in approved injectable products. Information provided includes excipient concentrations, functional roles, and frequency of use. This article is an update of an article originally published over a decade ago. Since then new products have been approved and safety concerns have evolved as the scientific community has learned about the usage of excipients. In addition, new excipients are being used in early phases of clinical trials to support novel therapeutic entities such as RNAi, aptamers, anti-sense, fusion proteins, monoclonal antibodies, and variant scaffolds. Because these excipients are not inert, various pharmacopoeias are responding with monographs or informational chapters addressing excipient functionality. The final sections of this article discuss new excipients, serving

Final safety evaluation report related to the certification of the advanced boiling water reactor design. Volume 2: Appendices

International Nuclear Information System (INIS)

1994-07-01

This safety evaluation report (SER) documents the technical review of the US Advanced Boiling Water Reactor (ABWR) standard design by the US Nuclear Regulatory Commission (NRC) staff. The application for the ABWR design was initially submitted by the General Electric Company, now GE Nuclear Energy (GE), in accordance with the procedures of Appendix O of Part 50 of Title 10 of the code of Federal Regulations (10 CFR Part 50). Later GE requested that its application be considered as an application for design approval and subsequent design certification pursuant to 10 CFR section 52.45. The ABWR is a single-cycle, forced-circulation, boiling water reactor (BWR) with a rated power of 3,926 megawatts thermal (MWt) and a design power of 4,005 MWt. To the extent feasible and appropriate, the staff relied on earlier reviews for those ABWR design features that are substantially the same as those previously considered. Unique features of the ABWR design include internal recirculation pumps, fine-motion control rod drives, microprocessor-based digital logic and control systems, and digital safety systems. On the basis of its evaluation and independent analyses, the NRC staff concludes that, subject to satisfactory resolution of the confirmatory items identified in Section 1.8 of this SER, GE's application for design certification meets the requirements of Subpart B of 10 CFR Part 52 that are applicable and technically relevant to the US ABWR standard design

42 CFR 8.34 - Court review of final administrative action; exhaustion of administrative remedies.

Science.gov (United States)

2010-10-01

... HEALTH AND HUMAN SERVICES GENERAL PROVISIONS CERTIFICATION OF OPIOID TREATMENT PROGRAMS Procedures for... Withdrawal of Approval of an Accreditation Body § 8.34 Court review of final administrative action...

Directory of Certificates of Compliance for Radioactive Materials Packages: Report of NRC approved packages

International Nuclear Information System (INIS)

1988-12-01

This directory contains a Report of the US Nuclear Regulatory Commission's Approved Packages (Volume 1), all Certificates of Compliance (Volume 2), and a Report of NRC Approved Quality Assurance Programs (Volume 3) for Radioactive Material Packages effective October 1, 1988. The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the front of Volume 2 of the directory. A listing by packaging types is included in the back of Volume 2. An alphabetical listing by Company name is included in the back of Volume 3 for approved QA programs. The Reports include a listing of all users of each package design and approved QA programs prior to the publication date of the directory

Directory of certificates of compliance for radioactive materials packages, Report of NRC approved packages

International Nuclear Information System (INIS)

1990-10-01

This directory contains a Report of the US Nuclear Regulatory Commission's Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Report of NRC Approved Quality Assurance Programs (Volume 3) for Radioactive Materials Packages effective October 1, 1990. The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the front of Volume 2 of the directory. A listing by packaging types is included in the back of Volume 2. An alphabetical listing by Company name is included in the back of Volume 3 for approved QA programs. The Reports include a listing of all users of each package design and approved QA programs prior to the publication date of the directory

78 FR 45231 - Medicare and Medicaid Programs; Initial Approval of Center for Improvement in Healthcare Quality...

Science.gov (United States)

2013-07-26

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Medicare & Medicaid Services [CMS-3280-FN] Medicare and Medicaid Programs; Initial Approval of Center for Improvement in Healthcare Quality's (CIHQ's) Hospital Accreditation Program AGENCY: Centers for Medicare and Medicaid Services, HHS. ACTION: Final...

Nuclear Electric flask design and safety case development during the last ten years

International Nuclear Information System (INIS)

Dougall, I.; Jones, D.K.

1994-01-01

The scope of Nuclear Electric's (NE) requirements for irradiated fuel transport and the relevant safety and regulatory compliance standards are outlined. To illustrate NE's approach to demonstrating package design compliance the basis of the safety case for unbottled Magnox fuel transport in the Mk M2 Magnox flask is described. The considerations which lay behind the development of the Mk A2 AGR Flask are indicated and a description is given of the main design features of this flask. Finally there is a summary of progress in obtaining Type B(M) approvals, based on the 1985 IAEA Regulations, for the requisite range of flask contents. (author)

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 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

Spent nuclear fuel project cold vacuum drying facility vacuum and purge system design description

Energy Technology Data Exchange (ETDEWEB)

IRWIN, J.J.

1998-11-30

This document provides the System Design Description (SDD) for the Cold Vacuum Drying Facility (CVDF) Vacuum and Purge System (VPS) . The SDD was developed in conjunction with HNF-SD-SNF-SAR-O02, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998), The HNF-SD-SNF-DRD-002, 1998, Cold Vacuum Drying Facility Design Requirements, and the CVDF Design Summary Report. The SDD contains general descriptions of the VPS equipment, the system functions, requirements and interfaces. The SDD provides references for design and fabrication details, operation sequences and maintenance. This SDD has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

Spent nuclear fuel project cold vacuum drying facility process water conditioning system design description

International Nuclear Information System (INIS)

IRWIN, J.J.

1998-01-01

This document provides the System Design Description (SDD) for the Cold Vacuum Drying Facility (CVDF) Process Water Conditioning (PWC) System. The SDD was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998), the HNF-SD-SNF-DRD-O02, 1998, Cold Vacuum Drying Facility Design Requirements, and the CVDF Design Summary Report. The SDD contains general descriptions of the PWC equipment, the system functions, requirements and interfaces. The SDD provides references for design and fabrication details, operation sequences and maintenance. This SDD has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

Spent nuclear fuel project cold vacuum drying facility vacuum and purge system design description

International Nuclear Information System (INIS)

IRWIN, J.J.

1998-01-01

This document provides the System Design Description (SDD) for the Cold Vacuum Drying Facility (CVDF) Vacuum and Purge System (VPS) . The SDD was developed in conjunction with HNF-SD-SNF-SAR-O02, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998), The HNF-SD-SNF-DRD-002, 1998, Cold Vacuum Drying Facility Design Requirements, and the CVDF Design Summary Report. The SDD contains general descriptions of the VPS equipment, the system functions, requirements and interfaces. The SDD provides references for design and fabrication details, operation sequences and maintenance. This SDD has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

Approaches to safety, environment and regulatory approval for the International Thermonuclear Experimental Reactor

International Nuclear Information System (INIS)

Saji, G.; Bartels, H.W.; Chuyanov, V.; Holland, D.; Kashirski, A.V.; Morozov, S.I.; Piet, S.J.; Poucet, A.; Raeder, J.; Rebut, P.H.; Topilski, L.N.

1995-01-01

International Thermonuclear Experimental Reactor (ITER) Engineering Design Activities (EDA) in safety and environment are approaching the point where conceptual safety design, topic studies and research will give way to project oriented engineering design activities. The Joint Central Team (JCT) is promoting safety design and analysis necessary for siting and regulatory approval. Scoping studies are underway at the general level, in terms of laying out the safety and environmental design framework for ITER. ITER must follow the nuclear regulations of the host country as the future construction site of ITER. That is, regulatory approval is required before construction of ITER. Thus, during the EDA, some preparations are necessary for the future application for regulatory approval. Notwithstanding the future host country's jurisdictional framework of nuclear regulations, the primary responsibility for safety and reliability of ITER rests with the legally responsible body which will operate ITER. Since scientific utilization of ITER and protection of the large investment depends on safe and reliable operation of ITER, we are highly motivated to achieve maximum levels of operability, maintainability, and safety. ITER will be the first fusion facility in which overall 'nuclear safety' provisions need to be integrated into the facility. For example, it will be the first fusion facility with significant decay heat and structural radiational damage. Since ITER is an experimental facility, it is also important that necessary experiments can be performed within some safety design limits without requiring extensive regulatory procedures. ITER will be designed with such a robust safety envelope compatible with the fusion power and the energy inventories. The basic approach to safety will be realized by 'defense-in-depth'. (orig.)

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

Design of a Scalable Modular Production System for a Two-stage Food Service Franchise System

Directory of Open Access Journals (Sweden)

Matt

2012-11-01

industrial case. Information was collected through multiple site visits, workshops and semi‐structured interviews with the company’s key staff of the project, as well as examination of relevant company documentations. By means of a scenario for the Central European market, the model was reviewed in terms of its development potential and finally approved for implementation. However, research through case survey requires further empirical investigation to fully establish this approach as a valid and reliable design tool.

A Document Imaging Technique for Implementing Electronic Loan Approval Process

Directory of Open Access Journals (Sweden)

J. Manikandan

2015-04-01

Full Text Available The image processing is one of the leading technologies of computer applications. Image processing is a type of signal processing, the input for image processor is an image or video frame and the output will be an image or subset of image [1]. Computer graphics and computer vision process uses an image processing techniques. Image processing systems are used in various environments like medical fields, computer-aided design (CAD, research fields, crime investigation fields and military fields. In this paper, we proposed a document image processing technique, for establishing electronic loan approval process (E-LAP [2]. Loan approval process has been tedious process, the E-LAP system attempts to reduce the complexity of loan approval process. Customers have to login to fill the loan application form online with all details and submit the form. The loan department then processes the submitted form and then sends an acknowledgement mail via the E-LAP to the requested customer with the details about list of documents required for the loan approval process [3]. The approaching customer can upload the scanned copies of all required documents. All this interaction between customer and bank take place using an E-LAP system.

77 FR 24585 - List of Approved Spent Fuel Storage Casks: HI-STORM 100, Revision 8

Science.gov (United States)

2012-04-25

... Storage Casks: HI-STORM 100, Revision 8 AGENCY: Nuclear Regulatory Commission. ACTION: Direct final rule... revising the Holtec International HI-STORM 100 System listing within the ``List of Approved Spent Fuel...) 72.214, by revising the Holtec International HI-STORM 100 System listing within the ``List of...

Auditing the process of ethics approval for Master's degrees at a ...

African Journals Online (AJOL)

2014-05-01

May 1, 2014 ... of ethics approval for Master's level research at the Nelson R Mandela ... The following information was retrieved: ... Any system designed to improve this situation must ensure that high standards of vigilance are maintained, ...

Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 2004 ed

International Nuclear Information System (INIS)

2004-10-01

The PACKTRAM database contains administrative and technical information provided annually by the issuing competent authority about package approval certificates. Such data are used mainly by national competent authorities and port and customs officials to assist in regulating radioactive material movements in their country, and also by manufacturers and shippers of radioactive material. The database carries information on extant certificates and those that expired within the last complete calendar year. This is the fifteenth PACKTRAM annual report to being published by the IAEA. It is distributed worldwide mainly to designated competent authorities, as well as to registered interested parties. The database itself is maintained at www.packtram.org and can be accessed by the general public

Evaluating the Status Approvals about Cinema (1989 to 2009

Directory of Open Access Journals (Sweden)

Elahe Dehghan Pishe

2012-06-01

Full Text Available The present study aimed to study and evaluate the state approvals in the field of The cabinet approval in mentioned period 1989 to 2009 in Iran. cinema from which keywords related to cinema is shown in their titles or texts will form this The method of this research is content analysis and the instrument used .research is a checklist with r= 0.91 using Scott formula. The content analysis checklist was constructed based on the model which classified arts policies into four types namely: facilitator, patron, architect and engineer. The findings revealed that in the investigated twenty-year process. the various states having come in 4-year intervals have been different in using the types of arts policies. The state in the first and second presidency of Akbar Hashemi Rafsanjani used the facilitator and engineer types; in the first presidency of Mohammad Khatami used the patron and architect types, in his second presidency the architect type; and finally in the first presidency of Mahmoud Ahmadinejad used the architect and engineer types more than the other types. Although there has been a difference between the types of arts policy in the cinema approvals in different periods of presidency. the architect and engineer types of arts policies have been used more than the facilitator and patron types.

Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project - Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

Saurwein, John

2011-07-15

This report is the Final Technical Report for the Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project conducted by a team led by General Atomics under DOE Award DE-NE0000245. The primary overall objective of the project was to develop and document a conceptual design for the Steam Cycle Modular Helium Reactor (SC-MHR), which is the reactor concept proposed by General Atomics for the NGNP Demonstration Plant. The report summarizes the project activities over the entire funding period, compares the accomplishments with the goals and objectives of the project, and discusses the benefits of the work. The report provides complete listings of the products developed under the award and the key documents delivered to the DOE.

Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project - Final Technical Report

International Nuclear Information System (INIS)

Saurwein, J.

2011-01-01

This report is the Final Technical Report for the Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project conducted by a team led by General Atomics under DOE Award DE-NE0000245. The primary overall objective of the project was to develop and document a conceptual design for the Steam Cycle Modular Helium Reactor (SC-MHR), which is the reactor concept proposed by General Atomics for the NGNP Demonstration Plant. The report summarizes the project activities over the entire funding period, compares the accomplishments with the goals and objectives of the project, and discusses the benefits of the work. The report provides complete listings of the products developed under the award and the key documents delivered to the DOE.

Designing the central knowledge base for the purposes of final works in architecture

Directory of Open Access Journals (Sweden)

Aleksić Ljiljana

2014-01-01

Full Text Available The solution for many issues related to the selection of construction products, currently present on the market, could be a Central knowledge base, consisting of verified and reliable data of construction products. Beside previous participants: investor, architect and contractor, that were involved in the processes of design and construction, herein is equally introduced manufacturer construction materials and products. The Central knowledge base consists of: a catalog sheets of the graphics base, alphanumeric base and base with textual data, and represents a flexible system that is subject to amendments. It is built to support architects during processes design and construction, as well as for education of students attending subject Final works at the Faculty of Civil Engineering in Subotica.

77 FR 65518 - Approval and Promulgation of Air Quality Implementation Plans; Delaware; Prevention of...

Science.gov (United States)

2012-10-29

... email. The www.regulations.gov Web site is an ``anonymous access'' system, which means EPA will not know... proposed revision to the Delaware SIP. The revision is to 7 DE Admin. Code 1125--Requirements for... DE Admin. Code 1125. Final approval of Delaware's October 12, 2011 SIP revision will put in place the...

5 CFR 7101.102 - Prior approval for outside employment.

Science.gov (United States)

2010-01-01

... STANDARDS OF ETHICAL CONDUCT FOR EMPLOYEES OF THE NATIONAL LABOR RELATIONS BOARD § 7101.102 Prior approval... forth, at a minimum: (i) The name of the employer; (ii) The nature of the legal activity or other work... designee may consult with the Designated Agency Ethics Official to ensure that the request for outside...

MINIMARS conceptual design: Final report

International Nuclear Information System (INIS)

Lee, J.D.

1986-09-01

This volume of the conceptual design report contains detailed information on the following: (1) plasma engineering, (2) tandem mirror optimization code, (3) configuration, (4) assembly and maintenance, (5) availability, (6) site and facilities, (7) magnet design, (8) end-cell shielding, (9) drift pumping system, (10) rf systems, (11) negative-ion neutral beam injection system, (12) sloshing-ion beamline, and (13) power balance and electrical systems

Safety culture in design. Final report

International Nuclear Information System (INIS)

Macchi, L.; Pietikaeinen, E.; Liinasuo, M.; Savioja, P.; Reiman, T.; Wahlstroem, M.; Kahlbom, U.; Rollenhagen, C.

2013-04-01

In this report we approach design from a safety culture approach As this research area is new and understudied, we take a wide scope on the issue. Different theoretical perspectives that can be taken when improving safety of the design process are considered in this report. We suggest that in the design context the concept of safety culture should be expanded from an organizational level to the level of the network of organizations involved in the design activity. The implication of approaching the design process from a safety culture perspective are discussed and the results of the empirical part of the research are presented. In the interview study in Finland and Sweden we identified challenges and opportunities in the design process from safety culture perspective. Also, a small part of the interview study concentrated on state of the art human factors engineering (HFE) practices in Finland and the results relating to that are presented. This report provide a basis for future development of systematic good design practices and for providing guidelines that can lead to safe and robust technical solutions. (Author)

Safety culture in design. Final report

Energy Technology Data Exchange (ETDEWEB)

Macchi, L.; Pietikaeinen, E.; Liinasuo, M.; Savioja, P.; Reiman, T.; Wahlstroem, M. [VTT Technical Research Centre of Finland, Espoo (Finland); Kahlbom, U. [Risk Pilot AB, Stockholm (Sweden); Rollenhagen, C. [Vattenfall, Stockholm, (Sweden)

2013-04-15

In this report we approach design from a safety culture approach As this research area is new and understudied, we take a wide scope on the issue. Different theoretical perspectives that can be taken when improving safety of the design process are considered in this report. We suggest that in the design context the concept of safety culture should be expanded from an organizational level to the level of the network of organizations involved in the design activity. The implication of approaching the design process from a safety culture perspective are discussed and the results of the empirical part of the research are presented. In the interview study in Finland and Sweden we identified challenges and opportunities in the design process from safety culture perspective. Also, a small part of the interview study concentrated on state of the art human factors engineering (HFE) practices in Finland and the results relating to that are presented. This report provide a basis for future development of systematic good design practices and for providing guidelines that can lead to safe and robust technical solutions. (Author)

78 FR 69299 - Approval and Promulgation of Air Quality Implementation Plans; Ohio; Ohio SO2

Science.gov (United States)

2013-11-19

... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 52 [EPA-R05-OAR-2011-0672; FRL-9902-03-Region 5] Approval and Promulgation of Air Quality Implementation Plans; Ohio; Ohio SO2 Air Quality Rule Revisions AGENCY: Environmental Protection Agency (EPA). ACTION: Direct final rule. SUMMARY: On June 24, 2011, Ohio...

77 FR 26441 - Approval and Promulgation of Implementation Plans; North Carolina; Charlotte; Ozone 2002 Base...

Science.gov (United States)

2012-05-04

... Promulgation of Implementation Plans; North Carolina; Charlotte; Ozone 2002 Base Year Emissions Inventory... final action to approve the ozone 2002 base year emissions inventory portion of the state implementation... Air Act (CAA or Act). EPA will take action on the South Carolina submission for the ozone 2002 base...

78 FR 4796 - Approval and Promulgation of Implementation Plans; South Carolina: New Source Review-Prevention...

Science.gov (United States)

2013-01-23

... (NO X ) and Sulfur Dioxide (SO 2 ) Budget Trading Program General Provisions. EPA took final action to... monoxide, carbon dioxide, carbonic acid, metallic carbides, or carbonates, and ammonium carbonate) which... NAAQS and the 2008 lead NAAQS. Further, EPA is proposing to approve South Carolina's removal of the 1...

Puget Sound Tidal Energy In-Water Testing and Development Project Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

Collar, Craig W

2012-11-16

Tidal energy represents potential for the generation of renewable, emission free, environmentally benign, and cost effective energy from tidal flows. A successful tidal energy demonstration project in Puget Sound, Washington may enable significant commercial development resulting in important benefits for the northwest region and the nation. This project promoted the United States Department of Energy's Wind and Hydropower Technologies Program's goals of advancing the commercial viability, cost-competitiveness, and market acceptance of marine hydrokinetic systems. The objective of the Puget Sound Tidal Energy Demonstration Project is to conduct in-water testing and evaluation of tidal energy technology as a first step toward potential construction of a commercial-scale tidal energy power plant. The specific goal of the project phase covered by this award was to conduct all activities necessary to complete engineering design and obtain construction approvals for a pilot demonstration plant in the Admiralty Inlet region of the Puget Sound. Public Utility District No. 1 of Snohomish County (The District) accomplished the objectives of this award through four tasks: Detailed Admiralty Inlet Site Studies, Plant Design and Construction Planning, Environmental and Regulatory Activities, and Management and Reporting. Pre-Installation studies completed under this award provided invaluable data used for site selection, environmental evaluation and permitting, plant design, and construction planning. However, these data gathering efforts are not only important to the Admiralty Inlet pilot project. Lessons learned, in particular environmental data gathering methods, can be applied to future tidal energy projects in the United States and other parts of the world. The District collaborated extensively with project stakeholders to complete the tasks for this award. This included Federal, State, and local government agencies, tribal governments, environmental groups, and

IAEA Board of Governors approves IAEA action plan to combat nuclear terrorism

International Nuclear Information System (INIS)

2002-01-01

The IAEA Board of Governors today approved in principal an action plan designed to upgrade worldwide protection against acts of terrorism involving nuclear and other radioactive materials. In approving the plan, the Board has recognized that the first line of defense against nuclear terrorism is the strong physical protection of nuclear facilities and materials. 'National measures for protecting nuclear material and facilities are uneven in their substance and application,' the IAEA says. 'There is wide recognition that the international physical protection regime needs to be strengthened.'

