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Sample records for qualification phast phast

  1. Process Heating Assessment and Survey Tool (PHAST) Introduction...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Process Heating Assessment and Survey Tool (PHAST) Introduction Date: January 30, 2007 Instructor: Dr. Arvind Thekdi Agenda ESA Training Web Cast Introduction - 15 minutes Process ...

  2. Process Heating Assessment and Survey Tool (PHAST) Introduction

    Broader source: Energy.gov [DOE]

    This presentation provides an introduction to PHAST, shows how to use the tool to survey process heating equipment that uses fuel, steam, or electricity, and helps plant personnel identify the most energy-intensive equipment.

  3. Process Heating Assessment and Survey Tool User Manuals

    Broader source: Energy.gov [DOE]

    PHAST 3.0 User Manuals are available for Electrotechnology and Fuel Fired Technology (for US and International units). The PHAST tool can be used to assess energy use and estimate energy use reduction for industrial process heating equipment.

  4. Process Heating Assessment and Survey Tool Fact Sheet

    Broader source: Energy.gov [DOE]

    This fact sheet describes how industrial plants can improve their process heating system performance using AMO's Process Heating Assessment and Survey Tool (PHAST)

  5. Chemical Processing Qualification Standard

    Office of Environmental Management (EM)

    6-2010 February 2010 DOE STANDARD CHEMICAL PROCESSING QUALIFICATION STANDARD DOE Defense ... River Operations Office is the sponsor for the Chemical Processing Qualification Standard. ...

  6. QuickPEP Tool Demonstration

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    ... QuickPEP Tool Demonstration SSSTSSAT PHAST N X EAT MotorMaster+ AirMaster+ PSAT 3E+ CHP Tool FSAT QuickPEP Tool Results Identify Energy Savings Opportunities By System Establish ...

  7. FAQS Gap Analysis Qualification Card - Chemical Processing |...

    Office of Environmental Management (EM)

    Chemical Processing FAQS Gap Analysis Qualification Card - Chemical Processing Functional Area Qualification Standard Gap Analysis Qualification Cards outline the differences ...

  8. Functional Area Qualification Standard Qualification Cards

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA). For each functional area, the FAQS identify the minimum technical competencies and supporting knowledge and skills for a typical qualified individual working in the area.

  9. Firearms Qualification Courses Manual

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2002-01-17

    Provides detailed requirements for qualification with various firearms. Errata Sheet 5-29-02. Cancels DOE M 473.2-1.

  10. Siemens Government Services ESCO Qualification Sheet | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Siemens Government Services ESCO Qualification Sheet Siemens Government Services ESCO Qualification Sheet Fact sheet outlines the energy service company (ESCO) qualification for ...

  11. Quality Procedure- Supplier Qualification

    Broader source: Energy.gov [DOE]

    This procedure establishes the responsibilities and process for supplier qualification activities conducted by Environmental Management (EM) Headquarters (HQ) Office of Standards and Quality Assurance in accordance with EM-QA-001, Environmental Management Quality Assurance Program.

  12. Firearms Qualification Courses Manual

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1997-08-21

    Defines the required courses of fire for authorized firearms in order to ensure the uniform qualification and requalification of DOE Federal Officers and Security Police Officers by certified Federal and contractor firearms instructors.

  13. Business Case for Technical Qualification Program Accreditation...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Business Case for Technical Qualification Program Accreditation Incentives Business Case for Technical Qualification Program Accreditation Incentives TQP Accreditation standardize ...

  14. Facility Representative Qualification Equivalencies Based on...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Facility Representative Qualification Equivalencies Based on Previous Experience Facility Representative Qualification Equivalencies Based on Previous Experience The referenced ...

  15. Functional Area Qualification Standard Gap Analysis Qualification Cards

    Broader source: Energy.gov [DOE]

    FAQS Gap Analysis Qualification Cards outline the differences between the last and latest version of the FAQ Standard.

  16. Firearms Qualification Courses Manual

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1997-07-08

    Defines the required courses of fire for authorized firearms in order to ensure the uniform qualification and requalification of DOE Federal Officers and Security Police Officers by certified Federal and contractor firearms instructors. DOE N 251.40, dated 5-3-01, extends this directive until 12-31-01. Cancels DOE M 5632.7-1.

  17. Qualification of Alternative Fuels

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Qualification of Alternative Fuels May 8, 2012 Pyrolysis Oil Workshop Thomas Butcher Sustainable Energy Technologies Department Applications Baseline - Residential and Light Commercial Pressure-atomized burners with 100-150 psi fuel pressure, no fuel heating; Cyclic operation - to 12,000 cycles per year; Fuel filtration to 90 microns or finer; Storage for periods of 1 year, possibly longer; Storage temperature varied; Visible range flame detection for safety; Nitrile seal materials common; Fuels

  18. Firearms Qualification Courses Manual

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1992-12-01

    The U.S. Department of Energy (DOE) requires all protective force personnel authorized to carry firearms to receive proper firearms training and qualification. The most important part of such training is the proper use of deadly force, which is included in the DOE Basic Security policy officer Program and is available as a separate program through the Safeguards and Security Central Training Academy. Canceled by DOE M 473.2-1 dated 07/08/1997.

  19. ORISE: Training and Qualification Programs

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Training and Qualification Programs As a core part of providing effective communication and training to protect the safety of workers, the Oak Ridge Institute for Science and Education (ORISE) works with the U.S. Department of Energy (DOE) to engage in federal and contractor training and qualification management. Through training and qualification programs, ORISE provides technical training expertise to federal and contract workers to ensure field sites are safe and that each project reflects a

  20. Schneider Electric ESCO Qualification Sheet

    Broader source: Energy.gov [DOE]

    Fact sheet outlines the energy service company (ESCO) qualifications for Schneider Electric in relation to the U.S. Department of Energy's (DOEs) energy savings performance contracts (ESPC).

  1. ORISE: Training and Qualification Programs

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    By completing the program-which features qualification standards and corresponding training activities-DOE personnel build knowledge, skills and confidence to carry out...

  2. NORESCO ESCO Qualification Sheet | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    NORESCO ESCO Qualification Sheet NORESCO ESCO Qualification Sheet Document outlines the energy service company (ESCO) qualifications for NORESCO in relation to the U.S. Department of Energy's (DOEs) energy savings performance contracts (ESPC). PDF icon noresco_escoqual.pdf

  3. Ameresco ESCO Qualification Sheet | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Ameresco ESCO Qualification Sheet Ameresco ESCO Qualification Sheet Document outlines the energy service company (ESCO) qualifications for Ameresco in relation to the U.S. Department of Energy's (DOEs) energy savings performance contracts (ESPC). PDF icon ameresco_escoqual.pdf

  4. Consolidated Edison Solutions, Inc. ESCO Qualification Sheet...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Sheet Consolidated Edison Solutions, Inc. ESCO Qualification Sheet Document outlines the energy service company (ESCO) qualifications for ConEdison Solutions. PDF icon ces

  5. FAQS Qualification Card - Chemical Processing | Department of...

    Energy Savers [EERE]

    Chemical Processing FAQS Qualification Card - Chemical Processing A key element for the Department's Technical Qualification Programs is a set of common Functional Area ...

  6. FAQS Gap Analysis Qualification Card Emergency Management

    Broader source: Energy.gov [DOE]

    Functional Area Qualification Standard Gap Analysis Qualification Cards outline the differences between the last and latest version of the FAQ Standard.

  7. Accelerated Stress Testing, Qualification Testing, HAST, Field...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Accelerated Stress Testing, Qualification Testing, HAST, Field Experience Accelerated Stress Testing, Qualification Testing, HAST, Field Experience This presentation, which was the ...

  8. Advanced Qualification of Additive Manufacturing Materials Workshop

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Advanced Qualification of Additive Manufacturing Materials Workshop Advanced Qualification of Additive Manufacturing Materials Workshop WHEN: Jul 20, 2015 8:30 AM - Jul 21, 2015...

  9. FAQS Gap Analysis Qualification Card- Quality Assurance

    Broader source: Energy.gov [DOE]

    Functional Area Qualification Standard Gap Analysis Qualification Cards outline the differences between the last and latest version of the FAQ Standard.

  10. FAQS Qualification Card- Construction Management

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  11. FAQS Qualification Card- Aviation Manager

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  12. FAQS Qualification Card Emergency Management

    Broader source: Energy.gov [DOE]

    A key element for the Departments Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  13. FAQS Qualification Card Waste Management

    Broader source: Energy.gov [DOE]

    A key element for the Departments Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  14. FAQS Qualification Card Facility Representative

    Broader source: Energy.gov [DOE]

    A key element for the Departments Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  15. Technical Qualification Program Accreditation Schedule | Department of

    Energy Savers [EERE]

    Energy Schedule Technical Qualification Program Accreditation Schedule Technical Qualification Program (TQP) Accreditation Schedule for CY 2013 and 2014. PDF icon TQP Accreditation Schedule More Documents & Publications Technical Qualification Program Self-Assessment Report - Nevada Site Office - 2009 Technical Qualification Program Self-Assessment Report - Richland Operations Office - 2014 FTCP Corrective Action Plan - Revision 1

  16. FAQS Gap Analysis Qualification Card - Occupational Safety | Department

    Energy Savers [EERE]

    of Energy Occupational Safety FAQS Gap Analysis Qualification Card - Occupational Safety Functional Area Qualification Standard Gap Analysis Qualification Cards outline the differences between the last and latest version of the FAQ Standard. File Occupational Safety Gap Analysis Qualification Card More Documents & Publications FAQS Gap Analysis Qualification Card - Environmental Restoration FAQS Gap Analysis Qualification Card - Waste Management FAQS Gap Analysis Qualification Card -

  17. TOUGH2 software qualification

    SciTech Connect (OSTI)

    Pruess, K.; Simmons, A.; Wu, Y.S.; Moridis, G.

    1996-02-01

    TOUGH2 is a numerical simulation code for multi-dimensional coupled fluid and heat flow of multiphase, multicomponent fluid mixtures in porous and fractured media. It belongs to the MULKOM ({open_quotes}MULti-KOMponent{close_quotes}) family of codes and is a more general version of the TOUGH simulator. The MULKOM family of codes was originally developed with a focus on geothermal reservoir simulation. They are suited to modeling systems which contain different fluid mixtures, with applications to flow problems arising in the context of high-level nuclear waste isolation, oil and gas recovery and storage, and groundwater resource protection. TOUGH2 is essentially a subset of MULKOM, consisting of a selection of the better tested and documented MULKOM program modules. The purpose of this package of reports is to provide all software baseline documents necessary for the software qualification of TOUGH2.

  18. Energy Systems Group ESCO Qualification Sheet | Department of...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Systems Group ESCO Qualification Sheet Energy Systems Group ESCO Qualification Sheet Document outlines the energy service company (ESCO) qualifications for Energy Systems Group in ...

  19. Microsoft Word - Attachment D - Position Qualifications.docx

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    D - POSITION QUALIFICATIONS POSITION QUALIFICATIONS NOTE: If accepted, the labor category and minimum position qualifications proposed will be incorporated into (andor replace)...

  20. Protocol, Qualification Standard for the Site Lead Program -...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Qualification Standard for the Site Lead Program - May 2011 Protocol, Qualification Standard for the Site Lead Program - May 2011 May 2011 Qualification Standard for the Site Lead...

  1. Lockheed Martin ESCO Qualification Sheet | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Lockheed Martin ESCO Qualification Sheet Lockheed Martin ESCO Qualification Sheet Document outlines the energy service company (ESCO) qualifications sheet for Lockheed Martin under the Department of Energy's (DOEs) energy savings performance contract (ESPC). PDF icon Download the ESCO qualifications sheet.

  2. FTCP-08-002, Technical Qualification Program Requalification...

    Energy Savers [EERE]

    More Documents & Publications Technical Qualification Program Self-Assessment Report - Richland Operations Office - 2014 Technical Qualification Program Accreditation Report - ...

  3. Facility Representative Qualification Equivalencies Based on Previous

    Energy Savers [EERE]

    Experience | Department of Energy Facility Representative Qualification Equivalencies Based on Previous Experience Facility Representative Qualification Equivalencies Based on Previous Experience The referenced document has been used by the Department of Energy, Idaho Operations Office (DOE-ID) to grant equivalencies to candidates undergoing qualification as a Facility Representative (FR) using the FR Functional Area Qualification Standards (FAQS). Since the generation of the referenced

  4. Technical Qualification Program Accreditation Objectives and Criteria |

    Energy Savers [EERE]

    Department of Energy Objectives and Criteria Technical Qualification Program Accreditation Objectives and Criteria The program clearly identifies and documents the process used to demonstrate employee technical competence. PDF icon TQP Accreditation Objectives and Criteria More Documents & Publications Technical Qualification Program Self-Assessment Report - Sandia Site Office - 2012 Technical Qualification Program Self-Assessment Report - Richland Operations Office - 2014 Technical

  5. Check Heat Transfer Surfaces | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Heat Transfer Surfaces Check Heat Transfer Surfaces This tip sheet discusses the importance of checking heat transfer surfaces in process heating systems. PROCESS HEAT TIP SHEET #4 PDF icon Check Heat Transfer Surfaces (September 2005) More Documents & Publications Improving Process Heating System Performance: A Sourcebook for Industry, Second Edition Check Burner Air to Fuel Ratios Process Heating Assessment and Survey Tool (PHAST) Introduction

  6. Qualification of Alternative Fuels | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Qualification of Alternative Fuels Qualification of Alternative Fuels Thomas Butcher presentation on May 8, 2012 at the Pyrolysis Oil Workshop on the qualification of alternative fuels. PDF icon pyrolysis_butcher.pdf More Documents & Publications Technical Information Exchange on Pyrolysis Oil: Potential for a Renewab;e Heating Oil Substation Fuel in New England Biodiesel_Fuel_Management_Best_Practices_Report.pdf Known Challenges Associated with the Production, Transportation, Storage and

  7. FAQS Qualification Card - NNSA Package Certification Engineer |

    Energy Savers [EERE]

    Department of Energy NNSA Package Certification Engineer FAQS Qualification Card - NNSA Package Certification Engineer A key element for the Department's Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety

  8. Technical Qualification Program Accreditation Objectives and...

    Broader source: Energy.gov (indexed) [DOE]

    PDF icon TQP Accreditation Objectives and Criteria More Documents & Publications Technical Qualification Program Self-Assessment Report - Sandia Site Office - 2012 Technical ...

  9. Technical Qualification Program Reaccreditation Report - Y-12...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Reaccreditation Report - Y-12 Site Office Technical Qualification Program Reaccreditation Report - Y-12 Site Office The accreditation process consists of three distinct activities: ...

  10. Nuclear Safety Specialist Functional Area Qualification Standard

    Energy Savers [EERE]

    83-2007 November 2007 DOE STANDARD NUCLEAR SAFETY SPECIALIST FUNCTIONAL AREA QUALIFICATION ... Center (NTC) * Institute of Nuclear Power Operations (INPO) * American Institute ...

  11. Nuclear Explosives Safety Study Functional Area Qualification...

    Energy Savers [EERE]

    85-2007 September 2007 DOE STANDARD NUCLEAR EXPLOSIVE SAFETY STUDY FUNCTIONAL AREA QUALIFICATION ... bombs, including: * Radar fuses * Contact fuses * Timer fuses * Power supplies b. ...

  12. AVIATION MANAGER QUALIFICATION STANDARD REFERENCE GUIDE

    Energy Savers [EERE]

    Manager Qualification Standard Reference Guide MARCH 2010 i This page is intentionally blank. Table of Contents ii LIST OF FIGURES ..................................................................................................................... iii LIST OF TABLES ....................................................................................................................... iii ACRONYMS

  13. AVIATION SAFETY OFFICER QUALIFICATION STANDARD REFERENCE GUIDE

    Energy Savers [EERE]

    Safety Officer Qualification Standard Reference Guide MARCH 2010 i This page is intentionally blank. Table of Contents ii LIST OF FIGURES ..................................................................................................................... iii LIST OF TABLES ....................................................................................................................... iii ACRONYMS

  14. Component and System Qualification Workshop Proceedings

    Broader source: Energy.gov [DOE]

    Proceedings from the U.S. DOE Hydrogen Component and System Qualification Workshop, held at Sandia National Laboratory in Livermore, CA, on November 4, 2010.

  15. Safety Software Quality Assurance Functional Area Qualification...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    72-2011, Safety Software Quality Assurance Functional Area Qualification Standard by Diane Johnson This SSQA FAQS identifies the minimum technical competency requirements for DOE...

  16. Advanced Qualification of Additive Manufacturing Workshop

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Additive Manufacturing Workshop Poster Abstract Submission - deadline July 10, 2015 Advanced Qualification of Additive Manufacturing Materials using in situ sensors, diagnostics...

  17. Clark Energy Group ESCO Qualification Sheet

    Broader source: Energy.gov [DOE]

    Document outlines the energy service company (ESCO) qualifications for Clark Energy Group in relation to the U.S. Department of Energy's (DOEs) energy savings performance contracts (ESPC).

  18. Technical Qualification Program Self-Assessment Report - Los...

    Office of Environmental Management (EM)

    3 Technical Qualification Program Self-Assessment Report - Los Alamos Site Office - 2013 This self-assessment of the Technical Qualifications and Federal Technical Capability ...

  19. Technical Qualification Program Self-Assessment Report - Los...

    Office of Environmental Management (EM)

    5 Technical Qualification Program Self-Assessment Report - Los Alamos Field Office - FY15 The FY15 self-assessment of the Technical Qualifications and Federal Technical Capabilit ...

  20. Technical Qualification Program Self-Assessment Report - Los...

    Office of Environmental Management (EM)

    4 Technical Qualification Program Self-Assessment Report - Los Alamos Field Office - FY14 The FY14 self-assessment of the Technical Qualifications Program and Federal Technical ...

  1. FAQS Gap Analysis Qualification Card – Nuclear Explosive Safety Study

    Broader source: Energy.gov [DOE]

    Functional Area Qualification Standard Gap Analysis Qualification Cards outline the differences between the last and latest version of the FAQ Standard.

  2. FAQS Gap Analysis Qualification Card – Construction Management

    Broader source: Energy.gov [DOE]

    Functional Area Qualification Standard Gap Analysis Qualification Cards outline the differences between the last and latest version of the FAQ Standard.

  3. FAQS Gap Analysis Qualification Card – Nuclear Safety Specialist

    Broader source: Energy.gov [DOE]

    Functional Area Qualification Standard Gap Analysis Qualification Cards outline the differences between the last and latest version of the FAQ Standard.

  4. FAQS Gap Analysis Qualification Card – Fire Protection Engineering

    Broader source: Energy.gov [DOE]

    Functional Area Qualification Standard Gap Analysis Qualification Cards outline the differences between the last and latest version of the FAQ Standard.

  5. FAQS Gap Analysis Qualification Card – Radiation Protection

    Broader source: Energy.gov [DOE]

    Functional Area Qualification Standard Gap Analysis Qualification Cards outline the differences between the last and latest version of the FAQ Standard.

  6. FAQS Gap Analysis Qualification Card – General Technical Base

    Broader source: Energy.gov [DOE]

    Functional Area Qualification Standard Gap Analysis Qualification Cards outline the differences between the last and latest version of the FAQ Standard.

  7. FAQS Gap Analysis Qualification Card – Senior Technical Safety Manager

    Broader source: Energy.gov [DOE]

    Functional Area Qualification Standard Gap Analysis Qualification Cards outline the differences between the last and latest version of the FAQ Standard.

  8. FAQS Gap Analysis Qualification Card – Technical Training

    Broader source: Energy.gov [DOE]

    Functional Area Qualification Standard Gap Analysis Qualification Cards outline the differences between the last and latest version of the FAQ Standard.

  9. Senior Technical Safety Manager Qualification Program Self-Assessment...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Senior Technical Safety Manager Qualification Program Self-Assessment - Chief of Nuclear Safety Senior Technical Safety Manager Qualification Program Self-Assessment - Chief of...

  10. FAQS Gap Analysis Qualification Card – Criticality Safety

    Broader source: Energy.gov [DOE]

    Functional Area Qualification Standard Gap Analysis Qualification Cards outline the differences between the last and latest version of the FAQ Standard.

  11. FAQS Gap Analysis Qualification Card – Mechanical Systems

    Broader source: Energy.gov [DOE]

    Functional Area Qualification Standard Gap Analysis Qualification Cards outline the differences between the last and latest version of the FAQ Standard.

  12. Model Request for Qualifications to Pre-Qualify Energy Service...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Request for Qualifications to Pre-Qualify Energy Service Companies Model Request for Qualifications to Pre-Qualify Energy Service Companies This page contains a model Request for ...

  13. FAQS Gap Analysis Qualification Card – Industrial Hygiene

    Broader source: Energy.gov [DOE]

    Functional Area Qualification Standard Gap Analysis Qualification Cards outline the differences between the last and latest version of the FAQ Standard.

  14. FAQS Gap Analysis Qualification Card – Facility Representative

    Broader source: Energy.gov [DOE]

    Functional Area Qualification Standard Gap Analysis Qualification Cards outline the differences between the last and latest version of the FAQ Standard.

  15. Weapons Quality Assurance Qualification Standard

    Energy Savers [EERE]

    5-2008 September 2008 DOE STANDARD WEAPON QUALITY ASSURANCE QUALIFICATION STANDARD NNSA Weapon Quality Assurance Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1025-2008 This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ DOE-STD-1025-2008 iv INTENTIONALLY BLANK DOE-STD-1025-2008 v

  16. IHE material qualification tests description and criteria

    SciTech Connect (OSTI)

    Slape, R J

    1984-06-01

    This report describes the qualification tests presently being used at Pantex Plant, Lawrence Livermore National Laboratory, and Los Alamos National Laboratory that are required by the Department of Energy prior to the approval for an explosive as an Insensitive High Explosive (IHE) material. The acceptance criteria of each test for IHE qualification is also discussed. 5 references, 10 figures.

  17. FAQS Qualification Card – Safeguards and Security

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  18. FAQS Qualification Card – Quality Assurance

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  19. FAQS Qualification Card – Nuclear Safety Specialist

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  20. FAQS Qualification Card- Aviation Safety Officer

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  1. FAQS Qualification Card – Technical Training

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  2. FAQS Qualification Card – Radiation Protection

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  3. FAQS Qualification Card – Mechanical Systems

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  4. FAQS Qualification Card – Fire Protection Engineering

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  5. FAQS Qualification Card Nuclear Operations Specialist

    Broader source: Energy.gov [DOE]

    A key element for the Departments Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  6. FAQS Qualification Card – General Technical Base

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  7. FAQS Qualification Card – Facility Maintenance Management

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  8. FAQS Qualification Card – Environmental Restoration

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  9. FAQS Qualification Card – Criticality Safety

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  10. FAQS Qualification Card- Civil Structural Engineering

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  11. FAQS Qualification Card Technical Program Manager

    Broader source: Energy.gov [DOE]

    A key element for the Departments Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  12. FAQS Qualification Card – Industrial Hygiene

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  13. FAQS Qualification Card – Environment Compliance

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  14. FAQS Qualification Card – Weapon Quality Assurance

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  15. Methods Data Qualification Interim Report

    SciTech Connect (OSTI)

    R. Sam Alessi; Tami Grimmett; Leng Vang; Dave McGrath

    2010-09-01

    The overall goal of the Next Generation Nuclear Plant (NGNP) Data Management and Analysis System (NDMAS) is to maintain data provenance for all NGNP data including the Methods component of NGNP data. Multiple means are available to access data stored in NDMAS. A web portal environment allows users to access data, view the results of qualification tests and view graphs and charts of various attributes of the data. NDMAS also has methods for the management of the data output from VHTR simulation models and data generated from experiments designed to verify and validate the simulation codes. These simulation models represent the outcome of mathematical representation of VHTR components and systems. The methods data management approaches described herein will handle data that arise from experiment, simulation, and external sources for the main purpose of facilitating parameter estimation and model verification and validation (V&V). A model integration environment entitled ModelCenter is used to automate the storing of data from simulation model runs to the NDMAS repository. This approach does not adversely change the why computational scientists conduct their work. The method is to be used mainly to store the results of model runs that need to be preserved for auditing purposes or for display to the NDMAS web portal. This interim report demonstrates the currently development of NDMAS for Methods data and discusses data and its qualification that is currently part of NDMAS.

  16. Technical Qualification Program Accreditation Pros and Cons | Department of

    Energy Savers [EERE]

    Energy Pros and Cons Technical Qualification Program Accreditation Pros and Cons Business Case for Accreditation Incentives - Challenge the Enterprise to Foster Confidence and Support of TQP Accreditation TQP Accreditation Lessons Learned PDF icon TQP Accreditation Pros and Cons More Documents & Publications Technical Qualification Program Reaccreditation Report - Y-12 Site Office Technical Qualification Program Reaccreditation Report - Sandia Site Office Technical Qualification Program

  17. Technical Qualification Program Administrative Forms | Department of Energy

    Energy Savers [EERE]

    Administrative Forms Technical Qualification Program Administrative Forms TQP Position Evaluation Questionnaire Form and TQP Resource Management Questionnaire Form PDF icon TQP Position Evaluation Questionnaire Form PDF icon TQP Resource Management Questionnaire Form More Documents & Publications Technical Qualification Program Reaccreditation Report - Sandia Site Office Technical Qualification Program Self-Assessment Report - Oak Ridge Office - 2014 Technical Qualification Program

  18. Constellation NewEnergy ESCO Qualification Sheet | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Constellation NewEnergy ESCO Qualification Sheet Constellation NewEnergy ESCO Qualification Sheet Document outlines the energy service company (ESCO) qualifications for Constellation NewEnergy, Inc., in relation to the U.S. Department of Energy's energy savings performance contract. PDF icon Download the Constellation NewEnergy ESCO Qualification Sheet.

  19. CEG Solutions LLC ESCO Qualification Sheet | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    CEG Solutions LLC ESCO Qualification Sheet CEG Solutions LLC ESCO Qualification Sheet Document outlines the energy service company (ESCO) qualifications for CEG Solutions LLC in relation to the U.S. Department of Energy's (DOE) energy savings performance contracts. PDF icon Download the CEG Solutions qualification sheet.

  20. FAQS Gap Analysis Qualification Card - Civil Structural Engineering |

    Energy Savers [EERE]

    Department of Energy Civil Structural Engineering FAQS Gap Analysis Qualification Card - Civil Structural Engineering Functional Area Qualification Standard Gap Analysis Qualification Cards outline the differences between the last and latest version of the FAQ Standard. File Civil Structural Engineering Gap Analysis Qualification Card More Documents & Publications DOE-STD-1182-2014 FAQS Qualification Card - Civil Structural Engineering FAQS Job Task Analyses - Civil/Structural

  1. FAQS Gap Analysis Qualification Card - Waste Management | Department of

    Office of Environmental Management (EM)

    Energy Technical Training FAQS Gap Analysis Qualification Card - Technical Training Functional Area Qualification Standard Gap Analysis Qualification Cards outline the differences between the last and latest version of the FAQ Standard. File Technical Training Gap Analysis Qualification Card More Documents & Publications DOE-STD-1179-2004 DOE-HDBK-1078-94 FAQS Reference Guide - Technical Training Energy

    Waste Management FAQS Gap Analysis Qualification Card - Waste Management

  2. Quality Procedure- Personnel Training and Qualification

    Broader source: Energy.gov [DOE]

    This procedure establishes the requirements for the training and qualification of personnel in the Office of Standards and Quality Assurance, and ensures that office personnel are properly trained and qualified to correctly perform their assigned tasks.

  3. Chapter 9 - Contracting Qualifications | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    9 - Contracting Qualifications Chapter 9 - Contracting Qualifications 9.4 - Contractor Responsibility Determinations PDF icon 9.1_Conflict_of_Interest_0.pdf PDF icon 9.2_Performance_Guarantees_0.pdf PDF icon 9.3_Debarment_and_Suspension_0.pdf More Documents & Publications AcqGuide9pt2.doc� AcqGuide9.3-OPAM AcqGuide9pt1.doc�

  4. Test Cloth Qualification | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Cloth Qualification Test Cloth Qualification The Department of Energy (DOE) develops standardized data templates for reporting the results of tests conducted in accordance with current DOE test procedures. Templates may be used by third-party laboratories under contract with DOE that conduct testing in support of ENERGY STAR® verification, DOE rulemakings, and enforcement of the federal energy conservation standards. File Test Cloth Correction Factors -- v2.0 More Documents & Publications

  5. Qualifications | Y-12 National Security Complex

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Qualifications Qualifications The America's Veterans to Tennessee Engineers STEM initiative is for military members just completing their service but still on active duty who want to be nuclear, chemical, mechanical, electrical or civil engineers. To be admitted to the program, participants must: have a high school diploma or equivalent, be departing the service with an "Honorable" discharge, be able to meet admission standards of the chosen institution of higher learning, be

  6. Advanced Qualification of Additive Manufacturing Materials Workshop

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    July » Advanced Qualification of Additive Manufacturing Materials Workshop Advanced Qualification of Additive Manufacturing Materials Workshop WHEN: Jul 20, 2015 8:30 AM - Jul 21, 2015 7:30 PM WHERE: La Fonda on the Plaza Santa Fe, New Mexico SPEAKER: Multiple speakers CONTACT: Caryll Blount (505) 665-3950 CATEGORY: Science TYPE: Workshop INTERNAL: Calendar Login Event Description Invited speakers from universities and research centers, both US-based and Europe-based, will provide updates on

  7. Construction, Qualification, and Low Rate Production Start-up...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Construction, Qualification, and Low Rate Production Start-up of a DC Bus Capacitor High ... Construction, Qualification, and Low Rate Production Start-up of a DC Bus Capacitor High ...

  8. FAQS Qualification Card - Occupational Safety | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Qualification Card - Occupational Safety FAQS Qualification Card - Occupational Safety A key element for the Department's Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA). For each functional area,

  9. FPL Energy Services ESCO Qualification Sheet | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    FPL Energy Services ESCO Qualification Sheet FPL Energy Services ESCO Qualification Sheet Document outlines the energy service company (ESCO) qualifications for FPL Energy Services in relation to the U.S. Department of Energy's (DOEs) energy savings performance contract (ESPC). PDF icon fpl_escoqual.pdf

  10. Honeywell International ESCO Qualification Sheet | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Honeywell International ESCO Qualification Sheet Honeywell International ESCO Qualification Sheet Document outlines the energy service company (ESCO) qualifications for Honeywell International in relation to the U.S. Department of Energy's (DOEs) energy savings performance contracts (ESPC). PDF icon honeywell_escoqual.pdf

  11. Johnson Controls ESCO Qualification Sheet | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Johnson Controls ESCO Qualification Sheet Johnson Controls ESCO Qualification Sheet Document outlines the energy service company (ESCO) qualifications for Johnson Controls in relation to the U.S. Department of Energy's (DOEs) energy savings performance contracts (ESPC). PDF icon johnsoncontrols_escoqual.pdf

  12. Business Case for Technical Qualification Program Accreditation Incentives

    Energy Savers [EERE]

    | Department of Energy Business Case for Technical Qualification Program Accreditation Incentives Business Case for Technical Qualification Program Accreditation Incentives TQP Accreditation standardize the program throughout the Department by ensuring consistent application of TQP requirements. PDF icon Business Case for TQP Accreditation Incentives More Documents & Publications Technical Qualification Program Self-Assessment Report - Los Alamos Site Office - 2007 Technical

  13. Pepco Energy Services ESCO Qualification Sheet | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Pepco Energy Services ESCO Qualification Sheet Pepco Energy Services ESCO Qualification Sheet Document outlines the energy service company (ESCO) qualifications for Pepco Energy Services in relation to the U.S. Department of Energy's (DOEs) energy savings performance contracts (ESPC). PDF icon pepco_escoqual.pdf

  14. Benham Companies ESCO Qualification Sheet | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Benham Companies ESCO Qualification Sheet Benham Companies ESCO Qualification Sheet Document outlines the energy service company (ESCO) qualifications for Leidos Engineering (part of Benham Companies) in relation to the U.S. Department of Energy's (DOE) energy savings performance contracts (ESPC). PDF icon benham_escoqual.pdf

  15. Quality Assurance Functional Area Qualification Standard

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2002-04-22

    Replaced by DOE-1150-2013 This QA Functional Area Qualification Standard establishes common functional area competency requirements for DOE personnel who provide assistance, direction, guidance, oversight, or evaluation of contractor technical QA activities impacting the safe operation of defense nuclear facilities.

  16. Quality Assurance Functional Area Qualification Standard

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2013-12-02

    The Quality Assurance (QA) Functional Area Qualification Standard (FAQS) establishes common functional area competency requirements for all DOE QA personnel who provide assistance, direction, guidance, oversight, or evaluation of contractor technical activities that could impact the safe operation of DOE’s defense nuclear facilities.

  17. Process Intensification - Chemical Sector Focus

    Energy Savers [EERE]

    Process Heating Systems Process Heating Systems Best operating practices and advanced process heating technologies can lead to significant energy savings at your plant. Use the software tools, training, and publications listed below to optimize performance and save energy. Process Heating Tools Tools to assess your energy system: Process Heating Assessment and Survey Tool (PHAST) Qualified Specialists Qualified Specialists have passed a rigorous competency examination on a specific industrial

  18. AGR-2 Data Qualification Interim Report

    SciTech Connect (OSTI)

    Michael L. Abbott

    2010-09-01

    Projects for the very high temperature reactor (VHTR) Technology Development Office program provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR program established the NGNP Data Management and Analysis System (NDMAS) to manage and document VHTR data qualification, for storage of the data in a readily accessible electronic form, and to assist in the analysis and presentation of the data. This document gives the status of NDMAS processing and qualification of data associated with the initial reactor cycle (147A) of the second Advanced Gas Reactor (AGR-2) experiment which began on June 21, 2010. Because it is early in the AGR-2 experiment, data from only two AGR-2 data streams are reported on: Fuel Fabrication and Fuel Irradiation data. As of August 1, 2010, approximately 311,000 irradiation data records have been stored in NDMAS, and qualification tests are in progress. Preliminary information indicates that TC 2 in Capsule 2 failed prior to start of the experiment, and NDMAS testing has thus far identified only two invalid data values from the METSO data collection system Data from the Fission Product Monitoring System (FPMS) are not currently processed until after reactor cycle shutdown and have not yet been received. A description of the ATR operating conditions data associated with the AGR-2 experiment (e.g., power levels) are summarized in the AGR-1 data qualification report (INL/EXT-09-16460). Since ATR data are collected under ATR program data quality requirements (i.e., outside the VHTR program), the NGNP program and NDMAS do not take additional actions to qualify these data other than NDMAS capture testing. Data qualification of graphite characterization data collected under the Graphite Technology Development Project is reported in a separate status report (Hull 2010).