Design, construction and conditions of the application of unreinforced concrete final lining in conventionally driven tunnels

Science.gov (United States)

Faltýnek, Jan; Hořejší, Jiří; Mařík, Libor; Růžička, Pavel

2017-09-01

The way to an economic design in the final lining in conventionally driven tunnels lies in structural analysing based on the actually encountered geotechnical conditions. Regarding reinforced concrete structures, many standards and regulations applicable to designing and building structures and taking them over by the client before their commissioning and before the end of the warranty period respectively exist in the Czech Republic. If the local conditions allow it, it is possible to design the final lining as an unreinforced concrete structure. In such a case it is necessary to take the differences into consideration in the structural design and in the possibilities of the lining behaviour and to set criteria for taking over the lining allowing for its use. Setting too stringent criteria for cracking can lead to an increase in the contract price, either because of the necessity for reinforcing the lining or because of the fact that the contractor reduces the risk by incorporating the assumed cost of repairs into the total cost. The paper describes basic differences in the approach to reinforced concrete and unreinforced concrete linings, the possibilities of limiting formation of cracks by means of the concrete mix design, by selection of the technological procedure of the work and the method of curing after stripping. The text contains a comparison of criteria for assessing the surface of an unreinforced concrete lining with criteria in foreign regulations.

Equipment design guidance document for flammable gas waste storage tank new equipment

International Nuclear Information System (INIS)

Smet, D.B.

1996-01-01

This document is intended to be used as guidance for design engineers who are involved in design of new equipment slated for use in Flammable Gas Waste Storage Tanks. The purpose of this document is to provide design guidance for all new equipment intended for application into those Hanford storage tanks in which flammable gas controls are required to be addressed as part of the equipment design. These design criteria are to be used as guidance. The design of each specific piece of new equipment shall be required, as a minimum to be reviewed by qualified Unreviewed Safety Question evaluators as an integral part of the final design approval. Further Safety Assessment may be also needed. This guidance is intended to be used in conjunction with the Operating Specifications Documents (OSDs) established for defining work controls in the waste storage tanks. The criteria set forth should be reviewed for applicability if the equipment will be required to operate in locations containing unacceptable concentrations of flammable gas

A Tool for Predicting Regulatory Approval After Phase II Testing of New Oncology Compounds.

Science.gov (United States)

DiMasi, J A; Hermann, J C; Twyman, K; Kondru, R K; Stergiopoulos, S; Getz, K A; Rackoff, W

2015-11-01

We developed an algorithm (ANDI) for predicting regulatory marketing approval for new cancer drugs after phase II testing has been conducted, with the objective of providing a tool to improve drug portfolio decision-making. We examined 98 oncology drugs from the top 50 pharmaceutical companies (2006 sales) that first entered clinical development from 1999 to 2007, had been taken to at least phase II development, and had a known final outcome (research abandonment or regulatory marketing approval). Data on safety, efficacy, operational, market, and company characteristics were obtained from public sources. Logistic regression and machine-learning methods were used to provide an unbiased approach to assess overall predictability and to identify the most important individual predictors. We found that a simple four-factor model (activity, number of patients in the pivotal phase II trial, phase II duration, and a prevalence-related measure) had high sensitivity and specificity for predicting regulatory marketing approval. © 2015 American Society for Clinical Pharmacology and Therapeutics.

The AGP-Project conceptual design for a Spanish HLW final disposal facility

International Nuclear Information System (INIS)

Biurrun, E.; Engelmann, H.-J.; Huertas, F.; Ulibarri, A.

1992-01-01

Within the framework of the AGP Project a Conceptual Design for a HLW Final Disposal Facility to be eventually built in an underground salt formation in Spain has been developed. The AGP Project has the character of a system analysis. In the current project phase I several alternatives has been considered for different subsystems and/or components of the repository. The system variants, developed to such extent as to allow a comparison of their advantages and disadvantages, will allow the selection of a reference concept, which will be further developed to technical maturity in subsequent project phases. (author)

Mechanical design of a pre-isolator for the CLIC final focusing magnets

CERN Document Server

Gaddi, A; Ramos, F; Siegrist, N

2012-01-01

Due to the very small vertical beam sizes, the final focusing elements at the future CLIC linear collider need to be stable against vibrations to below 0.15 nanometres at frequencies above about 4 Hz. One of the key elements in the strategy to achieve such a stable environment is a passive, heavy pre-isolator. In this report, the results from the dynamic finite element analyses of the proposed design for such a passive preisolator are summarized. Furthermore, the results from a low frequency, heavy mass passive vibration isolation test set-up used to validate the calculations are shown.

Retrievable storage concept designs. Final report

International Nuclear Information System (INIS)

Nickell, R.E.

1979-01-01

Three tasks related to the reference design of retrievable storage canisters for radioactive waste have been completed. The three tasks consist of the reference design itself, the definition of failure modes most appropriate for structural integrity determinations for the reference canister, and the development of a failure methodology for the structural integrity of the containers. The reference design is a sealed storage canister concept based upon the waste isolation pilot plant (WIPP) design, with slight modifications. The modifications consist of an alternate lifting yoke arrangement for the top head and a revised bottom head design for absorption of impact energy. Welded closures provide the seal at each end. Overpacking is considered as a possibility, but is not included in the preliminary reference design. The four failure modes that are deemed the most appropriate for the design of the reference canister are: (i) a loss of functional capability; (ii) ductile rupture of the canister; (iii) buckling of the structural members; and (iv) stress corrosion cracking. Failure scenarios are provided for each of the relevant failure modes. In addition, a failure methodology based upon the distribution of demand and the distribution of capacity for the structural members, with respect to each failure mode, is proffered

Further development of public participation in the site-selection and approval process of a final repository in Germany

Energy Technology Data Exchange (ETDEWEB)

Barth, Regine; Kallenbach-Herbert, Beate [OeEo-Institute e.V., Inst. for Applied Ecology, Darmstadt (Germany); Arens, Georg [Federal Office for Radiation Protection (BfS), Salzgitter (Germany)

2006-09-15

This paper reflects the first findings of a current research project funded by the German Federal Office for Radiation Protection and conducted by an interdisciplinary working group of the OEko-Institute. One focus of this project is the systematic analysis of past and existing participatory processes in different nuclear and non-nuclear projects. On the basis of this analysis and a literature review a specific concept for public participation in the site-selection and approval process of a repository for high radioactive waste (HAW repository) in Germany will be derived. The concept shall foster transparency and acceptance. The working group of the OEko-Institute combines long standing research experience and an intimate knowledge of radioactive waste management including political, technical, management and social problems of final disposal on the one hand. On the other hand members play an active role in stakeholder processes of different non-nuclear projects as well as experience with a wide range of participative measures and their impact. This allows an approach which integrates the specific features of radioactive waste disposal with a wider perspective on the demands and opportunities of stakeholder processes. The procedure of site selection for a HAW repository in Germany still has to be specified. The procedure introduced by the 'Committee on a Site Selection Procedure for Repository Sites' (Arbeitskreis Auswahlverfahren Endlagerstandorte - AkEnd) has not been adopted. The Committee had suggested installing a negotiation group to discuss the AkEnd proposals in the so called 'Phase II'. This suggestion could not be followed because not all relevant stakeholders were willing to participate. An internal draft for a federal law implementing main elements of the AkEnd findings was developed by the Ministry for Environment in 2005, but has never been brought to the cabinet. Due to the change of Government in Germany, the next steps still are

Further development of public participation in the site-selection and approval process of a final repository in Germany

International Nuclear Information System (INIS)

Barth, Regine; Kallenbach-Herbert, Beate; Arens, Georg

2006-01-01

This paper reflects the first findings of a current research project funded by the German Federal Office for Radiation Protection and conducted by an interdisciplinary working group of the OEko-Institute. One focus of this project is the systematic analysis of past and existing participatory processes in different nuclear and non-nuclear projects. On the basis of this analysis and a literature review a specific concept for public participation in the site-selection and approval process of a repository for high radioactive waste (HAW repository) in Germany will be derived. The concept shall foster transparency and acceptance. The working group of the OEko-Institute combines long standing research experience and an intimate knowledge of radioactive waste management including political, technical, management and social problems of final disposal on the one hand. On the other hand members play an active role in stakeholder processes of different non-nuclear projects as well as experience with a wide range of participative measures and their impact. This allows an approach which integrates the specific features of radioactive waste disposal with a wider perspective on the demands and opportunities of stakeholder processes. The procedure of site selection for a HAW repository in Germany still has to be specified. The procedure introduced by the 'Committee on a Site Selection Procedure for Repository Sites' (Arbeitskreis Auswahlverfahren Endlagerstandorte - AkEnd) has not been adopted. The Committee had suggested installing a negotiation group to discuss the AkEnd proposals in the so called 'Phase II'. This suggestion could not be followed because not all relevant stakeholders were willing to participate. An internal draft for a federal law implementing main elements of the AkEnd findings was developed by the Ministry for Environment in 2005, but has never been brought to the cabinet. Due to the change of Government in Germany, the next steps still are under consideration

Final safety evaluation report related to the certification of the advanced boiling water reactor design. Volume 1: Main report

International Nuclear Information System (INIS)

1994-07-01

This safety evaluation report (SER) documents the technical review of the US Advanced Boiling Water Reactor (ABWR) standard design by the US Nuclear Regulatory Commission (NRC) staff. The application for the ABWR design was initially submitted by the General Electric Company, now GE Nuclear Energy (GE), in accordance with the procedures of Appendix O of Part 50 of Title 10 of the Code of Federal Regulations (10 CFR Part 50). Later GE requested that its application be considered as an application for design approval and subsequent design certification pursuant to 10 CFR section 52.45. The ABWR is a single-cycle, forced-circulation, boiling water reactor (BWR) with a rated power of 3,926 megawatts thermal (MWt) and a design power of 4,005 MWt. To the extent feasible and appropriate, the staff relied on earlier reviews for those ABWR design features that are substantially the same as those previously considered. Unique features of the ABWR design include internal recirculation pumps, fine-motion control rod drives, microprocessor-based digital logic and control systems, and digital safety systems. On the basis of its evaluation and independent analyses, the NRC staff concludes that, subject to satisfactory resolution of the confirmatory items identified in Section 1.8 of this SER, GE's application for design certification meets the requirements of Subpart B of 10 CFR Part 52 that are applicable and technically relevant to the US ABWR standard design

Final safety evaluation report related to the certification of the advanced boiling water reactor design. Volume 1: Main report

Energy Technology Data Exchange (ETDEWEB)

1994-07-01

This safety evaluation report (SER) documents the technical review of the US Advanced Boiling Water Reactor (ABWR) standard design by the US Nuclear Regulatory Commission (NRC) staff. The application for the ABWR design was initially submitted by the General Electric Company, now GE Nuclear Energy (GE), in accordance with the procedures of Appendix O of Part 50 of Title 10 of the Code of Federal Regulations (10 CFR Part 50). Later GE requested that its application be considered as an application for design approval and subsequent design certification pursuant to 10 CFR {section} 52.45. The ABWR is a single-cycle, forced-circulation, boiling water reactor (BWR) with a rated power of 3,926 megawatts thermal (MWt) and a design power of 4,005 MWt. To the extent feasible and appropriate, the staff relied on earlier reviews for those ABWR design features that are substantially the same as those previously considered. Unique features of the ABWR design include internal recirculation pumps, fine-motion control rod drives, microprocessor-based digital logic and control systems, and digital safety systems. On the basis of its evaluation and independent analyses, the NRC staff concludes that, subject to satisfactory resolution of the confirmatory items identified in Section 1.8 of this SER, GE`s application for design certification meets the requirements of Subpart B of 10 CFR Part 52 that are applicable and technically relevant to the US ABWR standard design.

Working Towards Unified Safety Design Criteria for Modular High Temperature Gas-cooled Reactor Designs

International Nuclear Information System (INIS)

Reitsma, Frederik; Silady, Fred; Kunitomi, Kazuhiko

2014-01-01

The Nuclear Power Development Section of the IAEA recently received approval for a Coordinated Research Project (CRP) to investigate and make proposals on modular High Temperature Gas-cooled Reactor (HTGR) Safety design criteria. It is expected that these criteria would consider past experience and existing safety standards in the light of modular HTGR material and design characteristics to propose safety design criteria. It will consider the deterministic and risk-informed safety design standards that apply to the wide spectrum of Off- normal events under development worldwide for existing and planned HTGRs. The CRP would also take into account lessons from the Fukushima Daiichi accident, clarifying the safety approach and safety evaluation criteria for design and beyond design basis events, including those events that can affect multiple reactor modules and/or are dependent on the application proximate to the plant site. (e. g., industrial process steam/heat). The logical flow of criteria is from the fundamental inherent safety characteristics of modular HTGRs and associated expected performance characteristics, to the safety functions required to ensure those characteristics during the wide spectrum of Off-normal events, and finally to specific criteria related to those functions. This is detailed in the paper with specific examples included of how it may be applied. The results of the CRP will be made available to the member states and HTGR community. (author)

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

76 FR 29680 - Approval and Disapproval and Promulgation of State Implementation Plan Revisions; Infrastructure...

Science.gov (United States)

2011-05-23

..., marketable permits, and auctions of emissions rights), as well as schedules and timetables for compliance as...) program as required by part C of the Act, and the State's minor NSR program as required by 110(a)(2)(C...), respectively. Minor NSR Finally, with regards to minor NSR, in this action EPA is proposing to approve Wyoming...

Chemical Frustration. A Design Principle for the Discovery of New Complex Alloy and Intermetallic Phases, Final Report

Energy Technology Data Exchange (ETDEWEB)

Fredrickson, Daniel C [Univ. of Wisconsin, Madison, WI (United States)

2015-06-23

Final technical report for "Chemical Frustration: A Design Principle for the Discovery of New Complex Alloy and Intermetallic Phases" funded by the Office of Science through the Materials Chemistry Program of the Office of Basic Energy Sciences.

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 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

Design of modern vehicle electrical systems based on co-simulation and a model library; Entwurf moderner Bordnetze mittels Co-Simulation und Modellbibliothek

Energy Technology Data Exchange (ETDEWEB)

Zehetner, Josef; Lu, Di Wenpu; Watzenig, Daniel [Virtual Vehicle Research Center, Graz (Austria)

2013-08-15

The complexity of vehicle electrical and electronic systems, components, and functions is growing as they become increasingly networked with each other and with the internet. Vehicle electrical systems developers can manage this complexity now and in the future by employing simulation as a central tool in designing powerful and reliable vehicle electrical systems. Bosch Engineering offers a powerful simulation tool to support the design of vehicle power nets from initial requirements to final series approval, now being used also for hybrid and electric drive train development. (orig.)

Evaluation of Some Approved Basic Science and Technology Textbooks in Use in Junior Secondary Schools in Nigeria

Science.gov (United States)

Nwafor, C. E.; Umoke, C. C.

2016-01-01

This study was designed to evaluate the content adequacy and readability of approved basic science and technology textbooks in use in junior secondary schools in Nigeria. Eight research questions guided the study. The sample of the study consisted of six (6) approved basic science and technology textbooks, 30 Junior Secondary Schools randomly…

Innovative wetland reclamation design case studies : the Suncor fen and pond 1 marsh

Energy Technology Data Exchange (ETDEWEB)

Daly, C.A. [Suncor Energy, Fort McMurray, AB (Canada); Price, J.; Rezanezhad, F. [Waterloo Univ., ON (Canada); Rochefort, L.; Graf, M. [Laval Univ., Quebec City, PQ (Canada); Russell, B. [BGC Engineering Inc., Calgary, AB (Canada)

2010-07-01

Suncor Energy Inc. is an energy company strategically focused in Canada's Athabasca oil sands region. The company has more than 40 years of experience in pioneering commercial development. This presentation discussed reclamation requirements for Suncor Energy. Reclamation objectives that were addressed in this presentation included operating approvals, biodiversity and meeting stakeholder expectations. Several photographs of reclaimed forest areas were shown along with 5 freshwater wetland types and wetland values. Two innovative wetland reclamation design case studies were also presented, described and illustrated, with particular reference to the Suncor fen and pond 1 marsh. It was concluded that future work will involve finalizing site investigation and designs, as well as construction, vegetation, and monitoring. figs.

75 FR 26685 - Approval and Promulgation of Implementation Plans and Designation of Areas for Air Quality...

Science.gov (United States)

2010-05-12

... X emissions from Electric Generating Units (EGUs), major non-EGU industrial boilers, major cement kilns, and internal combustion engines. EPA approved Kentucky's rules as fulfilling Phase I and Phase II...

76 FR 33121 - List of Approved Spent Fuel Storage Casks: HI-STORM Flood/Wind Addition

Science.gov (United States)

2011-06-08

... Storage Casks: HI-STORM Flood/Wind Addition AGENCY: Nuclear Regulatory Commission. ACTION: Direct final... regulations to add the Holtec HI-STORM Flood/Wind cask system to the ``List of Approved Spent Fuel Storage... Title 10 of the Code of Federal Regulations Section 72.214 to add the Holtec HI- STORM Flood/Wind cask...

Exterior insulating shutter final prototype design. Final report, Phase II

Energy Technology Data Exchange (ETDEWEB)

Dike, G.A.; Kinney, L.F.

1982-12-01

The final prototype shutter described uses sliding panels composed of inch-thick thermax sandwiched between 60 mil thick ultraviolet-resistant plastic on the outside, and 20 mil stryrene on the inside. The shuter system was shown to have an effective R-value of 6 using ASHRAE procedures to convert from still air conditions to 15 mph wind conditions in a simulated cold environment. Tests were performed for cyclical operation, vulnerability to ice and wind, thermal performance, and air infiltration. Marketing efforts are described. Cost effectiveness is determined via present value analysis. (LEW)

76 FR 17160 - Office of New Reactors; Final Interim Staff Guidance on the Review of Nuclear Power Plant Designs...

Science.gov (United States)

2011-03-28

... design certification (DC) application for new nuclear power reactors under Title 10 of the Code of... NUCLEAR REGULATORY COMMISSION [NRC-2010-0033; DC/COL-ISG-021] Office of New Reactors; Final Interim Staff Guidance on the Review of Nuclear Power Plant Designs Using a Gas Turbine Driven Standby...

Directory of Certificates of Compliance for Radioactive-Materials Packages. Summary report of NRC approved packages

International Nuclear Information System (INIS)

1983-01-01

This directory contains a Summary Report of the US Nuclear Regulatory Commission's Approved Packages (Volume I), all Certificates of Compliance (Volume 2), and Summary Report of NRC Approved Quality Assurance Programs (Volume 3) for Radioactive Material Packages effective December 31, 1982. The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the back of Volumes 1 and 2 of the directory. A listing by packaging types is included in the back of Volume 2. An alphabetical listing by company name is included in the back of Volume 3 for approved QA programs. The Summary Reports include a listing of all users of each package design and approved QA programs prior to the publication date of the directory

76 FR 53853 - Approval and Promulgation of Implementation Plans and Designation of Areas for Air Quality...

Science.gov (United States)

2011-08-30

... Action Network (LEAN) v. EPA, No. 02-60991). The issues raised concerned EPA's decision to approve... Ambient Air Quality Standard,'' Memorandum from John S. Seitz, Director, Office of Air Quality Planning...

Final design of thermal diagnostic system in SPIDER ion source

Energy Technology Data Exchange (ETDEWEB)

Brombin, M., E-mail: matteo.brombin@igi.cnr.it; Dalla Palma, M.; Pasqualotto, R.; Pomaro, N. [Consorzio RFX, Corso Stati Uniti 4, I-35127 Padova (Italy)

2016-11-15

The prototype radio frequency source of the ITER heating neutral beams will be first tested in SPIDER test facility to optimize H{sup −} production, cesium dynamics, and overall plasma characteristics. Several diagnostics will allow to fully characterise the beam in terms of uniformity and divergence and the source, besides supporting a safe and controlled operation. In particular, thermal measurements will be used for beam monitoring and system protection. SPIDER will be instrumented with mineral insulated cable thermocouples, both on the grids, on other components of the beam source, and on the rear side of the beam dump water cooled elements. This paper deals with the final design and the technical specification of the thermal sensor diagnostic for SPIDER. In particular the layout of the diagnostic, together with the sensors distribution in the different components, the cables routing and the conditioning and acquisition cubicles are described.

Final design of thermal diagnostic system in SPIDER ion source

International Nuclear Information System (INIS)

Brombin, M.; Dalla Palma, M.; Pasqualotto, R.; Pomaro, N.

2016-01-01

The prototype radio frequency source of the ITER heating neutral beams will be first tested in SPIDER test facility to optimize H"− production, cesium dynamics, and overall plasma characteristics. Several diagnostics will allow to fully characterise the beam in terms of uniformity and divergence and the source, besides supporting a safe and controlled operation. In particular, thermal measurements will be used for beam monitoring and system protection. SPIDER will be instrumented with mineral insulated cable thermocouples, both on the grids, on other components of the beam source, and on the rear side of the beam dump water cooled elements. This paper deals with the final design and the technical specification of the thermal sensor diagnostic for SPIDER. In particular the layout of the diagnostic, together with the sensors distribution in the different components, the cables routing and the conditioning and acquisition cubicles are described.

36 CFR 401.6 - Approval by National Commission of Fine Arts.

Science.gov (United States)

2010-07-01

... Commission of Fine Arts. 401.6 Section 401.6 Parks, Forests, and Public Property AMERICAN BATTLE MONUMENTS COMMISSION MONUMENTS AND MEMORIALS § 401.6 Approval by National Commission of Fine Arts. A design for a... Commission of Fine Arts before the Commission can accept it. ...

Identification of characteristics which influence repository design domal salt, Task 1. Final report

International Nuclear Information System (INIS)

Rawlings, G.; Antonnen, G.; Chamness, M.

1984-04-01

The purpose of the complete project is to provide NRC with technical assistance to enable the focused, adequate review by NRC of the aspects related to design and construction of an underground test facility and final geologic repository as presented by the Department of Energy (DOE). The study presented in this report covers the identification of characteristics which influence design and construction of a geologic repository in domal salt. This report has identified five key issues, i.e., constructibility, thermal response, mechanical response, hydrologic response, and geochemical response. This report involves both short-term (up to closure) and long-term (post closure) effects. The characteristics of domal salt and its environment are described under the headings of stratigraphic/structural, tectonic, mechanical, thermal and hydrologic. Characteristics are separated into parameters (quantified and measured) and factors (qualitative). The characteristics are then subjectively ranked by their influence on the key issues. This takes into account the availability and suitability of conservative design/construction techniques, uncertainty in model and model sensitivity to the characteristic

Towards the final MRPC design. Performance test with heavy ion beam

Energy Technology Data Exchange (ETDEWEB)

Deppner, Ingo; Herrmann, Norbert [Physikalisches Institut Uni. Heidelberg, Heidelberg (Germany)

2015-07-01

The Compressed Baryonic Matter spectrometer (CBM) is a future heavy ion experiment located at the Facility for Anti-proton and Ion Research (FAIR) in Darmstadt, Germany. The key element in CBM providing hadron identification at incident energies between 2 and 35 AGeV will be a 120 m{sup 2} large Time-of-Flight (ToF) wall composed of Multi-gap Resistive Plate Chambers (MRPC) with a system time resolution better than 80 ps. Aiming for an interaction rate of 10 MHz for Au+Au collisions the MRPCs have to cope with an incident particle flux between 0.1 kHz/cm{sup 2} and 25 kHz/cm{sup 2} depending on their location. Characterized by granularity and rate capability the actual conceptual design of the ToF-wall foresees 4 different counter types called MRPC1 - MRPC4. In order to elaborate the final MRPC design of these counters a heavy ion test beam time was performed at GSI. In this contribution we present performance test results of 2 different MRPC3 full size prototypes developed at Heidelberg University and Tsinghua University, Beijing.

Electronic Approval of Invoices (AEF)

CERN Document Server

2004-01-01

With a view to the simplification of administrative procedures, AS and FI Departments have completed the second phase of the new procedure for the electronic approval of invoices via the EDH application. The aim of this new procedure is to rationalise the invoice approval process, notably by eliminating paper copies from the approval circuit. This will simplify the processing of invoices and facilitate their timely settlement, while at the same time maintaining a high level of security. Phase II includes handling the electronic approval process of invoices whose amounts do not correspond exactly to those of the associated orders. In such cases, budgetary approval is required for the entire invoiced amount. Further information can be obtained at : http://ais.cern.ch/projs/AEF/help/F_help.htm Phase II of the procedure will be introduced gradually with effect from April 2004. Finance Department, Accounts Payable Section Tel: 72295 Organisation and Procedures Tel: 75885 Information Technologies Department,...

78 FR 77571 - Fees for Certification Services and Approvals Performed Outside the United States; Technical...

Science.gov (United States)

2013-12-24

...-27043; Amdt. No. 61-132] RIN 2120-AI77 Fees for Certification Services and Approvals Performed Outside..., 2007 (72 FR 18556). In that rule, the FAA amended its regulations to revise the fee requirement for... direct final rule revising the fee requirement of 14 CFR 61.13 for the issuance of an airman certificate...

78 FR 28501 - Approval and Promulgation of Air Quality Implementation Plans; Minnesota; Flint Hills Resources...

Science.gov (United States)

2013-05-15

... steam-air decoking activities for certain boilers, revise the SO 2 emission limits for its fluid catalytic cracking unit, and make plans to add a boiler. See the January 31, 2013, direct final approval (78... concerns that SO 2 emissions are grossly underestimated when only fuel gas hydrogen sulfide (H 2 S) is used...

Investigating Teachers' Approval and Disapproval Behaviors Towards Academic and Social Behaviors of Students with and without Special Needs

Science.gov (United States)

Sazak-Pinar, Elif; Guner-Yildiz, Nevin

2013-01-01

The present study was designed to (a) investigate teachers' approval and disapproval behaviors towards academic and social behaviors of students in mainstreaming classrooms and (b) determine whether or not having special needs be a predictor of teachers' approval and disapproval behaviors. The study group consisted of 43 teachers who were working…

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

Marketing Approval of Ethical Kampo Medicines.

Science.gov (United States)

Hakamatsuka, Takashi

2017-01-01

Kampo medicine is an original traditional medicine in Japan. Currently, 148 ethical Kampo formulations (Kampo prescription drugs) are registered in the National Health Insurance Price List. Kampo medicines can be prescribed under the national insurance system, which shows that they are part of conventional medicine in Japan. Japan has a unified drug approval system that does not distinguish between Western and Kampo medicines, and both are subject to the same regulations. The application for the market approval of ethical Kampo medicines is based on the general notification for drugs, i.e., "Handling of Ethical Combination Drugs" in "Precautions Necessary When Applying for Drug Marketing Approval" (Yakushokushinsa Notification No. 1121-12 of November 21, 2014). Furthermore, applications for the market approval of ethical Kampo medicines should follow the Kampo-specific notification of "Handling of Ethical Kampo Medicines" (Yakushin Notification No. 804 of June 25, 1980). Data from comparative studies with standard decoctions must be submitted with approval applications according to Yakushin 2 Notification No. 120 of May 31, 1985. The safety, efficacy, and quality of Kampo medicines are comprehensively assured by the Japanese Pharmacopoeia, Good Manufacturing Practice, Good Agricultural and Collection Practices, marketing approval certificate, approval standard, and pharmacovigilance. I believe that the basic framework for the market approval of ethical Kampo medicines has been established as described above. The key factors for the practical application of superior manufacturing technology and research achievements and the promotion of drug development are the specific guidelines for the approval of drugs of herbal origin.

Preliminary Tritium Management Design Activities at ORNL

International Nuclear Information System (INIS)

Harrison, Thomas J.; Felde, David K.; Logsdon, Randall J.; McFarlane, Joanna; Qualls, A. L.

2016-01-01

Interest in salt-cooled and salt-fueled reactors has increased over the last decade (Forsberg et al. 2016). Several private companies and universities in the United States, as well as governments in other countries, are developing salt reactor designs and/or technology. Two primary issues for the development and deployment of many salt reactor concepts are (1) the prevention of tritium generation and (2) the management of tritium to prevent release to the environment. In 2016, the US Department of Energy (DOE) initiated a research project under the Advanced Reactor Technology Program to (1) experimentally assess the feasibility of proposed methods for tritium mitigation and (2) to perform an engineering demonstration of the most promising methods. This document describes results from the first year's efforts to define, design, and build an experimental apparatus to test potential methods for tritium management. These efforts are focused on producing a final design document as the basis for the apparatus and its scheduled completion consistent with available budget and approvals for facility use.

Preliminary Tritium Management Design Activities at ORNL

Energy Technology Data Exchange (ETDEWEB)

Harrison, Thomas J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Felde, David K. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Logsdon, Randall J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); McFarlane, Joanna [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Qualls, A. L. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2016-09-01

Interest in salt-cooled and salt-fueled reactors has increased over the last decade (Forsberg et al. 2016). Several private companies and universities in the United States, as well as governments in other countries, are developing salt reactor designs and/or technology. Two primary issues for the development and deployment of many salt reactor concepts are (1) the prevention of tritium generation and (2) the management of tritium to prevent release to the environment. In 2016, the US Department of Energy (DOE) initiated a research project under the Advanced Reactor Technology Program to (1) experimentally assess the feasibility of proposed methods for tritium mitigation and (2) to perform an engineering demonstration of the most promising methods. This document describes results from the first year’s efforts to define, design, and build an experimental apparatus to test potential methods for tritium management. These efforts are focused on producing a final design document as the basis for the apparatus and its scheduled completion consistent with available budget and approvals for facility use.

40 CFR 145.31 - Approval process.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 22 2010-07-01 2010-07-01 false Approval process. 145.31 Section 145.31 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) WATER PROGRAMS (CONTINUED) STATE UIC PROGRAM REQUIREMENTS Program Approval, Revision and Withdrawal § 145.31 Approval process. (a...

40 CFR 52.2122 - Approval status.

Science.gov (United States)

2010-07-01

... sources covered by CTGs issued by the previous January. (b) EPA disapproved South Carolina's generic...) APPROVAL AND PROMULGATION OF IMPLEMENTATION PLANS (CONTINUED) South Carolina § 52.2122 Approval status. (a) With the exceptions set forth in this subpart, the Administrator approves South Carolina's plans for...

Analysis of lomustine drug content in FDA-approved and compounded lomustine capsules.

Science.gov (United States)

KuKanich, Butch; Warner, Matt; Hahn, Kevin

2017-02-01

OBJECTIVE To determine the lomustine content (potency) in compounded and FDA-approved lomustine capsules. DESIGN Evaluation study. SAMPLE 2 formulations of lomustine capsules (low dose [7 to 11 mg] and high dose [40 to 48 mg]; 5 capsules/dose/source) from 3 compounders and from 1 manufacturer of FDA-approved capsules. PROCEDURES Lomustine content was measured by use of a validated high-pressure liquid chromatography method. An a priori acceptable range of 90% to 110% of the stated lomustine content was selected on the basis of US Pharmacopeia guidelines. RESULTS The measured amount of lomustine in all compounded capsules was less than the stated content (range, 59% to 95%) and was frequently outside the acceptable range (failure rate, 2/5 to 5/5). Coefficients of variation for lomustine content ranged from 4.1% to 16.7% for compounded low-dose capsules and from 1.1% to 10.8% for compounded high-dose capsules. The measured amount of lomustine in all FDA-approved capsules was slightly above the stated content (range, 104% to 110%) and consistently within the acceptable range. Coefficients of variation for lomustine content were 0.5% for low-dose and 2.3% for high-dose FDA-approved capsules. CONCLUSIONS AND CLINICAL RELEVANCE Compounded lomustine frequently did not contain the stated content of active drug and had a wider range of lomustine content variability than did the FDA-approved product. The sample size was small, and larger studies are needed to confirm these findings; however, we recommend that compounded veterinary formulations of lomustine not be used when appropriate doses can be achieved with FDA-approved capsules or combinations of FDA-approved capsules.

77 FR 24225 - Information Collection Approval; Temporary Non-Agricultural Employment of H-2B Aliens in the...

Science.gov (United States)

2012-04-23

... DEPARTMENT OF LABOR Employment and Training Administration Information Collection Approval; Temporary Non-Agricultural Employment of H-2B Aliens in the United States AGENCY: Employment and Training... the Temporary Non-Agricultural Employment of H-2B Aliens in the United States; Final Rule. See 77 FR...

75 FR 24394 - Animal Drugs, Feeds, and Related Products; Withdrawal of Approval of a New Animal Drug...

Science.gov (United States)

2010-05-05

... [Docket No. FDA-2010-N-0002] Animal Drugs, Feeds, and Related Products; Withdrawal of Approval of a New Animal Drug Application; Buquinolate; Coumaphos AGENCY: Food and Drug Administration, HHS. ACTION: Final rule. SUMMARY: The Food and Drug Administration (FDA) is amending the animal drug regulations by...

75 FR 48302 - Notice of Request for Extension of Approval of an Information Collection; Credit Account Approval...

Science.gov (United States)

2010-08-10

....gov ). FOR FURTHER INFORMATION CONTACT: For information on credit account approval for reimbursable..., at (301) 851-2908. SUPPLEMENTARY INFORMATION: Title: Credit Account Approval for Reimbursable... Inspection Service [Docket No. APHIS-2010-0071] Notice of Request for Extension of Approval of an Information...

78 FR 54617 - Notice of Request for Extension of Approval of an Information Collection; Credit Account Approval...

Science.gov (United States)

2013-09-05

...] Notice of Request for Extension of Approval of an Information Collection; Credit Account Approval for... (202) 799-7039 before coming. FOR FURTHER INFORMATION CONTACT: For information on credit account... Coordinator, at (301) 851-2908. SUPPLEMENTARY INFORMATION: Title: Credit Account Approval for Reimbursable...

40 CFR 52.1772 - Approval status.

Science.gov (United States)

2010-07-01

...) APPROVAL AND PROMULGATION OF IMPLEMENTATION PLANS (CONTINUED) North Carolina § 52.1772 Approval status. (a) With the exceptions set forth in this subpart, the Administrator approves North Carolina's plans for... CTGs issued by the previous January. (b) New Source review permits issued pursuant to section 173 of...

75 FR 26272 - Final Environmental Impact Statement; Environmental Education Center, Yosemite National Park...

Science.gov (United States)

2010-05-11

... DEPARTMENT OF THE INTERIOR National Park Service Final Environmental Impact Statement; Environmental Education Center, Yosemite National Park, Mariposa County, CA; Notice of Approval of Record of Decision SUMMARY: Pursuant to Sec. 102(2)(C) of the National Environmental Policy Act of 1969 (Pub. L. 91...

Final focus nomenclature

International Nuclear Information System (INIS)

Erickson, R.

1986-01-01

The formal names and common names for all devices in the final focus system of the SLC are listed. The formal names consist of a device type designator, microprocessor designator, and a four-digit unit number

9 CFR 147.52 - Approved tests.

Science.gov (United States)

2010-01-01

... 9 Animals and Animal Products 1 2010-01-01 2010-01-01 false Approved tests. 147.52 Section 147.52 Animals and Animal Products ANIMAL AND PLANT HEALTH INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE... Approved Tests § 147.52 Approved tests. (a) The procedures for the bacteriological examination of poultry...

30 CFR 14.10 - Post-approval product audit.

Science.gov (United States)

2010-07-01

..., AND APPROVAL OF MINING PRODUCTS REQUIREMENTS FOR THE APPROVAL OF FLAME-RESISTANT CONVEYOR BELTS General Provisions § 14.10 Post-approval product audit. (a) Approved conveyor belts will be subject to... based. MSHA will select an approved conveyor belt to be audited; the selected belt will be...

Red River Stream Improvement Final Design Nez Perce National Forest.

Energy Technology Data Exchange (ETDEWEB)

Watershed Consulting, LLC

2007-03-15

This report details the final stream improvement design along the reach of Red River between the bridge below Dawson Creek, upstream for approximately 2 miles, Idaho County, Idaho. Geomorphic mapping, hydrologic profiles and cross-sections were presented along with existing fish habitat maps in the conceptual design report. This information is used to develop a stream improvement design intended to improve aquatic habitat and restore riparian health in the reach. The area was placer mined using large bucket dredges between 1938 and 1957. This activity removed most of the riparian vegetation in the stream corridor and obliterated the channel bed and banks. The reach was also cut-off from most valley margin tributaries. In the 50 years since large-scale dredging ceased, the channel has been re-established and parts of the riparian zone have grown in. However, the recruitment of large woody debris to the stream has been extremely low and overhead cover is poor. Pool habitat makes up more than 37% of the reach, and habitat diversity is much better than the project reach on Crooked River. There is little large woody debris in the stream to provide cover for spawning and juvenile rearing, because the majority of the woody debris does not span a significant part of the channel, but is mainly on the side slopes of the stream. Most of the riparian zone has very little soil or subsoil left after the mining and so now consists primarily of unconsolidated cobble tailings or heavily compacted gravel tailings. Knapweed and lodgepole pine are the most successful colonizers of these post mining landforms. Tributary fans which add complexity to many other streams in the region, have been isolated from the main reach due to placer mining and road building.

76 FR 22861 - Approval and Promulgation of State Plans for Designated Facilities and Pollutants: Florida...

Science.gov (United States)

2011-04-25

... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 62 [EPA-R04-OAR-2010-0840(b); FRL-9298-8] Approval and... from Forsyth County, North Carolina; LMWC, SMWC, and OSWI units from Mecklenburg County, North Carolina..., North Carolina; and LMWC and HMIWI units from the State of South Carolina. These negative declarations...

GCFR demonstration plant: conceptual design and status report

International Nuclear Information System (INIS)

1980-12-01

Helium Breeder Associates (HBA), a non-profit corporation, has been the program manager and technical integrator of the Gas-Cooled Fast Reactor (GCFR) development effort since 1977. When DOE discontinued support of the GCFR in 1980, the HBA members undertook the task of providing for an orderly termination and documentation of the program. HBA does not agree with the government's rational for withdrawing support for this promising technology and has directed its termination and documentation toward preserving the current state of its development. Toward that end, HBA has compiled the following report which is a summary of the conceptual design of the demonstration plant and status of the program as of the end of 1980. It includes summaries of tasks that have not evolved to a final conclusion. Although the report has not been subjected to formal review and approval by the designers, it is intended to provide the reader with the design considerations that were current at the time of program termination. It is hoped that the report will be useful in restarting the program in the future by establishing the basis of the completed conceptual design and indicating a logical path for new design and development

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)

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

75 FR 1438 - Self-Regulatory Organizations; New York Stock Exchange LLC; Order Approving a Proposed Rule...

Science.gov (United States)

2010-01-11

...)(iv). Finally, because DMMs no longer act as agent for orders on the Display Book under the rules of... the Policy would not be in violation the Order Display rule \\8\\ and/or the Firm Quote rule \\9\\ under...-Regulatory Organizations; New York Stock Exchange LLC; Order Approving a Proposed Rule Change Rescinding...

75 FR 1439 - Self-Regulatory Organizations; NYSE Amex LLC; Order Approving a Proposed Rule Change Rescinding...

Science.gov (United States)

2010-01-11

...(a)(iv). Finally, because DMMs no longer act as agent for orders on the Display Book under the rules... fails to follow the Policy would not be in violation the Order Display rule \\8\\ and/or the Firm Quote...-Regulatory Organizations; NYSE Amex LLC; Order Approving a Proposed Rule Change Rescinding NYSE Information...

Final focus nomenclature

Energy Technology Data Exchange (ETDEWEB)

Erickson, R.

1986-08-08

The formal names and common names for all devices in the final focus system of the SLC are listed. The formal names consist of a device type designator, microprocessor designator, and a four-digit unit number. (LEW)

The surface physics work station: final design

International Nuclear Information System (INIS)

Landers, R.; Kleiman, G.G.; Castro, S.G.C. de; Douglas, R.A.; Nascente, P.A.P.

1996-01-01

Thanks to funding from FAPESP we will be installing in the beginning of 1997 a work station for electron spectroscopy designed for the study of clean solid surfaces and the modification of these surfaces by deposition in situ of ultra thin metallic films. The main analytical tool will be a high resolution hemispherical analyzer made by VSW-Omicrom (EA 125 HR) which is capable of better than 5 meV resolution and high transmission due to its five channeltron multi detection system. The system will also have a Rear View LEED Optics for single crystal studies. The system will be housed in a 16'' cylindrical chamber with mu metal magnetic shielding having two levels for analysis. The upper level will contain instruments for technique which do not require photons such as LEED and sample cleaning. The lower level will have the electron analyzer, conventional X-ray source (Al/Mg), electron gun for Auger, e-beam evaporators for thin film deposition and ports for the future addition of different detectors. We will have a manipulator with 5 degrees of freedom (thre translation and two rotational) and sample heating and LN cooling. Finally we will have a fast entry/preparation chamber. The pumping system will have a combination of turbomolecular and ion pumps for the main chamber and a turbo for the fast entr/prep chamber. The system will be used initially for the study of surface alloys by XPS and Photoelectron Diffraction but as soon as it is properly characterized it will be open for collaborations with other groups interested in using its capabilities. (author)

7 CFR 1710.406 - Loan approval.

Science.gov (United States)

2010-01-01

... 7 Agriculture 11 2010-01-01 2010-01-01 false Loan approval. 1710.406 Section 1710.406 Agriculture... GENERAL AND PRE-LOAN POLICIES AND PROCEDURES COMMON TO ELECTRIC LOANS AND GUARANTEES Application Requirements and Procedures for Loans § 1710.406 Loan approval. (a) A loan is approved when the Administrator...

40 CFR 123.61 - Approval process.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 21 2010-07-01 2010-07-01 false Approval process. 123.61 Section 123... REQUIREMENTS Program Approval, Revision, and Withdrawal § 123.61 Approval process. (a) After determining that a...; and (6) Briefly outline the fundamental aspects of the State's proposed program, and the process for...

Dental laboratory communication regarding removable dental prosthesis design in the UAE.