  19. RERTR Fuel Developmemt and Qualification Plan

    SciTech Connect (OSTI)

    Dan Wachs

    2007-01-01

    In late 2003 it became evident that U-Mo aluminum fuels under development exhibited significant fuel performance problems under the irradiation conditions required for conversion of most high-powered research reactors. Solutions to the fuel performance issue have been proposed and show promise in early testing. Based on these results, a Reduced Enrichment Research and Test Reactor (RERTR) program strategy has been mapped to allow generic fuel qualification to occur prior to the end of FY10 and reactor conversion to occur prior to the end of FY14. This strategy utilizes a diversity of technologies, test conditions, and test types. Scoping studies using miniature fuel plates will be completed in the time frame of 2006-2008. Irradiation of larger specimens will occur in the Advanced Test Reactor (ATR) in the United States, the Belgian Reactor-2 (BR2) reactor in Belgium, and in the OSIRIS reactor in France in 2006-2009. These scoping irradiation tests provide a large amount of data on the performance of advanced fuel types under irradiation and allow the down selection of technology for larger scale testing during the final stages of fuel qualification. In conjunction with irradiation testing, fabrication processes must be developed and made available to commercial fabricators. The commercial fabrication infrastructure must also be upgraded to ensure a reliable low enriched uranium (LEU) fuel supply. Final qualification of fuels will occur in two phases. Phase I will obtain generic approval for use of dispersion fuels with density less than 8.5 g-U/cm3. In order to obtain this approval, a larger scale demonstration of fuel performance and fabrication technology will be necessary. Several Materials Test Reactor (MTR) plate-type fuel assemblies will be irradiated in both the High Flux Reactor (HFR) and the ATR (other options include the BR2 and Russian Research Reactor, Dmitrovgrad, Russia [MIR] reactors) in 2008-2009. Following postirradiation examination, a report detailing very-high density fuel behavior will be submitted to the U.S. Nuclear Regulatory Commission (NRC). Assuming acceptable fuel behavior, it is anticipated that NRC will issue a Safety Evaluation Report granting generic approval of the developed fuels based on the qualification report. It is anticipated that Phase I of fuel qualification will be completed prior to the end of FY10. Phase II of the fuel qualification requires development of fuels with density greater than 8.5 g-U/cm3. This fuel is required to convert the remaining few reactors that have been identified for conversion. The second phase of the fuel qualification effort includes both dispersion fuels with fuel particle volume loading on the order of 65 percent, and monolithic fuels. Phase II presents a larger set of technical unknowns and schedule uncertainties than phase I. The final step in the fuel qualification process involves insertion of lead test elements into the converting reactors. Each reactor that plans to convert using the developed high-density fuels will develop a reactor specific conversion plan based upon the reactor safety basis and operating requirements. For some reactors (FRM-II, High-Flux Isotope Reactor [HFIR], and RHF) conversion will be a one-step process. In addition to the U.S. fuel development effort, a Russian fuel development strategy has been developed. Contracts with Russian Federation institutes in support of fuel development for Russian are in place.

  20. Instrumentation and Control Functional Area Qualification Standard

    Energy Savers [EERE]

    NOT MEASUREMENT SENSITIVE DOE-STD-1162-2013 June 2013 DOE STANDARD INSTRUMENTATION AND CONTROL FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A: Approved for public release; distribution is unlimited. DOE-STD-1162-2013 This document is available on the Department of Energy Technical Standards Program website at http://www.hss.energy.gov/nuclearsafety/ns/techstds/ ii

  1. Safeguards and Security Functional Area Qualification Standard

    Energy Savers [EERE]

    1-2009 May 2009 DOE STANDARD SAFEGUARDS AND SECURITY FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1171-2009 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ DOE-STD-1171-2009 iii APPROVAL The Federal

  2. Request for Qualifications for Sacramento Landfill

    Office of Energy Efficiency and Renewable Energy (EERE)

    This Request for Qualifications (RFQ) solicits experienced companies to design, permit, finance, build, and operate a solar photovoltaic farm (SPV Farm) on the City of Sacramento’s 28th Street Landfill. Respondents to this RFQ must demonstrate experience and capacity to design, permit, finance, build, and operate a SPV Farm that generates electricity that can be sold for electrical use through a power-purchase agreement. Submittals must be prepared and delivered in accordance with the requirements set forth in this document.

  3. Facility Representative Functional Area Qualification Standard

    Energy Savers [EERE]

    DOE-STD-1151-2010 October 2010 DOE STANDARD FACILITY REPRESENTATIVE FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1151-2010 ii This document is available on the Department of Energy Office of Health, Safety and Security Approved DOE Technical Standards Web Site at

  4. Fire Protection Engineering Functional Area Qualification Standard

    Energy Savers [EERE]

    37-2014 April 2014 _______________________________ Supersedes DOE-STD-1137-2007 September 2007 DOE STANDARD FIRE PROTECTION ENGINEERING FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A: Approved for public release; distribution is unlimited. DOE-STD-1137-2014 ii This document is available on the Department of Energy Technical Standards Program Website at

  5. Advanced Qualification of Additive Manufacturing Workshop

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Additive Manufacturing Workshop Advanced Qualification of Additive Manufacturing Materials (AM) Workshop Our goal is to define opportunities and research gaps within additive manufacturing (AM) and to engage the broader scientific/engineering community to discuss future research directions. thumbnail of thumbnail of Contact Institute Director Dr. Alexander V. Balatsky Institute for Materials Science (505) 665-0077 Email Deputy Director Dr. Jennifer S. Martinez Institute for Materials Science

  6. High Temperature Materials Interim Data Qualification Report

    SciTech Connect (OSTI)

    Nancy Lybeck

    2010-08-01

    ABSTRACT Projects for the very high temperature reactor (VHTR) Technology Development Office provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR program has established the NGNP Data Management and Analysis System (NDMAS) to ensure that VHTR data are qualified for use, stored in a readily accessible electronic form, and analyzed to extract useful results. This document focuses on the first NDMAS objective. It describes the High Temperature Materials characterization data stream, the processing of these data within NDMAS, and reports the interim FY2010 qualification status of the data. Data qualification activities within NDMAS for specific types of data are determined by the data qualification category assigned by the data generator. The High Temperature Materials data are being collected under NQA-1 guidelines, and will be qualified data. For NQA-1 qualified data, the qualification activities include: (1) capture testing, to confirm that the data stored within NDMAS are identical to the raw data supplied, (2) accuracy testing to confirm that the data are an accurate representation of the system or object being measured, and (3) documenting that the data were collected under an NQA-1 or equivalent Quality Assurance program. Currently, data from two test series within the High Temperature Materials data stream have been entered into the NDMAS vault: 1. Tensile Tests for Sm (i.e., Allowable Stress) Confirmatory Testing 1,403,994 records have been inserted into the NDMAS database. Capture testing is in process. 2. Creep-Fatigue Testing to Support Determination of Creep-Fatigue Interaction Diagram 918,854 records have been processed and inserted into the NDMAS database. Capture testing is in process.

  7. Technical Qualification Program Self-Assessment Report - Los Alamos Field

    Energy Savers [EERE]

    Office - 2014 | Department of Energy Los Alamos Field Office - 2014 Technical Qualification Program Self-Assessment Report - Los Alamos Field Office - 2014 This self-assessment for the Verification of the Closure of Federal Training & Qualification Deficiencies was conducted to provide Los Alamos Field Office (NA-LA) management specific information related to effectiveness of the closure actions for Federal Training and Qualification (T &Q) deficiencies identified by a recent

  8. FAQS Qualification Card - Confinement Ventilation and Process Gas

    Energy Savers [EERE]

    Treatment | Department of Energy Confinement Ventilation and Process Gas Treatment FAQS Qualification Card - Confinement Ventilation and Process Gas Treatment A key element for the Department's Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as

  9. FAQS Qualification Card - Deactivation and Decommissioning | Department of

    Energy Savers [EERE]

    Energy Deactivation and Decommissioning FAQS Qualification Card - Deactivation and Decommissioning A key element for the Department's Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA). For each

  10. FAQS Qualification Card - Instrumentation and Control | Department of

    Energy Savers [EERE]

    Energy Instrumentation and Control FAQS Qualification Card - Instrumentation and Control A key element for the Department's Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA). For each functional

  11. Microsoft Word - Attachment D - Position Qualifications.docx

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    D - POSITION QUALIFICATIONS POSITION QUALIFICATIONS NOTE: If accepted, the labor category and minimum position qualifications proposed will be incorporated into (and/or replace) the below listing. Historical Allocation (FTE) DESCRIPTION Program Manager 1 Requirements for the Program Manager include a Bachelors or higher degree in a social science, business, or related field; at least 10 years of supervisory and management experience of which 5 years must be in the operation, administration,

  12. Technical Qualification Program Self-Assessment Report - NNSA...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    NNSA Production Office - 2014 Technical Qualification Program Self-Assessment Report - NNSA Production Office - 2014 In preparation for the upcoming Chief for Defense Nuclear ...

  13. Technical Qualification Program Self-Assessment Report - Nevada...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Nevada Field Office - 2014 Technical Qualification Program Self-Assessment Report - Nevada Field Office - 2014 This self-assessment examined how the Nevada Field Office (NFO) ...

  14. Technical Qualification Program Self-Assessment Report - Los...

    Office of Environmental Management (EM)

    Site Office - 2007 Technical Qualification Program Self-Assessment Report - Los Alamos Site Office - 2007 The Federal Technical Capability Manual requires periodic self-assessment ...

  15. Technical Qualification Program Self-Assessment Report - Los...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Los Alamos Field Office - 2014 Technical Qualification Program Self-Assessment Report - Los Alamos Field Office - 2014 This self-assessment for the Verification of the Closure of ...

  16. CRAD, NNSA - Federal Employee Training and Qualification Program...

    Office of Environmental Management (EM)

    & Publications CRAD, NNSA - Facility Representatives (FR) Technical Qualification Program Self-Assessment Report - NNSA Production Office - 2014 CRAD, NNSA - Contractor Training...

  17. BLM Manual 2803: Qualifications for Holding FLPMA Grants | Open...

    Open Energy Info (EERE)

    search OpenEI Reference LibraryAdd to library PermittingRegulatory Guidance - GuideHandbook: BLM Manual 2803: Qualifications for Holding FLPMA GrantsPermitting...

  18. New Geothermal Site Identification and Qualification | Open Energy...

    Open Energy Info (EERE)

    Citation Geothermex Inc.. 2004. New Geothermal Site Identification and Qualification. Richmond, CA: California Energy Commission. Report No.: P500-04-051. Contract No.: 500-04-051....

  19. An overview of component qualification using Bayesian statistics...

    Office of Scientific and Technical Information (OSTI)

    using Bayesian statistics and energy methods. Citation Details In-Document Search Title: An overview of component qualification using Bayesian statistics and energy methods. ...

  20. DOE-STD-1176-2004; Chemical Processing Functional Area Qualification...

    Energy Savers [EERE]

    76-2004 January 2004 DOE STANDARD CHEMICAL PROCESSING FUNCTIONAL AREA QUALIFICATION ... River Operations Office is the Sponsor for the Chemical Processing Qualification Standard. ...

  1. Defense Program Equivalencies for Technical Qualification Standard Competencies12/12/1995

    Broader source: Energy.gov [DOE]

    Defense Programs has undertaken an effort to compare the competencies in the GeneralTechnical Base Qualification Standard and the Functional Area Qualification Standards withvarious positions in...

  2. Large Bore Powder Gun Qualification (U)

    SciTech Connect (OSTI)

    Rabern, Donald A.; Valdiviez, Robert

    2012-04-02

    A Large Bore Powder Gun (LBPG) is being designed to enable experimentalists to characterize material behavior outside the capabilities of the NNSS JASPER and LANL TA-55 PF-4 guns. The combination of these three guns will create a capability to conduct impact experiments over a wide range of pressures and shock profiles. The Large Bore Powder Gun will be fielded at the Nevada National Security Site (NNSS) U1a Complex. The Complex is nearly 1000 ft below ground with dedicated drifts for testing, instrumentation, and post-shot entombment. To ensure the reliability, safety, and performance of the LBPG, a qualification plan has been established and documented here. Requirements for the LBPG have been established and documented in WE-14-TR-0065 U A, Large Bore Powder Gun Customer Requirements. The document includes the requirements for the physics experiments, the gun and confinement systems, and operations at NNSS. A detailed description of the requirements is established in that document and is referred to and quoted throughout this document. Two Gun and Confinement Systems will be fielded. The Prototype Gun will be used primarily to characterize the gun and confinement performance and be the primary platform for qualification actions. This gun will also be used to investigate and qualify target and diagnostic modifications through the life of the program (U1a.104 Drift). An identical gun, the Physics Gun, will be fielded for confirmatory and Pu experiments (U1a.102D Drift). Both guns will be qualified for operation. The Gun and Confinement System design will be qualified through analysis, inspection, and testing using the Prototype Gun for the majority of process. The Physics Gun will be qualified through inspection and a limited number of qualification tests to ensure performance and behavior equivalent to the Prototype gun. Figure 1.1 shows the partial configuration of U1a and the locations of the Prototype and Physics Gun/Confinement Systems.

  3. Qualification Plus: Performance and Durability Tests Beyond IEC 61215 (Presentation)

    SciTech Connect (OSTI)

    Kurtz, S.; Jordan, J.; Kempe, M.; Miller, D.; Bosco, N.; Silverman, T.; Hacke, P.; Phillips, N.; Earnest, T.; Romero, R.

    2014-03-01

    Qualification Plus is an accelerated test protocol and quality management system that gives higher confidence in field performance of PV modules compared with conventional qualification testing. The test sequences are being developed as consensus standards, but the early publication of these tests enables the community to begin benefiting from them sooner.

  4. FAQS Qualification Card – Nuclear Explosive Safety Study

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  5. FAQS Qualification Card- Electrical Systems and Safety Oversight

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  6. Technical Qualification Program Self-Assessment Report - Richland

    Energy Savers [EERE]

    Operations Office - 2014 | Department of Energy Richland Operations Office - 2014 Technical Qualification Program Self-Assessment Report - Richland Operations Office - 2014 The Richland Operations Office (RL) Technical Qualification Program Plan establishes a process to objectively determine that individuals performing activities related to the technical support, management, oversight, or operation possess the necessary knowledge, skills, and abilities to perform their assigned duties and

  7. FAQS Qualification Card – Safeguards and Security General Technical Base

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  8. FAQS Qualification Card – Safety Software Quality Assurance

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  9. FAQS Qualification Card – Senior Technical Safety Manager

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  10. Equipment qualification issues research and resolution: Status report

    SciTech Connect (OSTI)

    Bonzon, L.L.; Wyant, F.J.; Bustard, L.D.; Gillen, K.T.

    1986-11-01

    Since its inception in 1975, the Qualification Testing Evaluation (QTE) Program has produced numerous results pertinent to equipment qualification issues. Many have been incorporated into Regulatory Guides, Rules, and industry practices and standards. This report summarizes the numerous reports and findings to date. Thirty separate issues are discussed encompassing three generic areas: accident simulation methods, aging simulation methods, and special topics related to equipment qualification. Each issue-specific section contains (1) a brief description of the issue, (2) a summary of the applicable research effort, and (3) a summary of the findings to date.

  11. Technical Qualification Program Self-Assessment Report - Los...

    Office of Environmental Management (EM)

    1 Technical Qualification Program Self-Assessment Report - Los Alamos Site Office - 2011 The purpose of the FTCP TQP self-assessment team evaluation was to conduct a thorough ...

  12. Construction, Qualification, and Low Rate Production Start-up...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    of a DC Bus Capacitor High Volume Manufacturing Facility with Capacity to Support 100,000 Electric Drive Vehicles Construction, Qualification, and Low Rate Production Start-up of a...

  13. CRAD, NNSA- Contractor Training and Qualification (T&Q)

    Office of Energy Efficiency and Renewable Energy (EERE)

    CRAD for Contractor Training and Qualification (T&Q). Criteria Review and Approach Documents (CRADs) that can be used to conduct a well-organized and thorough assessment of elements of safety and health programs.

  14. Testing, Evaluation, and Qualification of Bio-Oil for Heating...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Testing, Evaluation, and Qualification of Bio-Oil for Heating March 26, 2015 Dr. Thomas A. ... of 20% of the petroleum-derived heating oil in the Northeast with infrastructure ...

  15. Construction, Qualification, and Low Rate Production Start-up...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Bus Capacitor High Volume Manufacturing Facility with Capacity to Support 100,000 Electric Drive Vehicles Construction, Qualification, and Low Rate Production Start-up of a DC Bus ...

  16. SRNL PHASE 1 ASSESSMENT OF THE WTP WASTE QUALIFICATION PROGRAM

    SciTech Connect (OSTI)

    Peeler, D.; Hansen, E.; Herman, C.; Marra, S.; Wilmarth, B.

    2012-03-06

    The Hanford Tank Waste Treatment and Immobilization Plant (WTP) Project is currently transitioning its emphasis from an engineering design and construction phase toward facility completion, start-up and commissioning. With this transition, the WTP Project has initiated more detailed assessments of the requirements that must be met during the actual processing of the Hanford Site tank waste. One particular area of interest is the waste qualification program. In general, the waste qualification program involves testing and analysis to demonstrate compliance with waste acceptance criteria, determine waste processability, and demonstrate laboratory-scale unit operations to support WTP operations. The testing and analysis are driven by data quality objectives (DQO) requirements necessary for meeting waste acceptance criteria for transfer of high-level wastes from the tank farms to the WTP, and for ensuring waste processability including proper glass formulations during processing within the WTP complex. Given the successful implementation of similar waste qualification efforts at the Savannah River Site (SRS) which were based on critical technical support and guidance from the Savannah River National Laboratory (SRNL), WTP requested subject matter experts (SMEs) from SRNL to support a technology exchange with respect to waste qualification programs in which a critical review of the WTP program could be initiated and lessons learned could be shared. The technology exchange was held on July 18-20, 2011 in Richland, Washington, and was the initial step in a multi-phased approach to support development and implementation of a successful waste qualification program at the WTP. The 3-day workshop was hosted by WTP with representatives from the Tank Operations Contractor (TOC) and SRNL in attendance as well as representatives from the US DOE Office of River Protection (ORP) and the Defense Nuclear Facility Safety Board (DNFSB) Site Representative office. The purpose of the workshop was to share lessons learned and provide a technology exchange to support development of a technically defensible waste qualification program. The objective of this report is to provide a review, from SRNL's perspective, of the WTP waste qualification program as presented during the workshop. In addition to SRNL's perspective on the general approach to the waste qualification program, more detailed insight into the specific unit operations presented by WTP during the workshop is provided. This report also provides a general overview of the SRS qualification program which serves as a basis for a comparison between the two programs. Recommendations regarding specific steps are made based on the review and SRNL's lessons learned from qualification of SRS low-activity waste (LAW) and high-level waste (HLW) to support maturation of the waste qualification program leading to WTP implementation.

  17. An overview of component qualification using Bayesian statistics and energy

    Office of Scientific and Technical Information (OSTI)

    methods. (Technical Report) | SciTech Connect An overview of component qualification using Bayesian statistics and energy methods. Citation Details In-Document Search Title: An overview of component qualification using Bayesian statistics and energy methods. The below overview is designed to give the reader a limited understanding of Bayesian and Maximum Likelihood (MLE) estimation; a basic understanding of some of the mathematical tools to evaluate the quality of an estimation; an

  18. 40 MM Grenade Launcher Qualification Requirements at Department of Energy

    Energy Savers [EERE]

    Sites, IG-0806 | Department of Energy 40 MM Grenade Launcher Qualification Requirements at Department of Energy Sites, IG-0806 40 MM Grenade Launcher Qualification Requirements at Department of Energy Sites, IG-0806 The Department of Energy and its National Nuclear Security Administration (NNSA), operate some of the most sensitive Federal facilities in the United States. Because of the mission requirements, safeguards and security is a top priority at these sites. As part of its security

  19. An overview of component qualification using Bayesian statistics and energy

    Office of Scientific and Technical Information (OSTI)

    methods. (Technical Report) | SciTech Connect Technical Report: An overview of component qualification using Bayesian statistics and energy methods. Citation Details In-Document Search Title: An overview of component qualification using Bayesian statistics and energy methods. The below overview is designed to give the reader a limited understanding of Bayesian and Maximum Likelihood (MLE) estimation; a basic understanding of some of the mathematical tools to evaluate the quality of an

  20. Technical Qualification Program and FTCP Assessment CRADs | Department of

    Energy Savers [EERE]

    Energy and FTCP Assessment CRADs Technical Qualification Program and FTCP Assessment CRADs This document provides guidance and objectives and criteria to support assessments required by DOE O 426.1 Federal Technical Capability (FTC), Section 4. REQUIREMENTS, paragraph b. FTC Program Implementation, subparagraph (7) Self-Assessment. PDF icon FTCP and TQP Assessment CRADs, 2012 More Documents & Publications Technical Qualification Program Self-Assessment Report - Richland Operations Office

  1. Accelerated Stress Testing, Qualification Testing, HAST, Field Experience |

    Broader source: Energy.gov (indexed) [DOE]

    Department of Energy presentation, which was the opening session of the NREL 2013 Photovoltaic Module Reliability Workshop held on February 26, 2013 in Golden, CO, was presented by John Wohlgemuth. Entitled "Accelerated Stress Testing, Qualification Testing, HAST, Field Experience -- What Do They All Mean?" the presentation details efforts to develop accelerated stress tests beyond the qualification test levels, which are necessary to predict PV module wear-out. The commercial

  2. Tools and techniques for failure analysis and qualification of MEMS.

    Office of Scientific and Technical Information (OSTI)

    (Conference) | SciTech Connect Tools and techniques for failure analysis and qualification of MEMS. Citation Details In-Document Search Title: Tools and techniques for failure analysis and qualification of MEMS. Many of the tools and techniques used to evaluate and characterize ICs can be applied to MEMS technology. In this paper we discuss various tools and techniques used to provide structural, chemical, and electrical analysis and how these data aid in qualifying MEMS technologies.

  3. Environmental Qualification at Savannah River Site

    SciTech Connect (OSTI)

    Martin, S.A.; Murphy, S.L.; Riley, P.J.; Sharma, M.K.; Sheikh, N.A.; Weister, T.E.

    1992-01-01

    The objective of Environmental Qualification (EQ) is to demonstrate that equipment essential to the mitigation of consequences from, and monitoring of plant conditions following Design Basis Accidents (DBAs) will operate as intended under normal/abnormal and accident environmental conditions over the installed life. For example, if a component is needed to maintain the reactor in a safe shutdown condition during an accident, and if the component is subjected to a harsh environment during that accident, then documentation must be prepared addressing the ability of the equipment to work properly in the accident environment. The requirement for an EQ program at SRS was mandated by the Department of Energy (DOE) K-Reactor Safety Evaluation Report (SER) which requires SRS to: (1) provide a long term plan for an EQ program with DOE approval prior to restart and (2) prepare and submit to DOE, Justifications for Continued Operations, that justify restarting and operating the K-Reactor until a long term compliance can be achieved with DOE approval.

  4. Workshop on environmental qualification of electric equipment

    SciTech Connect (OSTI)

    Lofaro, R.; Gunther, W.; Villaran, M.; Lee, B.S.; Taylor, J.

    1994-05-01

    Questions concerning the Environmental Qualification (EQ) of electrical equipment used in commercial nuclear power plants have recently become the subject of significant interest to the US Nuclear Regulatory Commission (NRC). Initial questions centered on whether compliance with the EQ requirements for older plants were adequate to support plant operation beyond 40 years. After subsequent investigation, the NRC Staff concluded that questions related to the differences in EQ requirements between older and newer plants constitute a potential generic issue which should be evaluated for backfit, independent of license renewal activities. EQ testing of electric cables was performed by Sandia National Laboratories (SNL) under contract to the NRC in support of license renewal activities. Results showed that some of the environmentally qualified cables either failed or exhibited marginal insulation resistance after a simulated plant life of 20 years during accident simulation. This indicated that the EQ process for some electric cables may be non-conservative. These results raised questions regarding the EQ process including the bases for conclusions about the qualified life of components based upon artificial aging prior to testing.

  5. FTCP-08-001, Methodology for Counting TQP Personnel and Qualifications |

    Energy Savers [EERE]

    Department of Energy 1, Methodology for Counting TQP Personnel and Qualifications FTCP-08-001, Methodology for Counting TQP Personnel and Qualifications FTCP Issue Paper: FTCP-08-001 Approved by FTCP, July 28, 2008 Conference Call PDF icon FTCP-08-001 TQP Personnel and Qualifications More Documents & Publications FTCP-09-001, Safety System Oversight competencies and FAQS Options Technical Qualification Program Self-Assessment Report - Richland Operations Office - 2014 FTCP-09-003,

  6. DOE-STD-1177-2004; Emergency Management Functional Area Qualification...

    Office of Environmental Management (EM)

    ... Management's Qualification Standards Handbook establishes minimum education, training, ... Supporting Knowledge andor Skills a. Discuss the fundamentals of radiation protection as ...

  7. Nondestructive Testing Qualification of Main Circulatory Tube Pipes DU 500

    SciTech Connect (OSTI)

    Tabakova, Bojana M.; Tzokov, Petio

    2004-07-01

    The criteria for safe operation of nuclear energetic installations is given a higher priority in the policy of Kozloduy Nuclear Power Plant. An efficient non-destructive inspection is the key point for the safe service. Kozloduy NPP keeps on making investments in equipment and qualification of specialists in this field. The processes of qualification of the NDT components, important for the nuclear and radiation safety, make considerable improvement in Kozloduy NPP, thanks to the accumulated in the years experience in the activities of NDT inspection qualification, and to the help of our partners Serco Assurance and the Institute of Rzes. The results obtained by ultrasonic non-destructive inspection of circulation tube mains DU 500 WWER 440 type are under discussion in this report. (authors)

  8. Hanford Waste Vitrification Plant Project Waste Form Qualification Program Plan

    SciTech Connect (OSTI)

    Randklev, E.H.

    1993-06-01

    The US Department of Energy has created a waste acceptance process to help guide the overall program for the disposal of high-level nuclear waste in a federal repository. This Waste Form Qualification Program Plan describes the hierarchy of strategies used by the Hanford Waste Vitrification Plant Project to satisfy the waste form qualification obligations of that waste acceptance process. A description of the functional relationship of the participants contributing to completing this objective is provided. The major activities, products, providers, and associated scheduling for implementing the strategies also are presented.

  9. AGC-2 Irradiation Data Qualification Final Report

    SciTech Connect (OSTI)

    Laurence C. Hull

    2012-07-01

    The Graphite Technology Development Program will run a series of six experiments to quantify the effects of irradiation on nuclear grade graphite. The second Advanced Graphite Creep (AGC) experiment (AGC-2) began with Advanced Test Reactor (ATR) Cycle 149A on April 12, 2011, and ended with ATR Cycle 151B on May 5, 2012. The purpose of this report is to qualify AGC-2 irradiation monitoring data following INL Management and Control Procedure 2691, Data Qualification. Data that are Qualified meet the requirements for data collection and use as described in the experiment planning and quality assurance documents. Data that do not meet the requirements are Failed. Some data may not quite meet the requirements, but may still provide some useable information. These data are labeled as Trend. No Trend data were identified for the AGC-2 experiment. All thermocouples functioned throughout the AGC-2 experiment. There was one instance where spurious signals or instrument power interruption resulted in a recorded temperature value being well outside physical reality. This value was identified and labeled as Failed data. All other temperature data are Qualified. All helium and argon gas flow data are within expected ranges. Total gas flow was approximately 50 sccm through the capsule. Helium gas flow was briefly increased to 100 sccm during reactor shutdown. All gas flow data are Qualified. At the start of the experiment, moisture in the outflow gas line increased to 200 ppmv then declined to less than 10 ppmv over a period of 5 days. This increase in moisture coincides with the initial heating of the experiment and drying of the system. Moisture slightly exceeded 10 ppmv three other times during the experiment. While these moisture values exceed the 10 ppmv threshold value, the reported measurements are considered accurate and to reflect moisture conditions in the capsule. All moisture data are Qualified. Graphite creep specimens are subjected to one of three loads, 393 lbf, 491 lbf, or 589 lbf. Loads were consistently within 5% of the specified values throughout the experiment. Stack displacement increased consistently throughout the experiment with total displacement ranging from 1 to 1.5 inches. No anomalous values were identified. During reactor outages, a set of pneumatic rams are used to raise the stacks of graphite creep specimens to ensure the specimens have not become stuck within the test train. This stack raising was performed after all cycles when the capsule was in the reactor. All stacks were raised successfully after each cycle. The load and displacement data are Qualified

  10. Decant pump assembly and controls qualification testing - test report

    SciTech Connect (OSTI)

    Staehr, T.W., Westinghouse Hanford

    1996-05-02

    This report summarizes the results of the qualification testing of the supernate decant pump and controls system to be used for in-tank sludge washing in aging waste tank AZ-101. The test was successful and all components are qualified for installation and use in the tank.

  11. Functional Area Qualification Standard Job Task Analyses | Department of

    Energy Savers [EERE]

    Energy Job Task Analyses Functional Area Qualification Standard Job Task Analyses DOE Aviation Manager DOE Aviation Safety Officer Chemical Processing Civil/Structural Engineering Confinement Ventilation and Process Gas Treatment Construction Management Criticality Safety Deactivation and Decommissioning Electrical Systems and Safety Oversight Emergency Management Environmental Compliance Environmental Restoration Facility Representative Fire Protection Engineering General Technical Base

  12. Functional Area Qualification Standard Reference Guides | Department of

    Energy Savers [EERE]

    Energy Reference Guides Functional Area Qualification Standard Reference Guides Aviation Manager Aviation Safety Officer Chemical Processing Civil/Structural Engineering Construction Management Criticality Safety Criticality Safety Support Group, NNSA SC Electrical Systems and Safety Oversight Emergency Management Environmental Compliance Environmental Restoration Facility Maintenance Management Facility Representative Fire Protection Engineering General Technical Base Industrial Hygiene

  13. Functional Area Qualification Standards Review Process | Department of

    Energy Savers [EERE]

    Energy Review Process Functional Area Qualification Standards Review Process Document Available for Download PDF icon Review Process for Technical Standards More Documents & Publications DOE-STD-1176-2004 DOE-TSPP-4-2013, Developing DOE Technical Standards DOE-TSPP-5-2013, Coordination of Technical Standards

  14. Personnel Selection, Qualification, and Training Requirements for DOE Nuclear Facilities

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2001-07-12

    To establish selection, qualification, and training requirements for management and operating (M&O) contractor personnel involved in the operation, maintenance, and technical support of Department of Energy and National Nuclear Security Administration Category A and B reactors and non-reactor nuclear facilities. Canceled by DOE O 426.2

  15. High Temperature Materials Interim Data Qualification Report FY 2011

    SciTech Connect (OSTI)

    Nancy Lybeck

    2011-08-01

    Projects for the very high temperature reactor (VHTR) Technology Development Office provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR program has established the Next Generation Nuclear Plant (NGNP) Data Management and Analysis System (NDMAS) to ensure that VHTR data are qualified for use, stored in a readily accessible electronic form, and analyzed to extract useful results. This document focuses on the first NDMAS objective. It describes the High Temperature Materials characterization data stream, the processing of these data within NDMAS, and reports the interim fiscal year (FY) 2011 qualification status of the data. Data qualification activities within NDMAS for specific types of data are determined by the data qualification category assigned by the data generator. The High Temperature Materials data are being collected under the Nuclear Quality Assurance (NQA)-1 guidelines and will be qualified data. For NQA-1 qualified data, the qualification activities include: (1) capture testing to confirm that the data stored within NDMAS are identical to the raw data supplied, (2) accuracy testing to confirm that the data are an accurate representation of the system or object being measured, and (3) documenting that the data were collected under an NQA-1 or equivalent Quality Assurance program. Currently, data from seven test series within the High Temperature Materials data stream have been entered into the NDMAS vault, including tensile tests, creep tests, and cyclic tests. Of the 5,603,682 records currently in the vault, 4,480,444 have been capture passed, and capture testing is in process for the remaining 1,123,238.

  16. Safeguards and Security General Technical Base Qualification Standard

    Energy Savers [EERE]

    23-2009 July 2009 DOE STANDARD SAFEGUARDS AND SECURITY GENERAL TECHNICAL BASE QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1123-2009 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ DOE-STD-1123-2009 iii APPROVAL The

  17. Senior Technical Safety Manager Functional Area Qualification Standard

    Energy Savers [EERE]

    MEASUREMENT SENSITIVE DOE-STD-1175-2013 October 2013 DOE STANDARD SENIOR TECHNICAL SAFETY MANAGER FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A: Approved for public release; distribution is unlimited. DOE-STD-1175-2013 This document is available on the Department of Energy Technical Standards Program Website at

  18. Plutonium metal and oxide container weld development and qualification

    SciTech Connect (OSTI)

    Fernandez, R.; Horrell, D.R.; Hoth, C.W.; Pierce, S.W.; Rink, N.A.; Rivera, Y.M.; Sandoval, V.D.

    1996-01-01

    Welds were qualified for a container system to be used for long-term storage of plutonium metal and oxide. Inner and outer containers are formed of standard tubing with stamped end pieces gas-tungsten-arc (GTA) welded onto both ends. The weld qualification identified GTA parameters to produce a robust weld that meets the requirements of the Department of Energy standard DOE-STD-3013-94, ``Criteria for the Safe Storage of Plutonium Metals and Oxides.``

  19. Nuclear Explosive Safety Study Functional Area Qualification Standard

    Energy Savers [EERE]

    i NOT MEASUREMENT SENSITIVE DOE-STD-1185-2007 CHANGE NOTICE No.1 April 2010 DOE STANDARD NUCLEAR EXPLOSIVE SAFETY STUDY FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1185-2007 ii This document is available on the Department of Energy Technical Standards Program Web Site at

  20. Technical Qualification Program Self-Assessment Report - Los Alamos Site

    Office of Environmental Management (EM)

    Office - 2011 | Department of Energy 11 Technical Qualification Program Self-Assessment Report - Los Alamos Site Office - 2011 The purpose of the FTCP TQP self-assessment team evaluation was to conduct a thorough evaluation of the status of the implementation of the National Nuclear Security Administration (NNSA) LASO TQP. This report documents the activities and results of the team evaluation of the LASO TQP. The overall approach of the TQP self-assessment was to evaluate the personnel,

  1. AGR-2 Data Qualification Report for ATR Cycle 154B

    SciTech Connect (OSTI)

    Binh Pham; Jeff Einerson

    2014-01-01

    This report provides the data qualification status of Advanced Gas Reactor-2 (AGR-2) fuel irradiation experimental data from Advanced Test Reactor (ATR) Cycle 154B as recorded in the Nuclear Data Management and Analysis System (NDMAS). This is the last cycle of AGR-2 irradiation, as the test train was pulled from the ATR core during the outage portion of ATR Cycle 155A. The AGR-2 data streams addressed in this report include thermocouple (TC) temperatures, sweep gas data (flow rates including new Fission Product Monitoring (FPM) downstream flows from Fission Product Monitoring System (FPMS) detectors, pressure, and moisture content), and FPMS data (release rates and release-to-birth rate ratios [R/Bs]) for each of the six capsules in the AGR-2 experiment. The final data qualification status for these data streams is determined by a Data Review Committee (DRC) comprised of AGR technical leads, Sitewide Quality Assurance (QA), and NDMAS analysts. The Data Review Committee reviewed the data acquisition process, considered whether the data met the requirements for data collection as specified in QA-approved Very High Temperature Reactor (VHTR) data collection plans, examined the results of NDMAS data testing and statistical analyses, and confirmed the qualification status of the data as given in this report.

  2. U.S. Department of Energy Component and System Qualification Workshop |

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Department of Energy U.S. Department of Energy Component and System Qualification Workshop U.S. Department of Energy Component and System Qualification Workshop The U.S. Department of Energy (DOE) and Sandia National Laboratories co-hosted the U.S. DOE Component and System Qualification Workshop on November 4, 2010 in Livermore, CA. The goal of the Workshop was to identify key needs, barriers, and actions to facilitate the qualification and listing of hydrogen and fuel cell systems and

  3. Technical Qualification Program Self-Assessment Report- Pacific Northwest Site Office- 2013

    Broader source: Energy.gov [DOE]

    This self-assessment evaluated how well the Technical Qualification and Federal Capability Programs were implemented at the Pacific Northwest Site Office (PNSO).

  4. Technical Qualification Program Self-Assessment Report- Office of River Protection- 2014

    Broader source: Energy.gov [DOE]

    A self-assessment was performed in accordance with TRS-OA-IP-07, Management (Self) Assessment, Rev. 2, where information was retrieved from MGT-QT-PL-01, Technical Qualification Program (TQP) Plan, Rev. 3; MGT-QT-DI-01, Technical Qualification Program: Federal Technical Capability Agent Duties, Rev. 2; technical staff electronic training and qualifications files; and ORP's technical staff hard copy training and qualification files to determine the effectiveness of the implemented program and identify any weaknesses of the existing program at turn-over of responsibilities.

  5. U.S. Department of Energy Hydrogen Component and System Qualification Workshop- Presentations

    Broader source: Energy.gov [DOE]

    These presentations were given at the U.S. Department of Energy Hydrogen Component and System Qualification Workshop held November 4, 2010 in Livermore, CA.

  6. DOE-STD-1138-2000; Industrial Hygiene Funcational Area Qualification...

    Office of Environmental Management (EM)

    ... specified for engineers, or scientists in the OPM Qualification Standards Handbook. ... DOE-STD-1138-2000 9 c. Discuss the fundamentals of operating analytical equipment, ...

  7. Qualification of Three On-line Slurry Monitoring Devices for Application during Waste Retrieval Operations at DOE Sites

    SciTech Connect (OSTI)

    Bontha, Jagannadha R.; Bamberger, Judith A.; Hylton, Tom D.; May, T. H.

    2000-10-18

    Qualification of Three On-line Slurry Monitoring Devices for Application during Waste Retrieval Operations at DOE Sites

  8. Senior Technical Safety Manager Functional Area Qualification Standard

    Energy Savers [EERE]

    75-2006 i NOT MEASUREMENT SENSITIVE DOE-STD-1175-2006 October 2006 DOE STANDARD SENIOR TECHNICAL SAFETY MANAGER FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1175-2006 ii This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from ES&H Technical

  9. Fire Protection Engineering Functional Area Qualification Standard, 2007

    Energy Savers [EERE]

    37-2007 December 2007 Supersedes DOE-STD-1137-2000 July 2000 DOE STANDARD FIRE PROTECTION ENGINEERING FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1137-2007 ii Available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ DOE-STD-1137-2007

  10. Code qualification of structural materials for AFCI advanced recycling reactors.

    SciTech Connect (OSTI)

    Natesan, K.; Li, M.; Majumdar, S.; Nanstad, R.K.; Sham, T.-L.

    2012-05-31

    This report summarizes the further findings from the assessments of current status and future needs in code qualification and licensing of reference structural materials and new advanced alloys for advanced recycling reactors (ARRs) in support of Advanced Fuel Cycle Initiative (AFCI). The work is a combined effort between Argonne National Laboratory (ANL) and Oak Ridge National Laboratory (ORNL) with ANL as the technical lead, as part of Advanced Structural Materials Program for AFCI Reactor Campaign. The report is the second deliverable in FY08 (M505011401) under the work package 'Advanced Materials Code Qualification'. The overall objective of the Advanced Materials Code Qualification project is to evaluate key requirements for the ASME Code qualification and the Nuclear Regulatory Commission (NRC) approval of structural materials in support of the design and licensing of the ARR. Advanced materials are a critical element in the development of sodium reactor technologies. Enhanced materials performance not only improves safety margins and provides design flexibility, but also is essential for the economics of future advanced sodium reactors. Code qualification and licensing of advanced materials are prominent needs for developing and implementing advanced sodium reactor technologies. Nuclear structural component design in the U.S. must comply with the ASME Boiler and Pressure Vessel Code Section III (Rules for Construction of Nuclear Facility Components) and the NRC grants the operational license. As the ARR will operate at higher temperatures than the current light water reactors (LWRs), the design of elevated-temperature components must comply with ASME Subsection NH (Class 1 Components in Elevated Temperature Service). However, the NRC has not approved the use of Subsection NH for reactor components, and this puts additional burdens on materials qualification of the ARR. In the past licensing review for the Clinch River Breeder Reactor Project (CRBRP) and the Power Reactor Innovative Small Module (PRISM), the NRC/Advisory Committee on Reactor Safeguards (ACRS) raised numerous safety-related issues regarding elevated-temperature structural integrity criteria. Most of these issues remained unresolved today. These critical licensing reviews provide a basis for the evaluation of underlying technical issues for future advanced sodium-cooled reactors. Major materials performance issues and high temperature design methodology issues pertinent to the ARR are addressed in the report. The report is organized as follows: the ARR reference design concepts proposed by the Argonne National Laboratory and four industrial consortia were reviewed first, followed by a summary of the major code qualification and licensing issues for the ARR structural materials. The available database is presented for the ASME Code-qualified structural alloys (e.g. 304, 316 stainless steels, 2.25Cr-1Mo, and mod.9Cr-1Mo), including physical properties, tensile properties, impact properties and fracture toughness, creep, fatigue, creep-fatigue interaction, microstructural stability during long-term thermal aging, material degradation in sodium environments and effects of neutron irradiation for both base metals and weld metals. An assessment of modified versions of Type 316 SS, i.e. Type 316LN and its Japanese version, 316FR, was conducted to provide a perspective for codification of 316LN or 316FR in Subsection NH. Current status and data availability of four new advanced alloys, i.e. NF616, NF616+TMT, NF709, and HT-UPS, are also addressed to identify the R&D needs for their code qualification for ARR applications. For both conventional and new alloys, issues related to high temperature design methodology are described to address the needs for improvements for the ARR design and licensing. Assessments have shown that there are significant data gaps for the full qualification and licensing of the ARR structural materials. Development and evaluation of structural materials require a variety of experimental facilities that have been seriously degraded in the past. The availability and additional needs for the key experimental facilities are summarized at the end of the report. Detailed information covered in each Chapter is given.

  11. Resistance Weld Qualification Analysis for Radioactive Waste Canisters

    SciTech Connect (OSTI)

    Gupta, N.K.; Gong, C.

    1995-01-10

    High level radioactive waste canisters are sealed by resistance upset welding to ensure leak tight closures. Resistance welding is fast, uniform, and can be performed remotely to minimize radiation exposure to the operators. Canisters are constructed in accordance with ASME Band PV Code, Section VIII, Division 1, however, the resistance welds are not used in Section VIII. The resistance welds are qualified by analysis using material properties obtained from the test coupons. Burst tests are performed on canister welds to meet ASME Section IX welder qualification requirements. Since burst tests are not used in Section IX for resistance weld qualification, finite element results of canister resistance welds are compared with the finite element analysis results of resistance weld tests in ASME Section IX, QW-196 to establish similarity between the two weld tests. Detailed analyses show that the primary mode of failure in both the tests is shear and, therefore, the use of burst test in place of shear test is acceptable. It is believed that the detailed analyses and results could help in establishing acceptance criteria for resistance upset welding in ASME B&PV Code, Sections VIII, and IX.

  12. The DOE Advanced Gas Reactor Fuel Development and Qualification Program

    SciTech Connect (OSTI)

    David Petti

    2010-09-01

    The high outlet temperatures and high thermal-energy conversion efficiency of modular High Temperature Gas-cooled Reactors (HTGRs) enable an efficient and cost effective integration of the reactor system with non-electricity generation applications, such as process heat and/or hydrogen production, for the many petrochemical and other industrial processes that require temperatures between 300C and 900C. The Department of Energy (DOE) has selected the HTGR concept for the Next Generation Nuclear Plant (NGNP) Project as a transformative application of nuclear energy that will demonstrate emissions-free nuclear-assisted electricity, process heat, and hydrogen production, thereby reducing greenhouse-gas emissions and enhancing energy security. The objective of the DOE Advanced Gas Reactor (AGR) Fuel Development and Qualification program is to qualify tristructural isotropic (TRISO)-coated particle fuel for use in HTGRs. The Advanced Gas Reactor Fuel Development and Qualification Program consists of five elements: fuel manufacture, fuel and materials irradiations, post-irradiation examination (PIE) and safety testing, fuel performance modeling, and fission-product transport and source term evaluation. An underlying theme for the fuel development work is the need to develop a more complete, fundamental understanding of the relationship between the fuel fabrication process and key fuel properties, the irradiation and accident safety performance of the fuel, and the release and transport of fission products in the NGNP primary coolant system. An overview of the program and recent progress is presented.

  13. Qualification tests for {sup 192}Ir sealed sources

    SciTech Connect (OSTI)

    Iancso, Georgeta Iliescu, Elena Iancu, Rodica

    2013-12-16

    This paper describes the results of qualification tests for {sup 192}Ir sealed sources, available in Testing and Nuclear Expertise Laboratory of National Institute for Physics and Nuclear Engineering 'Horia Hulubei' (I.F.I.N.-HH), Romania. These sources had to be produced in I.F.I.N.-HH and were tested in order to obtain the authorization from The National Commission for Nuclear Activities Control (CNCAN). The sources are used for gammagraphy procedures or in gammadefectoscopy equipments. Tests, measurement methods and equipments used, comply with CNCAN, AIEA and International Quality Standards and regulations. The qualification tests are: 1. Radiological tests and measurements: dose equivalent rate at 1 m; tightness; dose equivalent rate at the surface of the transport and storage container; external unfixed contamination of the container surface. 2. Mechanical and climatic tests: thermal shock; external pressure; mechanic shock; vibrations; boring; thermal conditions for storage and transportation. Passing all tests, it was obtained the Radiological Security Authorization for producing the {sup 192}Ir sealed sources. Now IFIN-HH can meet many demands for this sealed sources, as the only manufacturer in Romania.

  14. Hanford Tank Waste Treatment and Immobilization Plant (WTP) Waste Feed Qualification Program Development Approach - 13114

    SciTech Connect (OSTI)

    Markillie, Jeffrey R.; Arakali, Aruna V.; Benson, Peter A.; Halverson, Thomas G.; Adamson, Duane J.; Herman, Connie C.; Peeler, David K.

    2013-07-01

    The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is a nuclear waste treatment facility being designed and constructed for the U.S. Department of Energy by Bechtel National, Inc. and subcontractor URS Corporation (under contract DE-AC27-01RV14136 [1]) to process and vitrify radioactive waste that is currently stored in underground tanks at the Hanford Site. A wide range of planning is in progress to prepare for safe start-up, commissioning, and operation. The waste feed qualification program is being developed to protect the WTP design, safety basis, and technical basis by assuring acceptance requirements can be met before the transfer of waste. The WTP Project has partnered with Savannah River National Laboratory to develop the waste feed qualification program. The results of waste feed qualification activities will be implemented using a batch processing methodology, and will establish an acceptable range of operator controllable parameters needed to treat the staged waste. Waste feed qualification program development is being implemented in three separate phases. Phase 1 required identification of analytical methods and gaps. This activity has been completed, and provides the foundation for a technically defensible approach for waste feed qualification. Phase 2 of the program development is in progress. The activities in this phase include the closure of analytical methodology gaps identified during Phase 1, design and fabrication of laboratory-scale test apparatus, and determination of the waste feed qualification sample volume. Phase 3 will demonstrate waste feed qualification testing in support of Cold Commissioning. (authors)

  15. U.S. Commits $14 million to U.S. - Ukraine Nuclear Fuel Qualification

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Project | Department of Energy Commits $14 million to U.S. - Ukraine Nuclear Fuel Qualification Project U.S. Commits $14 million to U.S. - Ukraine Nuclear Fuel Qualification Project March 15, 2007 - 10:55am Addthis KYIV, Ukraine - U.S. Department of Energy Deputy Secretary Clay Sell today announced that the United States will invest $14 million to provide 42 nuclear fuel assemblies to the South Ukraine Nuclear Power Plant under the U.S.-Ukraine Nuclear Fuel Qualification Project (UNFQP). In

  16. CRAD, NNSA - Federal Employee Training and Qualification Program (FED T&Q)

    Office of Environmental Management (EM)

    | Department of Energy Federal Employee Training and Qualification Program (FED T&Q) CRAD, NNSA - Federal Employee Training and Qualification Program (FED T&Q) CRAD for Federal Employee Training and Qualification Program (FED T&Q). Criteria Review and Approach Documents (CRADs) that can be used to conduct a well-organized and thorough assessment of elements of safety and health programs. CRADs consist of a Performance Objective that identifies the expectation(s) or requirement(s)

  17. EDS V25 containment vessel explosive qualification test report.

    SciTech Connect (OSTI)

    Rudolphi, John Joseph

    2012-04-01

    The V25 containment vessel was procured by the Project Manager, Non-Stockpile Chemical Materiel (PMNSCM) as a replacement vessel for use on the P2 Explosive Destruction Systems. It is the first EDS vessel to be fabricated under Code Case 2564 of the ASME Boiler and Pressure Vessel Code, which provides rules for the design of impulsively loaded vessels. The explosive rating for the vessel based on the Code Case is nine (9) pounds TNT-equivalent for up to 637 detonations. This limit is an increase from the 4.8 pounds TNT-equivalency rating for previous vessels. This report describes the explosive qualification tests that were performed in the vessel as part of the process for qualifying the vessel for explosive use. The tests consisted of a 11.25 pound TNT equivalent bare charge detonation followed by a 9 pound TNT equivalent detonation.

  18. Low-level radioactive waste form qualification testing

    SciTech Connect (OSTI)

    Sohal, M.S.; Akers, D.W.

    1998-06-01

    This report summarizes activities that have already been completed as well as yet to be performed by the Idaho National Engineering and Environmental Laboratory (INEEL) to develop a plan to quantify the behavior of radioactive low-level waste forms. It briefly describes the status of various tasks, including DOE approval of the proposed work, several regulatory and environmental related documents, tests to qualify the waste form, preliminary schedule, and approximate cost. It is anticipated that INEEL and Brookhaven National Laboratory will perform the majority of the tests. For some tests, services of other testing organizations may be used. It should take approximately nine months to provide the final report on the results of tests on a waste form prepared for qualification. It is anticipated that the overall cost of the waste quantifying service is approximately $150,000. The following tests are planned: compression, thermal cycling, irradiation, biodegradation, leaching, immersion, free-standing liquid tests, and full-scale testing.

  19. Lightning arrestor connector lead magnesium niobate qualification pellet test procedures.

    SciTech Connect (OSTI)

    Tuohig, W.; Mahoney, Patrick A.; Tuttle, Bruce Andrew; Wheeler, Jill Susanne

    2009-02-01

    Enhanced knowledge preservation for DOE DP technical component activities has recently received much attention. As part of this recent knowledge preservation effort, improved documentation of the sample preparation and electrical testing procedures for lead magnesium niobate--lead titanate (PMN/PT) qualification pellets was completed. The qualification pellets are fabricated from the same parent powders used to produce PMN/PT lightning arrestor connector (LAC) granules at HWF&T. In our report, the procedures for fired pellet surface preparation, electrode deposition, electrical testing and data recording are described. The dielectric measurements described in our report are an information only test. Technical reasons for selecting the electrode material, electrode size and geometry are presented. The electrical testing is based on measuring the dielectric constant and dissipation factor of the pellet during cooling from 280 C to 220 C. The most important data are the temperature for which the peak dielectric constant occurs (Curie Point temperature) and the peak dielectric constant magnitude. We determined that the peak dielectric constant for our procedure would be that measured at 1 kHz at the Curie Point. Both the peak dielectric constant and the Curie point parameters provide semi-quantitative information concerning the chemical and microstructural homogeneity of the parent material used for the production of PMN/PT granules for LACs. Finally, we have proposed flag limits for the dielectric data for the pellets. Specifically, if the temperature of the peak dielectric constant falls outside the range of 250 C {+-} 30 C we propose that a flag limit be imposed that will initiate communication between production agency and design agency personnel. If the peak dielectric constant measured falls outside the range 25,000 {+-} 10,000 we also propose that a flag limit be imposed.

  20. Technical Qualification Program Self-Assessment Report- Los Alamos Field Office- FY15

    Broader source: Energy.gov [DOE]

    The FY15 self-assessment of the Technical Qualifications and Federal Technical Capability program was conducted to provide Los Alamos Field Office (NA-LA) management specific information related to effectiveness of the documentation and implementation of these programs.

  1. Technical Qualification Program Self-Assessment Report- Livermore Field Office- 2013

    Broader source: Energy.gov [DOE]

    The purpose of the Livermore Field Office (LFO) Teclmical Qualification Program (TQP) is to ensure that federal teclmical personnel with safety oversight responsibilities at defense nuclear facilities at Lawrence Livermore National Laboratory possess competence commensurate with responsibilities.

  2. Sample results from the interim salt disposition program macrobatch 9 tank 21H qualification samples

    SciTech Connect (OSTI)

    Peters, T. B.

    2015-11-01

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 9 for the Interim Salt Disposition Program (ISDP). This document reports characterization data on the samples of Tank 21H.

  3. Technical Qualification Program Self-Assessment Report- Y-12 Site Office- 2010

    Office of Energy Efficiency and Renewable Energy (EERE)

    The National Nuclear Security Administration Y-12 Site Office (YSO) has successfully implemented a Technical Qualification Program (YSO TQP) that produces highly qualified, technical individuals to execute oversight of site activities and support the site missions.

  4. Technical Qualification Program Self-Assessment Report- Sandia Site Office- 2012

    Broader source: Energy.gov [DOE]

    This self assessment examined how Sandia Site Office (SSO) executes the Technical Qualification Program (TQP) as measured by the current Federal Technical Capability Panel criteria review and approach documents (CRADs) included in the assessment plan.

  5. H.A.R. 13-281 - Rules Governing Professional Qualifications ...

    Open Energy Info (EERE)

    search OpenEI Reference LibraryAdd to library Legal Document- RegulationRegulation: H.A.R. 13-281 - Rules Governing Professional QualificationsLegal Published NA Year Signed or...

  6. Senior Technical Safety Manager Qualification Program Self-Assessment- Chief of Nuclear Safety

    Broader source: Energy.gov [DOE]

    This Chief of Nuclear Safety (CNS) Report was prepared to summarize the results of the July 2013 CNS self-assessment of the Senior Technical Safety Manager Qualification Program.

  7. Technical Qualification Program Self-Assessment Report- Savannah River Site Office- 2011

    Broader source: Energy.gov [DOE]

    This self assessment evaluates the effective implementation of the Technical Qualification Programs (TQP). The Federal Technical Capability Panel (FTCP) also reviews the results of the TQP self-assessments and determines if further action is necessary on a Departmental level.

  8. An analysis of the qualification criteria for small radioactive material shipping packages

    SciTech Connect (OSTI)

    McClure, J.D.

    1983-05-01

    The RAM package design certification process has two important elements, testing and acceptance. These terms sound very similar but they have specific meanings. Qualification testing in the context of this study is the imposition of simulated accident test conditions upon the candidate package design. (Normal transportation environments may also be included.) Following qualification testing, the acceptance criteria provide the performance levels which, if demonstrated, indicate the ability of the RAM package to sustain the severity of the qualification testing sequence and yet maintain specified levels of package integrity. This study has used Severities of Transportation Accidents as a data base to examine the regulatory test criteria which are required to be met by small packages containing Type B quantities of radioactive material (RAM). The basic findings indicate that the present regulatory test standards provide significantly higher levels of protection for the surface transportation modes (truck, rail) than for RAM packages shipped by aircraft. It should also be noted that various risk assessment studies have shown that the risk to the public due to severe transport accidents by surface and air transport modes is very low. A key element in this study was the quantification of the severity of the transportation accident environment and the severity of the present qualification test standards (called qualification test standards in this document) so that a direct comparison could be made between them to assess the effectiveness of the existing qualification test standards. The manner in which this was accomplished is described.

  9. "Order Module--DOE O 426.2, PERSONNEL SELECTION, TRAINING, QUALIFICATION, AND CERTIFICATION REQUIREMENTS FOR DOE NUCLEAR FACILITIES

    Broader source: Energy.gov [DOE]

    "To establish selection, training, qualification, and certification requirements for contractor personnel who can impact the safety basis through their involvement in the operation, maintenance,...

  10. Waste Form Qualification Compliance Strategy for Bulk Vitrification

    SciTech Connect (OSTI)

    Bagaasen, Larry M.; Westsik, Joseph H.; Brouns, Thomas M.

    2005-01-03

    The Bulk Vitrification System is being pursued to assist in immobilizing the low-activity tank waste from the 53 million gallons of radioactive waste in the 177 underground storage tanks on the Hanford Site. To demonstrate the effectiveness of the bulk vitrification process, a research and development facility known as the Demonstration Bulk Vitrification System (DBVS) is being built to demonstrate the technology. Specific performance requirements for the final packaged bulk vitrification waste form have been identified. In addition to the specific product-performance requirements, performance targets/goals have been identified that are necessary to qualify the waste form but do not lend themselves to specifications that are easily verified through short-term testing. Collectively, these form the product requirements for the DBVS. This waste-form qualification (WFQ) strategy document outlines the general strategies for achieving and demonstrating compliance with the BVS product requirements. The specific objectives of the WFQ activities are discussed, the bulk vitrification process and product control strategy is outlined, and the test strategy to meet the WFQ objectives is described. The DBVS product performance targets/goals and strategies to address those targets/goals are described. The DBVS product-performance requirements are compared to the Waste Treatment and Immobilization Plant immobilized low-activity waste product specifications. The strategies for demonstrating compliance with the bulk vitrification product requirements are presented.

  11. Secondary Waste Cast Stone Waste Form Qualification Testing Plan

    SciTech Connect (OSTI)

    Westsik, Joseph H.; Serne, R. Jeffrey

    2012-09-26

    The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is being constructed to treat the 56 million gallons of radioactive waste stored in 177 underground tanks at the Hanford Site. The WTP includes a pretreatment facility to separate the wastes into high-level waste (HLW) and low-activity waste (LAW) fractions for vitrification and disposal. The LAW will be converted to glass for final disposal at the Integrated Disposal Facility (IDF). Cast Stone – a cementitious waste form, has been selected for solidification of this secondary waste stream after treatment in the ETF. The secondary-waste Cast Stone waste form must be acceptable for disposal in the IDF. This secondary waste Cast Stone waste form qualification testing plan outlines the testing of the waste form and immobilization process to demonstrate that the Cast Stone waste form can comply with the disposal requirements. Specifications for the secondary-waste Cast Stone waste form have not been established. For this testing plan, Cast Stone specifications are derived from specifications for the immobilized LAW glass in the WTP contract, the waste acceptance criteria for the IDF, and the waste acceptance criteria in the IDF Permit issued by the State of Washington. This testing plan outlines the testing needed to demonstrate that the waste form can comply with these waste form specifications and acceptance criteria. The testing program must also demonstrate that the immobilization process can be controlled to consistently provide an acceptable waste form product. This testing plan also outlines the testing needed to provide the technical basis for understanding the long-term performance of the waste form in the disposal environment. These waste form performance data are needed to support performance assessment analyses of the long-term environmental impact of the secondary-waste Cast Stone waste form in the IDF

  12. AGC-3 Experiment Irradiation Monitoring Data Qualification Final Report

    SciTech Connect (OSTI)

    Laurence Hull

    2014-10-01

    The Graphite Technology Development Program will run a series of six experiments to quantify the effects of irradiation on nuclear grade graphite. The third experiment, Advanced Graphite Creep 3 (AGC 3), began with Advanced Test Reactor (ATR) Cycle 152B on November 27, 2012, and ended with ATR Cycle 155B on April 23, 2014. This report documents qualification of AGC 3 experiment irradiation monitoring data for use by the Very High Temperature Reactor (VHTR) Technology Development Office (TDO) Program for research and development activities required to design and license the first VHTR nuclear plant. Qualified data meet the requirements for data collection and use as described in the experiment planning and quality assurance documents. Failed data do not meet the requirements. Trend data may not meet the requirements, but may still provide some useable information. All thermocouples (TCs) functioned throughout the AGC 3 experiment. There was one interval between December 18, 2012, and December 20, 2012, where 10 NULL values were reported for various TCs. These NULL values were deleted from the Nuclear Data Management and Analysis System database. All temperature data are Qualified for use by the VHTR TDO Program. Argon, helium, and total gas flow data were within expected ranges and are Qualified for use by the VHTR TDO Program. Total gas flow was approximately 50 sccm through the AGC 3 experiment capsule. Helium gas flow was briefly increased to 100 sccm during ATR shutdowns. At the start of the AGC 3 experiment, moisture in the outflow gas line was stuck at a constant value of 335.6174 ppmv for the first cycle (Cycle 152B). When the AGC 3 experiment capsule was reinstalled in ATR for Cycle 154B, a new moisture filter was installed. Moisture data from Cycle 152B are Failed. All moisture data from the final three cycles (Cycles 154B, 155A, and 155B) are Qualified for use by the VHTR TDO Program.

  13. DOE handbook: Guide to good practices for the selection, training, and qualification of shift supervisors

    SciTech Connect (OSTI)

    1999-04-01

    This Department of Energy (DOE) handbook is approved for use by all DOE Components and their contractors. The Handbook incorporates editorial changes to DOE-STD-1061-93, ``Guide to Good Practices for the Selection, Training, and Qualification of shift Supervisors,`` and supersedes DOE-STD-1061-93. Technical content of this Handbook has not changed from the original technical standard. Changes are primarily editorial improvements, redesignation of the standard to a Handbook, and format changes to conform with current Technical Standards Program procedures. This guide, used in conjunction with a facility-specific job analysis, provides a framework for the selection, training, qualification, and professional development of reactor facility and non-reactor nuclear facility shift supervisors. Training and qualification programs based on this guide should provide assurance that shift supervisors perform their jobs safely and competently.

  14. DOE handbook: Guide to good practices for training and qualification of chemical operators

    SciTech Connect (OSTI)

    1996-03-01

    The purpose of this Handbook is to provide contractor training organizations with information that can be used as a reference to refine existing chemical operator training programs, or develop new training programs where no program exists. This guide, used in conjunction with facility-specific job analyses, will provide a framework for training and qualification programs for chemical operators at DOE reactor and nonreactor facilities. Recommendations for qualification are made in four areas: education, experience, physical attributes, and training. Contents include: initial qualification; administrative training; industrial safety training; specialized skills training; on-the-job training; trainee evaluation; continuing training; training effectiveness evaluation; and program records. Two appendices describe Fundamentals training and Process operations. This handbook covers chemical operators in transportation of fuels and wastes, spent fuel receiving and storage, fuel disassembly, fuel reprocessing, and both liquid and solid low-level waste processing.

  15. FTCP-12-001, Use of "Expert Level" in Qualification Path Forward |

    Energy Savers [EERE]

    Department of Energy 1, Use of "Expert Level" in Qualification Path Forward FTCP-12-001, Use of "Expert Level" in Qualification Path Forward FTCP Issue Paper: FTCP-12-001 Approved by vote at May 15, 2012 meeting; to delete all reference to expert-level knowledge requirements in FAQS. PDF icon FTCP-12-001 Expert-Level More Documents & Publications FTCP Face to Face Meeting - September 13, 2011 FTCP Face to Face Meeting - May 15, 2012 FTCP Biennial Report - Calendar

  16. Technical Qualification Program Self-Assessment Report- Los Alamos Field Office- FY14

    Broader source: Energy.gov [DOE]

    The FY14 self-assessment of the Technical Qualifications Program and Federal Technical Capabilities Program was conducted to provide Los Alamos Field Office (NA-LA) management specific information related to effectiveness of the documentation and implementation of these programs.

  17. Technical Qualification Program and FTCP Self-Assessment Report- Idaho Operations Office- 2015

    Broader source: Energy.gov [DOE]

    The Department of Energy Idaho Operations Office conducted a management self-assessment of the DOE-ID Technical Qualification Program and Federal Technical Capability Program from October 26 thru December 15, 2015. The management self-assessment was conducted by the Assistant Manager, Nuclear and Safety Performance (also the Federal Technical Capabilities Panel Agent) and a Facility Representative.

  18. Technical Qualification Program Self-Assessment Report- Carlsbad Field Office- 2012

    Broader source: Energy.gov [DOE]

    Management Assessment (MA-12-08) was conducted from October 1-31, 2012. The management assessment team evaluated the specific requirement implementation, processes, and performance areas of the CBFO Technical Qualification Program (TQP). The assessment covered the relevant parts of DOE 0 426.1, Federal Technical Capability.

  19. Sample Results from the Interim Salt Disposition Program Macrobatch 6 Tank 21H Qualification Samples

    SciTech Connect (OSTI)

    Peters, T. B.; Fink, S. D.

    2012-12-11

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 6 for the Interim Salt Disposition Project (ISDP). This document reports partial results of the analyses of samples of Tank 21H. No issues with the projected Salt Batch 6 strategy are identified.

  20. Sample Results From The Interim Salt Disposition Program Macrobatch 6 Tank 21H Qualification Samples

    SciTech Connect (OSTI)

    Peters, T. B.; Fink, S. D.

    2012-12-20

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 6 for the Interim Salt Disposition Project (ISDP). This document reports partial results of the analyses of samples of Tank 21H. No issues with the projected Salt Batch 6 strategy are identified.

  1. Technical Qualification Program Self-Assessment Report- Nevada Site Office- 2009

    Broader source: Energy.gov [DOE]

    An accreditation assessment of the National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Technical Qualification Program (TQP) was conducted during the week of October 5-8, 2009. The accreditation of the TQP will enable NSO to demonstrate that they have an effective program in place to ensure the technical competency of the individuals performing these activities.

  2. Technical Qualification Program Self-Assessment Report- Office of Health, Safety and Security- 2014

    Broader source: Energy.gov [DOE]

    Beginning in April 2014, a self-assessment of the Technical Qualification Program (TQP) was performed in the Office of Health, Safety and Security (HSS). The assessment was led by the HSS TQP Manager who is assigned the responsibility for maintaining and implementing the programs.

  3. Personnel Selection, Training, Qualification, and Certification Requirements for DOE Nuclear Facilities

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2010-04-21

    The order establishes selection, training, qualification, and certification requirements for contractor personnel who can impact the safety basis through their involvement in the operation, maintenance, and technical support of Hazard Category 1, 2, and 3 nuclear facilities. Admin Chg 1, dated 7-29-13, supersedes DOE O 426.2.

  4. Personnel Selection, Training, Qualification, and Certification Requirements for DOE Nuclear Facilities

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2010-04-21

    The order establishes selection, training, qualification, and certification requirements for contractor personnel who can impact the safety basis through their involvement in the operation, maintenance, and technical support of Hazard Category 1, 2, and 3 nuclear facilities. Cancels DOE O 5480.20A. Admin Chg 1, dated 7-29-13.

  5. Model Request for Qualifications to Pre-Qualify Energy Service Companies

    Broader source: Energy.gov [DOE]

    This page contains model Request for Qualifications (RFQ) documents intended for use by a state program to pre-qualify Energy Service Companies (ESCOs) to be available for as-needed Energy Savings Performance Contracting (ESPC) services for state and local governments within the state.

  6. Qualification of Innovative High Level Waste Pipeline Unplugging Technologies

    SciTech Connect (OSTI)

    McDaniel, D.; Gokaltun, S.; Varona, J.; Awwad, A.; Roelant, D.; Srivastava, R.