Science.gov (United States)

Haj-Ali, Reem; Al Quran, Firas; Adel, Omar

2012-07-01

The purpose of this study was to determine the methods dental practitioners in the United Arab Emirates (UAE) use to communicate cast removable dental prosthesis (RDP) design to dental laboratories; identify common practices taken by dentists/dental technicians prior to fabrication of RDP framework; and seek out dental technicians' attitudes toward their role in RDP design decisions. All dental laboratories (n = 28) listed in a local telephone directory were invited to complete a questionnaire through a face-to-face interview. They were also requested to examine RDP cases fabricated in the past 2 months and identify steps taken by dentists/dental technicians prior to fabrication of the framework. Descriptive statistics were used to report frequencies and percentages. Twenty-one (75%) dental laboratories agreed to participate, out of which 19 had the facilities to fabricate chrome-cobalt RDPs. Cast RDPs comprised approximately 4.04% (±2.67) of services provided. A reported 84.2% of dentists frequently communicate through generic lab script, with 89.5% rarely/never giving details regarding RDP design. While 52.6% of labs agree/strongly agree that it is the dentist's responsibility to decide the final RDP design, 94.7% agree/strongly agree that dentists should depend on dental technicians for design-making decisions. A total of 19 RDP cases were reviewed. All 19 were surveyed and designed by dental technicians but received dentist approval of design prior to fabrication. Thirteen (68.4%) had rest-seat preparations done by dentists after approval, and new impressions sent to the lab. No other tooth modifications were noted. The responsibility of RDP design appeared to be largely delegated to dental technicians. Importance of tooth modifications seemed to be undervalued and not completed prior to framework fabrication. © 2012 by the American College of Prosthodontists.

78 FR 41307 - Approval and Promulgation of Air Quality Implementation Plans; State of Colorado; Second Ten-Year...

Science.gov (United States)

2013-07-10

... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 52 [EPA-R08-OAR-2010-0389; FRL-9832-1] Approval and Promulgation of Air Quality Implementation Plans; State of Colorado; Second Ten-Year PM 10 Maintenance Plan for Ca[ntilde]on City AGENCY: Environmental Protection Agency (EPA). ACTION: Direct final rule. SUMMARY...

78 FR 76310 - Agency Information Collection Activities: Submission to OMB for Review and Approval; Public...

Science.gov (United States)

2013-12-17

... collection will also provide information on CHWs' efforts to enroll clients and the successes and failures... forms; and 3. Client satisfaction surveys. ORHP is seeking approval from OMB for the three methods of... designed to gather information on successes and challenges associated with the program design and...

Microgrid Design, Development and Demonstration - Final Report for Phase I and Phase II

Energy Technology Data Exchange (ETDEWEB)

Bose, Sumit [GE Global Research Center, Niskayuna, NY (United States); Krok, Michael [GE Global Research Center, Niskayuna, NY (United States)

2011-02-08

This document constitutes GE’s final report for the Microgrid Design, Development and Demonstration program for DOE’s Office of Electricity Delivery and Energy Reliability, Award DE-FC02-05CH11349. It contains the final report for Phase I in Appendix I, and the results the work performed in Phase II. The program goal was to develop and demonstrate a Microgrid Energy Management (MEM) framework for a broad set of Microgrid applications that provides unified controls, protection, and energy management. This project contributed to the achievement of the U.S. Department of Energy’s Renewable and Distributed Systems Integration Program goals by developing a fully automated power delivery microgrid network that: - Reduces carbon emissions and emissions of other air pollutants through increased use of optimally dispatched renewable energy, - Increases asset use through integration of distributed systems, - Enhances reliability, security, and resiliency from microgrid applications in critical infrastructure protection, constrained areas of the electric grid, etc. - Improves system efficiency with on-site, distributed generation and improved economic efficiency through demand-side management.

Directory of certificates of compliance for radioactive materials packages; Summary Report of NRC Approved Packages

International Nuclear Information System (INIS)

1980-12-01

This directory contains a Summary Report of NRC approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Summary Report of NRC Approved Quality Assurance Programs for Radioactive Material Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the U.S. Nuclear Regulatory Commission. To assist in identifying packaging, and index by Model Number and corresponding Certificate of Compliance number is included at the back of each volume of the directory. The Summary Report includes a listing of all users of each package design prior to the publication date of the directory. Shipments of radioactive material using these packagings must be in accordance with the provisions of 49 CFR 173.393a and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure them--that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program

Fugitive hydrocarbon emissions from pacific OCS facilities. Volume 1. Final report

International Nuclear Information System (INIS)

1992-01-01

In January 1989, the Minerals Management Service (MMS) conducted a study using the latest approved methods for emission screening and sampling solely on Outer Continental Shelf (OCS) oil and gas platforms in the Santa Barbara Channel in order to determine platform emission rates more representative of that region. The study was designed and reviewed throughout its conduct by a Quality Review Board (QRB) composed of air resource agencies and industry. Representatives from the Tri-county Air Pollution Control Districts and the MMS actively participated at these meetings. Some participants expressed concerns about some of the methods used and the study results. ABB's thorough responses to these questions and comments were submitted to all reviewers before the printing of the final report, and are contained in appendices of the study final report now available to the public. The results of the MMS study show that the average emission factors for the Pacific OCS oil and gas facilities measured in 1989 are 3.5 times lower than those Pacific OCS facilities sampled in the 1979 API/Rockwell study, and 7.8 times lower than the Gulf of Mexico OCS facilities sampled in the same 1979 study. Efforts to determine the quantitative effect of inspection and maintenance programs on controlling emissions were inconclusive

Can an ethics officer role reduce delays in research ethics approval? A mixed-method evaluation of an improvement project.

Science.gov (United States)

Dixon-Woods, Mary; Foy, Chris; Hayden, Charlotte; Al-Shahi Salman, Rustam; Tebbutt, Stephen; Schroter, Sara

2016-08-31

Frustration continues to be directed at delays in gaining approvals for undertaking health research in the UK. We aimed to evaluate the impact of an ethics officer intervention on rates of favourable opinions (approval) and provisional opinions (requiring revision and resubmission) and on the time taken to reach a final opinion by research ethics committees (RECs), to characterise how the role operated in practice, and to investigate applicants' views. Mixed-method study involving (i) a 2-group, non-randomised before-and-after intervention study of RECs assigned an ethics officer and a matched comparator group; (ii) a process evaluation involving a survey of applicants and documentary analysis. 6 RECs and 3 associated ethics officers; 18 comparator RECs; REC applicants. Rates of provisional and favourable opinions between ethics officer and comparator RECs did not show a statistically significant effect of the intervention (logistic regression, p=0.26 for favourable opinions and p=0.31 for provisional opinions). Mean time to reach a decision showed a non-significant reduction (ANOVA, p=0.22) from 33.3 to 32.0 days in the ethics officer RECs compared with the comparator RECs (32.6 to 32.9 days). The survey (30% response rate) indicated applicant satisfaction and also suggested that ethics officer support might be more useful before submission. Ethics officers were successful in identifying many issues with applications, but the intervention did not function exactly as designed: in 31% of applicants, no contact between the applicants and the ethics officer took place before REC review. This study was a non-randomised comparison cohort study. Some data were missing. An ethics officer intervention, as designed and implemented in this study, did not increase the proportion of applications to RECs that were approved on first review and did not reduce the time to a committee decision. Published by the BMJ Publishing Group Limited. For permission to use (where not

76 FR 10598 - Medicare and Medicaid Programs; Approval of the Joint Commission for Deeming Authority for...

Science.gov (United States)

2011-02-25

... corporal punishment. To meet the requirements at Sec. 482.24(b)(2), the Joint Commission revised its... include both short-term and long-range patient goals. To meet the requirements at Sec. 482.61(c)(1)(iv.... B. Term of Approval Based on the review and observations described in section III. of this final...

40 CFR 52.1323 - Approval status.

Science.gov (United States)

2010-07-01

... on January 16, 1979 (44 FR 3274) are met. (b) The Administrator approves Rule 10 CSR 10-2.290 as.... (c) The Administrator approves Rule 10 CSR 10-2.230 as identified under § 52.1320, paragraph (c)(70... SIP would be the emission limits stated in the rule. (d) The Administrator approves Rule 10 CSR 10-5...

78 FR 57208 - Notice of Passenger Facility Charge (PFC) Approvals and Disapprovals

Science.gov (United States)

2013-09-17

... notice also includes information on four applications, one approved in July 2012 and the other three... carousel 9 and oversized bag belt TU3. Terminal redevelopment program--design and associated technical.... Rehabilitate terminal access road. Administration fees. DECISION DATE: October 18, 2012. FOR FURTHER...

Directory of Certificates of Compliance for radioactive materials packages: Report of NRC approved packages. Volume 1, Revision 18

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-10-01

The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the front of Volumes 1 and 2. An alphabetical listing by user name is included in the back of Volume 3 of approved QA programs. The reports include a listing of all users of each package design and approved QA programs prior to the publication date.

Directory of Certificates of Compliance for radioactive materials packages: Report of NRC approved packages. Volume 1, Revision 18

International Nuclear Information System (INIS)

1995-10-01

The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the front of Volumes 1 and 2. An alphabetical listing by user name is included in the back of Volume 3 of approved QA programs. The reports include a listing of all users of each package design and approved QA programs prior to the publication date

76 FR 76620 - Approval and Promulgation of Implementation Plans and Designations of Areas for Air Quality...

Science.gov (United States)

2011-12-08

..., Hall, Henry, Newton, Paulding, Rockdale, Spalding and Walton Counties in their entireties, and portions..., Douglas, Fayette, Forsyth, Fulton, Gwinnett, Hall, Henry, Newton, Paulding, Rockdale, Spalding and Walton... the criteria of the CAA. Accordingly, this action merely approves state law as meeting federal...

30 CFR 14.7 - Approval marking and distribution records.

Science.gov (United States)

2010-07-01

..., EVALUATION, AND APPROVAL OF MINING PRODUCTS REQUIREMENTS FOR THE APPROVAL OF FLAME-RESISTANT CONVEYOR BELTS General Provisions § 14.7 Approval marking and distribution records. (a) An approved conveyor belt must be marketed only under the name specified in the approval. (b) Approved conveyor belt must be legibly and...

Application of the new requirements of safety of the IAEA for the previous management to the final disposal of radioactive waste in the region: a personal vision; Aplicacion de los nuevos requisitos de seguridad del OIEA para la gestion previa a la disposicion final de desechos radiactivos en la region: una vision personal

Energy Technology Data Exchange (ETDEWEB)

Sed, Luis Andres Jova, E-mail: jovaluis@gmail.com [Centro Nacional de Seguridad Nuclear (CNSN), La Habana (Cuba)

2013-07-01

The work includes the requirements for the responsibilities associated with the management prior to the final disposal of radioactive waste and as they are referred to in the Region. Also discusses the requirements for the main stages of the management prior to the final disposal of radioactive waste. A very important section of the new requirements is that establish requirements for safe operation of facilities management prior to the final disposal of radioactive wastes and the implementation of activities under conditions of safety and development. The work is emphatic on the importance of safety justification since the beginning of the development of a facility as a basis for the decision-making and approval process. Emphasis is also on the gradual approach which should provide for the collection, analysis and interpretation of the relevant technical data, plans for the design and operation, and the formulation of the justification of the security. This paper gives a personal view of the situation in the Region.

Grid fault and design-basis for wind turbines. Final report

Energy Technology Data Exchange (ETDEWEB)

Hansen, A.D.; Cutululis, N.A.; Markou, H.; Soerensen, Poul; Iov, F.

2010-01-15

This is the final report of a Danish research project 'Grid fault and design-basis for wind turbines'. The objective of this project has been to assess and analyze the consequences of the new grid connection requirements for the fatigue and ultimate structural loads of wind turbines. The fulfillment of the grid connection requirements poses challenges for the design of both the electrical system and the mechanical structure of wind turbines. The development of wind turbine models and novel control strategies to fulfill the TSO's requirements are of vital importance in this design. Dynamic models and different fault ride-through control strategies have been developed and assessed in this project for three different wind turbine concepts (active stall wind turbine, variable speed doublyfed induction generator wind turbine, variable speed multipole permanent magnet wind turbine). A computer approach for the quantification of the wind turbines structural loads caused by the fault ride-through grid requirement, has been proposed and exemplified for the case of an active stall wind turbine. This approach relies on the combination of knowledge from complimentary simulation tools, which have expertise in different specialized design areas for wind turbines. In order to quantify the impact of the grid faults and grid requirements fulfillment on wind turbines structural loads and thus on their lifetime, a rainflow and a statistical analysis for fatigue and ultimate structural loads, respectively, have been performed and compared for two cases, i.e. one when the turbine is immediately disconnected from the grid when a grid fault occurs and one when the turbine is equipped with a fault ride-through controller and therefore it is able to remain connected to the grid during the grid fault. Different storm control strategies, that enable variable speed wind turbines to produce power at wind speeds higher than 25m/s and up to 50m/s without substantially increasing

29 CFR 1952.150 - Description of the plan as initially approved.

Science.gov (United States)

2010-07-01

... Carolina § 1952.150 Description of the plan as initially approved. (a) The Department of Labor has been designated by the Governor of North Carolina to administer the plan throughout the State. The Department of... are not covered by the Federal act by virtue of section 4(b)(1) thereof, dockside maritime and...

Drugs Approved for Kidney (Renal Cell) Cancer

Science.gov (United States)

... Your Treatment Research Drugs Approved for Kidney (Renal Cell) Cancer This page lists cancer drugs approved by the ... not listed here. Drugs Approved for Kidney (Renal Cell) Cancer Afinitor (Everolimus) Aldesleukin Avastin (Bevacizumab) Axitinib Bevacizumab Cabometyx ( ...

Spent nuclear fuel project cold vacuum drying facility tempered water and tempered water cooling system design description

International Nuclear Information System (INIS)

IRWIN, J.J.

1998-01-01

This document provides the System Design Description (SDD) for the Cold Vacuum Drying Facility (CVDF) Tempered Water (TW) and Tempered Water Cooling (TWC) System . The SDD was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998), The HNF-SD-SNF-DRD-O02, 1998, Cold Vacuum Drying Facility Design Requirements, and the CVDF Design Summary Report. The SDD contains general descriptions of the TW and TWC equipment, the system functions, requirements and interfaces. The SDD provides references for design and fabrication details, operation sequences and maintenance. This SOD has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

Final Focus Systems in Linear Colliders

International Nuclear Information System (INIS)

Raubenheimer, Tor

1998-01-01

In colliding beam facilities, the ''final focus system'' must demagnify the beams to attain the very small spot sizes required at the interaction points. The first final focus system with local chromatic correction was developed for the Stanford Linear Collider where very large demagnifications were desired. This same conceptual design has been adopted by all the future linear collider designs as well as the SuperConducting Supercollider, the Stanford and KEK B-Factories, and the proposed Muon Collider. In this paper, the over-all layout, physics constraints, and optimization techniques relevant to the design of final focus systems for high-energy electron-positron linear colliders are reviewed. Finally, advanced concepts to avoid some of the limitations of these systems are discussed

Trastuzumab emtansine: first global approval.

Science.gov (United States)

Ballantyne, Anita; Dhillon, Sohita

2013-05-01

Genentech and ImmunoGen are collaborating on the development of trastuzumab emtansine, a HER2 antibody-drug conjugate that comprises Genentech's trastuzumab antibody linked to ImmunoGen's anti-mitotic agent, mertansine (a maytansine derivative; also known as DM1). The conjugate combines two strategies: the anti-HER2 activity of trastuzumab, and the targeted intracellular delivery of mertansine, a tubulin polymerisation inhibitor which interferes with mitosis and promotes apoptosis. The linker in trastuzumab emtansine is a non-reducible thioether linker, N-succinimidyl-4-(N-maleimidomethyl) cyclohexane-1-carboxylate (SMCC, designated MCC after conjugation). Trastuzumab emtansine (Kadcyla™) has been launched in the USA as second-line monotherapy for HER2-positive metastatic breast cancer, and has been filed for approval in the EU and Japan in this indication. Trastuzumab emtansine is in phase III development as first-line combination therapy or monotherapy for metastatic HER2-positive breast cancer, and as third-line monotherapy for metastatic HER2-positive breast cancer. Phase II development is underway for early-stage breast cancer and phase II/III development is underway in patients with HER2-positive gastric cancer. This article summarizes the milestones in the development of trastuzumab emtansine leading to this first approval for the treatment of patients with HER2-positive, metastatic breast cancer who previously received trastuzumab and a taxane, separately or in combination.

Final design proposal: Theta Group-The Hotbox. A proposal in response to a commercial air transportation study

Science.gov (United States)

1991-01-01

The Hotbox is a 40 passenger commercial aircraft designed to have a minimum range of 5500 ft and cruise at a velocity of 30 ft/sec. The aircraft is designed to serve the longer range overseas market in Aeroworld. In order to serve all the airports in the overseas market, the Hotbox was required to be able to use a five foot gate. A weight requirement was set a 4.5 lbs in order to maximize aircraft efficiency. Finally, a single engine system was chosen because it minimized system weight, complexity and cost. The Hotbox is estimated to cost $152,000 Aeroworld dollars and will sell for $200.000. The propulsion system for the Hotbox consists of a nose mounted Astro 15 electric powered motor and a Top Flight 12-6 propeller. A Spica airfoil was selected for the Hotbox based on the ease of construction of its flat bottom and its positive lift and drag characteristics. A fuselage of rectangular cross section will internally contain the propulsion system, control system, and a passenger bay with 2x20 seating. A combination of directional and longitudinal control will enable the Hotbox to maneuver. The final design of the Hotbox provides for takeoff distance in 26.5 ft and normal cruise range of 17,000 ft.

23 CFR 810.106 - Approval of fringe and transportation corridor parking facilities.

Science.gov (United States)

2010-04-01

... agency or instrumentality of such State or political subdivision, has the authority and capability of...; and (8) Shall approve design standards for constructing the facility as developed in cooperation with... contract with any person to operate any parking facility constructed under this section. (c) In authorizing...

Trial endpoints for drug approval in oncology: Chemoprevention.

Science.gov (United States)

Beitz, J

2001-04-01

As with other drugs, new drug applications for marketing approval of chemopreventive drugs must include data from adequate and well-controlled clinical trials that demonstrate effectiveness and safety for the intended use. This article summarizes the regulatory requirements for traditional marketing approval, as well as for approval under the accelerated approval regulations. Unlike traditional approval, accelerated approval is based on a surrogate endpoint that is reasonably likely to predict clinical benefit. Discussions with the Food and Drug Administration (FDA) regarding the validity of trial endpoints that may serve as surrogates for clinical benefit for accelerated approval should take place as early as possible in drug development. Meetings with the FDA to discuss these issues may be requested throughout the clinical development of a new drug.

A History of the Sonocare CST-100: The First FDA-approved HIFU Device

Science.gov (United States)

Muratore, Robert

2006-05-01

The Sonocare CST-100 Therapeutic Ultrasound System, designed for the treatment of glaucoma, was developed in the 1980s and became the first high intensity focused ultrasound (HIFU) device to receive Food and Drug Administration approval. The system arose from studies done by F.L. Lizzi, Eng.Sc.D., of Riverside Research Institute and D.J. Coleman, M.D., of Cornell Medical Center/New York Hospital on the safety of ultrasound diagnosis of the eye. As safety limits were probed, therapeutic regimes were discovered. Optimization of operational parameters, clinical experience, and engineering design came together through a spin-off company, Sonocare, Inc., formed to produce and market the ophthalmic device. Various precedents were set during the approval process, including the acceptance by the FDA of radiation momentum imparted to an absorber as a measure of acoustic power. Many devices were sold, but the laser industry, grandfathered into the therapeutic field, eventually out-marketed Sonocare. The CST-100 remains as a model of elegant industrial design, and existing units are used daily in HIFU laboratory experiments.

Design and manufacture of a large superconducting homopolar motor (and status of superconducting a.c. generator)

International Nuclear Information System (INIS)

Appleton, A.D.

1983-01-01

This paper describes the design and manufacture of a large superconducting motor which, in the present time of financial restraints, is continuing at least to the point of having a completed cryostat with its superconducting winding operating with a dedicated helium refrigeration plant. Comments are also made on the superconducting a.c. generator project, although a final decision on the rating of a prototype and the approval of the funding has not yet been made, the selected rating is expected to be between 200 MW and 600 MW

Procedural law problems with the construction of installations (plants) for the final storage of radioactive materials

International Nuclear Information System (INIS)

Hoppe, W.; Bunse, B.