    2008-07-01

    In the past, some of the pipelines have plugged during high level waste (HLW) transfers resulting in schedule delays and increased costs. Furthermore, pipeline plugging has been cited by the 'best and brightest' technical review as one of the major issues that can result in unplanned outages at the Waste Treatment Plant causing inconsistent operation. As the DOE moves toward a more active high level waste retrieval, the site engineers will be faced with increasing cross-site pipeline waste slurry transfers that will result in increased probability of a pipeline getting plugged. Hence, availability of a pipeline unplugging tool/technology is crucial to ensure smooth operation of the waste transfers and in ensuring tank farm cleanup milestones are met. FIU had earlier tested and evaluated various unplugging technologies through an industry call. Based on mockup testing, two technologies were identified that could withstand the rigors of operation in a radioactive environment and with the ability to handle sharp 90 elbows. We present results of the second phase of detailed testing and evaluation of pipeline unplugging technologies and the objective is to qualify these pipeline unplugging technologies for subsequent deployment at a DOE facility. The current phase of testing and qualification comprises of a heavily instrumented 3-inch diameter (full-scale) pipeline facilitating extensive data acquisition for design optimization and performance evaluation, as it applies to three types of plugs atypical of the DOE HLW waste. Furthermore, the data from testing at three different lengths of pipe in conjunction with the physics of the process will assist in modeling the unplugging phenomenon that will then be used to scale-up process parameters and system variables for longer and site typical pipe lengths, which can extend as much as up to 19,000 ft. Detailed information resulting from the testing will provide the DOE end-user with sufficient data and understanding of the technology, and its limitations to aid in the benefit-cost analysis for management decision whether to deploy the technology or to abandon the pipeline as has been done in the past. In conclusion: The ultimate objective of this study is to qualify NuVision's unplugging technology for use at Hanford. Experimental testing has been conducted using three pipeline lengths and three types of blockages. Erosion rates have been obtained and pressure data is being analyzed. An amplification of the inlet pressure has been observed along the pipeline and is the key to determining up to what pipe lengths the technology can be used without surpassing the site pressure limit. In addition, we will attempt to establish what the expected unplugging rates will be at the longer pipe lengths for each of the three blockages tested. Detailed information resulting from the testing will provide the DOE end-user with sufficient data and understanding of the technology, and its limitations so that management decisions can be made whether the technology has a reasonable chance to successfully unplug a pipeline, such as a cross site transfer line or process transfer pipeline at the Waste Treatment Plant. (authors)

  7. Preliminary Assessment of the Hanford Tank Waste Feed Acceptance and Product Qualification Programs

    SciTech Connect (OSTI)

    Herman, C. C.; Adamson, Duane J.; Herman, D. T.; Peeler, David K.; Poirier, Micheal R.; Reboul, S. H.; Stone, M. E.; Peterson, Reid A.; Chun, Jaehun; Fort, James A.; Vienna, John D.; Wells, Beric E.

    2013-04-01

    The U.S. Department of Energy Office of Environmental Management (EM) is engaging the national laboratories to provide the scientific and technological rigor to support EM program and project planning, technology development and deployment, project execution, and assessment of program outcomes. As an early demonstration of this new responsibility, Savannah River National Laboratory (SRNL) and Pacific Northwest National Laboratory (PNNL) have been chartered to implement a science and technology program addressing Hanford Tank waste feed acceptance and product qualification. As a first step, the laboratories examined the technical risks and uncertainties associated with the planned waste feed acceptance and qualification testing for Hanford tank wastes. Science and technology gaps were identified for work associated with 1) feed criteria development with emphasis on identifying the feed properties and the process requirements, 2) the Tank Waste Treatment and Immobilization Plant (WTP) process qualification program, and 3) the WTP HLW glass product qualification program. Opportunities for streamlining the accetpance and qualification programs were also considered in the gap assessment. Technical approaches to address the science and technology gaps and/or implement the opportunities were identified. These approaches will be further refined and developed as strong integrated teams of researchers from national laboratories, contractors, industry, and academia are brought together to provide the best science and technology solutions. Pursuing the identified approaches will have immediate and long-term benefits to DOE in reducing risks and uncertainties associated with tank waste removal and preparation, transfers from the tank farm to the WTP, processing within the WTP Pretreatment Facility, and in producing qualified HLW glass products. Additionally, implementation of the identified opportunities provides the potential for long-term cost savings given the anticipated facility life of WTP.

  8. Development Of A Macro-Batch Qualification Strategy For The Hanford Tank Waste Treatment And Immobilization Plant

    SciTech Connect (OSTI)

    Herman, Connie C.

    2013-09-30

    The Savannah River National Laboratory (SRNL) has evaluated the existing waste feed qualification strategy for the Hanford Tank Waste Treatment and Immobilization Plant (WTP) based on experience from the Savannah River Site (SRS) Defense Waste Processing Facility (DWPF) waste qualification program. The current waste qualification programs for each of the sites are discussed in the report to provide a baseline for comparison. Recommendations on strategies are then provided that could be implemented at Hanford based on the successful Macrobatch qualification strategy utilized at SRS to reduce the risk of processing upsets or the production of a staged waste campaign that does not meet the processing requirements of the WTP. Considerations included the baseline WTP process, as well as options involving Direct High Level Waste (HLW) and Low Activity Waste (LAW) processing, and the potential use of a Tank Waste Characterization and Staging Facility (TWCSF). The main objectives of the Hanford waste feed qualification program are to demonstrate compliance with the Waste Acceptance Criteria (WAC), determine waste processability, and demonstrate unit operations at a laboratory scale. Risks to acceptability and successful implementation of this program, as compared to the DWPF Macro-Batch qualification strategy, include: Limitations of mixing/blending capability of the Hanford Tank Farm; The complexity of unit operations (i.e., multiple chemical and mechanical separations processes) involved in the WTP pretreatment qualification process; The need to account for effects of blending of LAW and HLW streams, as well as a recycle stream, within the PT unit operations; and The reliance on only a single set of unit operations demonstrations with the radioactive qualification sample. This later limitation is further complicated because of the 180-day completion requirement for all of the necessary waste feed qualification steps. The primary recommendations/changes include the following: Collection and characterization of samples for relevant process analytes from the tanks to be blended during the staging process; Initiation of qualification activities earlier in the staging process to optimize the campaign composition through evaluation from both a processing and glass composition perspective; Definition of the parameters that are important for processing in the WTP facilities (unit operations) across the anticipated range of wastes and as they relate to qualification-scale equipment; Performance of limited testing with simulants ahead of the waste feed qualification sample demonstration as needed to determine the available processing window for that campaign; and Demonstration of sufficient mixing in the staging tank to show that the waste qualification sample chemical and physical properties are representative of the transfers to be made to WTP. Potential flowcharts for derivatives of the Hanford waste feed qualification process are also provided in this report. While these recommendations are an extension of the existing WTP waste qualification program, they are more in line with the processes currently performed for SRS. The implementation of these processes at SRS has been shown to offer flexibility for processing, having identified potential processing issues ahead of the qualification or facility processing, and having provided opportunity to optimize waste loading and throughput in the DWPF.

  9. May 5, 2016, FTCP Face to Face Meeting Presentation - S&S Functional Area Qualification Standard

    Office of Environmental Management (EM)

    S&S Functional Area Qualification Standards S&S FAQS * The DOE NTC is currently working on updating the Functional Area Qualification Standards (FAQS) for Safeguards and Security (S&S) Federal personnel. * A steering committee consisting of several S&S Federal members selected from across the complex was formed. * The three Chief Security Officers were briefed, and they all agreed with the steering committee's recommendation to begin developing a Job Task Analysis (JTA) for each

  10. SLUDGE BATCH 4 FOLLOW-UP QUALIFICATION STUDIES TO EVALUATE HYDROGEN GENERATION

    SciTech Connect (OSTI)

    Pareizs, J; David Koopman, D; Dan Lambert, D; Cj Bannochie, C

    2007-08-23

    Follow-up testing was conducted to better understand the excessive hydrogen generation seen in the initial Sludge Batch 4 (SB4) qualification Sludge Receipt and Adjustment Tank/Slurry Mix Evaporator (SRAT/SME) simulation in the Savannah River National Laboratory (SRNL) Shielded Cells. This effort included both radioactive and simulant work. The initial SB4 qualification test produced 0.59 lbs/hr hydrogen in the SRAT, which was just below the DWPF SRAT limit of 0.65 lbs/hr, and the test produced over 0.5 lbs/hr hydrogen in the SME cycle on two separate occasions, which were over the DWPF SME limit of 0.223 lbs/hr.

  11. Characterization Of The As-Received Sludge Batch 9 Qualification Sample (Htf-51-15-81)

    SciTech Connect (OSTI)

    Pareizs, J.

    2015-09-30

    Savannah River National Laboratory (SRNL) personnel have been requested to qualify the next sludge batch (Sludge Batch 9 – SB9) for processing at the Defense Waste Processing Facility (DWPF). To accomplish this task, Savannah River Remediation (SRR) has sent SRNL a 3-L slurried sample of Tank 51H (HTF-51-15-81) to be characterized, washed, and then used in a lab-scale demonstration of the DWPF flowsheet (potentially after combining with Tank 40H sludge). This report documents the first steps of the qualification process – characterization of the as-received Tank 51H qualification sample. These results will be used to support a reprojection of SB9 by SRR from which final Tank 51H washing, frit development, and Chemical Processing Cell (CPC) activities will be based.

  12. Reliability Testing Beyond Qualification as a Key Component in Photovoltaic's Progress Toward Grid Parity: Preprint

    SciTech Connect (OSTI)

    Wohlgemuth, J. H.; Kurtz, S.

    2011-02-01

    This paper discusses why it is necessary for new lower cost PV modules to be tested using a reliability test sequence that goes beyond the Qualification test sequence now utilized for modules. Today most PV modules are warranted for 25 years, but the Qualification Test Sequence does not test for 25-year life. There is no accepted test protocol to validate a 25-year lifetime. This paper recommends the use of long term accelerated testing to compare now designs directly with older designs that have achieved long lifetimes in outdoor exposure. If the new designs do as well or better than the older ones, then it is likely that they will survive an equivalent length of time in the field.

  13. B-Plant D-Filter detector system qualification test report

    SciTech Connect (OSTI)

    Ritter, G.A., Westinghouse Hanford

    1996-08-23

    This report summarizes the results of qualification testing of the B Plant D-Filter Detector System. The purpose of this test was to verify that the system meets the performance requirements and that the unit is ready for field deployment. Testing was performed in the test pit in the 306E Facility. This detector system will be deployed in the B Plant D-Filter to measure beta/gamma dose rates from the filter bank.

  14. Technical Qualification Program Self-Assessment Report- Los Alamos Site Office- 2013

    Broader source: Energy.gov [DOE]

    This self-assessment of the Technical Qualifications and Federal Technical Capability program was conducted to provide Los Alamos Field Office (LAFO) management specific information related to effectiveness of the documentation and implementation of these programs. The conclusion of this assessment is that the areas assessed herein are compliant with the requirements, and that implementation of the requirements has been effective at this Field Office.

  15. Technical Qualification Program Self-Assessment Report- Office of Science- 2013

    Office of Energy Efficiency and Renewable Energy (EERE)

    Under DOE 426.1, Change 1. Headquarters and Field elements must conduct a self-assessment of Technical Qualification Program (TQP) and Federal Technical Capability Program (FTCP) implementation within their organization at least every four years. These assessments must be conducted in accordance with the requirements of DOE Order (0) 226.1 B, Implementation of Department of Energy Oversight Policy, dated 4-25-11, and the current objectives and criteria approved by the FTCP Chair.

  16. Results of a literature review on the environmental qualification of low-voltage electric cables

    SciTech Connect (OSTI)

    Lofaro, R.; Lee, B.; Villaran, M.; Gleason, J.; Aggarwal, S.

    1995-12-31

    In the design of nuclear power plants in the US, safety-related electric equipment must be qualified to provide reasonable assurance it can withstand the effects of a design basis event (DBE) and still be able to perform its prescribed safety function, even if the accident were to occur at the end of its service life. The requirement for environmental qualification (EQ) originates from the General Design Criteria in the Code of Federal Regulations, Title 10, Part 50 (10 CFR 50). The acceptable method of performing the qualification of this equipment has evolved over the years, starting with the NRC Division of Operating Reactors (DOR) Guidelines, which were issued in Bulletin 79--01B, and NUREG-0588 requirements and ending with the current EQ Rule, 10 CFR 50.49. While the EQ methods described in these documents have the same overall objective, there are some notable differences for which a clear technical basis has not been established. One difference is the preaging requirement for equipment prior to LOCA testing. In addition, specific issues related to current EQ practices have been raised by the US NRC which need to be addressed. These issues, which are discussed in detail later in this paper, are related to the sources of conservatism and uncertainty in IEEE Standard 323--1974, which is the qualification standard currently endorsed by the NRC. To address these issues, the NRC Office of Nuclear Reactor Regulation (NRR) implemented a Task Action Plan (TAP), and the Office of Nuclear Reactor Research (RES) initiated a complementary research program. The current focus of this program is on the qualification of low-voltage instrumentation and control cables. These cables were selected since they are not typically replaced on a routine basis, and their degradation could impact plant safety.

  17. General Technical Base Qualification Standard (DOE Defense Nuclear Facilities Technical Personnel)

    Energy Savers [EERE]

    DOE-STD-1146-2007 December 2007 DOE STANDARD GENERAL TECHNICAL BASE QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1146-2007 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ DOE-STD-1146-2007 iv INTENTIONALLY BLANK

  18. SRS SLUDGE BATCH QUALIFICATION AND PROCESSING; HISTORICAL PERSPECTIVE AND LESSONS LEARNED

    SciTech Connect (OSTI)

    Cercy, M.; Peeler, D.; Stone, M.

    2013-09-25

    This report provides a historical overview and lessons learned associated with the SRS sludge batch (SB) qualification and processing programs. The report covers the framework of the requirements for waste form acceptance, the DWPF Glass Product Control Program (GPCP), waste feed acceptance, examples of how the program complies with the specifications, an overview of the Startup Program, and a summary of continuous improvements and lessons learned. The report includes a bibliography of previous reports and briefings on the topic.

  19. Guide to good practices for training and qualification of instructors. DOE handbook

    SciTech Connect (OSTI)

    1996-03-01

    Purpose of this guide is to provide contractor training organizations with information that can be used to verify the adquacy and/or modify existing instructor training programs, or to develop new training programs. It contains good practices for the training and qualification of technical instructors and instructional technologists at DOE reactor and non-reactor nuclear facilities. It addresses the content of initial and continuing instructor training programs, evaluation of instructor training programs, and maintenance of instructor training records.

  20. Construction, Qualification, and Low Rate Production Start-up of a DC Bus

    Broader source: Energy.gov (indexed) [DOE]

    Capacitor High Volume Manufacturing Facility with Capacity to Support 100,000 Electric Drive Vehicles | Department of Energy 2 DOE Hydrogen and Fuel Cells Program and Vehicle Technologies Program Annual Merit Review and Peer Evaluation Meeting PDF icon arravt029_ape_sawyer_2012_p.pdf More Documents & Publications Construction, Qualification, and Low Rate Production Start-up of a DC Bus Capacitor High Volume Manufacturing Facility with Capacity to Support 100,000 Electric Drive Vehicles

  1. Construction, Qualification, and Low Rate Production Start-up of a DC Bus

    Broader source: Energy.gov (indexed) [DOE]

    Capacitor High Volume Manufacturing Facility with Capacity to Support 100,000 Electric Drive Vehicles | Department of Energy 1 DOE Hydrogen and Fuel Cells Program, and Vehicle Technologies Program Annual Merit Review and Peer Evaluation PDF icon arravt029_ape_sawyer_2011_p.pdf More Documents & Publications Construction, Qualification, and Low Rate Production Start-up of a DC Bus Capacitor High Volume Manufacturing Facility with Capacity to Support 100,000 Electric Drive Vehicles

  2. Qualification of data obtained during a severe accident. Illustrative examples from TMI-2 evaluations

    SciTech Connect (OSTI)

    Rempe, Joy L.; Knudson, Darrell L.

    2015-02-01

    The accidents at the Three Mile Island Unit 2 (TMI-2) Pressurized Water Reactor (PWR) and the Daiichi Units 1, 2, and 3 Boiling Water Reactors (BWRs) provide unique opportunities to evaluate instrumentation exposed to severe accident conditions. Conditions associated with the release of coolant and the hydrogen burn that occurred during the TMI-2 accident exposed instrumentation to harsh conditions, including direct radiation, radioactive contamination, and high humidity with elevated temperatures and pressures. Post-TMI-2 instrumentation evaluation programs focused on data required by TMI-2 operators to assess the condition of the reactor and containment and the effect of mitigating actions taken by these operators. Prior efforts also focused on sensors providing data required for subsequent forensic evaluations and accident simulations. This paper provides additional details related to the formal process used to develop a qualified TMI-2 data base and presents data qualification details for three parameters: reactor coolant system (RCS) pressure; containment building temperature; and containment pressure. These selected examples illustrate the types of activities completed in the TMI-2 data qualification process and the importance of such a qualification effort. These details are described to facilitate implementation of a similar process using data and examinations at the Daiichi Units 1, 2, and 3 reactors so that BWR-specific benefits can be obtained.

  3. DOE handbook: Guide to good practices for training and qualification of maintenance personnel

    SciTech Connect (OSTI)

    1996-03-01

    The purpose of this Handbook is to provide contractor training organizations with information that can be used to verify the adequacy of and/or modify existing maintenance training programs, or to develop new training programs. This guide, used in conjunction with facility-specific job analyses, provides a framework for training and qualification programs for maintenance personnel at DOE reactor and nonreactor nuclear facilities. Recommendations for qualification are made in four areas: education, experience, physical attributes, and training. The functional positions of maintenance mechanic, electrician, and instrumentation and control technician are covered by this guide. Sufficient common knowledge and skills were found to include the three disciplines in one guide to good practices. Contents include: qualifications; on-the-job training; trainee evaluation; continuing training; training effectiveness evaluation; and program records. Appendices are included which relate to: administrative training; industrial safety training; fundamentals training; tools and equipment training; facility systems and component knowledge training; facility systems and component skills training; and specialized skills training.

  4. SRNL PHASE 1 ASSESSMENT OF THE WAC/DQO AND UNIT OPERATIONS FOR THE WTP WASTE QUALIFICATION PROGRAM

    SciTech Connect (OSTI)

    Peeler, D.; Adamson, D.; Bannochie, C.; Cozzi, A.; Eibling, R.; Hay, M.; Hansen, E.; Herman, D.; Martino, C.; Nash, C.; Pennebaker, F.; Poirier, M.; Reboul, S.; Stone, M.; Taylor-Pashow, K.; White, T.; Wilmarth, B.

    2012-05-16

    The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is currently transitioning its emphasis from a design and construction phase toward start-up and commissioning. With this transition, the WTP Project has initiated more detailed assessments of the requirements related to actual processing of the Hanford Site tank waste. One particular area of interest is the waste qualification program to be implemented to support the WTP. Given the successful implementation of similar waste qualification efforts at the Savannah River Site (SRS), based on critical technical support and guidance from the Savannah River National Laboratory (SRNL), WTP requested the utilization of subject matter experts from SRNL to support a technology exchange to perform a review of the WTP waste qualification program, discuss the general qualification approach at SRS, and to identify critical lessons learned through the support of DWPF's sludge batch qualification efforts. As part of Phase 1, SRNL subject matter experts in critical technical and/or process areas reviewed specific WTP waste qualification information. The Phase 1 review was a collaborative, interactive, and iterative process between the two organizations. WTP provided specific analytical procedures, descriptions of equipment, and general documentation as baseline review material. SRNL subject matter experts reviewed the information and, as appropriate, requested follow-up information or clarification to specific areas of interest. This process resulted in multiple teleconferences with key technical contacts from both organizations resolving technical issues that lead to the results presented in this report. This report provides the results of SRNL's Phase 1 review of the WAC-DQO waste acceptance criteria and processability parameters, and the specific unit operations which are required to support WTP waste qualification efforts. The review resulted in SRNL providing concurrence, alternative methods, or gap identification for the proposed WTP analytical methods or approaches. For the unit operations, the SRNL subject matter experts reviewed WTP concepts compared to what is used at SRS and provided thoughts on the outlined tasks with respect to waste qualification. Also documented in this report are recommendations and an outline on what would be required for the next phase to further mature the WTP waste qualification program.

  5. SLUDGE BATCH 7B QUALIFICATION ACTIVITIES WITH SRS TANK FARM SLUDGE

    SciTech Connect (OSTI)

    Pareizs, J.; Click, D.; Lambert, D.; Reboul, S.

    2011-11-16

    Waste Solidification Engineering (WSE) has requested that characterization and a radioactive demonstration of the next batch of sludge slurry - Sludge Batch 7b (SB7b) - be completed in the Shielded Cells Facility of the Savannah River National Laboratory (SRNL) via a Technical Task Request (TTR). This characterization and demonstration, or sludge batch qualification process, is required prior to transfer of the sludge from Tank 51 to the Defense Waste Processing Facility (DWPF) feed tank (Tank 40). The current WSE practice is to prepare sludge batches in Tank 51 by transferring sludge from other tanks. Discharges of nuclear materials from H Canyon are often added to Tank 51 during sludge batch preparation. The sludge is washed and transferred to Tank 40, the current DWPF feed tank. Prior to transfer of Tank 51 to Tank 40, SRNL typically simulates the Tank Farm and DWPF processes with a Tank 51 sample (referred to as the qualification sample). With the tight schedule constraints for SB7b and the potential need for caustic addition to allow for an acceptable glass processing window, the qualification for SB7b was approached differently than past batches. For SB7b, SRNL prepared a Tank 51 and a Tank 40 sample for qualification. SRNL did not receive the qualification sample from Tank 51 nor did it simulate all of the Tank Farm washing and decanting operations. Instead, SRNL prepared a Tank 51 SB7b sample from samples of Tank 7 and Tank 51, along with a wash solution to adjust the supernatant composition to the final SB7b Tank 51 Tank Farm projections. SRNL then prepared a sample to represent SB7b in Tank 40 by combining portions of the SRNL-prepared Tank 51 SB7b sample and a Tank 40 Sludge Batch 7a (SB7a) sample. The blended sample was 71% Tank 40 (SB7a) and 29% Tank 7/Tank 51 on an insoluble solids basis. This sample is referred to as the SB7b Qualification Sample. The blend represented the highest projected Tank 40 heel (as of May 25, 2011), and thus, the highest projected noble metals content for SB7b. Characterization was performed on the Tank 51 SB7b samples and SRNL performed DWPF simulations using the Tank 40 SB7b material. This report documents: (1) The preparation and characterization of the Tank 51 SB7b and Tank 40 SB7b samples. (2) The performance of a DWPF Chemical Process Cell (CPC) simulation using the SB7b Tank 40 sample. The simulation included a Sludge Receipt and Adjustment Tank (SRAT) cycle, where acid was added to the sludge to destroy nitrite and reduce mercury, and a Slurry Mix Evaporator (SME) cycle, where glass frit was added to the sludge in preparation for vitrification. The SME cycle also included replication of five canister decontamination additions and concentrations. Processing parameters were based on work with a nonradioactive simulant. (3) Vitrification of a portion of the SME product and characterization and durability testing (as measured by the Product Consistency Test (PCT)) of the resulting glass. (4) Rheology measurements of the SRAT receipt, SRAT product, and SME product. This program was controlled by a Task Technical and Quality Assurance Plan (TTQAP), and analyses were guided by an Analytical Study Plan. This work is Technical Baseline Research and Development (R&D) for the DWPF. It should be noted that much of the data in this document has been published in interoffice memoranda. The intent of this technical report is bring all of the SB7b related data together in a single permanent record and to discuss the overall aspects of SB7b processing.

  6. Standard for the qualification of high capacity fossil fuel fired plant operators

    SciTech Connect (OSTI)

    Axtman, W.

    1996-12-31

    The American Society of Mechanical Engineers, at the request of the U.S. Environmental Protection Agency (EPA) and, in recognition of the needs and benefits associated with standard qualifications of operators of high capacity fossil fuel fired plants, established the Qualifications of High Capacity Fossil Fuel Fired Operator (QFO) Committee in 1994. The purpose of the QFO Committee is to develop and maintain such a standard for operators. This standard includes qualifications, duties, responsibilities and the certification requirements for operators as appropriate to The Clean Air Act as amended in 1990 for fossil fuel fired plants with inputs equal to or greater than 10,000 Btu/hr. This Standard does not cover the certification or validation of fossil plant operating procedures, operating practices, facility performance, nor compliance with any particular permit requirement. This standard recognizes the titles or positions to which any particular fossil plant operator may apply, will vary within a facility. Therefore, this standard does not attempt to identify the individual who is required to obtain certification in any class designation. The fossil plant owner is urged to contact the local jurisdiction in which the fossil plant is located in this regard. This standard does not in itself require certification but rather it serves as a means for complying with federal, state, and local regulations which require operators of fossil fuel fired boilers with inputs equal to or greater than 10,000,000 But/hr to be certified. Safety codes and standards are intended to enhance public health and safety. Revisions to this Standard result from committee considerations of factors such as technological advances, new data, and changing environmental and industry needs. Revisions do not imply that previous editions of this standard were inadequate.

  7. Technical Qualification Program Self-Assessment Report- Los Alamos Site Office- 2007

    Broader source: Energy.gov [DOE]

    The Federal Technical Capability Manual requires periodic self-assessment of the effectiveness of the implementation of the Manual and the Technical Qualification Program utilizing a defined set of Objectives and Criteria. The assessment documented by this report is the first periodic review conducted at LASO to meet this requirement. The assessment results are intended to establish a base-line on which to develop and improve the program so no final grade was assigned; however, only six of the twelve Objectives were identified as being met.

  8. Tank 30 and 37 Supernatant Sample Cross-Check and Evaporator Feed Qualification Analysis-2012

    SciTech Connect (OSTI)

    Oji, L. N.

    2013-03-07

    This report summarizes the analytical data reported by the F/H and Savannah River National Laboratories for the 2012 cross-check analysis for high level waste supernatant liquid samples from SRS Tanks 30 and 37. The intent of this Tank 30 and 37 sample analyses was to perform cross-checks against routine F/H Laboratory analyses (corrosion and evaporator feed qualification programs) using samples collected at the same time from both tanks as well as split samples from the tanks.

  9. Instrument Qualification of Custom Fabricated Water Activity Meter for Hot Cell Use

    SciTech Connect (OSTI)

    McCoskey, Jacob K.

    2014-01-22

    This report describes a custom fabricated water activity meter and the results of the qualification of this meter as described in the laboratory test plan LAB-PLN-11-00012, Testing and Validation of an Enhanced Acquisition and Control System. It was calibrated against several NaOH solutions of varying concentrations to quantify the accuracy and precision of the instrument at 20 C and 60 C. Also, a schematic and parts list of the equipment used to make the water activity meter will be presented in this report.

  10. Quality Assurance Program Plan for AGR Fuel Development and Qualification Program

    SciTech Connect (OSTI)

    W. Ken Sowder

    2004-02-01

    Quality Assurance Plan (QPP) is to document the Idaho National Engineering and Environmental Laboratory (INEEL) Management and Operating (M&O) Contractor’s quality assurance program for AGR Fuel Development and Qualification activities, which is under the control of the INEEL. The QPP is an integral part of the Gen IV Program Execution Plan (PEP) and establishes the set of management controls for those systems, structures and components (SSCs) and related quality affecting activities, necessary to provide adequate confidence that items will perform satisfactorily in service.

  11. Results Of Initial Analyses Of The Salt (Macro) Batch 9 Tank 21H Qualification Samples

    SciTech Connect (OSTI)

    Peters, T.

    2015-10-08

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Interim Salt Disposition Project (ISDP) Salt (Macro) Batch 9 for processing through the Actinide Removal Process (ARP) and the Modular Caustic-Side Solvent Extraction Unit (MCU). This document reports the initial results of the analyses of samples of Tank 21H. Analysis of the Tank 21H Salt (Macro) Batch 9 composite sample indicates that the material does not display any unusual characteristics. Further results on the chemistry and other tests will be issued in the future.

  12. Results of initial analyses of the salt (macro) batch 9 tank 21H qualification samples

    SciTech Connect (OSTI)

    Peters, T. B.

    2015-10-01

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Interim Salt Disposition Project (ISDP) Salt (Macro) Batch 9 for processing through the Actinide Removal Process (ARP) and the Modular Caustic-Side Solvent Extraction Unit (MCU). This document reports the initial results of the analyses of samples of Tank 21H. Analysis of the Tank 21H Salt (Macro) Batch 9 composite sample indicates that the material does not display any unusual characteristics or observations, such as floating solids, the presence of large amount of solids, or unusual colors. Further results on the chemistry and other tests will be issued in the future.

  13. GLASS FABRICATION AND ANALYSIS LITERATURE REVIEW AND METHOD SELECTION FOR WTP WASTE FEED QUALIFICATION

    SciTech Connect (OSTI)

    Peeler, D.

    2013-06-27

    Scope of the Report The objective of this literature review is to identify and review documents to address scaling, design, operations, and experimental setup, including configuration, data collection, and remote handling that would be used during waste feed qualification in support of the glass fabrication unit operation. Items addressed include:  LAW and HLW glass formulation algorithms;  Mixing and sampling;  Rheological measurements;  Heat of hydration;  Glass fabrication techniques;  Glass inspection;  Composition analysis;  Use of cooling curves;  Hydrogen generation rate measurement.

  14. DOE-STD-1135-99 Guidance for Nuclear Criticality Safety Engineer Training and Qualification

    Energy Savers [EERE]

    5-99 September 1999 DOE STANDARD GUIDANCE FOR NUCLEAR CRITICALITY SAFETY ENGINEER TRAINING AND QUALIFICATION U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS This document has been reproduced from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from the

  15. SAMPLE RESULTS FROM THE INTEGRATED SALT DISPOSITION PROGRAM MACROBATCH 5 TANK 21H QUALIFICATION SAMPLES

    SciTech Connect (OSTI)

    Peters, T.; Fink, S.

    2012-03-26

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 5 for the Integrated Salt Disposition Project (ISDP). This document reports partial results of the analyses of samples of Tank 21H. No issues with the projected Salt Batch 5 strategy are identified. Results of the analyses of the Tank 21H samples from this report in conjunction with the findings of the previous report, indicates that the material does not display any unusual characteristics.

  16. Qualification Requirements of Guided Ultrasonic Waves for Inspection of Piping in Light Water Reactors

    SciTech Connect (OSTI)

    Meyer, Ryan M.; Ramuhalli, Pradeep; Doctor, Steven R.; Bond, Leonard J.

    2013-08-01

    Guided ultrasonic waves (GUW) are being increasingly used for both NDT and monitoring of piping. GUW offers advantages over many conventional NDE technologies due to the ability to inspect large volumes of piping components without significant removal of thermal insulation or protective layers. In addition, regions rendered inaccessible to more conventional NDE technologies may be more accessible using GUW techniques. For these reasons, utilities are increasingly considering the use of GUWs for performing the inspection of piping components in nuclear power plants. GUW is a rapidly evolving technology and its usage for inspection of nuclear power plant components requires refinement and qualification to ensure it is able to achieve consistent and acceptable levels of performance. This paper will discuss potential requirements for qualification of GUW techniques for the inspection of piping components in light water reactors (LWRs). The Nuclear Regulatory Commission has adopted ASME Boiler and Pressure Vessel Code requirements in Sections V, III, and XI for nondestructive examination methods, fabrication inspections, and pre-service and in-service inspections. A Section V working group has been formed to place the methodology of GUW into the ASME Boiler and Pressure Vessel Code but no requirements for technique, equipment, or personnel exist in the Code at this time.

  17. Examination of a Junction-Box Adhesion Test for Use in Photovoltaic Module Qualification (Presentation)

    SciTech Connect (OSTI)

    Miller, D. C.; Wohlgemuth, J. H.

    2012-08-01

    Engineering robust adhesion of the junction-box (j-box) is a hurdle typically encountered by photovoltaic (PV) module manufacturers during product development. There are historical incidences of adverse effects (e.g., fires) caused when the j-box/adhesive/module system has failed in the field. The addition of a weight to the j-box during the 'damp heat' IEC qualification test is proposed to verify the basic robustness of its adhesion system. The details of the proposed test will be described, in addition to the preliminary results obtained using representative materials and components. The described discovery experiments examine moisture-cured silicone, foam tape, and hot-melt adhesives used in conjunction with PET or glass module 'substrates.' To be able to interpret the results, a set of material-level characterizations was performed, including thermogravimetric analysis, differential scanning calorimetry, and dynamic mechanical analysis. PV j-boxes were adhered to a substrate, loaded with a prescribed weight, and then placed inside an environmental chamber (at 85C, 85% relative humidity). Some systems did not remain attached through the discovery experiments. Observed failure modes include delamination (at the j-box/adhesive or adhesive/substrate interface) and phase change/creep. The results are discussed in the context of the application requirements, in addition to the plan for the formal experiment supporting the proposed modification to the qualification test.

  18. Examination of a Junction-Box Adhesion Test for Use in Photovoltaic Module Qualification: Preprint

    SciTech Connect (OSTI)

    Miller, D. C.; Wohlgemuth, J. H.

    2012-08-01

    Engineering robust adhesion of the junction-box (j-box) is a hurdle typically encountered by photovoltaic (PV) module manufacturers during product development. There are historical incidences of adverse effects (e.g., fires) caused when the j-box/adhesive/module system has failed in the field. The addition of a weight to the j-box during the 'damp heat' IEC qualification test is proposed to verify the basic robustness of its adhesion system. The details of the proposed test will be described, in addition to the preliminary results obtained using representative materials and components. The described discovery experiments examine moisture-cured silicone, foam tape, and hot-melt adhesives used in conjunction with PET or glass module 'substrates.' To be able to interpret the results, a set of material-level characterizations was performed, including thermogravimetric analysis, differential scanning calorimetry, and dynamic mechanical analysis. PV j-boxes were adhered to a substrate, loaded with a prescribed weight, and then placed inside an environmental chamber (at 85C, 85% relative humidity). Some systems did not remain attached through the discovery experiments. Observed failure modes include delamination (at the j-box/adhesive or adhesive/substrate interface) and phase change/creep. The results are discussed in the context of the application requirements, in addition to the plan for the formal experiment supporting the proposed modification to the qualification test.

  19. Characterization of the SRNL-Washed tank 51 sludge batch 9 qualification sample

    SciTech Connect (OSTI)

    Pareizs, J. M.

    2016-01-01

    Savannah River National Laboratory (SRNL) personnel have been requested to qualify the next sludge batch (Sludge Batch 9 – SB9) for processing at the Defense Waste Processing Facility (DWPF). To accomplish this task, Savannah River Remediation (SRR) sent SRNL a 3-L sample of Tank 51H slurry to be characterized, washed, and then used in a lab-scale demonstration of the DWPF flowsheet (after combining with Tank 40H sludge). SRNL has washed the Tank 51H sample per the Tank Farm washing strategy as of October 20, 2015. A part of the qualification process is extensive radionuclide and chemical characterization of the SRNL-washed Tank 51H slurry. This report documents the chemical characterization of the washed slurry; radiological characterization is in progress and will be documented in a separate report. The analytical results of this characterization are comparable to the Tank Farm projections. Therefore, it is recommended that SRNL use this washed slurry for the ongoing SB9 qualification activities.

  20. Guide to good practices for the selection, training, and qualification of shift technical advisors

    SciTech Connect (OSTI)

    1993-02-01

    The DOE Guide to Good Practices For the Selection, Training, and Qualification of Shift Technical Advisors can be used by any DOE nuclear facility that has implemented the shift technical advisor (STA) position. DOE Order 5480.20A, Personnel Selection, Qualification and Training Requirements for DOE Nuclear Facilities, states that only Category A reactors must have a shift technical advisor. However, many DOE nuclear facilities have implemented the shift technical advisor position to provide independent on-shift technical advice and counsel to the shift operating personnel to help determine cause and mitigation of facility accidents. Those DOE nuclear facilities that have implemented or are going to implement the shift technical advisor position will find this guide useful. This guide addresses areas that may be covered by other training programs. In these cases, it is unnecessary (and undesirable) to duplicate these areas in the STA training program as long as the specific skills and knowledge essential for STAs are addressed. The guide is based on the premise that the trainee has not completed any facility-specific training other than general employee training.

  1. Data Qualification Report: Calculated Porosity and Porosity-Derived Values for Lithostratigraphic Units for use on the Yucca Mountain Project

    SciTech Connect (OSTI)

    P. Sanchez

    2001-05-30

    The qualification is being completed in accordance with the Data Qualification Plan DQP-NBS-GS-000006, Rev. 00 (CRWMS M&O 2001). The purpose of this data qualification activity is to evaluate for qualification the unqualified developed input and porosity output included in Data Tracking Number (DTN) M09910POROCALC.000. The main output of the analyses documented in DTN M09910POROCALC.000 is the calculated total porosity and effective porosity for 40 Yucca Mountain Project boreholes. The porosity data are used as input to Analysis Model Report (AMR) 10040, ''Rock Properties Model'' (MDL-NBS-GS-000004, Rev. 00), Interim Change Notice [ICN] 02 (CRWMS M&O 2000b). The output from the rock properties model is used as input to numerical physical-process modeling within the context of a relationship developed in the AMR between hydraulic conductivity, bound water and zeolitic zones for use in the unsaturated zone model. In accordance with procedure AP-3.15Q, the porosity output is not used in the direct calculation of Principal Factors for post-closure safety or disruptive events. The original source for DTN M09910POROCALC.000 is a Civilian Radioactive Waste Management System (CRWMS) Management and Operating Contractor (M&O) report, ''Combined Porosity from Geophysical Logs'' (CRWMS M&O 1999a and hereafter referred to as Rael 1999). That report recalculated porosity results for both the historical boreholes covered in Nelson (1996), and the modern boreholes reported in CRWMS M&O (1996a,b). The porosity computations in Rael (1999) are based on density-porosity mathematical relationships requiring various input parameters, including bulk density, matrix density and air and/or fluid density and volumetric water content. The main output is computed total porosity and effective porosity reported on a foot-by-foot basis for each borehole, although volumetric water content is derived from neutron data as an interim output. This qualification report uses technical assessment and corroboration to evaluate the original subject DTN. Rael (1999) provides many technical details of the technical assessment and corroboration methods and partially satisfies the intent of the qualification plan for this analysis. Rael presents a modified method based on Nelson (1996) to recompute porosity and porosity-derived values and uses some of the same inputs. Rael's (1999) intended purpose was to document porosity output relatively free of biases introduced by differing computational methods or parameter selections used for different boreholes. The qualification report necessarily evaluates the soundness of the pre-Process Validation and Re-engineering (PVAR) analyses and methodology, as reported in Rael (1999).

  2. Qualification of the Nippon Instrumentation for use in Measuring Mercury at the Defense Waste Processing Facility

    SciTech Connect (OSTI)

    Edwards, T.; Mahannah, R.

    2011-07-05

    The Nippon Mercury/RA-3000 system installed in 221-S M-14 has been qualified for use. The qualification was a side-by-side comparison of the Nippon Mercury/RA-3000 system with the currently used Bacharach Mercury Analyzer. The side-by-side testing included standards for instrument calibration verifications, spiked samples and unspiked samples. The standards were traceable back to the National Institute of Standards and Technology (NIST). The side-by-side work included the analysis of Sludge Receipt and Adjustment Tank (SRAT) Receipt, SRAT Product, and Slurry Mix Evaporator (SME) samples. With the qualification of the Nippon Mercury/RA-3000 system in M-14, the DWPF lab will be able to perform a head to head comparison of a second Nippon Mercury/RA-3000 system once the system is installed. The Defense Waste Processing Facility (DWPF) analyzes receipt and product samples from the Sludge Receipt and Adjustment Tank (SRAT) to determine the mercury (Hg) concentration in the sludge slurry. The SRAT receipt is typically sampled and analyzed for the first ten SRAT batches of a new sludge batch to obtain an average Hg concentration. This average Hg concentration is then used to determine the amount of steam stripping required during the concentration/reflux step of the SRAT cycle to achieve a less than 0.6 wt% Hg in the SRAT product solids. After processing is complete, the SRAT product is sampled and analyzed for mercury to ensure that the mercury concentration does not exceed the 0.45 wt% limit in the Slurry Mix Evaporator (SME). The DWPF Laboratory utilizes Bacharach Analyzers to support these Hg analyses at this facility. These analyzers are more than 10 years old, and they are no longer supported by the manufacturer. Due to these difficulties, the Bacharach Analyzers are to be replaced by new Nippon Mercury/RA-3000 systems. DWPF issued a Technical Task Request (TTR) for the Savannah River National Laboratory (SRNL) to assist in the qualification of the new systems. SRNL prepared a task technical and quality assurance (TT&QA) plan that outlined the activities that are necessary and sufficient to meet the objectives of the TTR. In addition, TT&QA plan also included a test plan that provided guidance to the DWPF Lab in collecting the data needed to qualify the new Nippon Mercury/RA-3000 systems.

  3. Results Of Initial Analyses Of The Macrobatch 7 Tank 21H Qualification Samples

    SciTech Connect (OSTI)

    Peters, T. B.; Washington, A. L. II

    2013-07-08

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Salt (Macro) Batch 7 for the Interim Salt Disposition Program (ISDP) through ARP/MCU. This document reports the initial results of the analyses of samples of Tank 21H. Further results on the chemistry and other tests will be issued in the future. No issues with the projected Salt Batch 7 strategy are identified, other than the presence of visible quantities of dark colored solids. Based upon a SRNL settling test, the solids should settle well within the months-long settling period to be employed in Tank 21H. However, SRNL recommends analyzing the solids to provide input to OLI modeling in order to evaluate the impacts of these solids to present and future salt batches.

  4. AGR-3/4 Final Data Qualification Report for ATR Cycles 151A through 155B-1

    SciTech Connect (OSTI)

    Pham, Binh T.

    2015-03-01

    This report provides the qualification status of experimental data for the entire Advanced Gas Reactor 3/4 (AGR 3/4) fuel irradiation. AGR-3/4 is the third in a series of planned irradiation experiments conducted in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL) for the AGR Fuel Development and Qualification Program, which supports development of the advanced reactor technology under the INL ART Technology Development Office (TDO). The main objective of AGR-3/4 irradiation is to provide a known source of fission products for subsequent transport through compact matrix and structural graphite materials due to the presence of designed-to-fail fuel particles. Full power irradiation of the AGR 3/4 test began on December 14, 2011 (ATR Cycle 151A), and was completed on April 12, 2014 (end of ATR Cycle 155B) after 369.1 effective full power days of irradiation. The AGR-3/4 test was in the reactor core for eight of the ten ATR cycles between 151A and 155B. During the unplanned outage cycle, 153A, the experiment was removed from the ATR northeast flux trap (NEFT) location and stored in the ATR canal. This was to prevent overheating of fuel compacts due to higher than normal ATR power during the subsequent Powered Axial Locator Mechanism cycle, 153B. The AGR 3/4 test was inserted back into the ATR NEFT location during the outage of ATR Cycle 154A on April 26, 2013. Therefore, the AGR-3/4 irradiation data received during these 2 cycles (153A and 153B) are irrelevant and their qualification status isnot included in this report. Additionally, during ATR Cycle 152A the ATR core ran at low power for a short enough duration that the irradiation data are not used for physics and thermal calculations. However, the qualification status of irradiation data for this cycle is still covered in this report. As a result, this report includes data from 8 ATR Cycles: 151A, 151B, 152A, 152B, 154A, 154B, 155A, and 155B, as recorded in the Nuclear Data Management and Analysis System (NDMAS). The AGR 3/4 data streams addressed in this report include thermocouple (TC) temperatures, sweep gas data (flow rates, pressure, and moisture content), and Fission Product Monitoring System (FPMS) data (release rates, release to birth rate ratios [R/Bs], and particle failure counts) for each of the twelve capsules in the AGR 3/4 experiment. During Outage Cycle 155A, fourteen flow meters were installed downstream from fourteen FPMS monitors to measure flows from the monitors; qualification status of these data are also included in the report. The final data qualification status for these data streams is determined by a Data Review Committee (DRC) composed of AGR technical leads, Sitewide Quality Assurance (QA), and NDMAS analysts. For ATR Cycles 151A through 154B, the DRC convened on February 12, 2014, reviewed the data acquisition process, and considered whether the data met the requirements for data collection as specified in QA approved INL ART TDO data collection plans. The DRC also examined the results of NDMAS data testing and statistical analyses, and confirmed the qualification status of the data as given in this report. The qualification status of AGR-3/4 irradiation data during the first six cycles were previously reported in INL/EXT-14-31186 document. This report presents data qualification status for the entire AGR-3/4 irradiation.

  5. Sample Results From The Interim Salt Disposition Program Macrobatch 7 Tank 21H Qualification MST Solids Sample

    SciTech Connect (OSTI)

    Washington, A. L. II; Peters, T. B.

    2013-09-19

    Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Interim Salt Disposition Program (ISDP) Batch 7 processing. The Marcrobatch 7 material was received with visible fine particulate solids, atypical for these samples. The as received material was allowed to settle for a period greater than 24 hours. The supernatant was then decanted and utilized as our clarified feed material. As part of this qualification work, SRNL performed an Actinide Removal Process (ARP) test using the clarified feed material. From this test, the residual monosodium titanate (MST) was analyzed for radionuclide uptake after filtration from H-Tank Farm (HTF) feed salt solution. The results of these analyses are reported and are within historical precedent.

  6. AGR-2 Data Qualification Report for ATR Cycles 147A, 148A, 148B, and 149A

    SciTech Connect (OSTI)

    Michael L. Abbott; Keith A. Daum

    2011-08-01

    This report presents the data qualification status of fuel irradiation data from the first four reactor cycles (147A, 148A, 148B, and 149A) of the on-going second Advanced Gas Reactor (AGR-2) experiment as recorded in the NGNP Data Management and Analysis System (NDMAS). This includes data received by NDMAS from the period June 22, 2010 through May 21, 2011. AGR-2 is the second in a series of eight planned irradiation experiments for the AGR Fuel Development and Qualification Program, which supports development of the very high temperature gas-cooled reactor (VHTR) under the Next Generation Nuclear Plant (NGNP) Project. Irradiation of the AGR-2 test train is being performed at the Advanced Test Reactor (ATR) at the Idaho National Laboratory (INL) and is planned for 600 effective full power days (approximately 2.75 calendar years) (PLN-3798). The experiment is intended to demonstrate the performance of UCO (uranium oxycarbide) and UO2 (uranium dioxide) fuel produced in a large coater. Data qualification status of the AGR-1 experiment was reported in INL/EXT-10-17943 (Abbott et al. 2010).

  7. Sludge Washing And Demonstration Of The DWPF Flowsheet In The SRNL Shielded Cells For Sludge Batch 8 Qualification

    SciTech Connect (OSTI)

    Pareizs, J. M.; Crawford, C. L.

    2013-04-26

    The current Waste Solidification Engineering (WSE) practice is to prepare sludge batches in Tank 51 by transferring sludge from other tanks to Tank 51. Tank 51 sludge is washed and transferred to Tank 40, the current Defense Waste Processing Facility (DWPF) feed tank. Prior to transfer of Tank 51 to Tank 40, the Savannah River National Laboratory (SRNL) typically simulates the Tank Farm and DWPF processes using a Tank 51 sample (referred to as the qualification sample). WSE requested the SRNL to perform characterization on a Sludge Batch 8 (SB8) sample and demonstrate the DWPF flowsheet in the SRNL shielded cells for SB8 as the final qualification process required prior to SB8 transfer from Tank 51 to Tank 40. A 3-L sample from Tank 51 (the SB8 qualification sample; Tank Farm sample HTF-51-12-80) was received by SRNL on September 20, 2012. The as-received sample was characterized prior to being washed. The washed material was further characterized and used as the material for the DWPF process simulation including a Sludge Receipt and Adjustment Tank (SRAT) cycle, a Slurry Mix Evaporator (SME) cycle, and glass fabrication and chemical durability measurements.

  8. Reactor Testing and Qualification: Prioritized High-level Criticality Testing Needs

    SciTech Connect (OSTI)

    S. Bragg-Sitton; J. Bess; J. Werner; G. Harms; S. Bailey

    2011-09-01

    Researchers at the Idaho National Laboratory (INL) were tasked with reviewing possible criticality testing needs to support development of the fission surface power system reactor design. Reactor physics testing can provide significant information to aid in development of technologies associated with small, fast spectrum reactors that could be applied for non-terrestrial power systems, leading to eventual system qualification. Several studies have been conducted in recent years to assess the data and analyses required to design and build a space fission power system with high confidence that the system will perform as designed [Marcille, 2004a, 2004b; Weaver, 2007; Parry et al., 2008]. This report will provide a summary of previous critical tests and physics measurements that are potentially applicable to the current reactor design (both those that have been benchmarked and those not yet benchmarked), summarize recent studies of potential nuclear testing needs for space reactor development and their applicability to the current baseline fission surface power (FSP) system design, and provide an overview of a suite of tests (separate effects, sub-critical or critical) that could fill in the information database to improve the accuracy of physics modeling efforts as the FSP design is refined. Some recommendations for tasks that could be completed in the near term are also included. Specific recommendations on critical test configurations will be reserved until after the sensitivity analyses being conducted by Los Alamos National Laboratory (LANL) are completed (due August 2011).

  9. Tank 49H salt batch supernate qualification for ARP/MCU

    SciTech Connect (OSTI)

    Nash, C. A.; Peters, T.; Fink, S.; Foster, T.

    2008-08-25

    This report covers the laboratory testing and analyses of Tank 49H Qualification Sample Sets A and C, performed in support of initial radioactive operations of Actinide Removal Process (ARP) and Modular Caustic-Side Solvent Extraction Unit (MCU). Major goals of this work include checking that Tank 49H was well mixed after the last receipt of Tank 23H, characterizing Tank 49H supernate after solids are settled so that its composition can be compared to waste acceptance and hazard criteria, verifying actinide and strontium adsorption with a small scale test using monosodium titanate (MST) and filtration, checking MCU solvent performance when applied to the liquid produced from MST contact, and verifying that in-tank settling after a minimum of 30 days was at least as good or better at reducing solids content after a Tank 49H to Tank 50H transfer occurred than what was observed in less time in the lab. The first four items were covered by Sample Set A. The fifth item was covered by Sample Set C, which had several analyses after compositing as required in the nuclear criticality safety evaluation (NCSE).

  10. Trial Run of a Junction-Box Attachment Test for Use in Photovoltaic Module Qualification (Presentation)

    SciTech Connect (OSTI)

    Miller, D.; Deibert, S.; Wohlgemuth, J.

    2014-06-01

    Engineering robust adhesion of the junction-box (j-box) is a hurdle typically encountered by photovoltaic (PV) module manufacturers during product development and manufacturing process control. There are historical incidences of adverse effects (e.g., fires), caused when the j-box/adhesive/module system has failed in the field. The addition of a weight to the j-box during the 'damp-heat', 'thermal-cycle', or 'creep' tests within the IEC qualification protocol is proposed to verify the basic robustness of the adhesion system. The details of the proposed test are described, in addition to a trial run of the test procedure. The described experiments examine 4 moisture-cured silicones, 4 foam tapes, and a hot-melt adhesive used in conjunction with glass, KPE, THV, and TPE substrates. For the purpose of validating the experiment, j-boxes were adhered to a substrate, loaded with a prescribed weight, and then subjected to aging. The replicate mock-modules were aged in an environmental chamber (at 85 deg C/85% relative humidity for 1000 hours; then 100 degrees C/<10% relative humidity for 200 hours) or fielded in Golden, Miami, and Phoenix for 1 year. Attachment strength tests, including pluck and shear test geometries, were also performed on smaller component specimens.

  11. SAMPLE RESULTS FROM THE INTERIM SALT DISPOSITION PROGRAM MACROBATCH 8 TANK 21H QUALIFICATION SAMPLES

    SciTech Connect (OSTI)

    Peters, T. B.; Washington, A. L.

    2015-01-13

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 8 for the Interim Salt Disposition Program (ISDP). An Actinide Removal Process (ARP) and several Extraction-Scrub- Strip (ESS) tests were also performed. This document reports characterization data on the samples of Tank 21H as well as simulated performance of ARP and the Modular Caustic Side Solvent Extraction (CSSX) Unit (MCU). No issues with the projected Salt Batch 8 strategy are identified. A demonstration of the monosodium titanate (MST) (0.2 g/L) removal of strontium and actinides provided acceptable average decontamination factors for plutonium of 2.62 (4 hour) and 2.90 (8 hour); and average strontium decontamination factors of 21.7 (4 hour) and 21.3 (8 hour). These values are consistent with results from previous salt batch ARP tests. The two ESS tests also showed acceptable performance with extraction distribution ratios (D{sub (Cs)}) values of 52.5 and 50.4 for the Next Generation Solvent (NGS) blend (from MCU) and NGS (lab prepared), respectively. These values are consistent with results from previous salt batch ESS tests. Even though the performance is acceptable, SRNL recommends that a model for predicting extraction behavior for cesium removal for the blended solvent and NGS be developed in order to improve our predictive capabilities for the ESS tests.

  12. PULSE COMBUSTOR DESIGN QUALIFICATION TEST AND CLEAN COAL FEEDSTOCK TEST - VOLUME I AND VOLUME II

    SciTech Connect (OSTI)

    Unknown

    2002-02-08

    For this Cooperative Agreement, the pulse heater module is the technology envelope for an indirectly heated steam reformer. The field of use of the steam reformer pursuant to this Cooperative Agreement with DOE is for the processing of sub-bituminous coals and lignite. The main focus is the mild gasification of such coals for the generation of both fuel gas and char--for the steel industry is the main focus. An alternate market application for the substitution of metallurgical coke is also presented. This project was devoted to qualification of a 253-tube pulse heater module. This module was designed, fabricated, installed, instrumented and tested in a fluidized bed test facility. Several test campaigns were conducted. This larger heater is a 3.5 times scale-up of the previous pulse heaters that had 72 tubes each. The smaller heater has been part of previous pilot field testing of the steam reformer at New Bern, North Carolina. The project also included collection and reduction of mild gasification process data from operation of the process development unit (PDU). The operation of the PDU was aimed at conditions required to produce char (and gas) for the Northshore Steel Operations. Northshore Steel supplied the coal for the process unit tests.

  13. Sample Results From The Interim Salt Disposition Program Macrobatch 7 Tank 21H Qualification Samples

    SciTech Connect (OSTI)

    Peters, T. B.; Washington, A. L. II

    2013-08-08

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 7 for the Interim Salt Disposition Program (ISDP). An ARP and several ESS tests were also performed. This document reports characterization data on the samples of Tank 21H as well as simulated performance of ARP/MCU. No issues with the projected Salt Batch 7 strategy are identified, other than the presence of visible quantities of dark colored solids. A demonstration of the monosodium titanate (0.2 g/L) removal of strontium and actinides provided acceptable 4 hour average decontamination factors for Pu and Sr of 3.22 and 18.4, respectively. The Four ESS tests also showed acceptable behavior with distribution ratios (D(Cs)) values of 15.96, 57.1, 58.6, and 65.6 for the MCU, cold blend, hot blend, and Next Generation Solvent (NGS), respectively. The predicted value for the MCU solvent was 13.2. Currently, there are no models that would allow a prediction of extraction behavior for the other three solvents. SRNL recommends that a model for predicting extraction behavior for cesium removal for the blended solvent and NGS be developed. While no outstanding issues were noted, the presence of solids in the samples should be investigated in future work. It is possible that the solids may represent a potential reservoir of material (such as potassium) that could have an impact on MCU performance if they were to dissolve back into the feed solution. This salt batch is intended to be the first batch to be processed through MCU entirely using the new NGS-MCU solvent.

  14. SLUDGE WASHING AND DEMONSTRATION OF THE DWPF FLOWSHEET IN THE SRNL SHIELDED CELLS FOR SLUDGE BATCH 5 QUALIFICATION

    SciTech Connect (OSTI)

    Pareizs, J; Cj Bannochie, C; Damon Click, D; Dan Lambert, D; Michael Stone, M; Bradley Pickenheim, B; Amanda Billings, A; Ned Bibler, N

    2008-11-10

    Sludge Batch 5 (SB5) is predominantly a combination of H-modified (HM) sludge from Tank 11 that underwent aluminum dissolution in late 2007 to reduce the total mass of sludge solids and aluminum being fed to the Defense Waste Processing Facility (DWPF) and Purex sludge transferred from Tank 7. Following aluminum dissolution, the addition of Tank 7 sludge and excess Pu to Tank 51, Liquid Waste Operations (LWO) provided the Savannah River National Laboratory (SRNL) a 3-L sample of Tank 51 sludge for SB5 qualification. SB5 qualification included washing the sample per LWO plans/projections (including the addition of a Pu/Be stream from H Canyon), DWPF Chemical Process Cell (CPC) simulations, waste glass fabrication (vitrification), and waste glass chemical durability evaluation. This report documents: (1) The washing (addition of water to dilute the sludge supernatant) and concentration (decanting of supernatant) of the Tank 51 qualification sample to adjust sodium content and weight percent insoluble solids to Tank Farm projections. (2) The performance of a DWPF CPC simulation using the washed Tank 51 sample. This includes a Sludge Receipt and Adjustment Tank (SRAT) cycle, where acid is added to the sludge to destroy nitrite and remove mercury, and a Slurry Mix Evaporator (SME) cycle, where glass frit is added to the sludge in preparation for vitrification. The SME cycle also included replication of five canister decontamination additions and concentrations. Processing parameters for the CPC processing were based on work with a non radioactive simulant. (3) Vitrification of a portion of the SME product and Product Consistency Test (PCT) evaluation of the resulting glass. (4) Rheology measurements of the initial slurry samples and samples after each phase of CPC processing. This work is controlled by a Task Technical and Quality Assurance Plan (TTQAP) , and analyses are guided by an Analytical Study Plan. This work is Technical Baseline Research and Development (R&D) for the DWPF.

  15. SLUDGE BATCH 7 ACCEPTANCE EVALUATION: RADIONUCLIDE CONCENTRATIONS IN TANK 51 SB7 QUALIFICATION SAMPLE PREPARED AT SRNL

    SciTech Connect (OSTI)

    Pareizs, J.; Hay, M.

    2011-02-22

    Presented in this report are radionuclide concentrations required as part of the program of qualifying Sludge Batch Seven (SB7) for processing in the Defense Waste Processing Facility (DWPF). The SB7 material is currently in Tank 51 being washed and prepared for transfer to Tank 40. The acceptance evaluation needs to be completed prior to the transfer of the material in Tank 51 to Tank 40. The sludge slurry in Tank 40 has already been qualified for DWPF and is currently being processed as SB6. The radionuclide concentrations were measured or estimated in the Tank 51 SB7 Qualification Sample prepared at Savannah River National Laboratory (SRNL). This sample was prepared from the three liter qualification sample of Tank 51 sludge slurry (HTF-51-10-125) received on September 18, 2010. The sample was delivered to SRNL where it was initially characterized in the Shielded Cells. With consultation from the Liquid Waste Organization, the qualification sample was then modified by several washes and decants, which included addition of Pu from H Canyon and sodium nitrite per the Tank Farm corrosion control program. This final slurry now has a composition expected to be similar to that of the slurry in Tank 51 after final preparations have been made for transfer of that slurry to Tank 40. Determining the radionuclide concentrations in this Tank 51 SB7 Qualification Sample is part of the work requested in Technical Task Request (TTR) No. HLW-DWPF-TTR-2010-0031. The radionuclides included in this report are needed for the DWPF Radiological Program Evaluation, the DWPF Waste Acceptance Criteria (TSR/WAC) Evaluation, and the DWPF Solid Waste Characterization Program (TTR Task I.2). Radionuclides required to meet the Waste Acceptance Product Specifications (TTR Task III.2.) will be measured at a later date after the slurry from Tank 51 has been transferred to Tank 40. Then a sample of the as-processed SB7 will be taken and transferred to SRNL for measurement of these radionuclides. The results presented in this report are those necessary for DWPF to assess if the Tank 51 SB7 sample prepared at SRNL meets the requirements for the DWPF Radiological Program Evaluation, the DWPF Waste Acceptance Criteria evaluation, and the DWPF Solid Waste Characterization Program. Concentrations are given for thirty-four radionuclides along with total alpha and beta activity. Values for total gamma and total gamma plus beta activities are also calculated.

  16. Proposed Junction-Box Stress Test (Using an Added Weight) for Use During the Module Qualification (Presentation)

    SciTech Connect (OSTI)

    Miller, D. C.; Wohlgemuth, J. H.; Kurtz, S. R.

    2012-02-01

    Engineering robust adhesion of the junction-box (j-box) is a hurdle typically encountered by photovoltaic (PV) module manufacturers during product development. Furthermore, there are historical incidences of adverse effects (e.g., fires) caused when the j-box/adhesive/module system has failed in the field. The addition of a weight to the j-box during the 'damp heat' IEC qualification test is proposed to verify the basic robustness of the j-box adhesion system. The details of the proposed test are described, in addition to the preliminary results conducted using representative materials and components.

  17. AGR-2 Final Data Qualification Report for U.S. Capsules - ATR Cycles 147A Through 154B

    SciTech Connect (OSTI)

    Pham, Binh T; Einerson, Jeffrey J

    2014-07-01

    This report provides the data qualification status of AGR-2 fuel irradiation experimental data in four U.S. capsules from all 15 Advanced Test Reactor (ATR) Cycles 147A, 148A, 148B, 149A, 149B, 150A, 150B, 151A, 151B, 152A, 152B, 153A, 153B, 154A, and 154B, as recorded in the Nuclear Data Management and Analysis System (NDMAS). Thus, this report covers data qualification status for the entire AGR-2 irradiation and will replace four previously issued AGR-2 data qualification reports (e.g., INL/EXT-11-22798, INL/EXT-12-26184, INL/EXT-13-29701, and INL/EXT-13-30750). During AGR-2 irradiation, two cycles, 152A and 153A, occurred when the ATR core was briefly at low power, so AGR-2 irradiation data are not used for physics and thermal calculations. Also, two cycles, 150A and 153B, are Power Axial Locator Mechanism (PALM) cycles when the ATR power is higher than during normal cycles. During the first PALM cycle, 150A, the experiment was temporarily moved from the B-12 location to the ATR water canal and during the second PALM cycle, 153B, the experiment was temporarily moved from the B-12 location to the I-24 location to avoid being overheated. During the Outage cycle, 153A, seven flow meters were installed downstream from seven Fission Product Monitoring System (FPMS) monitors to measure flows from the monitors and these data are included in the NDMAS database. The AGR-2 data streams addressed in this report include thermocouple (TC) temperatures, sweep gas data (flow rates including new FPM downstream flows, pressure, and moisture content), and FPMS data (release rates and release-to-birth rate ratios [R/Bs]) for each of the four U.S. capsules in the AGR-2 experiment (Capsules 2, 3, 5, and 6). The final data qualification status for these data streams is determined by a Data Review Committee comprised of AGR technical leads, Very High Temperature Reactor (VHTR) Program Quality Assurance (QA), and NDMAS analysts. The Data Review Committee, which convened just before each data qualification report was issued, reviewed the data acquisition process, considered whether the data met the requirements for data collection as specified in QA-approved VHTR data collection plans, examined the results of NDMAS data testing and statistical analyses, and confirmed the qualification status of the data as given in each report. This report performs the following tasks: (1) combine existing qualification status of all AGR-2 data, (2) provide FPMS data qualification update and new release-to-birth ratio (R/B) data calculated using daily calculated birthrates, and (3) revise data qualification status of TC readings for some TCs in Capsule 6 based on their differences relative to calculated temperatures at TC locations. A total of 17,001,695 TC temperature and sweep gas data records were received and processed by NDMAS for four U.S. capsules during AGR-2 irradiation. Of these records, 9,655,474 (56.8% of the total) were determined to be Qualified; 5,792,052 (34.1% of the total) were determined to be Failed; and 1,554,169 (9.1% of the total) were determined to be Trend. For the first nice cycles, from ATR Cycle 147A to 151B, data records are 5- minute or 10-minute averaged values provided on weekly basis in EXCEL spreadsheets. For the last six cycles, ATR Cycle 152A through 154B, data records are instantaneous measurements recorded every minute and provided by .csv text files automatically every 2 hours. Therefore, the number of processed irradiation data was increased substantially from ATR Cycle 152A. For TC temperature data, there were 6,857,675 records and of these data 5,288,249 records (77.1% of the total TC data) were Failed due to TC instrument failures and 418,569 records (6.1% of the total TC data) were Trend due to large differences between TC readings and calculated values. By the end of Cycle 154A, all TCs in the AGR-2 test train failed. The overall percentage of Failed TC records is high, to some extent, because TCs failed toward the end of irradiation when the recording frequency was higher. For sweep gas data, there were 10,1

  18. DEVELOPMENT QUALIFICATION AND DISPOSAL OF AN ALTERNATIVE IMMOBILIZED LOW-ACTIVITY WASTE FORM AT THE HANFORD SITE

    SciTech Connect (OSTI)

    SAMS TL; EDGE JA; SWANBERG DJ; ROBBINS RA

    2011-01-13

    Demonstrating that a waste form produced by a given immobilization process is chemically and physically durable as well as compliant with disposal facility acceptance criteria is critical to the success of a waste treatment program, and must be pursued in conjunction with the maturation of the waste processing technology. Testing of waste forms produced using differing scales of processing units and classes of feeds (simulants versus actual waste) is the crux of the waste form qualification process. Testing is typically focused on leachability of constituents of concern (COCs), as well as chemical and physical durability of the waste form. A principal challenge regarding testing immobilized low-activity waste (ILAW) forms is the absence of a standard test suite or set of mandatory parameters against which waste forms may be tested, compared, and qualified for acceptance in existing and proposed nuclear waste disposal sites at Hanford and across the Department of Energy (DOE) complex. A coherent and widely applicable compliance strategy to support characterization and disposal of new waste forms is essential to enhance and accelerate the remediation of DOE tank waste. This paper provides a background summary of important entities, regulations, and considerations for nuclear waste form qualification and disposal. Against this backdrop, this paper describes a strategy for meeting and demonstrating compliance with disposal requirements emphasizing the River Protection Project (RPP) Integrated Disposal Facility (IDF) at the Hanford Site and the fluidized bed steam reforming (FBSR) mineralized low-activity waste (LAW) product stream.

  19. Nuclear power plant cable materials : review of qualification and currently available aging data for margin assessments in cable performance.

    SciTech Connect (OSTI)

    Celina, Mathias Christopher; Gillen, Kenneth Todd; Lindgren, Eric Richard

    2013-05-01

    A selective literature review was conducted to assess whether currently available accelerated aging and original qualification data could be used to establish operational margins for the continued use of cable insulation and jacketing materials in nuclear power plant environments. The materials are subject to chemical and physical degradation under extended radiationthermal- oxidative conditions. Of particular interest were the circumstances under which existing aging data could be used to predict whether aged materials should pass loss of coolant accident (LOCA) performance requirements. Original LOCA qualification testing usually involved accelerated aging simulations of the 40-year expected ambient aging conditions followed by a LOCA simulation. The accelerated aging simulations were conducted under rapid accelerated aging conditions that did not account for many of the known limitations in accelerated polymer aging and therefore did not correctly simulate actual aging conditions. These highly accelerated aging conditions resulted in insulation materials with mostlyinert' aging processes as well as jacket materials where oxidative damage dropped quickly away from the air-exposed outside jacket surface. Therefore, for most LOCA performance predictions, testing appears to have relied upon heterogeneous aging behavior with oxidation often limited to the exterior of the cable cross-section - a situation which is not comparable with the nearly homogenous oxidative aging that will occur over decades under low dose rate and low temperature plant conditions. The historical aging conditions are therefore insufficient to determine with reasonable confidence the remaining operational margins for these materials. This does not necessarily imply that the existing 40-year-old materials would fail if LOCA conditions occurred, but rather that unambiguous statements about the current aging state and anticipated LOCA performance cannot be provided based on original qualification testing data alone. The non-availability of conclusive predictions for the aging conditions of 40-year-old cables implies that the same levels of uncertainty will remain for any re-qualification or extended operation of these cables. The highly variable aging behavior of the range of materials employed also implies that simple, standardized aging tests are not sufficient to provide the required aging data and performance predictions for all materials. It is recommended that focused studies be conducted that would yield the material aging parameters needed to predict aging behaviors under low dose, low temperature plant equivalent conditions and that appropriately aged specimens be prepared that would mimic oxidatively-aged 40- to 60- year-old materials for confirmatory LOCA performance testing. This study concludes that it is not sufficient to expose materials to rapid, high radiation and high temperature levels with subsequent LOCA qualification testing in order to predictively quantify safety margins of existing infrastructure with regard to LOCA performance. We need to better understand how cable jacketing and insulation materials have degraded over decades of power plant operation and how this aging history relates to service life prediction and the performance of existing equipment to withstand a LOCA situation.