1984-01-01

The underground exploration of the salt-mine Gorleben has to be permitted according to sec. 126 para. 3, 51 et seq. Federal Mining Act. There is, however, no need for carrying out a nuclear law procedure for the official approval of the plan because the construction of the exploration mine does not represent the construction of a final storage facility. The operation of exploration measures does not create legally relevant prejudices for procedures of the official approval of the plan according to Atomic Energy Law. (HP) [de

Integrated Circuit Design in US High-Energy Physics

Energy Technology Data Exchange (ETDEWEB)

Geronimo, G. D. [Brookhaven National Lab. (BNL), Upton, NY (United States); Christian, D. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Bebek, C. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Garcia-Sciveres, M. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Lippe, H. V. D. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Haller, G. [SLAC National Accelerator Lab., Menlo Park, CA (United States); Grillo, AA [Univ. of California, Santa Cruz, CA (United States); Newcomer, M [Univ. of Pennsylvania, Philadelphia, PA (United States)

2013-07-10

This whitepaper summarizes the status, plans, and challenges in the area of integrated circuit design in the United States for future High Energy Physics (HEP) experiments. It has been submitted to CPAD (Coordinating Panel for Advanced Detectors) and the HEP Community Summer Study 2013(Snowmass on the Mississippi) held in Minnesota July 29 to August 6, 2013. A workshop titled: US Workshop on IC Design for High Energy Physics, HEPIC2013 was held May 30 to June 1, 2013 at Lawrence Berkeley National Laboratory (LBNL). A draft of the whitepaper was distributed to the attendees before the workshop, the content was discussed at the meeting, and this document is the resulting final product. The scope of the whitepaper includes the following topics: Needs for IC technologies to enable future experiments in the three HEP frontiers Energy, Cosmic and Intensity Frontiers; Challenges in the different technology and circuit design areas and the related R&D needs; Motivation for using different fabrication technologies; Outlook of future technologies including 2.5D and 3D; Survey of ICs used in current experiments and ICs targeted for approved or proposed experiments; IC design at US institutes and recommendations for collaboration in the future.

The influence of husbands' approval on women's use of prenatal care

African Journals Online (AJOL)

Administrator

wanted the pregnancy or a wife's level of education. It was also found that the impact of a husband's approval on prenatal care is greatest among women under the age of 20. Conclusion: The findings of this study underscore the importance of targeting men when designing interventions that are intended to raise the ...

Trends in global approvals of biotech crops (1992-2014).

Science.gov (United States)

Aldemita, Rhodora R; Reaño, Ian Mari E; Solis, Renando O; Hautea, Randy A

2015-01-01

With the increasing number of genetically modified (GM) events, traits, and crops that are developed to benefit the global population, approval of these technologies for food, feed, cultivation and import in each country may vary depending on needs, demand and trade interest. ISAAA established a GMO Approval Database to document global approvals of biotech crops. GM event name, crops, traits, developer, year of approval for cultivation, food/feed, import, and relevant dossiers were sourced from credible government regulatory websites and biosafety clearinghouses. This paper investigates the trends in GM approvals for food, feed and cultivation based on the number of approving countries, GM crops, events, and traits in the last 23 y (1992-2014), rationale for approval, factors influencing approvals, and their implications in GM crop adoption. Results show that in 2014, there was an accumulative increase in the number of countries granting approvals at 29 (79% developing countries) for commercial cultivation and 31 (70% developing countries) for food and 19 (80% developing developing) for feed; 2012 had the highest number of approving countries and cultivation approvals; 2011 had the highest number of country approvals for feed, and 2014 for food approvals. Herbicide tolerance trait had the highest events approved, followed by insect tolerance traits. Approvals for food product quality increased in the second decade. Maize had the highest number of events approved (single and stacked traits), and stacked traits product gradually increased which is already 30% of the total trait approvals. These results may indicate understanding and acceptance of countries to enhance regulatory capability to be able to benefit from GM crop commercialization. Hence, the paper provided information on the trends on the growth of the GM crop industry in the last 23 y which may be vital in predicting future GM crops and traits.

40 CFR 52.2352 - Change to approved plan.

Science.gov (United States)

2010-07-01

... Utah's approved State Implementation Plan (SIP). This rule language pertains to State Sales Tax... 40 Protection of Environment 4 2010-07-01 2010-07-01 false Change to approved plan. 52.2352... (CONTINUED) APPROVAL AND PROMULGATION OF IMPLEMENTATION PLANS (CONTINUED) Utah § 52.2352 Change to approved...

The Evolution of Approval Services.

Science.gov (United States)

Warzala, Martin

1994-01-01

Describes major developments in book approval plans used by academic libraries for acquisition and for information dissemination and document distribution services based on approval-like concepts. Topics addressed include publishers; marketing; the impact of library automation; value-added services; the economic climate; the influence of…

Approval plans issues and innovations

CERN Document Server

Katz, Linda S

2013-01-01

How can you, as an acquisition librarians, keep current on the output of hundreds of publishers? The answer, of course, is that you cannot. For over 30 years, approval plans have been used by librarians to acquire current titles, save staff time, and build core collections. Even today, these reasons seem appropriate, as libraries try to maintain up-to-date collections and control personnel and operating budgets. However, as shown in Approval Plans: Issues and Innovations, the use of approval plans is not so simple and straightforward; their use is subject to complex procedures and policies--an

Directory of certificates of compliance for radioactive materials packages: Summary report of NRC approved quality assurance programs for radioactive material packages

International Nuclear Information System (INIS)

1987-11-01

This directory contains a Summary Report of the US Nuclear Regulatory Commission's Summary Report of NRC Approved Quality Assurance Programs (Volume 3) for Radioactive Material Packages effective October 1, 1987. This directory makes available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an alphabetical listing by Company name is included in the back of Volume 3 for approved QA programs. The Summary Reports include a listing of all users of each package design and approved QA programs prior to the publication date of the directory

The Iodine Satellite (iSat) Project Development Towards Critical Design Review

Science.gov (United States)

Dankanich, John W.; Calvert, Derek; Kamhawi, Hani; Hickman, Tyler; Szabo, James; Byrne, Lawrence

2015-01-01

Despite the prevalence of small satellites in recent years, the systems flown to date have very limited propulsion capability. SmallSats are typically secondary payloads and have significant constraints for volume, mass, and power in addition to limitations on the use of hazardous propellants or stored energy. These constraints limit the options for SmallSat maneuverability. NASA's Space Technology Mission Directorate approved the iodine Satellite flight project for a rapid demonstration of iodine Hall thruster technology in a 12U (cubesat units) configuration under the Small Spacecraft Technology Program. The mission is a partnership between NASA MSFC, NASA GRC, and Busek Co, Inc., with the Air Force supporting the propulsion technology maturation. The team is working towards the critical design review in the final design and fabrication phase of the project. The current design shows positive technical performance margins in all areas. The iSat project is planned for launch readiness in the spring of 2017.

48 CFR 750.7105 - Approving authorities.

Science.gov (United States)

2010-10-01

... CONTRACT MANAGEMENT EXTRAORDINARY CONTRACTUAL ACTIONS Extraordinary Contractual Actions To Protect Foreign Policy Interests of the United States 750.7105 Approving authorities. All authority to approve actions...

AP1000, a nuclear central of advanced design; AP1000, una central nuclear de diseno avanzado

Energy Technology Data Exchange (ETDEWEB)

Hernandez M, N.; Viais J, J. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)]. e-mail: nhm@nuclear.inin.mx

2005-07-01

The AP1000 is a design of a nuclear reactor of pressurized water (PWR) of 1000 M We with characteristic of safety in a passive way; besides presenting simplifications in the systems of the plant, the construction, the maintenance and the safety, the AP1000 is a design that uses technology endorsed by those but of 30 years of operational experience of the PWR reactors. The program AP1000 of Westinghouse is focused to the implementation of the plant to provide improvements in the economy of the same one and it is a design that is derived directly of the AP600 designs. On September 13, 2004 the US-NRC (for their initials in United States- Nuclear Regulatory Commission) approved the final design of the AP1000, now Westinghouse and the US-NRC are working on the whole in a complete program for the certification. (Author)

78 FR 72040 - Approval and Promulgation of Implementation Plans and Designation of Areas for Air Quality...

Science.gov (United States)

2013-12-02

... factors such as the Great Recession and weather'' and that EPA cannot approve the redesignation request... influenced by temporary economic conditions (the ``Great Recession'') and that EPA has failed to provide any... Georgia electric generating units (EGUs) in 2008, emissions in the first year of the ``Great Recession...

Proceedings of the second international workshop on design and construction of final repositories

Energy Technology Data Exchange (ETDEWEB)

Simmons, G R

1995-11-01

Many international radioactive waste disposal programs are in the design and construction phases for underground laboratories and repositories. To provide a forum for discussion Svensk Kaernbraenslehantering AB (SKB) in 1992 initiated an international workshop series in which the organizations considering disposal in hard crystalline rock could meet to discuss issues relevant to The Design and Construction of Final Repositories. The first workshop with the theme `Excavation through water conducting major fracture zones` was hosted by SKB in Saestaholm, Sweden on 1993 March 30 to 31 and the workshop proceedings are SKB Technical Report 94-06. Atomic Energy of Canada Limited hosted the second workshop with the theme `Factors influencing repository design and layout` in Winnipeg, Canada on 1994 February 15 to 17. Thirty-eight people from organizations in eight countries and representative of the European Community participated in the Workshop. This report is the summary of the second workshop. The discussions at the Workshop were recorded and reproduced in the summary. Some editorial license was used to provide the text that follows. The participants were given the opportunity to comment on the text prior to publication. Unfortunately some individual speakers could not be identified on the recording of the Workshop discussions and are labelled `unidentified` in the text. (author).

Proceedings of the second international workshop on design and construction of final repositories

International Nuclear Information System (INIS)

Simmons, G.R.

1995-11-01

Many international radioactive waste disposal programs are in the design and construction phases for underground laboratories and repositories. To provide a forum for discussion Svensk Kaernbraenslehantering AB (SKB) in 1992 initiated an international workshop series in which the organizations considering disposal in hard crystalline rock could meet to discuss issues relevant to The Design and Construction of Final Repositories. The first workshop with the theme 'Excavation through water conducting major fracture zones' was hosted by SKB in Saestaholm, Sweden on 1993 March 30 to 31 and the workshop proceedings are SKB Technical Report 94-06. Atomic Energy of Canada Limited hosted the second workshop with the theme 'Factors influencing repository design and layout' in Winnipeg, Canada on 1994 February 15 to 17. Thirty-eight people from organizations in eight countries and representative of the European Community participated in the Workshop. This report is the summary of the second workshop. The discussions at the Workshop were recorded and reproduced in the summary. Some editorial license was used to provide the text that follows. The participants were given the opportunity to comment on the text prior to publication. Unfortunately some individual speakers could not be identified on the recording of the Workshop discussions and are labelled 'unidentified' in the text. (author)

76 FR 37056 - Notice of Revision and Request for Extension of Approval of an Information Collection; Pale Cyst...

Science.gov (United States)

2011-06-24

... help prevent the artificial spread of pale cyst nematode, a major pest of potato crops in cool... Nematode'' because the title of the original subpart, ``Potato Cyst Nematode,'' was changed in a 2009 final...] Notice of Revision and Request for Extension of Approval of an Information Collection; Pale Cyst Nematode...

Waste analysis plan for confirmation or completion of Tank Farms backlog waste designation

International Nuclear Information System (INIS)

1993-08-01

This waste analysis plan satisfies the requirements of Item 3 of Ecology Order 93NM-201 as amended per the Settlement Agreement. Item 3 states: ''Within forty (40) calendar days of receipt of this Order, the US Department of Energy Richland Operations (DOE-RL) and Westinghouse Hanford Company (WHC) shall provide Ecology with a plan for review and approval detailing the established criteria and procedures for waste inspection, segregation, sampling, designation, and repackaging of all containers reported in item number-sign 1. The report shall include sampling plan criteria for different contaminated media, i.e., soils, compactable waste, high-efficiency particular air (HEPA) filters, etc., and a schedule for completing the work within the time allowed under this Order.'' Item 3 was amended per the Settlement Agreement as follows: ''In addition to the waste inspection plans for the ''unknowns'' previously provided and currently being supplemented, DOE-RL and WHC shall provide a draft waste analysis plan for the containers reported in Item 1 of the Order to Ecology by July 12, 1993. A final, DOE-RL approved waste analysis plan shall be submitted to Ecology by September 1, 1993, for Ecology's written approval by September 15, 1993.'' Containers covered by the Order, Settlement Agreement, and this waste analysis plan consist of all those reported under Item 1 of the Order, less any containers that have been identified in unusual occurrences reported by Tank Farms. This waste analysis plan describes the procedures that will be undertaken to confirm or to complete designation of the solid waste identified in the Order

Umatilla Satellite and Release Sites Project : Final Siting Report.

Energy Technology Data Exchange (ETDEWEB)

Montgomery, James M.

1992-04-01

This report presents the results of site analysis for the Umatilla Satellite and Release Sites Project. The purpose of this project is to provide engineering services for the siting and conceptual design of satellite and release facilities for the Umatilla Basin hatchery program. The Umatilla Basin hatchery program consists of artificial production facilities for salmon and steelhead to enhance production in the Umatilla River as defined in the Umatilla master plan approved in 1989 by the Northwest Power Planning Council. Facilities identified in the master plan include adult salmon broodstock holding and spawning facilities, facilities for recovery, acclimation, and/or extended rearing of salmon juveniles, and development of river sites for release of hatchery salmon and steelhead. The historic and current distribution of fall chinook, summer chinook, and coho salmon and steelhead trout was summarized for the Umatilla River basin. Current and future production and release objectives were reviewed. Twenty seven sites were evaluated for the potential and development of facilities. Engineering and environmental attributes of the sites were evaluated and compared to facility requirements for water and space. Site screening was conducted to identify the sites with the most potential for facility development. Alternative sites were selected for conceptual design of each facility type. A proposed program for adult holding facilities, final rearing/acclimation, and direct release facilities was developed.

Final safety evaluation report related to the certification of the Advanced Boiling Water Reactor design. Supplement 1

International Nuclear Information System (INIS)

1997-05-01

This report supplements the final safety evaluation report (FSER) for the US Advanced Boiling Water Reactor (ABWR) standard design. The FSER was issued by the US Nuclear Regulatory Commission (NRC) staff as NUREG-1503 in July 1994 to document the NRC staff's review of the US ABWR design. The US ABWR design was submitted by GE Nuclear Energy (GE) in accordance with the procedures of Subpart B to Part 52 of Title 10 of the Code of Federal Regulations. This supplement documents the NRC staff's review of the changes to the US ABWR design documentation since the issuance of the FSER. GE made these changes primarily as a result of first-of-a-kind-engineering (FOAKE) and as a result of the design certification rulemaking for the ABWR design. On the basis of its evaluations, the NRC staff concludes that the confirmatory issues in NUREG-1503 are resolved, that the changes to the ABWR design documentation are acceptable, and that GE's application for design certification meets the requirements of Subpart B to 10 CFR Part 52 that are applicable and technically relevant to the US ABWR design

Final safety evaluation report related to the certification of the Advanced Boiling Water Reactor design. Supplement 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-05-01

This report supplements the final safety evaluation report (FSER) for the US Advanced Boiling Water Reactor (ABWR) standard design. The FSER was issued by the US Nuclear Regulatory Commission (NRC) staff as NUREG-1503 in July 1994 to document the NRC staff`s review of the US ABWR design. The US ABWR design was submitted by GE Nuclear Energy (GE) in accordance with the procedures of Subpart B to Part 52 of Title 10 of the Code of Federal Regulations. This supplement documents the NRC staff`s review of the changes to the US ABWR design documentation since the issuance of the FSER. GE made these changes primarily as a result of first-of-a-kind-engineering (FOAKE) and as a result of the design certification rulemaking for the ABWR design. On the basis of its evaluations, the NRC staff concludes that the confirmatory issues in NUREG-1503 are resolved, that the changes to the ABWR design documentation are acceptable, and that GE`s application for design certification meets the requirements of Subpart B to 10 CFR Part 52 that are applicable and technically relevant to the US ABWR design.

Vedolizumab: first global approval.

Science.gov (United States)

Poole, Raewyn M

2014-07-01

Vedolizumab [Entyvio(®) (US, Europe)], a humanized monoclonal antibody α4β7 integrin receptor antagonist, has been developed by Millennium Pharmaceuticals (d/b/a Takeda Pharmaceuticals International) for the treatment of ulcerative colitis and Crohn's disease. Vedolizumab has received its first global approval for the treatment of ulcerative colitis and Crohn's disease in the US, for use in adult patients with moderate-to-severe disease who have had an inadequate response, loss of response or intolerance to one or more standard therapies (corticosteroids, immunomodulators or tumour necrosis factor-α inhibitor) or demonstrated dependence on corticosteroids. Vedolizumab has since been approved for ulcerative colitis and Crohn's disease in the EU, Norway, Iceland and Liechtenstein. This article summarizes the milestones in the development of vedolizumab leading to its first approval for the treatment of ulcerative colitis and Crohn's disease.

Final design and progress of WEAVE : the next generation wide-field spectroscopy facility for the William Herschel Telescope

NARCIS (Netherlands)

Dalton, Gavin; Trager, Scott; Abrams, Don Carlos; Bonifacio, Piercarlo; Aguerri, J. Alfonso L.; Middleton, Kevin; Benn, Chris; Dee, Kevin; Sayède, Frédéric; Lewis, Ian; Pragt, Johannes; Pico, Sergio; Walton, Nic; Rey, Jeurg; Allende Prieto, Carlos; Peñate, José; Lhome, Emilie; Agócs, Tibor; Alonso, José; Terrett, David; Brock, Matthew; Gilbert, James; Schallig, Ellen; Ridings, Andy; Guinouard, Isabelle; Verheijen, Marc; Tosh, Ian; Rogers, Kevin; Lee, Martin; Steele, Iain; Stuik, Remko; Tromp, Niels; Jaskó, Attila; Carrasco, Esperanza; Farcas, Szigfrid; Kragt, Jan; Lesman, Dirk; Kroes, Gabby; Mottram, Chris; Bates, Stuart; Rodriguez, Luis Fernando; Gribbin, Frank; Delgado, José Miguel; Herreros, José Miguel; Martin, Carlos; Cano, Diego; Navarro, Ramon; Irwin, Mike; Lewis, Jim; Gonzalez Solares, Eduardo; Murphy, David; Worley, Clare; Bassom, Richard; O'Mahoney, Neil; Bianco, Andrea; Zurita, Christina; ter Horst, Rik; Molinari, Emilio; Lodi, Marcello; Guerra, José; Martin, Adrian; Vallenari, Antonella; Salasnich, Bernardo; Baruffolo, Andrea; Jin, Shoko; Hill, Vanessa; Smith, Dan; Drew, Janet; Poggianti, Bianca; Pieri, Mat; Dominquez Palmero, Lillian; Farina, Cecilia

2016-01-01

We present the Final Design of the WEAVE next-generation spectroscopy facility for the William Herschel Telescope (WHT), together with a status update on the details of manufacturing, integration and the overall project schedule now that all the major fabrication contracts are in place. We also

Final design and progress of WEAVE: the next generation wide-field spectroscopy facility for the William Herschel Telescope

NARCIS (Netherlands)

Dalton, Gavin; Trager, Scott; Abrams, Don Carlos; Bonifacio, Piercarlo; Aguerri, J. Alfonso L.; Middleton, Kevin; Benn, Chris; Dee, Kevin; Sayède, Frédéric; Lewis, Ian; Pragt, Johannes; Pico, Sergio; Walton, Nic; Rey, Jeurg; Allende Prieto, Carlos; Peñate, José; Lhome, Emilie; Agócs, Tibor; Alonso, José; Terrett, David; Brock, Matthew; Gilbert, James; Schallig, Ellen; Ridings, Andy; Guinouard, Isabelle; Verheijen, Marc; Tosh, Ian; Rogers, Kevin; Lee, Martin; Steele, Iain; Stuik, Remko; Tromp, Niels; Jaskó, Attila; Carrasco, Esperanza; Farcas, Szigfrid; Kragt, Jan; Lesman, Dirk; Kroes, Gabby; Mottram, Chris; Bates, Stuart; Rodriguez, Luis Fernando; Gribbin, Frank; Delgado, José Miguel; Herreros, José Miguel; Martin, Carlos; Cano, Diego; Navarro, Ramon; Irwin, Mike; Lewis, Jim; Gonzalez Solares, Eduardo; Murphy, David; Worley, Clare; Bassom, Richard; O'Mahoney, Neil; Bianco, Andrea; Zurita, Christina; ter Horst, Rik; Molinari, Emilio; Lodi, Marcello; Guerra, José; Martin, Adrian; Vallenari, Antonella; Salasnich, Bernardo; Baruffolo, Andrea; Jin, Shoko; Hill, Vanessa; Smith, Dan; Drew, Janet; Poggianti, Bianca; Pieri, Mat; Dominquez Palmero, Lillian; Farina, Cecilia

2016-01-01

We present the Final Design of the WEAVE next-generation spectroscopy facility for the William Herschel Telescope (WHT), together with a status update on the details of manufacturing, integration and the overall project schedule now that all the major fabrication contracts are in place. We also

5 CFR 3601.107 - Prior approval for outside employment and business activities.

Science.gov (United States)

2010-01-01

... STANDARDS OF ETHICAL CONDUCT FOR EMPLOYEES OF THE DEPARTMENT OF DEFENSE § 3601.107 Prior approval for.... It does not include a routine commercial transaction or the purchase of an asset or interest, such as... component designated agency ethics official or designee may, by a written notice, exempt categories of...

19 CFR 115.55 - Termination of approval.

Science.gov (United States)

2010-04-01

... vehicle by a major repair or alteration of any of the essential features required in § 115.51. Repairs by... TREASURY CARGO CONTAINER AND ROAD VEHICLE CERTIFICATION PURSUANT TO INTERNATIONAL CUSTOMS CONVENTIONS Procedures for Approval of Individual Road Vehicles § 115.55 Termination of approval. Approval of a road...