  20. AlGaN UV LED and Photodiodes Radiation Hardness and Space Qualifications and Their Applications in Space Science and High Energy Density Physics

    SciTech Connect (OSTI)

    Sun, K. X.

    2011-05-31

    This presentation provides an overview of robust, radiation hard AlGaN optoelectronic devices and their applications in space exploration & high energy density physics. Particularly, deep UV LED and deep UV photodiodes are discussed with regard to their applications, radiation hardness and space qualification. AC charge management of UV LED satellite payload instruments, which were to be launched in late 2012, is covered.

  1. Results from the DOE Advanced Gas Reactor Fuel Development and Qualification Program

    SciTech Connect (OSTI)

    David Petti

    2014-06-01

    Modular HTGR designs were developed to provide natural safety, which prevents core damage under all design basis accidents and presently envisioned severe accidents. The principle that guides their design concepts is to passively maintain core temperatures below fission product release thresholds under all accident scenarios. This level of fuel performance and fission product retention reduces the radioactive source term by many orders of magnitude and allows potential elimination of the need for evacuation and sheltering beyond a small exclusion area. This level, however, is predicated on exceptionally high fuel fabrication quality and performance under normal operation and accident conditions. Germany produced and demonstrated high quality fuel for their pebble bed HTGRs in the 1980s, but no U.S. manufactured fuel had exhibited equivalent performance prior to the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. The design goal of the modular HTGRs is to allow elimination of an exclusion zone and an emergency planning zone outside the plant boundary fence, typically interpreted as being about 400 meters from the reactor. To achieve this, the reactor design concepts require a level of fuel integrity that is better than that claimed for all prior US manufactured TRISO fuel, by a few orders of magnitude. The improved performance level is about a factor of three better than qualified for German TRISO fuel in the 1980’s. At the start of the AGR program, without a reactor design concept selected, the AGR fuel program selected to qualify fuel to an operating envelope that would bound both pebble bed and prismatic options. This resulted in needing a fuel form that could survive at peak fuel temperatures of 1250°C on a time-averaged basis and high burnups in the range of 150 to 200 GWd/MTHM (metric tons of heavy metal) or 16.4 to 21.8% fissions per initial metal atom (FIMA). Although Germany has demonstrated excellent performance of TRISO-coated UO2 particle fuel up to about 10% FIMA and 1150°C, UO2 fuel is known to have limitations because of CO formation and kernel migration at the high burnups, power densities, temperatures, and temperature gradients that may be encountered in the prismatic modular HTGRs. With uranium oxycarbide (UCO) fuel, the kernel composition is engineered to prevent CO formation and kernel migration, which are key threats to fuel integrity at higher burnups, temperatures, and temperature gradients. Furthermore, the recent poor fuel performance of UO2 TRISO fuel pebbles measured in Chinese irradiation testing in Russia and in German pebbles irradiated at 1250°C, and historic data on poorer fuel performance in safety testing of German pebbles that experienced burnups in excess of 10% FIMA [1] have each raised concern about the use of UO2 TRISO above 10% FIMA and 1150°C and the degree of margin available in the fuel system. This continues to be an active area of study internationally.

  2. Verification Of The Defense Waste Processing Facility's (DWPF) Process Digestion Methods For The Sludge Batch 8 Qualification Sample

    SciTech Connect (OSTI)

    Click, D. R.; Edwards, T. B.; Wiedenman, B. J.; Brown, L. W.

    2013-03-18

    This report contains the results and comparison of data generated from inductively coupled plasma atomic emission spectroscopy (ICP-AES) analysis of Aqua Regia (AR), Sodium Peroxide/Sodium Hydroxide Fusion Dissolution (PF) and Cold Chem (CC) method digestions and Cold Vapor Atomic Absorption analysis of Hg digestions from the DWPF Hg digestion method of Sludge Batch 8 (SB8) Sludge Receipt and Adjustment Tank (SRAT) Receipt and SB8 SRAT Product samples. The SB8 SRAT Receipt and SB8 SRAT Product samples were prepared in the SRNL Shielded Cells, and the SRAT Receipt material is representative of the sludge that constitutes the SB8 Batch or qualification composition. This is the sludge in Tank 51 that is to be transferred into Tank 40, which will contain the heel of Sludge Batch 7b (SB7b), to form the SB8 Blend composition.

  3. SLUDGE WASHING AND DEMONSTRATION OF THE DWPF FLOWSHEET IN THE SRNL SHIELDED CELLS FOR SLUDGE BATCH 7A QUALIFICATION

    SciTech Connect (OSTI)

    Pareizs, J.; Billings, A.; Click, D.

    2011-07-08

    Waste Solidification Engineering (WSE) has requested that characterization and a radioactive demonstration of the next batch of sludge slurry (Sludge Batch 7a*) be completed in the Shielded Cells Facility of the Savannah River National Laboratory (SRNL) via a Technical Task Request (TTR). This characterization and demonstration, or sludge batch qualification process, is required prior to transfer of the sludge from Tank 51 to the Defense Waste Processing Facility (DWPF) feed tank (Tank 40). The current WSE practice is to prepare sludge batches in Tank 51 by transferring sludge from other tanks. Discharges of nuclear materials from H Canyon are often added to Tank 51 during sludge batch preparation. The sludge is washed and transferred to Tank 40, the current DWPF feed tank. Prior to transfer of Tank 51 to Tank 40, SRNL simulates the Tank Farm and DWPF processes with a Tank 51 sample (referred to as the qualification sample). Sludge Batch 7a (SB7a) is composed of portions of Tanks 4, 7, and 12; the Sludge Batch 6 heel in Tank 51; and a plutonium stream from H Canyon. SRNL received the Tank 51 qualification sample (sample ID HTF-51-10-125) following sludge additions to Tank 51. This report documents: (1) The washing (addition of water to dilute the sludge supernate) and concentration (decanting of supernate) of the SB7a - Tank 51 qualification sample to adjust sodium content and weight percent insoluble solids to Tank Farm projections. (2) The performance of a DWPF Chemical Process Cell (CPC) simulation using the washed Tank 51 sample. The simulation included a Sludge Receipt and Adjustment Tank (SRAT) cycle, where acid was added to the sludge to destroy nitrite and reduce mercury, and a Slurry Mix Evaporator (SME) cycle, where glass frit was added to the sludge in preparation for vitrification. The SME cycle also included replication of five canister decontamination additions and concentrations. Processing parameters were based on work with a non-radioactive simulant. (3) Vitrification of a portion of the SME product and characterization and durability testing (as measured by the Product Consistency Test (PCT)) of the resulting glass. (4) Rheology measurements of the initial slurry samples and samples after each phase of CPC processing. This program was controlled by a Task Technical and Quality Assurance Plan (TTQAP), and analyses were guided by an Analytical Study Plan. This work is Technical Baseline Research and Development (R&D) for the DWPF. It should be noted that much of the data in this document has been published in interoffice memoranda. The intent of this technical report is bring all of the SB7a related data together in a single permanent record and to discuss the overall aspects of SB7a processing.

  4. LL/ILW: Post-Qualification of Old Waste through Non-Destructive Extraction of Barrels from Cement Shields - 13535

    SciTech Connect (OSTI)

    Oehmigen, Steffen; Ambos, Frank

    2013-07-01

    Currently there is a large number of radioactive waste drums entombed in cement shields at German nuclear power plants. These concrete containers used in the past for the waste are not approved for the final repository. Compliance with current acceptance criteria of the final repository has to be proven by qualification measures on the waste. To meet these criteria, a new declaration and new packing is necessary. A simple non-destructive extraction of about 2000 drums from their concrete shields is not possible. So different methods were tested to find a way of non-destructive extraction of old waste drums from cement shields and therefore reduce the final repository volume and final repository costs by using a container accepted and approved for Konrad. The main objective was to build a mobile system to offer this service to nuclear plant stations. (authors)

  5. Technical considerations related to interim source-term assumptions for emergency planning and equipment qualification. [PWR; BWR

    SciTech Connect (OSTI)

    Niemczyk, S.J.; McDowell-Boyer, L.M.

    1982-09-01

    The source terms recommended in the current regulatory guidance for many considerations of light water reactor (LWR) accidents were developed a number of years ago when understandings of many of the phenomena pertinent to source term estimation were relatively primitive. The purpose of the work presented here was to develop more realistic source term assumptions which could be used for interim regulatory purposes for two specific considerations, namely, equipment qualification and emergency planning. The overall approach taken was to adopt assumptions and models previously proposed for various aspects of source term estimation and to modify those assumptions and models to reflect recently gained insights into, and data describing, the release and transport of radionuclides during and after LWR accidents. To obtain illustrative estimates of the magnitudes of the source terms, the results of previous calculations employing the adopted assumptions and models were utilized and were modified to account for the effects of the recent insights and data.

  6. AGR-2 Data Qualification Report for ATR Cycles 149B, 150A, 150B, 151A, and 151B

    SciTech Connect (OSTI)

    Michael L. Abbott; Binh T. Pham

    2012-06-01

    This report provides the data qualification status of AGR-2 fuel irradiation experimental data from Advanced Test Reactor (ATR) cycles 149B, 150A, 150B, 151A, and 151B), as recorded in the Nuclear Data Management and Analysis System (NDMAS). The AGR-2 data streams addressed include thermocouple temperatures, sweep gas data (flow rate, pressure, and moisture content), and fission product monitoring system (FPMS) data for each of the six capsules in the experiment. A total of 3,307,500 5-minute thermocouple and sweep gas data records were received and processed by NDMAS for this period. There are no AGR-2 data for cycle 150A because the experiment was removed from the reactor. Of these data, 82.2% were determined to be Qualified based on NDMAS accuracy testing and data validity assessment. There were 450,557 Failed temperature records due to thermocouple failures, and 138,528 Failed gas flow records due to gas flow cross-talk and leakage problems that occurred in the capsules after cycle 150A. For FPMS data, NDMAS received and processed preliminary release rate and release-to-birth rate ratio (R/B) data for the first three reactor cycles (cycles 149B, 150B, and 151B). This data consists of 45,983 release rate records and 45,235 R/B records for the 12 radionuclides reported. The qualification status of these FPMS data has been set to In Process until receipt of QA-approved data generator reports. All of the above data have been processed and tested using a SAS-based enterprise application software system, stored in a secure Structured Query Language database, and made available on the NDMAS Web portal (http://ndmas.inl.gov) for both internal and external VHTR project participants.

  7. Analysis of tank 4 (FTF-4-15-22, 23) surface and subsurface supernatant samples in support of enrichment control, corrosion control and evaporator feed qualification programs

    SciTech Connect (OSTI)

    Oji, L. N.

    2015-09-09

    This report provides the results of analyses on Savannah River Site Tank 4 surface and subsurface supernatant liquid samples in support of the Enrichment Control Program (ECP), the Corrosion Control Program (CCP) and the Evaporator Feed Qualification (EFQ) Program. The purpose of the ECP sample taken from Tank 4 in August 2015 was to determine if the supernatant liquid would be “acceptable feed” to the 2H and 3H evaporator systems.

  8. Risk-Informed Safety Margin Characterization Case Study: Selection of Electrical Equipment to Be Subjected to Environmental Qualification

    SciTech Connect (OSTI)

    D. P. Blanchard; R. W. Youngblood

    2014-06-01

    The Risk-Informed Safety Margin Characterization (RISMC) pathway of the DOE’s Light Water Reactor Sustainability (LWRS) program focuses on advancing the state of the art in safety analysis and risk assessment to support decision-making on nuclear power plant operation well beyond the originally designed lifetime of the plants (i.e., beyond 60 years). Among the issues being addressed in RISMC is the significance of SSC aging and how confident we are about our understanding of its impact on the margin between the loads SSCs are expected to see during normal operation and accident conditions, and the SSC capacities (their ability to resist those loads) as the SSCs age. In this paper, a summary is provided of a case study that examines SSC aging from an environmental qualification (EQ) perspective. The case study illustrates how the state of knowledge regarding SSC margin can be characterized given the overall integrated plant design, and was developed to demonstrate a method for deciding on which cables to focus, which cables are not so important from an environmental qualification margin standpoint, and what plant design features or operating characteristics determine the role that environmental qualification plays in establishing a safety case on which decisions regarding margin can be made. The selection of cables for which demonstration of margin with respect to aging and environmental challenges uses a technique known as Prevention Analysis. Prevention Analysis is a Boolean method for optimal selection of SSCs (that is, those combinations of SSCs both necessary and sufficient to meet a predetermined selection criterion) in a manner that allows demonstration that plant-level safety can be demonstrated by the collection of selected SSCs alone. Choosing the set of SSCs that is necessary and sufficient to satisfy the safety objectives, and demonstrating that the safety objectives can be met effectively, determines where resources are best allocated to assure SSC performance margin. The paper describes the resulting component types that were selected by Prevention Analysis and identifies the accident sequence characteristics that cause these component types to be important from an EQ and aging perspective (and, hence, worthwhile evaluating the extent of safety margin). In addition, component types not selected as needing significant margin from an EQ and aging perspective are discussed and an engineering rationale is developed justifying the lack of need to apply resources to demonstrating margin for these component types. This rationale is in terms of design features of the plant and operating characteristics that make these component types less important from an EQ and aging perspective. While the case study focuses on EQ and aging of equipment and cables located inside the containment of this PWR, the prevention analysis method is demonstrated to be an effective technique for identification of minimal collections of components that would be effective in managing safety for a variety of issues associated with aging and long-term operation of the fleet of plants.

  9. SLUDGE BATCH 5 ACCEPTANCE EVALUATION RADIONUCLIDE CONCENTRATIONS IN TANK 51 SB5 QUALIFICATION SAMPLE PREPARED AT SRNL

    SciTech Connect (OSTI)

    Bannochie, C; Ned Bibler, N; David Diprete, D

    2008-07-28

    Presented in this report are radionuclide concentrations required as part of the program of qualifying Sludge Batch Five (SB5) for processing in the Defense Waste Processing Facility (DWPF). Part of this SB5 material is currently in Tank 51 being washed and prepared for transfer to Tank 40. The acceptance evaluation needs to be completed prior to the transfer of the material in Tank 51 to Tank 40 to complete the formation of SB5. The sludge slurry in Tank 40 has already been qualified for DWPF and is currently being processed as SB4. The radionuclide concentrations were measured or estimated in the Tank 51 SB5 Qualification Sample prepared at Savannah River National Laboratory (SRNL). This sample was prepared from the three liter sample of Tank 51 sludge slurry taken on March 21, 2008. The sample was delivered to SRNL where it was initially characterized in the Shielded Cells. Under direction of the Liquid Waste Organization it was then modified by five washes, six decants, an addition of Pu/Be from Canyon Tank 16.4, and an addition of NaNO2. This final slurry now has a composition expected to be similar to that of the slurry in Tank 51 after final preparations have been made for transfer of that slurry to Ta Determining the radionuclide concentrations in this Tank 51 SB5 Qualification Sample is part of the work requested in Technical Task Request (TTR) No. HLW-DWPF-TTR-2008-0010. The work with this qualification sample is covered by a Task Technical and Quality Assurance Plan and an Analytical Study Plan. The radionuclides included in this report are needed for the DWPF Radiological Program Evaluation, the DWPF Waste Acceptance Criteria (TSR/WAC) Evaluation, and the DWPF Solid Waste Characterization Program (TTR Task 2). Radionuclides required to meet the Waste Acceptance Product Specifications (TTR Task 5) will be measured at a later date after the slurry from Tank 51 has been transferred to Tank 40. Then a sample of the as-processed SB5 will be taken and transferred to SRNL for measurement of these radionuclides. Data presented in this report represents the measured or estimated radionuclide concentrations obtained from several standard and special analytical methods performed by Analytical Development (AD) personnel within SRNL. The method for I-129 measurement in sludge is described in detail. Most of these methods were performed on solutions resulting from the dissolutions of the slurry samples. Concentrations are given for twenty-nine radionuclides along with total alpha and beta activity. Values for total gamma and total gamma plus beta activities are also calculated. Results also indicate that 98% of the Tc-99 and 92% of the I-129 that could have been in this sludge batch have been removed by chemical processing steps in the SRS Canyons or Tank Farm.

  10. SLUDGE BATCH 6 ACCEPTANCE EVALUATION: RADIONUCLIDE CONCENTRATIONS IN TANK 51 SB6 QUALIFICATION SAMPLE PREPARED AT SRNL

    SciTech Connect (OSTI)

    Bannochie, C.; Bibler, N.; Diprete, D.

    2010-05-21

    Presented in this report are radionuclide concentrations required as part of the program of qualifying Sludge Batch Six (SB6) for processing in the Defense Waste Processing Facility (DWPF). The SB6 material is currently in Tank 51 being washed and prepared for transfer to Tank 40. The acceptance evaluation needs to be completed prior to the transfer of the material in Tank 51 to Tank 40. The sludge slurry in Tank 40 has already been qualified for DWPF and is currently being processed as SB5. The radionuclide concentrations were measured or estimated in the Tank 51 SB6 Qualification Sample prepared at Savannah River National Laboratory (SRNL). This sample was prepared from the three liter sample of Tank 51 sludge slurry (HTF-51-09-110) taken on October 8, 2009. The sample was delivered to SRNL where it was initially characterized in the Shielded Cells. Under the direction of the Liquid Waste Organization it was then modified by eight washes, nine decants, an addition of Pu from Canyon Tank 16.3, and an addition of NaNO{sub 2}. This final slurry now has a composition expected to be similar to that of the slurry in Tank 51 after final preparations have been made for transfer of that slurry to Tank 40. Determining the radionuclide concentrations in this Tank 51 SB6 Qualification Sample is part of the work requested in Technical Task Request (TTR) No. HLW-DWPF-TTR-2009-0014. The work with this qualification sample is covered by a Task Technical and Quality Assurance Plan and an Analytical Study Plan. The radionuclides included in this report are needed for the DWPF Radiological Program Evaluation, the DWPF Waste Acceptance Criteria (TSR/WAC) Evaluation, and the DWPF Solid Waste Characterization Program (TTR Task I.2). Radionuclides required to meet the Waste Acceptance Product Specifications (TTR Task II.2.) will be measured at a later date after the slurry from Tank 51 has been transferred to Tank 40. Then a sample of the as-processed SB6 will be taken and transferred to SRNL for measurement of these radionuclides. The results presented in this report are those necessary for DWPF to assess if the Tank 51 SB6 sample prepared at SRNL meets the requirements for the DWPF Radiological Program Evaluation, the DWPF Waste Acceptance Criteria evaluation, and the DWPF Solid Waste Characterization Program. The sample is the same as that on which the chemical composition was reported. Concentrations are given for thirty-four radionuclides along with total alpha and beta activity. Values for total gamma and total gamma plus beta activities are also calculated. Results also indicate that 99% of the Tc-99 and at least 90% of the I-129 that could have been in this sludge batch have been removed by chemical processing steps in the SRS Canyons or Tank Farm.

  11. Qualification of Daiichi Units 1, 2, and 3 Data for Severe Accident Evaluations - Process and Illustrative Examples from Prior TMI-2 Evaluations

    SciTech Connect (OSTI)

    Rempe, Joy Lynn; Knudson, Darrell Lee

    2014-09-01

    The accidents at the Three Mile Island Unit 2 (TMI-2) Pressurized Water Reactor (PWR) and the Daiichi Units 1, 2, and 3 Boiling Water Reactors (BWRs) provide unique opportunities to evaluate instrumentation exposed to severe accident conditions. Conditions associated with the release of coolant and the hydrogen burn that occurred during the TMI-2 accident exposed instrumentation to harsh conditions, including direct radiation, radioactive contamination, and high humidity with elevated temperatures and pressures. As part of a program initiated in 2012 by the Department of Energy Office of Nuclear Energy (DOE-NE), a review was completed to gain insights from prior TMI-2 sensor survivability and data qualification efforts. This initial review focused on the set of sensors deemed most important by post-TMI-2 instrumentation evaluation programs. Instrumentation evaluation programs focused on data required by TMI-2 operators to assess the condition of the reactor and containment and the effect of mitigating actions taken by these operators. In addition, prior efforts focused on sensors providing data required for subsequent forensic evaluations and accident simulations. To encourage the potential for similar activities to be completed for qualifying data from Daiichi Units 1, 2, and 3, this report provides additional details related to the formal process used to develop a qualified TMI-2 data base and presents data qualification details for three parameters: primary system pressure; containment building temperature; and containment pressure. As described within this report, sensor evaluations and data qualification required implementation of various processes, including comparisons with data from other sensors, analytical calculations, laboratory testing, and comparisons with sensors subjected to similar conditions in large-scale integral tests and with sensors that were similar in design to instruments easily removed from the TMI-2 plant for evaluations. As documented in this report, results from qualifying data for these parameters led to key insights related to TMI-2 accident progression. Hence, these selected examples illustrate the types of activities completed in the TMI-2 data qualification process and the importance of such a qualification effort. These details are documented in this report to facilitate implementation of similar process using data and examinations at the Daiichi Units 1, 2, and 3 reactors so that BWR-specific benefits can be obtained.

  12. AGR-3/4 Data Qualification Report for ATR Cycles 151A, 151B, 152A, 152B, 154A, and 154B

    SciTech Connect (OSTI)

    Binh T. Pham

    2014-02-01

    This data report provides the qualification status of Advanced Gas Reactor-3/4 (AGR-3/4) fuel irradiation experimental data from Advanced Test Reactor (ATR) Cycles 151A, 151B, 152A, 152B, 154A, and 154B, as recorded in the Nuclear Data Management and Analysis System (NDMAS). Of these cycles, ATR Cycle 152A is a low power cycle that occurred when the ATR core was briefly at low power. The irradiation data are not used for physics and thermal calculation, but the qualification status of these cycle data is still covered in this report. On the other hand, during ATR Cycles 153A (unplanned Outage cycle) and 153B (Power Axial Locator Mechanism [PALM] cycle), the AGR-3/4 was pulled out from the ATR core and stored in the canal to avoid being overheated. Therefore, qualification of the AGR-3/4 irradiation data from these 2 cycles was excluded in this report. By the end of ATR Cycle 154B, AGR-3/4 was irradiated for a total of 264.1 effective full power days. The AGR-3/4 data streams addressed in this report include thermocouple (TC) temperatures, sweep gas data (flow rates, pressure, and moisture content), and Fission Product Monitoring System (FPMS) data (release rates and release-to-birth rate ratios [R/Bs]) for each of the twelve capsules in the AGR-3/4 experiment. The final data qualification status for these data streams is determined by a Data Review Committee (DRC) composed of AGR technical leads, Sitewide Quality Assurance (QA), and NDMAS analysts. The DRC convened on February 12, 2014, reviewed the data acquisition process, and considered whether the data met the requirements for data collection as specified in QA-approved Very High Temperature Reactor (VHTR) Technology Development Office (TDO) data collection plans. The DRC also examined the results of NDMAS data testing and statistical analyses, and confirmed the qualification status of the data as given in this report.

  13. Trial-Run of a Junction-Box Attachment Test for Use in Photovoltaic Module Qualification: Preprint

    SciTech Connect (OSTI)

    Miller, D. C.; Deibert, S. L.; Wohlgemuth, J. H.

    2014-06-01

    Engineering robust adhesion of the junction box (j-box) is a hurdle typically encountered by photovoltaic module manufacturers during product development and manufacturing process control. There are historical incidences of adverse effects (e.g., fires) caused when the j-box/adhesive/module system has failed in the field. The addition of a weight to the j-box during the 'damp-heat,' 'thermal-cycle,' or 'creep' tests within the IEC qualification protocol is proposed to verify the basic robustness of the adhesion system. The details of the proposed test are described, in addition to a trial-run of the test procedure. The described experiments examine four moisture-cured silicones, four foam tapes, and a hot-melt adhesive used in conjunction with glass, KPE, THV, and TPE substrates. For the purpose of validating the experiment, j-boxes were adhered to a substrate, loaded with a prescribed weight, and then subjected to aging. The replicate mock-modules were aged in an environmental chamber (at 85 degrees C/85% relative humidity for 1000 hours; then 100 degrees C/<10% relative humidity for 200 hours) or fielded in Golden (CO), Miami (FL), and Phoenix (AZ) for one year. Attachment strength tests, including pluck and shear test geometries, were also performed on smaller component specimens.

  14. VERIFICATION OF THE DEFENSE WASTE PROCESSING FACILITY'S (DWPF) PROCESS DIGESTION METHOD FOR THE SLUDGE BATCH 7A QUALIFICATION SAMPLE

    SciTech Connect (OSTI)

    Click, D.; Edwards, T.; Jones, M.; Wiedenman, B.

    2011-03-14

    For each sludge batch that is processed in the Defense Waste Processing Facility (DWPF), the Savannah River National Laboratory (SRNL) performs confirmation of the applicability of the digestion method to be used by the DWPF lab for elemental analysis of Sludge Receipt and Adjustment Tank (SRAT) receipt samples and SRAT product process control samples. DWPF SRAT samples are typically dissolved using a room temperature HF-HNO{sub 3} acid dissolution (i.e., DWPF Cold Chem Method, see DWPF Procedure SW4-15.201) and then analyzed by inductively coupled plasma - atomic emission spectroscopy (ICP-AES). This report contains the results and comparison of data generated from performing the Aqua Regia (AR), Sodium peroxide/Hydroxide Fusion (PF) and DWPF Cold Chem (CC) method digestions of Sludge Batch 7a (SB7a) SRAT Receipt and SB7a SRAT Product samples. The SB7a SRAT Receipt and SB7a SRAT Product samples were prepared in the SRNL Shielded Cells, and the SRAT Receipt material is representative of the sludge that constituates the SB7a Batch or qualification composition. This is the sludge in Tank 51 that is to be transferred into Tank 40, which will contain the heel of Sludge Batch 6 (SB6), to form the Sb7a Blend composition.

  15. Literature review of environmental qualification of safety-related electric cables: Summary of past work. Volume 1

    SciTech Connect (OSTI)

    Subudhi, M.

    1996-04-01

    This report summarizes the findings from a review of published documents dealing with research on the environmental qualification of safety-related electric cables used in nuclear power plants. Simulations of accelerated aging and accident conditions are important considerations in qualifying the cables. Significant research in these two areas has been performed in the US and abroad. The results from studies in France, Germany, and Japan are described in this report. In recent years, the development of methods to monitor the condition of cables has received special attention. Tests involving chemical and physical examination of cable`s insulation and jacket materials, and electrical measurements of the insulation properties of cables are discussed. Although there have been significant advances in many areas, there is no single method which can provide the necessary information about the condition of a cable currently in service. However, it is possible that further research may identify a combination of several methods that can adequately characterize the cable`s condition.

  16. SLUDGE WASHING AND DEMONSTRATION OF THE DWPF FLOWSHEET IN THE SRNL SHIELDED CELLS FOR SLUDGE BATCH 6 QUALIFICATION

    SciTech Connect (OSTI)

    Pareizs, J.; Pickenheim, B.; Bannochie, C.; Billings, A.; Bibler, N.; Click, D.

    2010-10-01

    Prior to initiating a new sludge batch in the Defense Waste Processing Facility (DWPF), Savannah River National Laboratory (SRNL) is required to simulate this processing, including Chemical Process Cell (CPC) simulation, waste glass fabrication, and chemical durability testing. This report documents this simulation for the next sludge batch, Sludge Batch 6 (SB6). SB6 consists of Tank 12 material that has been transferred to Tank 51 and subjected to Low Temperature Aluminum Dissolution (LTAD), Tank 4 sludge, and H-Canyon Pu solutions. Following LTAD and the Tank 4 addition, Liquid Waste Operations (LWO) provided SRNL a 3 L sample of Tank 51 sludge for SB6 qualification. Pu solution from H Canyon was also received. SB6 qualification included washing the sample per LWO plans/projections (including the addition of Pu from H Canyon), DWPF CPC simulations, waste glass fabrication (vitrification), and waste glass characterization and chemical durability evaluation. The following are significant observations from this demonstration. Sludge settling improved slightly as the sludge was washed. SRNL recommended (and the Tank Farm implemented) one less wash based on evaluations of Tank 40 heel projections and projections of the glass composition following transfer of Tank 51 to Tank 40. Thorium was detected in significant quantities (>0.1 wt % of total solids) in the sludge. In past sludge batches, thorium has been determined by Inductively Coupled Plasma-Mass Spectroscopy (ICP-MS), seen in small quantities, and reported with the radionuclides. As a result of the high thorium, SRNL-AD has added thorium to their suite of Inductively Coupled Plasma-Atomic Emission Spectroscopy (ICP-AES) elements. The acid stoichiometry for the DWPF Sludge Receipt and Adjustment Tank (SRAT) processing of 115%, or 1.3 mol acid per liter of SRAT receipt slurry, was adequate to accomplish some of the goals of SRAT processing: nitrite was destroyed to below 1,000 mg/kg and mercury was removed to below the DWPF target with 750 g of steam per g of mercury. However, rheological properties did not improve and were above the design basis. Hydrogen generation rates did not exceed DWPF limits during the SRAT and Slurry Mix Evaporator (SME) cycles. However, hydrogen generation during the SRAT cycle approached the DWPF limit. The glass fabricated with the Tank 51 SB6 SME product and Frit 418 was acceptable with respect to chemical durability as measured by the Product Consistency Test (PCT). The PCT response was also predictable by the current durability models of the DWPF Product Composition Control System (PCCS). It should be noted, however, that in the first attempt to make glass from the SME product, the contents of the fabrication crucible foamed over. This may be a result of the SME product's REDOX (Reduction/Oxidation - Fe{sup 2+}/{Sigma}Fe) of 0.08 (calculated from SME product analytical results). The following are recommendations drawn from this demonstration. In this demonstration, at the request of DWPF, SRNL caustic boiled the SRAT contents prior to acid addition to remove water (to increase solids concentration). During the nearly five hours of caustic boiling, 700 ppm of antifoam was required to control foaming. SRNL recommends that DWPF not caustic boil/concentrate SRAT receipt prior to acid addition until further studies can be performed to provide a better foaming control strategy or a new antifoam is developed for caustic boiling. Based on this set of runs and a recently completed demonstration with the SB6 Waste Acceptance Product Specifications (WAPS) sample, it is recommended that DWPF not add formic acid at the design addition rate of two gallons per minute for this sludge batch. A longer acid addition time appears to be helpful in allowing slower reaction of formic acid with the sludge and possibly decreases the chance of a foam over during acid addition.

  17. Qualification of JEFF3.1.1 library for high conversion reactor calculations using the ERASME/R experiment

    SciTech Connect (OSTI)

    Vidal, J. F.; Noguere, G.; Peneliau, Y.; Santamarina, A.

    2012-07-01

    With its low CO{sub 2} production, Nuclear Energy appears to be an efficient solution to the global warming due to green-house effect. However, current LWR reactors are poor uranium users and, pending the development of Fast Neutron Reactors, alternative concepts of PWR with higher conversion ratio (HCPWR) are being studied again at CEA, first studies dating from the middle 80's. In these French designs, low moderation ratio has been performed by tightening the lattice pitch, achieving a conversion ratio of 0.8-0.9 with a MOX fuel coming from PWR UOX recycling. Theses HCPWRs are characterized by a harder neutron spectrum and the calculation uncertainties on the fundamental neutronics parameters are increased by a factor 3 regarding a standard PWR lattice, due to the major contribution of the Plutonium isotopes and of the epithermal energy range to the reaction rates. In order to reduce these uncertainties, a 3-year experimental validation program called ERASME has been performed by CEA from 1984 to 1986 in the EOLE reactor. Monte Carlo analysis of the ERASME/R experiments with the Monte Carlo code TRIPOLI4 allowed the qualification of the recommended JEFF.3.1.1 library for major neutronics parameters. K{sub eff} of the MOX under-moderated lattice is over-predicted by 440 {+-} 830 pcm (2{sigma}); the conversion ratio, indicator of the good use of uranium, is also slightly over-predicted: 2 % {+-} 4 % (2{sigma}) and the same for B4C absorber rods worth and soluble boron worth, over-predicted by 2 %, both in the 2 standard deviations range. The radial fission maps of heterogeneities (water-holes, B4C and fertile rods) are well reproduced: maximal (C-E)/E dispersion is 1.3 %, maximal power peak error is 2.7 %. The void reactivity worth is the only parameter poorly calculated with an overprediction of +12.4% {+-} 1.5%. ERASME/R analysis of MOX reactivity, void effect and spectral indexes will contribute to the reevaluation of {sup 241}Am and Plutonium isotopes nuclear data for the next library JEFF3.2. (authors)

  18. Mechanical Systems Qualification Standard

    Energy Savers [EERE]

    (IDIQ Attachment J-8) | Department of Energy Plan and Savings Calculations Methods Outline (IDIQ Attachment J-8) Measurement and Verification Plan and Savings Calculations Methods Outline (IDIQ Attachment J-8) Document outlines measurement and verification planning and savings calculation methods for an energy savings performance contract. Microsoft Office document icon mv_plan_outline.doc More Documents & Publications Post-Installation Report Outline (IDIQ Attachment J-9) Annual Report

  19. Ameresco ESCO Qualification Sheet

    Energy Savers [EERE]

    customer value and environmental sustainability through energy efficiency measures, alternative energy infrastructure solutions, and innovative facility renewal strategies....

  20. AGR-2 Data Qualification Report for ATR Cycles 151B-2, 152A, 152B, 153A, 153B and 154A

    SciTech Connect (OSTI)

    Binh T. Pham; Jeffrey J. Einerson

    2013-09-01

    This report documents the data qualification status of AGR-2 fuel irradiation experimental data from Advanced Test Reactor (ATR) Cycles 152A, 152B, 153A, 153B, and 154A, as recorded in the Nuclear Data Management and Analysis System (NDMAS). The AGR-2 data streams addressed include thermocouple (TC) temperatures, sweep gas data (flow rate, pressure, and moisture content), and fission product monitoring system (FPMS) data for each of the six capsules in the experiment. A total of 13,400,520 every minute instantaneous TC and sweep gas data records were received and processed by NDMAS for this period. Of these data, 8,911,791 records (66.5% of the total) were determined to be Qualified based on NDMAS accuracy testing and data validity assessment. For temperature, there were 4,266,081 records (74% of the total TC data) that were Failed due to TC instrument failures. For sweep gas flows, there were 222,648 gas flow records (2.91% of the flow data) that were Failed. The inlet gas flow failures due to gas flow cross-talk and leakage problems that occurred after Cycle 150A were corrected by using the same gas mixture in all six capsules and the Leadout. For FPMS data, NDMAS received and processed preliminary release rate and release-to-birth rate ratio (R/B) data for three reactor cycles (Cycles 149B, 150B, and 151A) . This data consists of 45,983 release rate records and 45,235 R/B records for the 12 radionuclides reported. The qualification status of these FPMS data has been set to In Process until receipt of Quality Assurance-approved data generator reports. All of the above data have been processed and tested using a SAS-based enterprise application software system, stored in a secure Structured Query Language database, made available on the NDMAS Web portal (http://ndmas.inl.gov), and approved by the INL STIM for release to both internal and appropriate external Very High Temperature Reactor Program participants.

  1. Mechanical qualification of the support structure for MQXF, the Nb3Sn low-β quadrupole for the high luminosity LHC

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Juchno, M.; Ambrosio, G.; Anerella, M.; Bajas, H.; Bajko, M.; Bourcey, N.; Cheng, D. W.; Felice, H.; Ferracin, P.; Grosclaude, P.; et al

    2016-01-26

    Within the scope of the High Luminosity LHC project, the collaboration between CERN and U.S. LARP is developing new low-β quadrupoles using the Nb3Sn superconducting technology for the upgrade of the LHC interaction regions. The magnet support structure of the first short model was designed and two units were fabricated and tested at CERN and at LBNL. The structure provides the preload to the collars-coils subassembly by an arrangement of outer aluminum shells pre-tensioned with water-pressurized bladders. For the mechanical qualification of the structure and the assembly procedure, superconducting coils were replaced with solid aluminum “dummy coils”, the structure wasmore » preloaded at room temperature, and then cooled-down to 77 K. Mechanical behavior of the magnet structure was monitored with the use of strain gauges installed on the aluminum shells, the dummy coils and the axial preload system. As a result, this paper reports on the outcome of the assembly and the cool-down tests with dummy coils, which were performed at CERN and at LBNL, and presents the strain gauge measurements compared to the 3D finite element model predictions.« less

  2. General Technical Base Qualification Standard

    Office of Environmental Management (EM)

    ... level knowledge of DOE P 226.1B, Department of Energy Oversight Policy, and its implementing Order DOE O 226.1B, Implementation of Department of Energy Oversight Policy. ...

  3. NGNP Fuel Qualification White Paper

    SciTech Connect (OSTI)

    David A. Petti

    2010-07-01

    The Japanese high temperature gas reactor program is centered on the High Temperature Engineering Test Reactor (HTTR), which has a thermal power of 30 MW and 950°C maximum coolant outlet temperature. The HTTR achieved criticality in November 1998 and has undergone a series of rise-to-power tests [Fujikawa 2004]. In December 2001, an outlet temperature of 850°C was achieved and in April 2004 a temperature of 950°C was achieved. As of July 2004, the reactor had operated for 224 effective full power days (EFPD). The planned core life cycle is 660 EFPD [Verfondern 2000]. It is planned to couple a high temperature process heat application to the HTTR through its intermediate heat exchanger in the future.

  4. Functional Area Qualification Standards Template

    Broader source: Energy.gov [DOE]

    This FAQS template has been derived from DOE FTCP Operational Plans over the years as a “best practice format” after FTCP member-composed teams have provided valuable recommendations on important FAQS elements.

  5. Photovoltaic Module Qualification Plus Testing

    SciTech Connect (OSTI)

    Kurtz, S.; Wohlgemuth, J.; Kempe, M.; Bosco, N.; Hacke, P.; Jordan, D.; Miller, D. C.; Silverman, T. J.; Phillips, N.; Earnest, T.; Romero, R.

    2013-12-01

    This report summarizes a set of test methods that are in the midst of being incorporated into IEC 61215 for certification of a module design or other tests that go beyond certification to establish bankability.

  6. Qualification of the Savannah River National Laboratories Coulometer, Model SRNL-Rev. 2 (Serial # SRNL-003 Coulometer) for use in Process 3401a, Plutonium Assay by Controlled Coulometer

    SciTech Connect (OSTI)

    Tandon, Lav; Colletti, Lisa M.; Drake, Lawrence R.; Lujan, Elmer J. W.; Garduno, Katherine

    2012-08-22

    This report discusses the process used to prove in the SRNL-Rev.2 coulometer for isotopic data analysis used in the special plutonium material project. In May of 2012, the PAR 173 coulometer system that had been the workhorse of the Plutonium Assay team since the early 1970s became inoperable. A new coulometer system had been purchased from Savannah River National Laboratory (SRNL) and installed in August of 2011. Due to funding issues the new system was not qualified at that time. Following the failure of the PAR 173, it became necessary to qualify the new system for use in Process 3401a, Plutonium Assay by Controlled Coulometry. A qualification plan similar to what is described in PQR -141a was followed. Experiments were performed to establish a statistical summary of the performance of the new system by monitoring the repetitive analysis of quality control sample, PEOL, and the assay of plutonium metals obtained from the Plutonium Exchange Program. The data for the experiments was acquired using work instructions ANC125 and ANC195. Figure 1 shows approximately 2 years of data for the PEOL material obtained using the PAR 173. The required acceptance criteria for the sample are that it returns the correct value for the quality control material of 88.00% within 2 sigma (95% Confidence Interval). It also must meet daily precision standards that are set from the historical data analysis of decades of data. The 2 sigma value that is currently used is 0.146 % as evaluated by the Statistical Science Group, CCS-6. The average value of the PEOL quality control material run in 10 separate days on the SRNL-03 coulometer is 87.98% with a relative standard deviation of 0.04 at the 95% Confidence interval. The date of data acquisition is between 5/23/2012 to 8/1/2012. The control samples are run every day experiments using the coulometer are carried out. It is also used to prove an instrument is in statistical control before any experiments are undertaken. The total number of replicate controls run with the new coulometer to date, is n=18. This value is identical to that calculated by the LANL statistical group for this material from data produced by the PAR 173 system over the period of October 2007 to May 2011. The final validation/verification test was to run a blind sample over multiple days. AAC participates in a plutonium exchange program which supplies blind Pu metal samples to the group on a regular basis. The Pu material supplied for this study was ran using the PAR 173 in the past and more recently with the new system. Table 1a contains the values determined through the use of the PAR 173 and Table 1b contains the values obtained with the new system. The Pu assay value obtained on the SRNL system is for paired analysis and had a value of 98.88+/-0.07% RSD at 95% CI. The Pu assay value (decay corrected to July 2012) of the material determined in prior measurements using the PAR173 is 99.05 +/- 0.06 % RSD at 95% CI. We believe that the instrument is adequate to meet the needs of the program.

  7. Neutronics qualification of the Jules Horowitz reactor fuel by interpretation of the VALMONT experimental program - Transposition of the uncertainties on the reactivity of JHR with JEF2.2 and JEFF3.1.1

    SciTech Connect (OSTI)

    Leray, O.; Hudelot, J. P.; Antony, M.; Doederlein, C.; Santamarina, A.; Bernard, D.; Vaglio-Gaudard, C.

    2011-07-01

    The new European material testing Jules Horowitz Reactor (JHR), currently under construction in Cadarache center (CEA France), will use LEU (20% enrichment in {sup 235}U) fuels (U{sub 3}Si{sub 2} for the start up and UMoAl in the future) which are quite different from the industrial oxide fuel, for which an extensive neutronics qualification database has been established. The HORUS3D/N neutronics calculation scheme, used for the design and safety studies of the JHR, is being developed within the framework of a rigorous verification-validation-qualification methodology. In this framework, the experimental VALMONT (Validation of Aluminium Molybdenum uranium fuel for Neutronics) program has been performed in the MINERVE facility of CEA Cadarache (France), in order to qualify the capability of HORUS3D/N to accurately calculate the reactivity of the JHR reactor. The MINERVE facility using the oscillation technique provides accurate measurements of reactivity effect of samples. The VALMONT program includes oscillations of samples of UAl{sub x}/Al and UMo/Al with enrichments ranging from 0.2% to 20% and Uranium densities from 2.2 to 8 g/cm{sup 3}. The geometry of the samples and the pitch of the experimental lattice ensure maximum representativeness with the neutron spectrum expected for JHR. By comparing the effect of the sample with the one of a known fuel specimen, the reactivity effect can be measured in absolute terms and be compared to computational results. Special attention was paid to the rigorous determination and reduction of the experimental uncertainties. The calculational analysis of the VALMONT results was performed with the French deterministic code APOLLO2. A comparison of the impact of the different calculation methods, data libraries and energy meshes that were tested is presented. The interpretation of the VALMONT experimental program allowed the qualification of JHR fuel UMoAl8 (with an enrichment of 19.75% {sup 235}U) by the Minerve-dedicated interpretation tool: PIMS. The effect of energy meshes and evaluations put forward the JEFF3.1.1/SHEM scheme that leads to a better calculation of the reactivity effect of VALMONT samples. Then, in order to quantify the impact of the uncertainties linked to the basic nuclear data, their propagation from the cross section measurement to the final computational result was analysed in a rigorous way by using a nuclear data re-estimation method based on Gauss-Newton iterations. This study concludes that the prior uncertainties due to nuclear data (uranium, aluminium, beryllium and water) on the reactivity of the Begin Of Cycle (BOC) for the JHR core reach 1217 pcm at 2{sigma}. Now, the uppermost uncertainty on the JHR reactivity is due to aluminium. (authors)

  8. Subsea control system undergoes qualification test

    SciTech Connect (OSTI)

    Lia, A.

    1996-10-01

    The booming market for subsea equipment has spawned the development of new control technologies. Proper testing is required before incorporating these new systems in production applications. In early 1996, French firm ECA began a 6-month test of a lightweight subsea control system at the offshore premises of Frame Engineering in Bergen, Norway. The purpose of the 6-month experiment is to test the various components of a control system. These include the tele-operated valve (TOV), a 66-lb (30-kg) module which provides electrohydraulic control of a Christmas tree, the subsea hydro-electric pump (HPU), the electrical inductively coupled link which provides power and data transmission on a single wire cable, and the subsea mateable optical connector.

  9. Memorandum, Technical Qualification Program Accreditation Incentives |

    Energy Savers [EERE]

    Department of Energy Protective Force Career Options Committee - July 23, 2009 Memorandum, Protective Force Career Options Committee - July 23, 2009 On March 31,2009, this office commissioned a study to examine career opportunities and retirement options for the Department of Energy (DOE) protective force members. On March 3 1,2009, this office commissioned a study to examine career opportunities and retirement options for the Department of Energy (DOE) protective force members. The study

  10. Summary of Booster Development and Qualification Report

    SciTech Connect (OSTI)

    Francois, Elizabeth G.; Harry, Herbert H.; Hartline, Ernest L.; Hooks, Daniel E.; Johnson, Carl E.; Morris, John S.; Novak, Alan M.; Ramos, Kyle J.; Sanders, Victor E.; Scovel, Christina A.; Lorenz, Thomas; Wright, Mark; Botcher, Tod; Marx, Erin; Gibson, Kevin

    2012-06-21

    This report outlines booster development work done at Los Alamos National Laboratory from 2007 to present. The booster is a critical link in the initiation train of explosive assemblies, from complex devices like nuclear weapons to conventional munitions. The booster bridges the gap from a small, relatively sensitive detonator to an insensitive, but massive, main charge. The movement throughout the explosives development community is to use more and more insensitive explosive components. With that, more energy is needed out of the booster. It has to initiate reliably, promptly, powerfully and safely. This report is divided into four sections. The first provides a summary of a collaborative effort between LANL, LLNL, and AWE to identify candidate materials and uniformly develop a testing plan for new boosters. Important parameters and the tests required to measure them were defined. The nature of the collaboration and the specific goals of the participating partners has changed over time, but the booster development plan stands on its own merit as a complete description of the test protocol necessary to compare and qualify booster materials, and is discussed in its entirety in this report. The second section describes a project, which began in 2009 with the Department of Defense to develop replacement booster formulations for PBXN-7. Replacement of PBXN-7 was necessary because it contained Triaminotrinitrobenzene (TATB), which was becoming unavailable to the DoD and because it contained Cyclotrimethylenetrinitramine (RDX), which was sensitive and toxic. A LANL-developed explosive, Diaminoazoxyfurazan (DAAF), was an important candidate. This project required any replacement formulation be a drop-in replacement in existing munitions. This project was timely, in that it made use of the collaborative booster development project, and had the additional constraint of matching shock sensitivity. Additionally it needed to be a safety improvement, and a performance improvement, especially at cold temperatures. The requirements of this project necessitated novel test development and a different approach to ranking booster qualities. Results of this project have been documented to the DoD and the relevant portions are included within. The third section of this booster report outlines testing related to main charge initiation merit. Initiability can be evaluated by looking at critical diameter, run distance, and shock sensitivity. Once a booster is initiated, it needs to be powerful enough to initiate the main charge symmetrically and evenly. Main charge initiability is evaluated directly by observing detonation wave symmetry, curvature, and first break out over the surface of a charge. Furthermore it must be insensitive to accidents and insults, and safe and reliable across a range of temperatures. These effects, tests, and results will be discussed individually in the context of DAAF and other explosives similarly tested. The last section provides a conclusion and summary of our experimental work and recommendations for the path forward. References and additional supporting documentation and results are provided in the appendices at the end of this report.

  11. Aviation Safety Officer Functional Area Qualification Standard

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    ... It should be noted that the competencies of management and leadership, general technical knowledge, regulations, administrative capability, and assessment and oversight are all ...

  12. Aviation Manager Functional Area Qualification Standard

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    ... It should be noted that the competencies of management and leadership, general technical knowledge, regulations, administrative capability, and assessment and oversight are all ...

  13. Functional Area Qualification Standards | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Technical Base DOE-STD-1146-2007 (Reaffirmed 2015) 2015-03 Industrial Hygiene DOE-STD-1138-2007 2007-11 Instrumentation and Control DOE-STD-1162-2013 2013-06 Mechanical Systems ...

  14. Occupational Safety Functional Area Qualification Standard

    Office of Environmental Management (EM)

    ... Explain how DOE P 226.1B, Department of Energy Oversight Policy and DOE O 226.1B, Implementation of Department of Energy Oversight Policy incorporate quality principles. Mandatory ...

  15. Facility Maintenance Management Functional Area Qualification...

    Office of Environmental Management (EM)

    ... DOE O 433.1B and in accordance with DOE O 226.1B. B. Review submitted NMMP description ... facility maintenance management. 1. DOE O 226.1B, Implementation of Department of Energy ...

  16. Nuclear Safety Specialist FTCP Functional Area Qualification...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    ... Discuss the application of the Center for Chemical Process Safety's Guidelines for Hazard ... DOE-STD-1104-2014. Objective B.: Perform reviews and determine the adequacy of the ...

  17. Industrial Hygiene Functional Area Qualification Standard

    Energy Savers [EERE]

    Barriers to Industrial Energy Efficiency Report to Congress June 2015 United States Department of Energy Washington, DC 20585 Department of Energy | June 2015 Message from the Assistant Secretary The industrial sector has shown steady progress in improving energy efficiency over the past few decades and energy efficiency improvements are expected to continue. Studies suggest, however, that there is potential to accelerate the rate of adopting energy efficient technologies and practices that

  18. Technical Qualifications for Treating Photovoltaic Assets as...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    operation of a business are mutually exclusive terms. Therefore, to establish whether a piece of property should be considered realty, it must be determined which term best applies...

  19. TRANSPORTATION AND TRAFFIC MANAGEMENT QUALIFICATION STANDARD...

    Office of Environmental Management (EM)

    a familiarity level knowledge of chemical terms related to transportation as ... action tracking system CCP commercial chemical product CFR Code of Federal Regulations ...

  20. FTCP Functional Area Qualification Standards - TEMPLATE

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    certifications, and in some cases, a knowledge sampling obtained through written andor oral examinations. Equivalencies must be granted in accordance with the TQP plan of the...

  1. Quality Assurance Functional Area Qualification Standard

    Energy Savers [EERE]

    Quadrennial Technology Review Workshops Quadrennial Technology Review Workshops PDF icon Department of Energy Quadrennial Technology Review Building &amp; Industrial Efficiency Workshop PDF icon Department of Energy Quadrennial Technology Review Alternative Fuels Workshop PDF icon VehicleEfficiencyElectrificationPortfolio.pdf PDF icon Department of Energy Quadrennial Technology Review Clean Electricity Workshop PDF icon Department of Energy Quadrennial Technology Review Grid Modernization

  2. Radiation Protection Functional Area Qualification Standard

    Energy Savers [EERE]

    Energy 2/11 Radiation Monitoring Data from Fukushima Area - 3/22/11 This data was recorded from DOE's Aerial Monitoring System as well as ground detectors deployed along with its Consequence Management Response Teams. File AMS_Data_for_USDoS__March22_1530_JLC.pptx More Documents & Publications Radiation Monitoring Data from Fukushima Area - 3/25/11 Radiation Monitoring Data from Fukushima Area Radiation Monitoring Data from Fukushima Area - 4/4 Energy

    5/11 Radiation Monitoring

  3. FPL Energy Services ESCO Qualification Sheet

    Energy Savers [EERE]

    8.1 million 1,211,441 HVAC, Energy Management Control System, Central Chiller Plant, Demand Response Programs Kennedy Space Center 6.8 million 1,790,328 HVAC, Controls,...

  4. Environmental Compliance Functional Area Qualification Standard

    Energy Savers [EERE]

    Nationwide Greenhouse Gas Emissions | Department of Energy Environmental Assessment of Plug-In Hybrid Electric Vehicles Volume 1: Nationwide Greenhouse Gas Emissions Environmental Assessment of Plug-In Hybrid Electric Vehicles Volume 1: Nationwide Greenhouse Gas Emissions In the most comprehensive environmental assessment of electric transportation to date, the Electric Power Research Institute (EPRI) and the Natural Resources Defense Council (NRDC) are examining the greenhouse gas emissions

  5. FAQS Qualification Card - Transportation and Traffic Management |

    Office of Environmental Management (EM)

    Boost Industrial Efficiency | Department of Energy FACT SHEET: Energy Department Actions to Deploy Combined Heat and Power, Boost Industrial Efficiency FACT SHEET: Energy Department Actions to Deploy Combined Heat and Power, Boost Industrial Efficiency October 21, 2013 - 11:30am Addthis News Media Contact (202) 586-4940 Underscoring President Obama's Climate Action Plan to cut harmful emissions and double energy efficiency, the Energy Department is taking action to develop the next

  6. Advanced Qualification of Additive Manufacturing Workshop

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Cost: 250 Registration fee Sponsors: Los Alamos National Laboratory - NSECIMS, MaRIE Hotel Reservations: Guests can begin booking reservations at La Fonda online or by...

  7. Aviation Safety Officer, Functional Area Qualification Standard

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2010-01-20

    The Aviation Safety Officer FAQS establishes common functional area competency requirements for all DOE aviation safety personnel who provide assistance, or direction, guidance, oversight, or evaluation of contractor technical activities that could impact the safe operation of DOE’s facilities.

  8. Aviation Manager Functional Area Qualification Standard

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2009-12-09

    The Aviation Manager FAQS establishes common functional area competency requirements for all DOE Aviation Manager personnel who provide assistance, direction, guidance, oversight, or evaluation of contractor technical activities that could impact the safe operation of DOE’s defense nuclear facilities.

  9. NNSA PACKAGE CERTIFICATION ENGINEER QUALIFICATION STANDARD REFERENCE...

    Office of Environmental Management (EM)

    ... OTA offsite transportation authorization OTC offsite transportation certificate PAAA ... Discuss the purposes of the OTC and the OTA and how they differ. Describe the information ...

  10. FAQS Qualification Card - Confinement Ventilation and Process...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in ...

  11. Criticality Safety Functional Area Qualification Standard

    Energy Savers [EERE]

    Capability Panel consists of senior U.S. Department of Energy (DOE) managers responsible for overseeing the Federal Technical Capability Program. This Panel is responsible ...

  12. Personnel Selection, Training, Qualification, and Certification...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    DOE Nuclear Facilities by Sam Rosenbloom Functional areas: Administrative Change, Defense Nuclear Facility Safety and Health Requirement, Safety, Training The order establishes...

  13. FAQS Gap Analysis Qualification Card - Environmental Restoration |

    Office of Environmental Management (EM)

    | Department of Energy FACT SHEET: Clean Coal University Research Awards and Project Descriptions FACT SHEET: Clean Coal University Research Awards and Project Descriptions As part of President Obama's all-of-the-above approach to American energy, the Energy Department announced on June 6, 2012, that nine universities have won awards for research projects that will continue to support innovation and development of clean coal technologies. This fact sheet includes detailed project

  14. Fire Protection Engineering Functional Area Qualification Standard...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    EVALUATION REQUIREMENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 CONTINUING EDUCATION, TRAINING AND PROFICIENCY REQUIREMENTS . ...

  15. Advanced Qualification of Additive Manufacturing Workshop

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Systems Using Hardware-in-the-Loop (Poster) (Conference) | SciTech Connect Advanced Platform for Development and Evaluation of Grid Interconnection Systems Using Hardware-in-the-Loop (Poster) Citation Details In-Document Search Title: Advanced Platform for Development and Evaluation of Grid Interconnection Systems Using Hardware-in-the-Loop (Poster) This poster describes a Grid Interconnection System Evaluator (GISE) that leverages hardware-in-the-loop (HIL) simulation techniques to rapidly

  16. Technical Qualifications and Federal Technical Capabilities Program...

    Office of Environmental Management (EM)

    more tedious overall and time consuming than the process of evaluating via the oral evaluation (OE) or observed performance (OP) method. The criterion was met. Objective:...

  17. Constellation NewEnergy ESCO Qualification Sheet

    Energy Savers [EERE]

    and selling Renewable Energy Credits. Constellation was a recent recipient of the DOE Green Power Leadership Award for innovation in providing our customers with renewable...

  18. AGC-3 IRRADIATION DATA QUALIFICATION FINAL REPORT

    SciTech Connect (OSTI)

    Hull, Laurence

    2014-08-01

    All thermocouples functioned throughout the AGC-3 experiment. There was one interval between Dec 18, 2012 and Dec 20, 2012 where 10 NULL values were reported for various thermocouples. These NULL values were deleted from the database. All temperature data are Qualified. During Oct and Nov 2013, 135,849 helium and argon gas flow values were below 0. These negative gas flow values are not correct and are Failed. The remaining argon, helium, and total gas flow data are within expected ranges and are Qualified. Total gas flow was approximately 50 sccm through the capsule. Helium gas flow was briefly increased to 100 sccm during reactor shutdowns. At the start of the experiment, moisture in the outflow gas line was stuck at a constant value of 335.6174 ppmv for the first cycle. When the capsule was reinstalled in the reactor for Cycle 154B, a new moisture filter was installed. Moisture data from Cycle 152B are Failed. All moisture data from the final three cycles are Qualified. Graphite creep specimens were subjected to one of two loads, 393 lbf or 589 lbf. The experiment plan included three loads, but problems with gas leaks in the rams applying the load to the stacks resulted in lower loads being applied to some of the stacks. While the loads applied are not the loads in the plan, the loads were consistently applied throughout the experiment. Therefore the reported loads are accurate and can be used in analysis of graphite creep. Loads were consistently within 5% of the specified values throughout the experiment. Stack displacement increased consistently throughout the experiment with total displacement ranging from 1 to 1.25 inches. No anomalous values were identified. During reactor outages, a set of pneumatic rams was used to raise the stacks of graphite creep specimens to ensure the specimens had not become stuck within the test train. This stack raising was performed three times; all stacks were raised successfully each time. The load and displacement data are Qualified.

  19. Quality Assurance Functional Area Qualification Standard - DOE...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    establishes common functional area competency requirements for DOE personnel who provide assistance, direction, guidance, oversight, or evaluation of contractor technical QA...

  20. Quality Assurance Functional Area Qualification Standard - DOE...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    common functional area competency requirements for all DOE QA personnel who provide assistance, direction, guidance, oversight, or evaluation of contractor technical...

  1. Test plan for: TSAP bit qualification: Temperature criteria

    SciTech Connect (OSTI)

    Ralston, G.L.

    1995-10-23

    This is the Test Plan for acquiring TSAP bit temperature performance data. Hanford Site waste tanks are currently being sampled by several methods. One of these, Rotary Mode Core Sampling (RMCS), uses a cutting bit/sample tube arrangement to obtain core samples of tank contents. Recent efforts to improve sample recovery have resulted in a new bit/sample tube design. Prior to field use, bit performance in two key areas needs to be tested. These areas are: penetration into steel plate, and a temperature rise as a function of downforce, rpm, and time. A performance test in the above two areas was conducted in August, 1995. Based on a review of that test activity, selected follow-on testing is planned to confirm data obtained in the temperature area. The results of both test activities will then be released as a single test report.

  2. Qualifications of Candle Filters for Combined Cycle Combustion Applications

    SciTech Connect (OSTI)

    Tomasz Wiltowski

    2008-08-31

    The direct firing of coal produces particulate matter that has to be removed for environmental and process reasons. In order to increase the current advanced coal combustion processes, under the U.S. Department of Energy's auspices, Siemens Westinghouse Power Corporation (SWPC) has developed ceramic candle filters that can operate at high temperatures. The Coal Research Center of Southern Illinois University (SIUC), in collaboration with SWPC, developed a program for long-term filter testing at the SIUC Steam Plant followed by experiments using a single-filter reactor unit. The objectives of this program funded by the U.S. Department of Energy were to identify and demonstrate the stability of porous candle filter elements for use in high temperature atmospheric fluidized-bed combustion (AFBC) process applications. These verifications were accomplished through extended time slipstream testing of a candle filter array under AFBC conditions using SIUC's existing AFBC boiler. Temperature, mass flow rate, and differential pressure across the filter array were monitored for a duration of 45 days. After test exposure at SIUC, the filter elements were characterized using Scanning Electron Microscopy and BET surface area analyses. In addition, a single-filter reactor was built and utilized to study long term filter operation, the permeability exhibited by a filter element before and after the slipstream test, and the thermal shock resilience of a used filter by observing differential pressure changes upon rapid heating and cooling of the filter. The data acquired during the slipstream test and the post-test evaluations demonstrated the suitability of filter elements in advanced power generation applications.

  3. Technical Qualification Program Self-Assessment Report - Richland...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    related to the technical support, management, oversight, or operation possess the necessary knowledge, skills, and abilities to perform their assigned duties and responsibilities. ...

  4. Next Generation Nuclear Plant Materials Selection and Qualification Program Plan

    SciTech Connect (OSTI)

    R. Doug Hamelin; G. O. Hayner

    2004-11-01

    The U.S. Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design is a graphite-moderated, helium-cooled, prismatic or pebble bed thermal neutron spectrum reactor with an average reactor outlet temperature of at least 1000 C. The NGNP will use very high burn up, lowenriched uranium, TRISO-Coated fuel in a once-through fuel cycle. The design service life of the NGNP is 60 years.

  5. Civil/Structural Engineering Functional Area Qualification Standard

    Office of Environmental Management (EM)

    ... Supporting Knowledge andor Skills: a. Discuss the provisions of DOE O 226.1B, Department of Energy Oversight Policy related to: 1) the role of civilstructural engineering ...

  6. Technical Qualification Program Accreditation Report- Nevada Site Office

    Broader source: Energy.gov [DOE]

    This report documents the activities and results of the Accreditation Review Team evaluation of the NSO TQP for the Accreditation Board.

  7. Safety Software Quality Assurance Functional Area Qualification Standard

    Energy Savers [EERE]

    of Energy Safety Planning Guidance for Hydrogen and Fuel Cell Projects Safety Planning Guidance for Hydrogen and Fuel Cell Projects Hydrogen and fuel cell project safety by U.S. Department of Energy, Fuel Cell Technologies Program PDF icon safety_guidance.pdf More Documents & Publications Safety Planning Guidance for Hydrogen and Fuel Cell Projects H2 Refuel H-Prize Safety Guidance Webinar H2 Refuel H-Prize Safety Guidance Webinar H2 Safety Snapshot - Vol. 2, Issue 2, July 2011

    2-2011

  8. 40 MM Grenade Launcher Qualification Requirements at Department...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    launcher, which utilizes high explosive ammunition to defeat adversary personnel and equipment. A number of Department sites have procured these weapons. PDF icon 40 MM...

  9. An overview of component qualification using Bayesian statistics...

    Office of Scientific and Technical Information (OSTI)

    Example problems with solutions have been supplied as a learning aid. Bold letters are ... COMPUTING, AND INFORMATION SCIENCE; LEARNING; STATISTICS; MATHEMATICS Word Cloud More ...

  10. Technical Qualification Program Accreditation Report- NNSA Service Center

    Broader source: Energy.gov [DOE]

    This report documents the activities of the Accreditation Review Team and the results of its evaluation of the NNSA Service Center TQP for the TQP Accreditation Board.

  11. Central Characterization Program (CCP) Training and Qualification Plan

    Broader source: Energy.gov [DOE]

    Supporting Technical Document for the Radiological Release Accident Investigation Report (Phase II Report)

  12. Model Energy Service Company Pre-Qualification Contract

    Broader source: Energy.gov [DOE]

    This page contains information and documents for creating a contract between an Energy Service Company and a state energy office (or other entity managing a performance contracting program).

  13. QP-7.1 Supplier Qualification Rev0.pdf

    Office of Environmental Management (EM)

  14. Qualification of the Joints for the ITER Central Solenoid

    SciTech Connect (OSTI)

    Martovetsky, N; Berryhill, A; Kenney, S

    2011-09-01

    The ITER Central Solenoid has 36 interpancake joints, 12 bus joints, and 12 feeder joints in the magnet. The joints are required to have resistance below 4 nOhm at 45 kA at 4.5 K. The US ITER Project Office developed two different types of interpancake joints with some variations in details in order to find a better design, qualify the joints, and establish a fabrication process. We built and tested four samples of the sintered joints and two samples with butt-bonded joints (a total of eight joints). Both designs met the specifications. Results of the joint development, test results, and selection of the baseline design are presented and discussed in the paper. The ITER Central Solenoid (CS) consists of six modules. Each module is composed of six wound hexapancakes and one quadrapancake. The multipancakes are connected electrically and hydraulically by in-line interpancake joints. The joints are located at the outside diameter (OD) of the module. Cable in conduit conductor (CICC) high-current joints are critical elements in the CICC magnets. In addition to low resistivity, the CS joints must fit a space envelope equivalent to the regular conductor cross section and must have low hydraulic impedance and enough structural strength to withstand the hoop and compressive forces during operation, including cycling. This paper is the continuation of the work reported on the intermodule joints.

  15. Safety Software Quality Assurance Functional Area Qualification Standard

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2011-02-10

    This SSQA FAQS identifies the minimum technical competency requirements for DOE personnel who have a responsibility for safety software. Although there may be other competency requirements associated with the positions held by DOE personnel, this technical FAQS is limited to identifying the specific technical competencies required throughout all defense nuclear facilities

  16. Nuclear Explosive Safety Study Functional Area Qualification Standard

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2010-05-27

    A Nuclear Explosive Safety Study (NESS) is performed on all DOE Nuclear Explosive Operations (NEOs) in accordance with DOE O 452.1D, Nuclear Explosive and Weapon Surety Program; DOE O 452.2D, Nuclear Explosive Safety; and DOE M 452.2-2, Nuclear Explosive Safety Evaluation Processes.

  17. New geothermal site identification and qualification. Final report

    SciTech Connect (OSTI)

    Not Available

    2004-04-01

    This study identifies remaining undeveloped geothermal resources in California and western Nevada, and it estimates the development costs of each. It has relied on public-domain information and such additional data as geothermal developers have chosen to make available. Reserve estimation has been performed by volumetric analysis with a probabilistic approach to uncertain input parameters. Incremental geothermal reserves in the California/Nevada study area have a minimum value of 2,800 grosss MW and a most-likely value of 4,300 gross MW. For the state of California alone, these values are 2,000 and 3,000 gross MW, respectively. These estimates may be conservative to the extent that they do not take into account resources about which little or no public-domain information is available. The average capital cost of incremental generation capacity is estimated to average $3,100/kW for the California/Nevada study area, and $2,950/kW for the state of California alone. These cost estimates include exploration, confirmation drilling, development drilling, plant construction, and transmission-line costs. For the purposes of this study, a capital cost of $2,400/kW is considered competitive with other renewable resources. The amount of incremental geothermal capacity available at or below $2,400/kW is about 1,700 gross MW for the California/Nevada study area, and the same amount (within 50-MW rounding) for the state of California alone. The capital cost estimates are only approximate, because each developer would bring its own experience, bias, and opportunities to the development process. Nonetheless, the overall costs per project estimated in this study are believed to be reasonable.

  18. Technical Qualification Program Accreditation Report- Sandia Site Office

    Broader source: Energy.gov [DOE]

    This report documents the activities of the Accreditation Review Team and the results of its evaluation of the SSO TQP for the Accreditation Board.

  19. Technical Qualification Program Reaccreditation Report- Sandia Site Office

    Broader source: Energy.gov [DOE]

    This report documents the activities and results of the Reaccreditation Review Team evaluation of the SSO TQP for the Reaccreditation Board.

  20. Electrical Systems And Safety Oversight Functional Area Qualification...

    Office of Environmental Management (EM)

    ... fundamentals * Protection device fundamentals DOE-STD-1170-2007 38 38. Electrical ... Electrical Safety Handbook; and 10 CFR 851, Worker Safety and Health Program. ...

  1. NNSA Package Certification Engineer Functional Area Qualification Standard

    Energy Savers [EERE]

    Department of Energy Highly Enriched Uranium Removal Featured on The Rachel Maddow Show NNSA Highly Enriched Uranium Removal Featured on The Rachel Maddow Show March 22, 2012 - 11:37am Addthis NNSA Administrator Thomas D’Agostino appeared live last night to break the news with Rachel Maddow that all remaining weapons-usable material has been successfully removed from Mexico. | Photo courtesy of the NNSA. NNSA Administrator Thomas D'Agostino appeared live last night to break the news

  2. Mechanical qualification of the support structure for MQXF, the...

    Office of Scientific and Technical Information (OSTI)

    European Organization for Nuclear Research (CERN), Geneva ... Type: Accepted Manuscript Journal Name: IEEE Transactions on ... Sponsoring Org: USDOE Office of Science (SC), High Energy ...