20 CFR 617.22 - Approval of training.

Science.gov (United States)

2010-04-01

.... Perkins Vocational and Applied Technology Education Act, and employers). (i) This means that training is...) Conditions for approval. Training shall be approved for an adversely affected worker if the State agency...) available for an adversely affected worker. (i) This means that for the worker for whom approval of training...

Virotherapy: cancer gene therapy at last? [version 1; referees: 2 approved

Directory of Open Access Journals (Sweden)

Alan E. Bilsland

2016-08-01

Full Text Available For decades, effective cancer gene therapy has been a tantalising prospect; for a therapeutic modality potentially able to elicit highly effective and selective responses, definitive efficacy outcomes have often seemed out of reach. However, steady progress in vector development and accumulated experience from previous clinical studies has finally led the field to its first licensed therapy. Following a pivotal phase III trial, Imlygic (talimogene laherparepvec/T-Vec received US approval as a treatment for cutaneous and subcutaneous melanoma in October 2015, followed several weeks later by its European authorisation. These represent the first approvals for an oncolytic virotherapy. Imlygic is an advanced-generation herpesvirus-based vector optimised for oncolytic and immunomodulatory activities. Many other oncolytic agents currently remain in development, providing hope that current success will be followed by other diverse vectors that may ultimately come to constitute a new class of clinical anti-cancer agents. In this review, we discuss some of the key oncolytic viral agents developed in the adenovirus and herpesvirus classes, and the prospects for further enhancing their efficacy by combining them with novel immunotherapeutic approaches.

Fast Flux Test Facility final safety analysis report. Amendment 72

Energy Technology Data Exchange (ETDEWEB)

Gantt, D. A.

1992-08-01

This document provides the Final Safety Analysis Report (FSAR) Amendment 72 for incorporation into the Fast Flux Test Facility (FFTF) FSAR set. This amendment change incorporates Engineering Change Notices issued subsequent to Amendment 71 and approved for incorporation before June 24, 1992. These include changes in: Chapter 2, Site Characteristics; Chapter 3, Design Criteria Structures, Equipment, and Systems; Chapter 5B, Reactor Coolant System; Chapter 7, Instrumentation and Control Systems; Chapter 8, Electrical Systems - The description of the Class 1E, 125 Vdc systems is updated for the higher capacity of the newly installed, replacement batteries; Chapter 9, Auxiliary Systems - The description of the inert cell NASA systems is corrected to list the correct number of spare sample points; Chapter 11, Reactor Refueling System; Chapter 12, Radiation Protection and Waste Management; Chapter 13, Conduct of Operations; Chapter 16, Quality Assurance; Chapter 17, Technical Specifications; Chapter 19, FFTF Fire Specifications for Fire Detection, Alarm, and Protection Systems; Chapter 20, FFTF Criticality Specifications; and Appendix B, Primary Piping Integrity Evaluation.

Time to institutional review board approval with local versus central review in a multicenter pragmatic trial.

Science.gov (United States)

Neuman, Mark D; Gaskins, Lakisha J; Ziolek, Tracy

2018-02-01

Central institutional review board (IRB) review will be required for National Institutes of Health-funded multisite human subjects research as of January 2018, with similar requirements extending to most US multisite human research in 2020. Nonetheless, little is known regarding the relative efficiency of central versus local IRB review for multicenter studies. We compared the amount of time required for central versus local IRB review and approval for sites in one ongoing multicenter randomized trial. The REGAIN Trial (Regional versus General Anesthesia for Promoting Independence after Hip Fracture; clinicaltrials.gov number: NCT02507505) is an ongoing randomized trial comparing standard-care spinal anesthesia to standard-care general anesthesia for patients undergoing hip fracture surgery. After approval of the protocol by the sponsor IRB, each participating US site opted either to submit the protocol for local IRB review or to designate the sponsor IRB as the IRB of record (i.e. central IRB) via an authorization agreement after a limited local review. For each US REGAIN site approved through 18 April 2017, we assessed (1) the time in calendar days from protocol receipt to IRB submission, (2) the time in calendar days from IRB submission to IRB approval, and (3) the total time in calendar days from protocol receipt to IRB approval (i.e. time from protocol receipt to IRB submission plus time from IRB submission to IRB approval). The main study protocol was submitted to the sponsor IRB on 25 May 2015 and approved on 8 July 2015 (44 days). Out of 34 sites, 9 received initial approval from the central (sponsor) IRB; 25 sought initial approval via local review. The median time from protocol receipt to IRB submission was 39 days for sites approved by the central IRB (interquartile range: 35-134) versus 58 days for sites approved via local review (interquartile range: 41-105; p = 0.711). The median time from IRB submission to IRB approval for sites approved by

30 CFR 75.1108 - Approved conveyor belts.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Approved conveyor belts. 75.1108 Section 75... Fire-Resistant Hydraulic Fluids on Underground Equipment § 75.1108 Approved conveyor belts. (a) Until December 31, 2009 conveyor belts placed in service in underground coal mines shall be: (1) Approved under...

45 CFR 1340.13 - Approval of applications.

Science.gov (United States)

2010-10-01

... 45 Public Welfare 4 2010-10-01 2010-10-01 false Approval of applications. 1340.13 Section 1340.13... NEGLECT PREVENTION AND TREATMENT PROGRAM CHILD ABUSE AND NEGLECT PREVENTION AND TREATMENT Grants to States § 1340.13 Approval of applications. (a) The Commissioner shall approve an application for an award for...

78 FR 28622 - Notice of Approval of Record of Decision for Extending F-Line Streetcar Service to Fort Mason...

Science.gov (United States)

2013-05-15

...] Notice of Approval of Record of Decision for Extending F-Line Streetcar Service to Fort Mason Center... Environmental Impact Statement (Final EIS) for extending the F-Line historic streetcar service to Fort Mason... turnaround terminus at the Fort Mason Center; and installing appurtenant features such as signals, crossings...

Tokamak blanket design study, final report

International Nuclear Information System (INIS)

1980-08-01

A cylindrical module concept was developed, analyzed, and incorporated in a tokamak blanket system that includes piping systems, vacuum boundary sealing, and support structures. The design is based on the use of state-of-the-art structural materials (20% cold-worked type 316 stainless steel), lithium as the breeding material, and pressurized helium as the coolant. The module design consists of nested concentric cylinders (with an outer diameter of 10 cm) and features direct wall cooling by helium flowing between the outer (first-wall) cylinder and the inner (lithium-containing) cylinder. Each cylinder can withstand full coolant pressure, thus enhancing reliability. Results show that stainless steel is a viable material for a first wall subjected to a neutron wall loading of 4 MW/m 2 and a particle heat flux of 1 MW/m 2 . Lifetime analysis shows that the first-wall design meets the goal of operating at 20-min cycles with 95% duty for 100,000 cycles. To reduce system complexity, a larger 20-cm-diam module also was analyzed for incorporation in the blanket assembly. Reliability assessment indicates that it may be possible to double the module in size from 10 to 20 cm in diameter. With a modest increase in coolant pumping power, a blanket assembly comprising 20-cm-diam modules can still achieve 100,000 operating cycles - equivalent to a 3.6-year design lifetime - with only one or two helium coolant leaks into the plasma

Tokamak blanket design study, final report

Energy Technology Data Exchange (ETDEWEB)

1980-08-01

A cylindrical module concept was developed, analyzed, and incorporated in a tokamak blanket system that includes piping systems, vacuum boundary sealing, and support structures. The design is based on the use of state-of-the-art structural materials (20% cold-worked type 316 stainless steel), lithium as the breeding material, and pressurized helium as the coolant. The module design consists of nested concentric cylinders (with an outer diameter of 10 cm) and features direct wall cooling by helium flowing between the outer (first-wall) cylinder and the inner (lithium-containing) cylinder. Each cylinder can withstand full coolant pressure, thus enhancing reliability. Results show that stainless steel is a viable material for a first wall subjected to a neutron wall loading of 4 MW/m/sup 2/ and a particle heat flux of 1 MW/m/sup 2/. Lifetime analysis shows that the first-wall design meets the goal of operating at 20-min cycles with 95% duty for 100,000 cycles. To reduce system complexity, a larger 20-cm-diam module also was analyzed for incorporation in the blanket assembly. Reliability assessment indicates that it may be possible to double the module in size from 10 to 20 cm in diameter. With a modest increase in coolant pumping power, a blanket assembly comprising 20-cm-diam modules can still achieve 100,000 operating cycles - equivalent to a 3.6-year design lifetime - with only one or two helium coolant leaks into the plasma.

A planning support system to optimize approval of private housing development projects

Science.gov (United States)

Hussnain, M. Q.; Wakil, K.; Waheed, A.; Tahir, A.

2016-06-01

Out of 182 million population of Pakistan, 38% reside in urban areas having an average growth rate of 1.6%, raising the urban housing demand significantly. Poor state response to fulfil the housing needs has resulted in a mushroom growth of private housing schemes (PHS) over the years. Consequently, only in five major cities of Punjab, there are 383 legal and 150 illegal private housing development projects against 120 public sector housing schemes. A major factor behind the cancerous growth of unapproved PHS is the prolonged and delayed approval process in concerned approval authorities requiring 13 months on average. Currently, manual and paper-based approaches are used for vetting and for granting the permission which is highly subjective and non-transparent. This study aims to design a flexible planning support system (PSS) to optimize the vetting process of PHS projects under any development authority in Pakistan by reducing time and cost required for site and documents investigations. Relying on the review of regulatory documents and interviews with professional planners and land developers, this study describes the structure of a PSS developed using open- source geo-spatial tools such as OpenGeo Suite, PHP, and PostgreSQL. It highlights the development of a Knowledge Module (based on regulatory documents) containing equations related to scheme type, size (area), location, access road, components of layout plan, planning standards and other related approval checks. Furthermore, it presents the architecture of the database module and system data requirements categorized as base datasets (built-in part of PSS) and input datasets (related to the housing project under approval). It is practically demonstrated that developing a customized PSS to optimize PHS approval process in Pakistan is achievable with geospatial technology. With the provision of such a system, the approval process for private housing schemes not only becomes quicker and user-friendly but also

21 CFR 820.30 - Design controls.

Science.gov (United States)

2010-04-01

... QUALITY SYSTEM REGULATION Design Controls § 820.30 Design controls. (a) General. (1) Each manufacturer of...) Devices automated with computer software; and (ii) The devices listed in the following chart. Section... in, input to the design and development process. The plans shall be reviewed, updated, and approved...

Chloroquine, a FDA-approved Drug, Prevents Zika Virus Infection and its Associated Congenital Microcephaly in Mice.

Science.gov (United States)

Li, Chunfeng; Zhu, Xingliang; Ji, Xue; Quanquin, Natalie; Deng, Yong-Qiang; Tian, Min; Aliyari, Roghiyh; Zuo, Xiangyang; Yuan, Ling; Afridi, Shabbir Khan; Li, Xiao-Feng; Jung, Jae U; Nielsen-Saines, Karin; Qin, Frank Xiao-Feng; Qin, Cheng-Feng; Xu, Zhiheng; Cheng, Genhong

2017-10-01

Zika virus (ZIKV) has become a global public health emergency due to its rapidly expanding range and its ability to cause severe congenital defects such as microcephaly. However, there are no FDA-approved therapies or vaccines against ZIKV infection. Through our screening of viral entry inhibitors, we found that chloroquine (CQ), a commonly used antimalarial and a FDA-approved drug that has also been repurposed against other pathogens, could significantly inhibit ZIKV infection in vitro, by blocking virus internalization. We also demonstrated that CQ attenuates ZIKV-associated morbidity and mortality in mice. Finally, we proved that CQ protects fetal mice from microcephaly caused by ZIKV infection. Our methodology of focusing on previously identified antivirals in screens for effectiveness against ZIKV proved to be a rapid and efficient means of discovering new ZIKV therapeutics. Selecting drugs that were previously FDA-approved, such as CQ, also improves the likelihood that they may more quickly reach stages of clinical testing and use by the public. Copyright © 2017. Published by Elsevier B.V.

27 CFR 5.55 - Certificates of label approval.

Science.gov (United States)

2010-04-01

..., DEPARTMENT OF THE TREASURY LIQUORS LABELING AND ADVERTISING OF DISTILLED SPIRITS Requirements for Approval of... certificates of label approval and certificates of exemption from label approval, as well as appeal procedures...

Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 1998 edition

International Nuclear Information System (INIS)

1998-08-01

The information contained in this report is given in six tables. Tables 1 to 4 present administrative data including issue and expiration dates, package identification, package serial numbers, modes for which the package/shipments approved and the edition of Safety Series No. 6 on which the approval has been based. The technical information on package mass, authorized contents, and detailed and general description of the package are contained in Table 5. Table 6 shows the certificates reported to the IAEA Secretariat by each participating Member State

Directory of certificates of compliance for radioactive materials packages. Summary report of NRC approved packages

International Nuclear Information System (INIS)

1979-10-01

This directory contains a Summary Report of NRC Approved Packages for radioactive material packages effective September 14, 1979. Purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance number is included at the back of each volume of the directory. The Summary Report includes a listing of all users of each package design prior to the publication date of the directory

Directory of certificates of compliance for radioactive materials packages. Summary report of NRC approved packages

Energy Technology Data Exchange (ETDEWEB)

None

1979-10-01

This directory contains a Summary Report of NRC Approved Packages for radioactive material packages effective September 14, 1979. Purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance number is included at the back of each volume of the directory. The Summary Report includes a listing of all users of each package design prior to the publication date of the directory.

Waste Isolation Pilot Plant design validation: Final report

International Nuclear Information System (INIS)

1986-10-01

This report provides documentation of actual underground conditions encountered as they relate to the design criteria, design bases, and design configurations for the reference design of the underground openings. It includes a selection of the more essential data collected during the design validation effort and an interpretation of these data

46 CFR 188.10-3 - Approved container.

Science.gov (United States)

2010-10-01

... 46 Shipping 7 2010-10-01 2010-10-01 false Approved container. 188.10-3 Section 188.10-3 Shipping... PROVISIONS Definition of Terms Used in This Subchapter § 188.10-3 Approved container. This term means a container which is properly labeled, marked and approved by DOT for the commodity which it contains. [CGFR...

75 FR 64675 - Approval and Promulgation of Implementation Plans and Designation of Areas for Air Quality...

Science.gov (United States)

2010-10-20

...'s Approval of the El Paso Section 110(a)(1) Maintenance Plan for the 1997 8-Hour Ozone Standard... BPA State Implementation Plan (SIP), a 1997 8-hour ozone maintenance plan that includes a 2021 Motor... the 1997 8-hour ozone standard for the El Paso 1997 8-hour attainment area. DATES: Effective Date...

Design Review Report for Concrete Cover Block Replaced by Steel Plate

Energy Technology Data Exchange (ETDEWEB)

JAKA, O.M.

2000-07-27

The design for the steel cover plates to replace concrete cover blocks for U-109 was reviewed and approved in a design review meeting. The design for steel plates to replace concrete blocks were reviewed and approved by comparison and similarity with U-109 for the following additional pits: 241-U-105. 241-I-103, 241-Ax-101. 241-A-101, 241-SX-105, 241-S-A, 241-S-C, 241-SX-A.

Electronic Approval of Invoices (AEF)

CERN Multimedia

2003-01-01

With a view to the simplification of administrative procedures, AS and FI Divisions have drawn up a new procedure for the electronic approval of invoices via the EDH application. The aim of this new procedure is to rationalise the invoice approval process, notably by eliminating paper copies from the approval circuit. This will simplify the processing of invoices and facilitate their timely settlement, while at the same time maintaining a high level of security. This new procedure, in its current phase, will be gradually implemented from 1 November 2003 onwards. For clarification and further information, please see: http://ais.cern.ch/projs/AEF/help/help.htm . Finance Division, Accounts Payable Tel.: 7.22.95

Building an Undergraduate Book Approval Plan for a Large Academic Library

Directory of Open Access Journals (Sweden)

Denise Koufogiannakis

2007-05-01

Full Text Available The University of Alberta Libraries (UAL, working with two book vendors, created large-scale undergraduate book approval plans to deliver new publications. Detailed selections profiles were created for many subject areas, designed to deliver books that would have been obvious choices by subject selectors. More than 5800 monographs were received through the book approval plans during the pilot period. These volumes proved to be highly relevant to users, showing twice as much circulation as other monographs acquired during the same time period. Goals achieved through this project include: release of selectors’ time from routine work, systematic acquisition of a broadly based high-demand undergraduate collection and faster delivery of undergraduate materials. This successful program will be expanded and incorporated into UAL’s normal acquisitions processes for undergraduate materials.

Design of a β=0.175 2-gap spoke resonator

International Nuclear Information System (INIS)

Krawczyk, F.L.; Chan, K.C.D.; Garnett, R.; Gentzlinger, R.; LaFave, R.P.; Kelley, J.P.; Schrage, D.L.; Tajima, T.; Roybal, P.L.

2003-01-01

In this paper, we present the electromagnetic and structural design of a low-β superconducting spoke resonator for a beam-test in the Low Energy Demonstration Accelerator (LEDA). This test is part of the Advanced Accelerator Applications (AAA) project. Recently, the sole use of superconducting resonators from 6.7 MeV on has been approved for this project. The beam test will use the lowest-β resonator from this accelerator design. The choices of the cavity dimensions are driven by its use immediately after the LEDA Radio-Frequency Quadrupole (RFQ). The frequency is 350 MHz, the length corresponds to a geometric β (β g ) of 0.175. Our design approach has been to carry out an integrated RF and mechanical design from the start. The final cavity is well understood in terms of RF and mechanical properties. The RF properties, like Q, R/Q, peak surface fields and acceleration efficiency are very reasonable for such a low-β structure. The design also includes power coupler, vacuum and pick-up ports and their influences. The mechanical design added tuning sensitivities, tuning forces, stiffening schemes and the understanding of stresses under various load conditions. This presentation reflects changes in the coupling port and the beam aperture compared to a previously presented design [1]. (author)

Application of the new requirements of safety of the IAEA for the previous management to the final disposal of radioactive waste in the region: a personal vision

International Nuclear Information System (INIS)

Sed, Luis Andres Jova

2013-01-01

The work includes the requirements for the responsibilities associated with the management prior to the final disposal of radioactive waste and as they are referred to in the Region. Also discusses the requirements for the main stages of the management prior to the final disposal of radioactive waste. A very important section of the new requirements is that establish requirements for safe operation of facilities management prior to the final disposal of radioactive wastes and the implementation of activities under conditions of safety and development. The work is emphatic on the importance of safety justification since the beginning of the development of a facility as a basis for the decision-making and approval process. Emphasis is also on the gradual approach which should provide for the collection, analysis and interpretation of the relevant technical data, plans for the design and operation, and the formulation of the justification of the security. This paper gives a personal view of the situation in the Region

The PACKTRAM database on national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. User's guide for compiled system program

International Nuclear Information System (INIS)

1995-01-01

The PACKTRAM system program enables Member States to prepare data diskettes on national competent authorities' approval certificates for package design, special form material and shipment of radioactive material, for submission to the IAEA, and facilitates data manipulation and report preparation for the IAEA. The system program is provided as a 424 kbyte executable file, for which this document is the User Guide. The system is fully menu-driven and requires an IBM-compatible personal computer with a minimum of 640 kbyte random access memory, a hard drive and one 3-1/2 inch diskette drive. 3 refs, 6 tabs

Safety evaluation report related to the preliminary design of the Standard Nuclear Steam Supply Reference System, RESAR SP/90 (Docket No. STN 50-601)

International Nuclear Information System (INIS)

1991-04-01

On October 24, 1983, the Westinghouse Electric Corporation tendered its application for a preliminary design approval of the advanced pressurized-water reactor design for the SP/90 reactor. The Westinghouse Reference Safety Analysis Report (RESAR SP/90, Docket No. STN 50-601), describing the design of the facility, was submitted from October 24, 1983 through March 9, 1987. Staff of the US Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, has prepared this safety evaluation report of the RESAR SP/90 on the basis of its review. Because of the stage of the design, there are open issues that have not been resolved. These issues are discussed in detail throughout this report, and a summary is provided in Section 1.6 of this report. The applicant will be required to address these and any additional such concerns that may be raised during the course of the staff's review of advanced light-water reactors in support of a final design approval application. This report shall not constitute a commitment to issue a permit or license or in any way affect the authority of the Commission, its adjudicatory boards, and other presiding officers in any proceeding under Subpart G of Title 10 of the Code of Federal Regulations, Part 2

Alpha Group: The Behemoth Apteryx. Final design proposal

Science.gov (United States)

1991-01-01

The participation of the University of Notre Dame's Alpha Design Group in the NASA/Universities Space Research Association (USRA) University Advanced Design Program for the 1990 to 1991 academic year is presented. Alpha Design Group presented a design for an aircraft called The Behemoth Apteryx.

Trends in global approvals of biotech crops (1992–2014)

Science.gov (United States)

Aldemita, Rhodora R; Reaño, Ian Mari E; Solis, Renando O; Hautea, Randy A

2015-01-01

ABSTRACT With the increasing number of genetically modified (GM) events, traits, and crops that are developed to benefit the global population, approval of these technologies for food, feed, cultivation and import in each country may vary depending on needs, demand and trade interest. ISAAA established a GMO Approval Database to document global approvals of biotech crops. GM event name, crops, traits, developer, year of approval for cultivation, food/feed, import, and relevant dossiers were sourced from credible government regulatory websites and biosafety clearinghouses. This paper investigates the trends in GM approvals for food, feed and cultivation based on the number of approving countries, GM crops, events, and traits in the last 23 y (1992–2014), rationale for approval, factors influencing approvals, and their implications in GM crop adoption. Results show that in 2014, there was an accumulative increase in the number of countries granting approvals at 29 (79% developing countries) for commercial cultivation and 31 (70% developing countries) for food and 19 (80% developing developing) for feed; 2012 had the highest number of approving countries and cultivation approvals; 2011 had the highest number of country approvals for feed, and 2014 for food approvals. Herbicide tolerance trait had the highest events approved, followed by insect tolerance traits. Approvals for food product quality increased in the second decade. Maize had the highest number of events approved (single and stacked traits), and stacked traits product gradually increased which is already 30% of the total trait approvals. These results may indicate understanding and acceptance of countries to enhance regulatory capability to be able to benefit from GM crop commercialization. Hence, the paper provided information on the trends on the growth of the GM crop industry in the last 23 y which may be vital in predicting future GM crops and traits. PMID:26039675

Vermont Designated Natural Areas

Data.gov (United States)

Vermont Center for Geographic Information — Under Natural Areas Law (10 Vermont Statutes Annotated, Chapter 83 � 2607) the FPR commissioner, with the approval of the governor, may designate and set aside areas...

10 CFR Appendix C to Part 52 - Design Certification Rule for the AP600 Design

Science.gov (United States)

2010-01-01

... approval, but only for that plant; 7. All environmental issues concerning severe accident mitigation design... specified in the severe accident mitigation design alternatives evaluation. C. The Commission does not...-specific DCD. b. A proposed departure from Tier 2, other than one affecting resolution of a severe accident...

Design, construction and testing of a DC bioeffects test enclosure for small animals. Final report

Energy Technology Data Exchange (ETDEWEB)

Frazier, M J; Preache, M M

1980-11-01

This final report describes both the engineering development of a DC bioeffects test enclosure for small laboratory animals, and the biological protocol for the use of such enclosures in the testing of animals to determine possible biological effects of the environment associated with HVDC transmission lines. The test enclosure which has been designed is a modular unit, which will house up to eight rat-sized animals in individual compartments. Multiple test enclosures can be used to test larger numbers of animals. A prototype test enclosure has been fabricated and tested to characterize its electrical performance characteristics. The test enclosure provides a simulation of the dominant environment associated with HVDC transmission lines; namely, a static electric field and an ion current density. A biological experimental design has been developed for assessing the effects of the dominant components of the HVDC transmission line environment.

FDA Approval: Ibrutinib for Patients with Previously Treated Mantle Cell Lymphoma and Previously Treated Chronic Lymphocytic Leukemia.

Science.gov (United States)

de Claro, R Angelo; McGinn, Karen M; Verdun, Nicole; Lee, Shwu-Luan; Chiu, Haw-Jyh; Saber, Haleh; Brower, Margaret E; Chang, C J George; Pfuma, Elimika; Habtemariam, Bahru; Bullock, Julie; Wang, Yun; Nie, Lei; Chen, Xiao-Hong; Lu, Donghao Robert; Al-Hakim, Ali; Kane, Robert C; Kaminskas, Edvardas; Justice, Robert; Farrell, Ann T; Pazdur, Richard

2015-08-15

On November 13, 2013, the FDA granted accelerated approval to ibrutinib (IMBRUVICA capsules; Pharmacyclics, Inc.) for the treatment of patients with mantle cell lymphoma (MCL) who have received at least one prior therapy. On February 12, 2014, the FDA granted accelerated approval for the treatment of patients with chronic lymphocytic leukemia (CLL) who have received at least one prior therapy. Ibrutinib is a first-in-class Bruton's tyrosine kinase (BTK) inhibitor that received all four expedited programs of the FDA: Fast-Track designation, Breakthrough Therapy designation, Priority Review, and Accelerated Approval. Both approvals were based on overall response rate (ORR) and duration of response (DOR) in single-arm clinical trials in patients with prior treatment. In MCL (N = 111), the complete and partial response rates were 17.1% and 48.6%, respectively, for an ORR of 65.8% [95% confidence interval (CI), 56.2%-74.5%]. The median DOR was 17.5 months (95% CI, 15.8-not reached). In CLL (N = 48), the ORR was 58.3% (95% CI, 43.2%-72.4%), and the DOR ranged from 5.6 to 24.2 months. The most common adverse reactions (≥ 30% in either trial) were thrombocytopenia, diarrhea, neutropenia, bruising, upper respiratory tract infection, anemia, fatigue, musculoskeletal pain, peripheral edema, and nausea. ©2015 American Association for Cancer Research.

Final safety evaluation report related to the certification of the System 80+ design: Docket Number 52-002. Supplement 1

International Nuclear Information System (INIS)

1997-05-01

This report supplements the final safety evaluation report (FSER) for the System 80+ standard design. The FSER was issued by the US Nuclear Regulatory Commission (NRC) staff as NUREG-1462 in August 1994 to document the NRC staff's review of the System 80+ design. The System 80+ design was submitted by Asea Brown Boveri-Combustion Engineering (ABB-CE), in accordance with the procedures of Subpart B to Part 52 of Title 10 of the Code of Federal Regulations. This supplement documents the NRC staff's review of the changes to the System 80+ design documentation since the issuance of the FSER. ABB-CE made these changes as a result of its review of the System 80+ design details. The NRC staff concludes that the changes to the System 80+ design documentation are acceptable, and that ABB-CE's application for design certification meets the requirements of Subpart B to 10 CFR Part 52 that are applicable and technically relevant to the System 80+ design

76 FR 41075 - Approval and Promulgation of Air Quality Implementation Plans; Illinois; Indiana; Michigan...

Science.gov (United States)

2011-07-13

... requirements are designed to ensure that the structural components of each state's air quality management... Management (IDEM); Michigan Department of Environmental Quality (MDEQ); Minnesota Pollution Control Agency... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 52 [EPA-R05-OAR-2007-1179; FRL-9436-7] Approval and...

Unique characteristics of regulatory approval and pivotal studies of orphan anticancer drugs in Japan.

Science.gov (United States)

Nakayama, Hiroki; Tsukamoto, Katsura

2018-04-17

The approval of orphan anticancer drugs has increased, with the number exceeding that of non-orphan drugs in Japan in recent years. Although orphan anticancer drugs may have unique characteristics due to their rarity, these have not been fully characterized. We investigated anticancer drugs approved in Japan between April 2004 and November 2017 to reveal the characteristics of regulatory approval and pivotal studies on orphan anticancer drugs compared to non-orphan drugs. The median regulatory review time and number of patients in pivotal studies on orphan anticancer drugs (281.0 days [interquartile range, 263.3-336.0]; 222.5 patients [66.0-454.3]) were significantly lower than those on non-orphan drugs (353.0 days [277.0-535.5]; 521.0 patients [303.5-814.5], respectively) (P < 0.001). Phase II, non-randomized and non-controlled designs were more frequently used in pivotal studies on orphan anticancer drugs (45.9%, 41.9% and 43.2%) than non-orphan drugs (17.2%, 14.1% and 14.1%, respectively). Response rate was more commonly used as a primary endpoint in pivotal studies on orphan anticancer drugs (48.6%) than non-orphan drugs (17.2%). Indications limited by molecular features, second or later treatment line, and accelerated approval in the United States were associated with the use of response rate in orphan anticancer drug studies. In conclusion, we demonstrated that orphan anticancer drugs in Japan have unique characteristics compared to non-orphan drugs: shorter regulatory review and pivotal studies frequently using phase II, non-randomized, or non-controlled designs and response rate as a primary endpoint, with fewer patients.

Subjective and objective peer approval evaluations and self-esteem development: A test of reciprocal, prospective, and long-term effects.

Science.gov (United States)

Gruenenfelder-Steiger, Andrea E; Harris, Michelle A; Fend, Helmut A

2016-10-01

A large body of literature suggests a clear, concurrent association between peer approval and self-esteem in adolescence. However, little empirical work exists on either the prospective or reciprocal relation between peer approval and self-esteem during this age period. Moreover, it is unclear from past research whether both subjectively perceived peer approval and objectively measured peer approval are related to subsequent self-esteem over time (and vice versa) and whether these paths have long-term associations into adulthood. Using data from a large longitudinal study that covers a time span of 2 decades, we examined reciprocal, prospective relations between self-esteem and peer approval during ages 12-16 in addition to long-term relations between these variables and later social constructs at age 35. Cross-lagged regression analyses revealed small but persistent effect sizes from both types of peer approval to subsequent self-esteem in adolescence, controlling for prior self-esteem. However, effects in the reverse direction were not confirmed. These findings support the notion that peer relationships serve an important function for later self-esteem, consistent with many theoretical tenets of the importance of peers for building a strong identity. Finally, we found long-term relations between adult social constructs and adolescent objective and subjective peer approval as well as self-esteem. Therefore, not only do peer relationships play a role in self-esteem development across adolescence, but they remain impactful throughout adulthood. In sum, the current findings highlight the lasting, yet small link between peer relationships and self-esteem development and call for investigations of further influential factors for self-esteem over time. (PsycINFO Database Record (c) 2016 APA, all rights reserved).

78 FR 3897 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2013-01-17

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort AGENCY: National Institute for Occupational Safety and Health... number of work days aggregating at least 250 work days, occurring either solely under this employment or...

78 FR 3898 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2013-01-17

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort AGENCY: National Institute for Occupational Safety and Health... number of work days aggregating at least 250 work days, occurring either solely under this employment or...

Directory of certificates of compliance for radioactive materials packages: Report of NRC approved quality assurance programs for radioactive material packages

International Nuclear Information System (INIS)

1988-12-01

This directory contains a Report of the US Nuclear Regulatory Commission's Approved Packages (Volume 1), all Certificates of Compliance (Volume 2), and a Report of NRC Approved Quality Assurance Programs (Volume 3) for Radioactive Material Packages effective October 1, 1988. The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the front of Volume 2 of the directory. A listing by packaging types is included in the back of Volume 2. An alphabetical listing by Company name is included in the back of Volume 3 for approved QA programs. The Reports include a listing of all users of each package design and approved QA programs prior to the publication date of the directory

Analysis of the Education Program Approval Process: A Program Evaluation.

Science.gov (United States)

Fountaine, Charles A.; And Others

A study of the education program approval process involving the Veterans Administration (VA) and the State Approving Agencies (SAAs) had the following objectives: to describe the present education program approval process; to determine time and costs associated with the education program approval process; to describe the approval process at…

Design of strong wooden box coated with fiberglass reinforced resin for shipping and burial of contaminated glove boxes. Final report

International Nuclear Information System (INIS)

1982-01-01

The project scope of work included the complete decontamination and decommissioning (D and D) of the Westinghouse ARD Fuel Laboratories at the Cheswick Site in the shortest possible time. This has been accomplished in the following four phases: (1) preparation of documents and necessary paperwork; packaging and shipping of all special nuclear materials in an acceptable form to a reprocessing agency; (2) decontamination of all facilities, glove boxes and equipment; loading of generated waste into bins, barrels and strong wooden boxes; (3) shipping of al bins, barrels and boxes containing waste to the designated burial site; removal of all utility services from the laboratories; and (4) final survey of remaining facilities and certification for nonrestricted use; preparation of final report. This attachment contains design of strong wooden box coated with fiberglass reinforced resin for shipping and burial of contaminated glove boxes

Convenio "Andres Bello:" Informe Final [de la] Segunda Reunion de Ministros de Educacion de la Region Andina ("Andres Bello" Agreement: Final Report of the Second Meeting of the Andean Region Ministers of Education).

Science.gov (United States)

Ministros de Educacion de la Region Andina, Lima (Peru).

This final report of the second meeting of the Andean Region Ministers of Education subscribing to the Andres Bello Agreement on education and culture contains a resume of the individual sessions and the proposals approved during that meeting. The proposals cover various educational problems and issues and begin with the Declaration of Lima which…

75 FR 35437 - Notice of Request for Extension of a Currently Approved Information Collection

Science.gov (United States)

2010-06-22

... from construction of a fire station with fire fighting and rescue equipment to financing a 911 emergency system. These facilities are designed to provide fire protection and emergency rescue services to... for a currently approved information collection in support of the program for Fire and Rescue Loans...

The Finnish final disposal programme proceeds to the site selection

International Nuclear Information System (INIS)

Seppaelae, T.

1999-01-01

Research for the selection of the final disposal site has been carried out already since the beginning of 1980's. Field studies were started in 1987: In the recent years, studied sites have included Olkiluoto in Eurajoki, Haestholmen in Loviisa, Romuvaara in Kuhmo and Kivetty in Aeaenekoski. Based on 40 years operation of four power plant units, the estimate for the accumulation of spent fuel to be disposed of in Finland is 2,600 tU. A 'Decision in Principle' is needed from the Finnish government to select the final disposal site, Posiva submitted the application for a policy decision in May 1999. The intended site of the facility is Olkiluoto which produces most of the spent fuel in Finland: A disposal would minimise the need of transports. In a poll among the inhabitants of Eurajoki, 60 per cent approved the final disposal facility. After a positive decision of the government, Posiva will construct an underground research facility in Olkiluoto. The construction of the final disposal facility will take place in the 2010's, the facility should be operational in 2020. (orig.) [de

Patient-Centered Drug Approval: The Role of Patient Advocacy in the Drug Approval Process.

Science.gov (United States)

Mattingly, T Joseph; Simoni-Wastila, Linda

2017-10-01

Recent approval of eteplirsen for Duchenne muscular dystrophy (DMD), a rare disease with few treatment alternatives, has reignited the debate over the U.S. drug approval process. The evolution of legal and regulatory restrictions to the marketing and sale of pharmaceuticals has spanned more than a century, and throughout this history, patient advocacy has played a significant role. Scientific evidence from clinical trials serves as the foundation for drug approval, but the patient voice has become increasingly influential. Although the gold standard for establishing safety and efficacy through randomized controlled trials has been in place for more than 50 years, it poses several limitations for rare disorders where patient recruitment for traditional clinical trials is a major barrier. Organized efforts by patient advocacy groups to help patients with rare diseases access investigational therapy have had a legislative and regulatory effect. After approval by the FDA, patient access to therapy may still be limited by cost. A managed care organization (MCO) with the fiduciary responsibility of managing the health of a population must weigh coverage decisions for costly therapies with questionable effectiveness against alternatives within the constraint of a finite budget. Even when the FDA deems a drug safe and effective, an MCO may determine that the drug should only be made available at a tier level where out-of-pocket costs are still too high for many patients. This limitation of availability may be due to cost, other treatment alternatives, or outcomes from existing clinical evidence. However, if the MCO makes a costly new treatment for a rare disease readily available, it may temporarily satisfy a small contingency at the cost of all of its members. This article examines the risks and benefits of patient-centered drug approval and the potential economic effect of patient-centered drug approval on population health. There is no funding to disclose. Mattingly

49 CFR 1522.109 - TSA review and approval.

Science.gov (United States)

2010-10-01

... 49 Transportation 9 2010-10-01 2010-10-01 false TSA review and approval. 1522.109 Section 1522.109..., DEPARTMENT OF HOMELAND SECURITY SECURITY RULES FOR ALL MODES OF TRANSPORTATION TSA-APPROVED VALIDATION FIRMS AND VALIDATORS TSA-Approved Validation Firms and Validators for the Certified Cargo Screening Program...

49 CFR 1522.115 - Renewal of TSA approval.

Science.gov (United States)

2010-10-01

... 49 Transportation 9 2010-10-01 2010-10-01 false Renewal of TSA approval. 1522.115 Section 1522.115..., DEPARTMENT OF HOMELAND SECURITY SECURITY RULES FOR ALL MODES OF TRANSPORTATION TSA-APPROVED VALIDATION FIRMS AND VALIDATORS TSA-Approved Validation Firms and Validators for the Certified Cargo Screening Program...

29 CFR 1952.157 - Changes to approved plan.

Science.gov (United States)

2010-07-01

... (CONTINUED) APPROVED STATE PLANS FOR ENFORCEMENT OF STATE STANDARDS North Carolina § 1952.157 Changes to approved plan. (a) Legislation. (1) On March 29, 1994, the Assistant Secretary approved North Carolina's... section 17 of the Act as amended on November 5, 1990. (2) [Reserved] (b) The Voluntary Protection Program...

48 CFR 2922.103-4 - Approvals.

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 7 2010-10-01 2010-10-01 false Approvals. 2922.103-4 Section 2922.103-4 Federal Acquisition Regulations System DEPARTMENT OF LABOR SOCIOECONOMIC PROGRAMS APPLICATION OF LABOR LAWS TO GOVERNMENT ACQUISITIONS Basic Labor Policies 2922.103-4 Approvals. The “agency...

38 CFR 21.7220 - Course approval.

Science.gov (United States)

2010-07-01

...) VOCATIONAL REHABILITATION AND EDUCATION All Volunteer Force Educational Assistance Program (Montgomery GI...; Pub. L. 98-525) (b) Course approval criteria. In administering benefits payable under 38 U.S.C...) Section 21.4265—Practical training approved as institutional training or on-job training; (10) Section 21...

SUNSTORE 3. Phase 1. Project design and tender. Final report; SUNSTORE 3. Fase 1. Projektering og udbud. Slutrapport

Energy Technology Data Exchange (ETDEWEB)

Soerensen, P.A. (PlanEnergi, Skoerping (Denmark)); Moeller Nielsen, C. (Dronninglund Fjernvarme, Dronninglund (Denmark)); Baunwall, M. (NIRAS Aalborg (Denmark)); Munkholt, H. (GG-Construction, Aalborg (Denmark)); Paaske, B. (Teknologisk Institut, AArhus (Denmark)); Schmidt, T. (SOLITES, Stuttgart (Germany))

2011-03-15

The objective of the project has been to carry out detailed design and tendering for a heat production plant consisting of: - 35.000 m{sub 2} solar thermal collectors, - 60.000 m{sub 3} pit heat storage, - 3 MW{sub heat} heat pump, covering app. 50% of the heat production at Dronninglund district heating plant (Denmark). The final report for the project includes detailed design of the pit heat storage (a further development of a 10.000 m{sub 3} storage implemented in Marstal) and simulation of the total production system in the simulation software TRNSYS. (ln)

280 GHz Gyro-BWO design study: Final report

International Nuclear Information System (INIS)

1988-07-01

This report summarizes the results of a design study of a 280 GHz Gyro-BWO tunable source. The purpose of this study is to identify and propose viable design alternatives for any significant technological risk associated with building an operational BWO system. The tunable Gyro-BWO system will have three major components: a Gyro-BWO microwave tube, a superconducting magnet, and a power supply/modulator. The design tasks for this study in order of decreasing importance are: design and specification of the superconducting magnet; preliminary design and layout of a Gyro-BWO microwave tube; and specification for the power supply/modulator. 2 refs., 4 figs

Results of readiness review for start of Title II Design of ESF in salt

International Nuclear Information System (INIS)

1986-01-01

The Readiness Review Board recommends that the ESF Title II Design be initiated after approval of revised Functional Design Criteria for Title II design. This review was conducted assuming a Deaf Smith location for ESF. Seventy-four open items and eight technical holds were identified during the Readiness Review that must be addressed and resolved to ensure successful completion of the ESF Title II Design. These items include definition and approval of surface based, EDH, and subsurface testing requirements; development of an approved OCRWM/SRPO licensing position for the ESF; and acquisition and availability of site-specific confirmatory data. A Risk Assessment should be conducted to define corrective action data and technical, cost and schedule impacts and associated program risks of continuation of Title II design activities beyond those dates

33 CFR 115.70 - Advance approval of bridges.

Science.gov (United States)

2010-07-01

... 33 Navigation and Navigable Waters 1 2010-07-01 2010-07-01 false Advance approval of bridges. 115... BRIDGES BRIDGE LOCATIONS AND CLEARANCES; ADMINISTRATIVE PROCEDURES § 115.70 Advance approval of bridges. (a) The General Bridge Act of 1946 requires the approval of the location and plans of bridges prior...

Knowledge and Processes in Design. DPS Final Report.

Science.gov (United States)

Pirolli, Peter

Four papers from a project concerning information-processing characterizations of the knowledge and processes involved in design are presented. The project collected and analyzed verbal protocols from instructional designers, architects, and mechanical engineers. A framework was developed for characterizing the problem spaces of design that…

Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 1994 ed

International Nuclear Information System (INIS)

1994-08-01

This is the fifth annual report being published by the Secretariat of the International Atomic Energy Agency since implementing its database on package approval certificates (PACKTRAM) at the recommendation of the Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM). The reporting format was established at consecutive meetings of SAGSTRAM, whose membership consists of national competent authorities responsible for the transport of radioactive material from those Member States who have a nuclear industry and others who have shown a keen interest in the IAEA's transport safety programme. Through the PACKTRAM database, the Secretariat collects administrative and technical information on package approval certificates to assist national competent authorities in regulating radioactive material movements in their country. The database carries information on extant certificates and those that expired within the last two complete calendar years. The 1985 Edition of IAEA Safety Series No. 6, the ''Regulations for the Safe Transport of Radioactive Material'' highlights the role of competent authorities in assuring regulatory compliance in their own countries. Package approval certificates are an important aspect of that function. This document aims to be a useful reference for competent authorities as well as for manufacturers and shippers of radioactive material

Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 1995 edition

International Nuclear Information System (INIS)

1995-09-01

This is the sixth annual report being published by the Secretariat of the International Atomic Energy Agency since implementing its database on package approval certificates (PACKTRAM) at the recommendation of the Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM). The reporting format was established at consecutive meetings of SAGSTRAM, whose membership consists of national competent authorities responsible for the transport of radioactive material from those Member States who have a nuclear industry and others who have shown a keen interest in the IAEA's transport safety programme. Through the PACKTRAM database, the Secretariat collects administrative and technical information on package approval certificates to assist national competent authorities in regulating radioactive material movements in their country. The database carries information on extant certificates and those that expired within the last complete calendar year. The 1985 Edition of IAEA Safety Series No. 6, the ''Regulations for the Safe Transport of Radioactive Material'' highlights the role of competent authorities in assuring regulatory compliance in their own countries. Package approval certificates are an important aspect of that function. This document aims to be a useful reference for competent authorities as well as for manufacturers and shippers of radioactive material. 6 tabs

Streamlining the Capstone Process: A Time-Saving Approval System for Graduate Theses/Projects

Science.gov (United States)

Grooms, James; Kline, Douglas; Cummings, Jeffrey

2016-01-01

Capstones have become an integral part of many information systems programs, both at the undergraduate and graduate level. One of the challenges can be tracking the process from the start of the capstone to completion. This paper describes the analysis, design and implementation of a web application for the approval workflow of a master's program…

46 CFR 160.055-9 - Procedure for approval-standard and nonstandard life preservers.

Science.gov (United States)

2010-10-01

... design shall follow the procedures of subpart 159.005 of this chapter, as explained in § 160.001-3 of... manufacturer by the Coast Guard for a nonstandard life preserver approved after tests. (d) Private brand labels. Private brand labels are those bearing the name and address of a distributor in lieu of the manufacturer...

Completion report for the UMTRA project Vitro processing site, Salt Lake City, Utah

International Nuclear Information System (INIS)

1996-08-01

This completion report provides evidence that the final Salt Lake City, Utah, processing site property conditions are in accordance with the approval design and that all U.S. Environmental Protection Agency (EPA) standards have been satisfied. Included as appendixes to support the stated conclusions are the record drawings; a summary of grid test results; contract specifications and construction drawing and the EPA standards; the audit, inspection, and surveillance summary; the permit information; and project photographs. The principal objectives of remedial action at Salt Lake City were to remove the tailings from the former processing site, render the site free of contamination to EPA standards, and restore the site to the final design grade elevations. The final remedial action plan, which is approved by the U.S. Department of Energy and concurred upon by the U.S. Nuclear Regulator Commission and the state of Utah, contains the conceptual design used to develop the final approved design. During remedial action construction operations, conditions were encountered that required design features that differed form the conceptual design. These conditions and the associated design changes are noted in the record drawings. All remedial action activities were completed in conformance with the specifications and drawings. In the opinion of the state of Utah, the record drawings accurately reflect existing property conditions at the processing site

Completion report for the UMTRA Project Vitro Processing Site. Revision 1

International Nuclear Information System (INIS)

1995-03-01

This completion report provides evidence that the final Salt Lake City, Utah, processing site property conditions are in accordance with the approved design and that all US Environmental Protection Agency (EPA) standards have been satisfied. Included as appendixes to support the stated conclusions are the record drawings; a summary of grid test results; contract specifications and construction drawings, the EPA standards (40 CFR Part 192); the audit, inspection, and surveillance summary; the permit information; and project photographs. The principal objective of the remedial action at Salt Lake City is to remove the tailings from the Vitro processing site, render the site free of contamination to EPA standards, and restore the site to the final design grade elevations. The final remedial action plan (RAP), which is approved by the US Department of Energy (DOE) and concurred upon by the US Nuclear Regulatory Commission (NRC) and the state of Utah, contains the conceptual design used to develop the final approved design. During remedial action construction operations, conditions were encountered that required design features that differed from the conceptual design. These conditions and the associated design changes are noted in the record drawings. All remedial action activities were completed in conformance with the specifications and drawings; the record drawings, in the state of Utah's opinion, reflect an accurate depiction of the existing property conditions at the processing site. 25 refs., 3 figs., 22 tabs

Empirical pillar design methods review report: Final report

International Nuclear Information System (INIS)

1988-02-01

This report summarizes and evaluates empirical pillar design methods that may be of use during the conceptual design of a high-level nuclear waste repository in salt. The methods are discussed according to category (i.e, main, submain, and panel pillars; barrier pillars; and shaft pillars). Of the 21 identified for main, submain, and panel pillars, one method, the Confined Core Method, is evaluated as being most appropriate for conceptual design. Five methods are considered potentially applicable. Of six methods identified for barrier pillars, one method based on the Load Transfer Distance concept is considered most appropriate for design. Based on the evaluation of 25 methods identified for shaft pillars, an approximate sizing criterion is proposed for use in conceptual design. Aspects of pillar performance relating to creep, ground deformation, interaction with roof and floor rock, and response to high temperature environments are not adequately addressed by existing empirical design methods. 152 refs., 22 figs., 14 tabs

E-Approval Plans in Research Libraries

Science.gov (United States)

Pickett, Carmelita; Tabacaru, Simona; Harrell, Jeanne

2014-01-01

Research libraries have long invested in approval plan services, which offer an economical way to acquire scholarly and scientific publications. Traditional approval plans have evolved and now enable libraries to expand their e-book offerings to better serve researchers. Publishers offer a myriad of e-book purchasing options. These range from…

Premarket Approvals (PMA)

Data.gov (United States)

U.S. Department of Health & Human Services — Premarket approval by FDA is the required process of scientific review to ensure the safety and effectiveness of all devices classified as Class III devices. An...

75 FR 28814 - FHA Lender Approval, Annual Renewal, Periodic Updates and Required Reports From FHA Approved Lenders

Science.gov (United States)

2010-05-24

... proposal. This information is required for: (1) FHA lender approval, (2) Annual renewal of each FHA lender... following information: Title of Proposal: FHA Lender Approval, Annual Renewal, Periodic Updates and Required... and HUD-92001-C. Description of the Need for the Information and Its Proposed Use: This information is...

Request for interim approval to operate Trench 94 of the 218-E-12B Burial Ground as a chemical waste landfill for disposal of polychlorinated biphenyl waste in submarine reactor compartments

International Nuclear Information System (INIS)

Cummins, G.D.

1994-06-01

This request is submitted to seek interim approval to operate a Toxic Substances Control Act (TSCA) of 1976 chemical waste landfill for the disposal of polychlorinated biphenyl (PCB) waste. Operation of a chemical waste landfill for disposal of PCB waste is subject to the TSCA regulations of 40 CFR 761. Interim approval is requested for a period not to exceed 5 years from the date of approval. This request covers only the disposal of small 10 quantities of solid PCB waste contained in decommissioned, defueled submarine reactor compartments (SRC). In addition, the request applies only to disposal 12 of this waste in Trench 94 of the 218-E-12B Burial Ground (Trench 94) in the 13 200 East Area of the US Department of Energy's (DOE) Hanford Facility. Disposal of this waste will be conducted in accordance with the Compliance 15 Agreement (Appendix H) between the DOE Richland Operations Office (DOE-RL) and 16 the US Environmental Protection Agency (EPA), Region 10. During the 5-year interim approval period, the DOE-RL will submit an application seeking final 18 approval for operation of Trench 94 as a chemical waste landfill, including 19 any necessary waivers, and also will seek a final dangerous waste permit from 20 the Washington State Department of Ecology (Ecology) for disposal of lead 21 shielding contained in the SRCS

7 CFR 1710.105 - State regulatory approvals.

Science.gov (United States)

2010-01-01

... and Basic Policies § 1710.105 State regulatory approvals. (a) In States where a borrower is required... loans are approved by RUS: (1) Loans requiring an Environmental Impact Statement; (2) Loans to finance...

SWEETLEAD: an in silico database of approved drugs, regulated chemicals, and herbal isolates for computer-aided drug discovery.

Directory of Open Access Journals (Sweden)

Paul A Novick

Full Text Available In the face of drastically rising drug discovery costs, strategies promising to reduce development timelines and expenditures are being pursued. Computer-aided virtual screening and repurposing approved drugs are two such strategies that have shown recent success. Herein, we report the creation of a highly-curated in silico database of chemical structures representing approved drugs, chemical isolates from traditional medicinal herbs, and regulated chemicals, termed the SWEETLEAD database. The motivation for SWEETLEAD stems from the observance of conflicting information in publicly available chemical databases and the lack of a highly curated database of chemical structures for the globally approved drugs. A consensus building scheme surveying information from several publicly accessible databases was employed to identify the correct structure for each chemical. Resulting structures are filtered for the active pharmaceutical ingredient, standardized, and differing formulations of the same drug were combined in the final database. The publically available release of SWEETLEAD (https://simtk.org/home/sweetlead provides an important tool to enable the successful completion of computer-aided repurposing and drug discovery campaigns.

Perspectives used for gaining approval of budgets.

Science.gov (United States)

Franks-Joiner, G L

1990-01-01

Nurse executives think about problems using a certain perspective which may influence decisions on budgetary matters. The nurse executives' perspective used in decision-making may influence which budget proposals are developed and approved. A study was performed to determine the perspective used by nurse executives in decision-making on supplementary budget item proposals and whether perspective use influenced approval. Findings showed that use of the system view or dual-domain perspective in a proposal may enhance nurse executives' changes of gaining approval.

78 FR 2315 - Projects Approved for Consumptive Uses of Water

Science.gov (United States)

2013-01-10

... SUSQUEHANNA RIVER BASIN COMMISSION Projects Approved for Consumptive Uses of Water AGENCY: Susquehanna River Basin Commission. ACTION: Notice. SUMMARY: This notice lists the projects approved by rule..., receiving approval for the consumptive use of water pursuant to the Commission's approval by rule process...

78 FR 15402 - Projects Approved for Consumptive Uses of Water

Science.gov (United States)

2013-03-11

... SUSQUEHANNA RIVER BASIN COMMISSION Projects Approved for Consumptive Uses of Water AGENCY: Susquehanna River Basin Commission. ACTION: Notice. SUMMARY: This notice lists the projects approved by rule..., receiving approval for the consumptive use of water pursuant to the Commission's approval by rule process...

78 FR 11947 - Projects Approved for Consumptive Uses of Water

Science.gov (United States)

2013-02-20

... SUSQUEHANNA RIVER BASIN COMMISSION Projects Approved for Consumptive Uses of Water AGENCY: Susquehanna River Basin Commission. ACTION: Notice. SUMMARY: This notice lists the projects approved by rule..., receiving approval for the consumptive use of water pursuant to the Commission's approval by rule process...

78 FR 17281 - Projects Approved for Consumptive Uses of Water

Science.gov (United States)

2013-03-20

... SUSQUEHANNA RIVER BASIN COMMISSION Projects Approved for Consumptive Uses of Water AGENCY: Susquehanna River Basin Commission. ACTION: Notice. SUMMARY: This notice lists the projects approved by rule..., receiving approval for the consumptive use of water pursuant to the Commission's approval by rule process...

77 FR 16317 - Projects Approved for Consumptive Uses of Water

Science.gov (United States)

2012-03-20

... SUSQUEHANNA RIVER BASIN COMMISSION Projects Approved for Consumptive Uses of Water AGENCY: Susquehanna River Basin Commission. ACTION: Notice. SUMMARY: This notice lists the projects approved by rule..., receiving approval for the consumptive use of water pursuant to the Commission's approval by rule process...

77 FR 66909 - Projects Approved for Consumptive Uses of Water

Science.gov (United States)

2012-11-07

... SUSQUEHANNA RIVER BASIN COMMISSION Projects Approved for Consumptive Uses of Water AGENCY: Susquehanna River Basin Commission. ACTION: Notice. SUMMARY: This notice lists the projects approved by rule... below, receiving approval for the consumptive use of water pursuant to the Commission's approval by rule...

77 FR 21143 - Projects Approved for Consumptive Uses of Water

Science.gov (United States)

2012-04-09

... SUSQUEHANNA RIVER BASIN COMMISSION Projects Approved for Consumptive Uses of Water AGENCY: Susquehanna River Basin Commission. ACTION: Notice. SUMMARY: This notice lists the projects approved by rule..., receiving approval for the consumptive use of water pursuant to the Commission's approval by rule process...

77 FR 25010 - Projects Approved for Consumptive Uses of Water

Science.gov (United States)

2012-04-26

... SUSQUEHANNA RIVER BASIN COMMISSION Projects Approved for Consumptive Uses of Water AGENCY: Susquehanna River Basin Commission. ACTION: Notice. SUMMARY: This notice lists the projects approved by rule... below, receiving approval for the consumptive use of water pursuant to the Commission's approval by rule...

77 FR 34455 - Projects Approved for Consumptive Uses of Water

Science.gov (United States)

2012-06-11

... SUSQUEHANNA RIVER BASIN COMMISSION Projects Approved for Consumptive Uses of Water AGENCY: Susquehanna River Basin Commission. ACTION: Notice. SUMMARY: This notice lists the projects approved by rule..., receiving approval for the consumptive use of water pursuant to the Commission's approval by rule process...

77 FR 55891 - Projects Approved for Consumptive Uses of Water

Science.gov (United States)

2012-09-11

... SUSQUEHANNA RIVER BASIN COMMISSION Projects Approved for Consumptive Uses of Water AGENCY: Susquehanna River Basin Commission. ACTION: Notice. SUMMARY: This notice lists the projects approved by rule..., receiving approval for the consumptive use of water pursuant to the Commission's approval by rule process...

77 FR 55892 - Projects Approved for Consumptive Uses of Water

Science.gov (United States)

2012-09-11

... SUSQUEHANNA RIVER BASIN COMMISSION Projects Approved for Consumptive Uses of Water AGENCY: Susquehanna River Basin Commission. ACTION: Notice. SUMMARY: This notice lists the projects approved by rule..., receiving approval for the consumptive use of water pursuant to the Commission's approval by rule process...

77 FR 59239 - Projects Approved for Consumptive Uses of Water

Science.gov (United States)

2012-09-26

... SUSQUEHANNA RIVER BASIN COMMISSION Projects Approved for Consumptive Uses of Water AGENCY: Susquehanna River Basin Commission. ACTION: Notice. SUMMARY: This notice lists the projects approved by rule..., receiving approval for the consumptive use of water pursuant to the Commission's approval by rule process...

76 FR 47085 - Effective Date of Requirement for Premarket Approval for a Pacemaker Programmer

Science.gov (United States)

2011-08-04

... manufacturers take action to prevent the further use of devices for which no PMA or PDP has been filed and may... completion of a product development protocol (PDP) for the class III preamendments device pacemaker... injury designed to be eliminated or reduced by requiring this device to meet the statute's approval...

Securing classification and regulatory approval for deepwater projects: management challenges in a global environment

Energy Technology Data Exchange (ETDEWEB)

Feijo, Luiz P.; Burton, Gareth C. [American Bureau of Shipping (ABS), Rio de Janeiro, RJ (Brazil)

2008-07-01

As the offshore industry continues to develop and move into increasingly deeper waters, technological boundaries are being pushed to new limits. Along with these advances, the design, fabrication and installation of deepwater oil and gas projects has become an increasingly global endeavor. After providing an overview of the history and role of Classification Societies, this paper reviews the challenges of securing classification and regulatory approval in a global environment. Operational, procedural and technological changes which one Classification Society; the American Bureau of Shipping, known as ABS, has implemented to address these challenges are presented. The result of the changes has been a more customized service aiming at faster and more streamlined classification approval process. (author)

Directory of certificates of compliance for radioactive materials packages: Report of NRC approved quality assurance programs for radioactive materials packages

International Nuclear Information System (INIS)

1990-10-01

The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of compliance Number is included at the front of Volume 2 of the directory. A listing by packaging types is included in the back of Volume 2. An alphabetical listing by Company name is included in the back of Volume 3 for approved QA programs. The Reports include a listing of all users of each package design and approved QA programs prior to the publication date of the directory

Directory of certificates of compliance for radioactive materials packages: Report of NRC approved quality assurance programs for radioactive materials packages

International Nuclear Information System (INIS)

1989-10-01

The purpose of this directory is to make available a convenient source of information on packaging which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the front of Volume 2 of the directory. A listing by packaging types is included in the back of Volume 2. An alphabetical listing by Company name is included in the back of Volume 3 for approved QA programs. The Reports include a listing of all users of each package design and approved QA programs prior to the publication date of the directory

Resolution of thermal-hydraulic safety and licensing issues for the system 80+trademark design

International Nuclear Information System (INIS)

Carpentino, S.E.; Ritterbusch, S.E.; Schneider, R.E.

1995-01-01

The System 80+ trademark Standard Design is an evolutionary Advanced Light Water Reactor (ALWR) with a generating capacity of 3931 MWt (1350 MWe). The Final Design Approval (FDA) for this design was issued by the Nuclear Regulatory Commission (NRC) in July 1994. The design certification by the NRC is anticipated by the end of 1995 or early 1996. NRC review of the System 80+ design has involved several new safety issues never before addressed in a regulatory atmosphere. In addition, conformance with the Electric Power Research Institute (EPRI) ALWR Utility Requirements Document (URD) required that the System 80+ plant address nuclear industry concerns with regard to design, construction, operation and maintenance of nuclear power plants. A large number of these issues/concerns deals with previously unresolved generic thermal-hydraulic safety issues and severe accident prevention and mitigation. This paper discusses the thermal-hydraulic analyses and evaluations performed for the System 80+ design to resolve safety and licensing issues relevant to both the Nuclear Stream Supply System (NSSS) and containment designs. For the NSSS design, the Safety Depressurization System mitigation capability and resolution of the boron dilution concern are described. Examples of containment design issues dealing with containment shell strength, robustness of the reactor cavity walls and hydrogen mixing under severe accident conditions are also provided. Finally, the overall approach used in the application of NRC's new (NUREG-1465) radiological source term for System 80+ evaluation is described. The robustness of the System 80+ containment design to withstand severe accident consequences was demonstrated through detailed thermal-hydraulic analyses and evaluations. This advanced design to shown to meet NRC severe accident policy goals and ALWR URD requirements without any special design features and unnecessary costs

Final design report, September 11, 1986

International Nuclear Information System (INIS)

1988-11-01

The task is to design the quasi-optical microwave components for each of five different optical paths within the MFTF-B machine. Each path contains two reflectors. The function of the two reflectors in each path is to modify the output field of a waveguide to a desired pattern within the plasma. For all five beam paths, the waveguide output is assumed to be a TE 01 mode as decided at the July 18, design review. Each optical train consists of two reflectors. The first reflector is an off axis paraboloid which focuses the beam. The first reflector also contains the groove pattern of the twist polarizer. The second reflector receives the polarized beam from the first reflector. The function of the second reflector is to modify the phase of the polarized wavefront received from the first reflector. This modification shapes the wavefront profile in the plasma

Space Program Annual Report, For Approval

International Nuclear Information System (INIS)

TM Schaefer

2004-01-01

Knolls Atomic Power Laboratory (KAPL) (lead) has been requested by the Reference to create an unclassified report on the Prometheus Program's Jupiter Icy Moons Orbiter (JIMO) mission. This report is expected to be issued annually and be similar in level of content and scope to the NR Program's annual report ''The United States Naval Nuclear Propulsion Program'' (referred to as the Grey Book). The attachment to this letter provides a draft of the Prometheus Program report for NR review and approval. As stated in the Reference, a March 2005 issuance is planned following a coordinated NR Headquarter's review. The information contained in the attached report was obtained from open literature sources, NASA documents and Naval Reactors Program literature. The photographs contained in the report are drafts and their quality will be improved in the final version of the report. This report has been reviewed by the KAPL and Bettis Space Power Plant Staff and has been concurred with by the Manager of Space Power Plant (MJ Wollman) and the Manager of Bettis Reactor Engineering (C Eshelman)

Applying for ethical approval for research: the main issues.

Science.gov (United States)

Gelling, Leslie

2016-01-13

The need to obtain research ethical approval is common to all research involving human participants. This approval must be obtained before research participants can be approached and before data collection can begin. The process of ethical review is one way that research participants can be confident that possible risks have been considered, minimised and deemed acceptable. This article outlines some of the main issues researchers should consider when planning an application for research ethical approval by answering the following six questions: 'Do I need research ethical approval?', 'How many applications will I need to make?', 'Where should I apply for research ethical approval?', 'What do I need to include in my application?', 'What do research ethics committees look for?' and 'What other approvals might I need?' Answering these questions will enable researchers to navigate the ethical review process.