  3. Rocky Flats plant qualification testing for PRES Program

    SciTech Connect (OSTI)

    Kautz, D.D.; Tanaka, G.J.

    1994-06-24

    The authors recently completed several tests for EG&G - Rocky Flats, Inc. (RFP) to qualify welding procedures for the PRESS program. The welds that were tested were the Monel 400 to vanadium friction weld used in the Sail-A and the vanadium electron beam welds from the Mast Inner Subassembly. Tests were performed to determine the structural properties of the parts under conditions similar to those encountered in a weapons handling and storage environment. These tests included impact, tensile and pressure loading. Metallographic analysis was done where appropriate to document weld quality. All results were satisfactory for PRESS program purposes.

  4. NNSA Package Certification Engineer Functional Area Qualification Standard

    Office of Environmental Management (EM)

    Department of Energy NNSA Awards $4M for STEM Education, Launches New Partnership with HBCUs NNSA Awards $4M for STEM Education, Launches New Partnership with HBCUs October 12, 2012 - 3:12pm Addthis The National Nuclear Security Administration (NNSA) today announced that it has awarded $4 million in grants to 22 Historically Black Colleges and Universities (HBCUs) and six Department of Energy sites in key Science, Technology, Engineering and Mathematics (STEM) areas. This funding launches

  5. Technical Qualification Program Reaccreditation Report- Y-12 Site Office

    Broader source: Energy.gov [DOE]

    This report documents the results of the review of the National Nuclear Security Administration (NNSA) Y-12 Site Office (YSO) TQP by the TQP Reaccreditation Review Team.

  6. DOE-STD-1161-2003; Mechanical Systems Functional Area Qualification...

    Energy Savers [EERE]

    ... of Heating, Refrigeration and Air-Conditioning Engineers 1791 Tullie Circle, NE Atlanta, GA 30329 http:www.ashrae.org DOE-STD-1161-2003 30 INTENTIONALLY BLANK ...

  7. Technical Qualification Program Self-Assessment Report- Idaho Operations Office- 2011

    Broader source: Energy.gov [DOE]

    This TQP self-assessment was performed by a review team with extensive assessment experience. The assessment approach consisted of interviewing Managers, Division Directors, Team Leads, Qualifying Officials, and a representative sample of TQP participants, reviewing applicable records, reports, and IDMS documents, and observing continuing training activities.

  8. Final Report, Volume 2, The Development of Qualification Standards for Cast Duplex Stainless Steel

    SciTech Connect (OSTI)

    Russell, Steven, W.; Lundin, Carl, W.

    2005-09-30

    The scope of testing cast Duplex Stainless Steel (DSS) required testing to several ASTM specifications, while formulating and conducting industry round robin tests to verify and study the reproducibility of the results. ASTM E562 (Standard Test Method for Determining Volume Fraction by Systematic manual Point Count) and ASTM A923 (Standard Test Methods for Detecting Detrimental Intermetallic Phase in Wrought Duplex Austenitic/Ferritic Stainless Steels) were the specifications utilized in conducting this work. An ASTM E562 industry round robin, ASTM A923 applicability study, ASTM A923 industry round robin, and an ASTM A923 study of the effectiveness of existing foundry solution annealing procedures for producing cast DSS without intermetallic phases were implemented. In the ASTM E562 study, 5 samples were extracted from various cast austenitic and DSS in order to have varying amounts of ferrite. Each sample was metallographically prepared by UT and sent to each of 8 participants for volume fraction of ferrite measurements. Volume fraction of ferrite was measured using manual point count per ASTM E562. FN was measured from the Feritescope???????® and converted to volume fraction of ferrite. Results indicate that ASTM E562 is applicable to DSS and the results have excellent lab-to-lab reproducibility. Also, volume fraction of ferrite conversions from the FN measured by the Feritescope???????® were similar to volume fraction of ferrite measured per ASTM E562. In the ASTM A923 applicability to cast DSS study, 8 different heat treatments were performed on 3 lots of ASTM A890-4A (CD3MN) castings and 1 lot of 2205 wrought DSS. The heat treatments were selected to produce a wide range of cooling rates and hold times in order to study the suitability of ASTM A923 to the response of varying amounts on intermetallic phases [117]. The test parameters were identical to those used to develop ASTM A923 for wrought DSS. Charpy V-notch impact samples were extracted from the castings and wrought DSS and tested per ASTM A923 method B (Charpy impact test). Method A (sodium hydroxide etch test) was performed on one half of a fractured Charpy V-notch impact sample and Method C (ferric chloride corrosion weight loss test) was performed on another half. Test results for the three cast lots and one wrought lot indicate that ASTM A923 is relevant for detecting intermetallic phases in cast DSS. In the ASTM A923 round robin study, five laboratories conducted ASTM A923 Methods A & C on cast DSS material and the lab-to-lab reproducibility of the data was determined. Two groups of samples were sent to the participants. Group 1 samples were tested per ASTM A923 Method A, group 2 samples were tested by ASTM A923 Method C. Testing procedures for this round robin study were identical to those used in the ASTM A923 applicability study. Results from this round robin indicate that there is excellent lab-to-lab reproducibility of ASTM A923 with respect to cast DSS and that ASTM A923 could be expanded to cover both wrought and cast DSS. In the ASTM A923 study of the effectiveness of existing foundry solution annealing procedures for producing cast DSS without intermetallic phases, Ten heats of ASTM A890-4A (CD3MN) in the foundry solution annealed condition were tested per ASTM A923 Methods A, B, & C. Testing of these materials per ASTM A923 was used to determine if the foundry solution anneal procedures were adequate to completely eliminate any intermetallic phases, which may have precipitated during the casting and subsequent heat treatment processes. All heats showed no sign of intermetallic phase per Method A, passed minimum Charpy impact energy requirements per Method B (> 40 ft-lbs @ -40???????°C (-40???????°F)), and showed negligible weight loss per Method C (< 10 mdd). These results indicate that the solution annealing procedure used by foundri

  9. DOE-STD-1173-2003; Criticality Safety Functional Area Qualification...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    ... 15. Criticality safety personnel shall demonstrate a working level knowledge of the Nuclear Safety Management Rule, 10CFR830, requirements related to Unreviewed Safety Questions ...

  10. DOE-STD-1150-2002; Quality Assurance Functional Area Qualification...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    ... Describe methods for assuring that items remain properly identified throughout their life cycle. 3. QA personnel shall have a familiarity level knowledge of maintenance management ...

  11. DOE-STD-1165-2003; Aviation Manager Functional Area Qualification...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    ... AND LEVELS OF KNOWLEDGE ...... 19 DOE-STD-1165-2003 vi INTENTIONALLY BLANK DOE-STD-1165-2003 vii ACKNOWLEDGMENT The Office of Aviation Management (ME-2.4) and the ...

  12. DOE-STD-1179-2004; Technical Training Functional Area Qualification...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    ... shall demonstrate a working level knowledge of the requirements and attributes associated with an effectiv e records management system. Supporting Knowledge andor Skills a. ...

  13. DOE-STD-1174-2003; Radiation Protection Functional Area Qualification...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    ... of Energy employees 13. Radiation protection personnel shall demonstrate a familiarity level knowledge of radioactive waste management: Supporting Knowledge andor Skills a. ...

  14. Digial Technology Qualification Task 2 - Suitability of Digital Alternatives to Analog Sensors and Actuators

    SciTech Connect (OSTI)

    Ted Quinn; Jerry Mauck

    2012-09-01

    The next generation reactors in the U.S. are an opportunity for vendors to build new reactor technology with advanced Instrumentation and Control Systems (control rooms, DCS, etc.). The advances made in the development of many current generation operating reactors in other parts of the world are being used in the design and construction of new plants. These new plants are expected to have fully integrated digital control rooms, computerized procedures, integrated surveillance testing with on-line monitoring and a major effort toward improving the O&M and fault survivability of the overall systems. In addition the designs are also incorporating major improvements in the man-machine interface based on lessons learned in nuclear and other industries. The above relates primarily to the scope of supply in instrumentation and control systems addressed by Chapter 7 of the Standard Review Plan (SRP) NUREG-0800 (Reference 9.5), and the associated Balance of Plant (BOP) I&C systems. This does not relate directly to the actuator and motor, breaker, initiation circuitry, valve position, etc. which is the subject of this report and normally outside of the traditional Distributed Control System (DCS), for both safety and non-safety systems. The recommendations presented in this report will be used as input to I&C research programming for the implementation of lessons learned during the early phases of new build both for large light water reactors (LWR) and also small modular reactors (SMR). This report is intended to support current research plans and provide user (vendor, owner-operator) input to the optimization of these research plans.

  15. Technical Qualifications for Treating Photovoltaic Assets as Real Property by Real Estate Investment Trusts (REITs)

    SciTech Connect (OSTI)

    Feldman, D.; Mendelsohn, M.; Coughlin, J.

    2012-06-01

    It has been proposed that Real Estate Investment Trusts (REITs) have the potential to lower the cost and increase the adoption of photovoltaic systems (PV) by offering a more attractive source of capital. The purpose of this paper is to explain the fundamental physical characteristics of PV and compare them to the characteristics of 'real' property, to help determine whether REITs can own PV systems.

  16. Technical Qualification Program Self-Assessment Report- Oak Ridge Office- 2014

    Broader source: Energy.gov [DOE]

    This assessment, using criteria referred to in DOE O 426.1, Federal Technical Capability, is designed to evaluate the effectiveness of the implementation of the FTCP and the TQP at ORO. The purpose of this report is to document the results of ORO's self-assessment. The remaining sections of this report include the assessment scope and methodology, the results of the assessment, and supporting information.

  17. Welding and brazing qualifications (supplement to ASME Boiler and Pressure Vessel Code, Section IX)

    SciTech Connect (OSTI)

    Not Available

    1981-11-01

    This standard supplements the requirements of the 1980 edition of the ASME Boiler and Pressure Vessel Code (the Code), Section IX. When this standard is invoked or referenced, the applicable subsections of Section IX of the Code are also invoked or referenced. The paragraph numbers in this standard apply only to the 1980 edition of Section IX and its addenda. The user of this standard is responsible for obtaining and applying the edition and revision of this standard that supplement the edition and addenda of Section IX that are in legal effect at the time of use.

  18. Welding and brazing qualifications (supplement to ASME boiler and pressure vessel code, Section IX)

    SciTech Connect (OSTI)

    Not Available

    1980-01-01

    This standard supplements the requirements of the 1977 edition of the ASME Boiler and Pressure Vessel Code (the Code), Section IX. When this standard is invoked or referenced, the applicable subsections of Section IX of the Code are also invoked or referenced. The paragraph numbers apply only to the 1977 edition of Section IX and its addenda. The user of this standard is responsible for obtaining and applying the edition and revision of this standard that supplement the edition and Addenda of Section IX that are in legal effect at the time of use.

  19. Technical Qualification Program Self-Assessment Report- Savannah River Operations Office- 2010

    Broader source: Energy.gov [DOE]

    A set of disciplined Criteria, Review, and Approach Documents (CRADs) were developed by the Team Leader utilizing criteria and objectives provided on the FTCP website. Specific "lines of inquiry" were tailored to the organization and assessment processes of the DOE-SR.

  20. Final Report, Volume 2, The Development of Qualification Standards for Cast Duplex Stainless Steel

    SciTech Connect (OSTI)

    Russell, Steven, W.; Lundin, Carl, D.

    2005-09-30

    The scope of testing cast Duplex Stainless Steel (DSS) required testing to several ASTM specifications, while formulating and conducting industry round robin tests to verify and study the reproducibility of the results. ASTM E562 (Standard Test Method for Determining Volume Fraction by Systematic manual Point Count) and ASTM A923 (Standard Test Methods for Detecting Detrimental Intermetallic Phase in Wrought Duplex Austenitic/Ferritic Stainless Steels) were the specifications utilized in conducting this work. An ASTM E562 industry round robin, ASTM A923 applicability study, ASTM A923 industry round robin, and an ASTM A923 study of the effectiveness of existing foundry solution annealing procedures for producing cast DSS without intermetallic phases were implemented. In the ASTM E562 study, 5 samples were extracted from various cast austenitic and DSS in order to have varying amounts of ferrite. Each sample was metallographically prepared by UT and sent to each of 8 participants for volume fraction of ferrite measurements. Volume fraction of ferrite was measured using manual point count per ASTM E562. FN was measured from the Feritescope{reg_sign} and converted to volume fraction of ferrite. Results indicate that ASTM E562 is applicable to DSS and the results have excellent lab-to-lab reproducibility. Also, volume fraction of ferrite conversions from the FN measured by the Feritescope{reg_sign} were similar to volume fraction of ferrite measured per ASTM E562. In the ASTM A923 applicability to cast DSS study, 8 different heat treatments were performed on 3 lots of ASTM A890-4A (CD3MN) castings and 1 lot of 2205 wrought DSS. The heat treatments were selected to produce a wide range of cooling rates and hold times in order to study the suitability of ASTM A923 to the response of varying amounts on intermetallic phases [117]. The test parameters were identical to those used to develop ASTM A923 for wrought DSS. Charpy V-notch impact samples were extracted from the castings and wrought DSS and tested per ASTM A923 method B (Charpy impact test). Method A (sodium hydroxide etch test) was performed on one half of a fractured Charpy V-notch impact sample and Method C (ferric chloride corrosion weight loss test) was performed on another half. Test results for the three cast lots and one wrought lot indicate that ASTM A923 is relevant for detecting intermetallic phases in cast DSS. In the ASTM A923 round robin study, five laboratories conducted ASTM A923 Methods A & C on cast DSS material and the lab-to-lab reproducibility of the data was determined. Two groups of samples were sent to the participants. Group 1 samples were tested per ASTM A923 Method A, group 2 samples were tested by ASTM A923 Method C. Testing procedures for this round robin study were identical to those used in the ASTM A923 applicability study. Results from this round robin indicate that there is excellent lab-to-lab reproducibility of ASTM A923 with respect to cast DSS and that ASTM A923 could be expanded to cover both wrought and cast DSS. In the ASTM A923 study of the effectiveness of existing foundry solution annealing procedures for producing cast DSS without intermetallic phases, Ten heats of ASTM A890-4A (CD3MN) in the foundry solution annealed condition were tested per ASTM A923 Methods A, B, & C. Testing of these materials per ASTM A923 was used to determine if the foundry solution anneal procedures were adequate to completely eliminate any intermetallic phases, which may have precipitated during the casting and subsequent heat treatment processes. All heats showed no sign of intermetallic phase per Method A, passed minimum Charpy impact energy requirements per Method B (> 40 ft-lbs {at} -40 C (-40 F)), and showed negligible weight loss per Method C (< 10 mdd). These results indicate that the solution annealing procedure used by foundries is adequate to produce a product free from intermetallic phases.

  1. Proton and gamma irradiation of Fabry-Perot quantum cascade lasers for space qualification

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Myers, Tanya L.; Cannon, Bret D.; Brauer, Carolyn S.; Hansen, Stewart; Crowther, Blake

    2015-01-20

    Fabry-Perot quantum cascade lasers (QCLs) were characterized following irradiation by high energy (64 MeV) protons and Cobalt-60 gamma rays. Seven QCLs were exposed to radiation dosages that are typical for a space mission in which the total accumulated dosages from both radiation sources varied from 20 krad(Si) to 46.3 krad(Si). The QCLs did not show any measurable changes in threshold current or slope efficiency suggesting the suitability of QCLs for use in space-based missions.

  2. General Technical Base Qualification Equivalencies Based On Previous Experience, 12/12/95

    Broader source: Energy.gov [DOE]

    "The header lists the general field of experience, Commercial Nuclear Power or Navy Nuclear PowerProgram, with all other categories under these two areas. The subheader lists the position title of...

  3. Accelerated Stress Testing, Qualification Testing, HAST, Field Experience - What Do They All Mean? (Presentation)

    SciTech Connect (OSTI)

    Wohlgemuth, J.

    2013-05-01

    This presentation discusses the need for a set of tests for modules that would predict their long term-field performance.

  4. Qualification of the US made conductors for ITER TF magnet system

    SciTech Connect (OSTI)

    Martovetsky, N; Hatfield, D; Miller, J; Bruzzone, P; Stepanov, B; Seber, B

    2009-10-08

    The US Domestic Agency (USDA) is one of the six suppliers of the TF conductor for ITER. In order to qualify conductors according to ITER requirements we prepared several lengths of the CICC and short samples for testing in the SULTAN facility in CRPP, Switzerland. We also fully characterized the strands that were used in these SULTAN samples. Fabrication experience and test results are presented and discussed.

  5. Qualification of the US Made Conductors for ITER TF Magnet System

    SciTech Connect (OSTI)

    Martovetsky, Nicolai N; Hatfield, Daniel R; Miller, John R; Bruzzone, P.; Stepanov, B.; Seber, B.

    2010-01-01

    The US Domestic Agency (USDA) is one of the six suppliers of the TF conductor for ITER. In order to qualify conductors according to ITER requirements we prepared several lengths of the CICC and short samples for testing in the SULTAN facility in CRPP, Switzerland. We also fully characterized the strands that were used in these SULTAN samples. Fabrication experience and test results are presented and discussed.

  6. Corrosion test qualification for in situ stress relief of recirculating steam generators' U-bends

    SciTech Connect (OSTI)

    Monter, J.V.; Miglin, B.P.; Lauer, J.A.

    1989-02-01

    Highly stressed alloy 600 is susceptible to intergranular stress corrosion cracking (IGSCC) in high-purity water at nuclear steam generator (NSG) operating temperatures. Two regions in recirculating steam generators (RSG) are particularly prone to primary-side-initiated SCC: tube expansion transitions of the tube in the tubesheet and tight radii tube bends. One remedial measure to improve IGSCC in these regions is to heat the tubes and thus relieve the residual stresses that contribute significantly to the cracking problem. This article describes a corrosion test program using the accelerated SCC environments of sodium tetrathionate and sodium hydroxide to qualify an in situ stress-relief process for the most SCC-susceptible U-bends in an RSG.

  7. DOE-STD-1160-2003; Occupational Safety Functional Area Qualification...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    ... N.J. Atkins RL (Team Lead) R. C. Caummisar ID Y. B. Gentry SR T. C. Gepner EM J. C. Greenberg ID D. W. Harvey NS T. E. Krietz EM J. O. Low AL A. Maniez SR J. G. Mullins OR L. G. ...

  8. QP-2.1 Personnel Training and Qualification Rev0.pdf

    Office of Environmental Management (EM)

  9. Technical Qualification Program Self-Assessment Report- Idaho Operations Office- 2014

    Broader source: Energy.gov [DOE]

    This TQP self-assessment was performed by a review team with extensive assessment experience. The team lead has participated on past TQP Accreditation reviews and team members are currently qualified in diverse TQP functional areas. The TQP records coordinator assisted on the review team.

  10. A high voltage test stand for electron gun qualification for LINACs

    SciTech Connect (OSTI)

    Wanmode, Yashwant D.; Mulchandani, J.; Acharya, M.; Bhisikar, A.; Singh, H.G.; Shrivastava, Purushottam

    2011-07-01

    An electron gun lest stand has been developed at RRCAT. The test stand consists of a high voltage pulsed power supply, electron gun filament supply, grid supply, UHV system and electron gun current measurement system. Several electron guns developed indigenously were evaluated on this test stand. The shielding is provided for the electron gun set up. Electron gun tests can be tested upto 55 kV with pulse width of 15 microsecs and pulse repetition rates up to 200 Hz. The technical details of the subsystems are furnished and results of performance of the test stand have been reported in this paper. (author)

  11. Supplemental Immobilization Cast Stone Technology Development and Waste Form Qualification Testing Plan

    SciTech Connect (OSTI)

    Westsik, Joseph H.; Serne, R. Jeffrey; Pierce, Eric M.; Cozzi, Alex; Chung, Chul-Woo; Swanberg, David J.

    2013-05-31

    The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is being constructed to treat the 56 million gallons of radioactive waste stored in 177 underground tanks at the Hanford Site. The WTP includes a pretreatment facility to separate the wastes into high-level waste (HLW) and low-activity waste (LAW) fractions for vitrification and disposal. The LAW will be converted to glass for final disposal at the Integrated Disposal Facility (IDF). The pretreatment facility will have the capacity to separate all of the tank wastes into the HLW and LAW fractions, and the HLW Vitrification Facility will have the capacity to vitrify all of the HLW. However, a second immobilization facility will be needed for the expected volume of LAW requiring immobilization. A number of alternatives, including Cast Stone—a cementitious waste form—are being considered to provide the additional LAW immobilization capacity.

  12. DOE-STD-1170-2003; Electrical Systems Functional Area Qualification...

    Energy Savers [EERE]

    ... knowledge of safety and health fundamentals related to electrical systems and components. ... * Low-voltage circuit breaker fundamentals * Ground-fault protection fundamentals ...

  13. DOE-STD-1146-2001; General Technical Base Qualification Standard...

    Office of Environmental Management (EM)

    NUCLEAR FUNDAMENTALS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... NUCLEAR FUNDAMENTALS 1. Personnel shall demonstrate a familiarity level knowledge of basic ...

  14. GUM Analysis for TIMS Isotopic Ratios in BEP0 Graphite Qualification Samples, Round 2

    SciTech Connect (OSTI)

    Gerlach, David C.; Heasler, Patrick G.; Reid, Bruce D.

    2009-01-01

    In May 2007, one set of three samples from NBL were addressed to Steve Petersen for TIMS analysis, and included BEP0 samples numbered 27008, 30986, and 50846. All cores were trimmed by tooling, and lightly cleaned by CO2 pellet blasting. Small discs were cut from the second set of samples for SIMS analysis, with the remainder of each used for TIMS preparation.

  15. GUM Analysis for SIMS Isotopic Ratios in BEP0 Graphite Qualification Samples, Round 2

    SciTech Connect (OSTI)

    Gerlach, David C.; Heasler, Patrick G.; Reid, Bruce D.

    2009-01-01

    This report describes GUM calculations for TIMS and SIMS isotopic ratio measurements of reactor graphite samples. These isotopic ratios are used to estimate reactor burn-up, and currently consist of various ratios of U, Pu, and Boron impurities in the graphite samples. The GUM calculation is a propagation of error methodology that assigns uncertainties (in the form of standard error and confidence bound) to the final estimates.

  16. Technical Qualification Program Self-Assessment Report- Nevada Field Office- 2014

    Broader source: Energy.gov [DOE]

    This self-assessment examined how the Nevada Field Office (NFO) implements the FTCP and TQP as measured by the current FTCP criteria review and approach documents (CRADs) included in the assessment plan. The self-assessment was conducted April 21 – May 5, 2014.

  17. Senior Technical Safety Manager Qualification Standard Reference Guide … October 2013

    Office of Environmental Management (EM)

    NATION SENECA NATION Energy Organizational Development Energy Organizational Development A A " " First Steps First Steps " " Grant Grant November 8, 2007 November 8, 2007 SENECA NATION SENECA NATION In appreciation & Acknowledgment: In appreciation & Acknowledgment: - - Seneca Nation Council Seneca Nation Council Arlene Arlene Bova Bova , Councilor & Energy , Councilor & Energy development advocate development advocate - - Dept. of Energy, Tribal Energy Dept.

  18. Technical Qualification Program Self-Assessment Report- NA-SH- 2013

    Broader source: Energy.gov [DOE]

    The Office of the Associate Administrator for Safety and Health (NA-SH) TQP applies to those personnel who oversee defense nuclear facilities, to support the mission of NNSA. The requirement for this SA comes from DOE O 426.1A that states "Headquarters and Field Elements must conduct self-assessment of TQP and FTCP implementation within their organization at least every 4 years."

  19. Technical Qualification Program Self-Assessment Report- NNSA Production Office- 2014

    Broader source: Energy.gov [DOE]

    In preparation for the upcoming Chief for Defense Nuclear Safety (CDNS) review, a self-assessment of NNSA Production Office (NPO) oversight of the B&W Pantex Plant and the Y-12 National Security Complex was completed from October 2013 – January 2014. The scope included all available CDNS Criteria, Review, and Approach Documents (CRADS) identified as of September 2013.

  20. U.S. Department of Energy Hydrogen Component and System Qualification...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Chris Radley Altergy Systems Fuel Tank Manufacturing, Testing, Field Performance, and Certification Dr. Norman L. Newhouse Lincoln Composites Balance of Plant (BoP) Components ...

  1. DOE-STD-1146-2007 | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    December 05, 2007 General Technical Base Qualification Standard Reaffirmed 2015 The General Technical Base Qualification Standard establishes common technical competency ...

  2. Microsoft PowerPoint - LANL Student Symposium Poster.pptx

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Fire severity qualification was determined using geospatial applications and ground ... Fire severity qualification was determined using geospatial applications and ground ...

  3. Risk Informed Safety Margin Characterization Case Study: Selection of Electrical Equipment To Be Subjected to Environmental Qualification

    SciTech Connect (OSTI)

    D. Blanchard; R. Youngblood

    2012-04-01

    In general, the margins-based safety case helps the decision-maker manage plant margins most effectively. It tells the plant decision-maker such things as what margin is present (at the plant level, at the functional level, at the barrier level, at the component level), and where margin is thin or perhaps just degrading. If the plant is safe, it tells the decision-maker why the plant is safe and where margin needs to be maintained, and perhaps where the plant can afford to relax.

  4. Final Report, Volume 4, The Development of Qualification Standards for Cast Super Duplex Stainless Steel (2507 Wrought Equivalent)

    SciTech Connect (OSTI)

    Hariharan, Vasudevan; Lundin, Carl, W.

    2005-09-30

    The objective of the program is to determine the suitability of ASTM A923 ???¢????????Standard Test methods for Detecting Detrimental Intermetallic Phase in Wrought Duplex Austenitic-Ferritic Stainless Steels???¢??????? for 25 Cr Cast Super Duplex Stainless Steels (ASTM A890-5A). Different tests were carried out on the materials procured from various steel foundries as stated in the ASTM A923. The foundries were designated as Foundry A, B, C and D. All the materials were foundry solution annealed. Materials from Foundry D were solution heat treated at The University of Tennessee also and then they were subjected to heat treatment schedule which was derived from the testing of wrought DSS to establish the A923 specification. This was possible because the material from the same heat was sufficient for conducting the full scope of heat treatment. This was done prior to carrying out various other tests. Charpy samples were machined. The Ferrite content was measured in all the Charpy samples using Feritscope???????® and ASTM E562 Manual Point Count Method. After the ferrite content was measured the samples were sent to AMC-Vulcan, Inc. in Alabama to conduct the Charpy impact test based on ASTM A923 Test Method B. This was followed by etch testing and corrosion analysis based on ASTM A923 Test Methods A and C respectively at University of Tennessee. Hardness testing using Rockwell B and C was also carried out on these samples. A correlation was derived between all the three test methods and the best method for evaluating the presence of intermetallic in the material was determined. The ferrite content was correlated with the toughness values. Microstructural analysis was carried out on the etch test samples using Scanning Electron Microscopy in order to determine if intermetallic phases were present. The fracture surfaces from Charpy test specimens were also observed under SEM in order to determine the presence of any cracks and whether it was a brittle or a ductile fracture. A correlation was carried out between the ferrite content, hardness values and the type of fracture. SEM was also carried out on the corrosion samples in order to see the difference on the surface after corrosion analysis has been carried out. Energy Dispersive Spectroscopy was carried out on the material acquired from Foundry D in order to determine the variation in the amount of the chemical composition of various elements when the material is subjected to different heat treatment schedules. X-Ray analysis was also carried out in order to verify whether it is possible to identify the different phases present in the material. Volume percentage of ferrite was also calculated from X-Ray diffraction and compared with the Feritscope???????® and ASTM E562 Manual Point Count data in order to determine whether X-Ray Diffraction is a suitable method for carrying out qualitative analysis of different phases present. From the various tests that were conducted, it was concluded that since ASTM A923 Methods adequately identifies the presence of intermetallic phases in A890 ???¢???????? 5A grade Cast Super Duplex Stainless Steel A890 ???¢???????? 5A can be directly included in ASTM A923. Correlation was determined between all the ASTM A923 Test Methods A, B and C and Test Method B were identified as the best method for detecting the presence of detrimental intermetallic phases. The micrographs from the A890-4A grade (now in ASTM A923) were identified as applicable for the A890-5A grade to compare and detect the presence of intermetallic phases. Using these micrographs one can verify whether an A890-5A sample has an unaffected, affected or a possibly

  5. Final Report, Volume 4, The Develpoment of Qualification Standards forCast Super Duplex Stainless Steel (2507 Wrought Equivalent)

    SciTech Connect (OSTI)

    Hariharan, Vasudevan; Lundin, Carl, D.

    2005-09-30

    The objective of the program is to determine the suitability of ASTM A923 Standard Test methods for Detecting Detrimental Intermetallic Phase in Wrought Duplex Austenitic-Ferritic Stainless Steels for 25 Cr Cast Super Duplex Stainless Steels (ASTM A890-5A). Different tests were carried out on the materials procured from various steel foundries as stated in the ASTM A923. The foundries were designated as Foundry A, B, C and D. All the materials were foundry solution annealed. Materials from Foundry D were solution heat treated at The University of Tennessee also and then they were subjected to heat treatment schedule which was derived from the testing of wrought DSS to establish the A923 specification. This was possible because the material from the same heat was sufficient for conducting the full scope of heat treatment. This was done prior to carrying out various other tests. Charpy samples were machined. The Ferrite content was measured in all the Charpy samples using Feritscope{reg_sign} and ASTM E562 Manual Point Count Method. After the ferrite content was measured the samples were sent to AMC-Vulcan, Inc. in Alabama to conduct the Charpy impact test based on ASTM A923 Test Method B. This was followed by etch testing and corrosion analysis based on ASTM A923 Test Methods A and C respectively at University of Tennessee. Hardness testing using Rockwell B and C was also carried out on these samples. A correlation was derived between all the three test methods and the best method for evaluating the presence of intermetallic in the material was determined. The ferrite content was correlated with the toughness values. Microstructural analysis was carried out on the etch test samples using Scanning Electron Microscopy in order to determine if intermetallic phases were present. The fracture surfaces from Charpy test specimens were also observed under SEM in order to determine the presence of any cracks and whether it was a brittle or a ductile fracture. A correlation was carried out between the ferrite content, hardness values and the type of fracture. SEM was also carried out on the corrosion samples in order to see the difference on the surface after corrosion analysis has been carried out. Energy Dispersive Spectroscopy was carried out on the material acquired from Foundry D in order to determine the variation in the amount of the chemical composition of various elements when the material is subjected to different heat treatment schedules. X-Ray analysis was also carried out in order to verify whether it is possible to identify the different phases present in the material. Volume percentage of ferrite was also calculated from X-Ray diffraction and compared with the Feritscope{reg_sign} and ASTM E562 Manual Point Count data in order to determine whether X-Ray Diffraction is a suitable method for carrying out qualitative analysis of different phases present. From the various tests that were conducted, it was concluded that since ASTM A923 Methods adequately identifies the presence of intermetallic phases in A890-5A grade Cast Super Duplex Stainless Steel A890-5A can be directly included in ASTM A923. Correlation was determined between all the ASTM A923 Test Methods A, B and C and Test Method B were identified as the best method for detecting the presence of detrimental intermetallic phases. The micrographs from the A890-4A grade (now in ASTM A923) were identified as applicable for the A890-5A grade to compare and detect the presence of intermetallic phases. Using these micrographs one can verify whether an A890-5A sample has an unaffected, affected or a possibly affected structure. It was also observed that when compared to the A890-4A grade A890-5A grade is more sensitive to heat treatment. From the ferrite and hardness measurement a correlation was developed between toughness, volume percentage ferrite and hardness of the material. From SEM and EDS the type of intermetallic phase present and its chemical composition was determined. The best method for calculating volume percentage ferrite was determined between the Ferits

  6. Evaluation of ISDP Batch 2 Qualification Compliance to 512-S, DWPF, Tank Farm, and Saltstone Waste Acceptance Criteria

    SciTech Connect (OSTI)

    Shafer, A.

    2010-05-05

    The purpose of this report is to document the acceptability of the second macrobatch (Salt Batch 2) of Tank 49H waste to H Tank Farm, DWPF, and Saltstone for operation of the Interim Salt Disposition Project (ISDP). Tank 49 feed meets the Waste Acceptance Criteria (WAC) requirements specified by References 11, 12, and 13. Salt Batch 2 material is qualified and ready to be processed through ARP/MCU to the final disposal facilities.

  7. Preliminary plan for the qualification of the LEU/Th fuel cycle for the Fort St. Vrain HTGR

    SciTech Connect (OSTI)

    Gulden, T.D.; Gainey, B.W.; Altschwager, C.J.

    1980-03-01

    This plan was prepared to ensure that low-enriched uranium/thorium (LEU/Th) would be available as a backup to the highly enriched uranium/thorium (HEU/Th) fuel cycle currently being used in the Fort St. Vrain (FSV) high-temperature gas-cooled reactor (HTGR) in the event that the US nonproliferation policies require it. It describes the program that would be required to develop, qualify, and introduce an LEU/Th fuel cycle into the FSV HTGR on the earliest possible and most optimistic schedule. The results of the study indicate that licensing of the LEU/Th fuel cycle for FSV could be completed and fuel manufacturing could begin about 4.5 years from inception of the program.

  8. Qualification and initial characterization of a high-purity 233U spike for use in uranium analyses

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Mathew, K. J.; Canaan, R. D.; Hexel, C.; Giaquinto, J.; Krichinsky, A. M.

    2015-08-20

    Several high-purity 233U items potentially useful as isotope dilution mass spectrometry standards for safeguards, non-proliferation, and nuclear forensics measurements are identified and rescued from downblending. By preserving the supply of 233U materials of different pedigree for use as source materials for certified reference materials (CRMs), it is ensured that the safeguards community has high quality uranium isotopic standards required for calibration of the analytical instruments. One of the items identified as a source material for a high-purity CRM is characterized for the uranium isotope-amount ratios using thermal ionization mass spectrometry (TIMS). Additional verification measurements on this material using quadrupole inductivelymore » coupled plasma mass spectrometry (ICPMS) are also performed. As a result, the comparison of the ICPMS uranium isotope-amount ratios with the TIMS data, with much smaller uncertainties, validated the ICPMS measurement practices. ICPMS is proposed for the initial screening of the purity of items in the rescue campaign.« less

  9. The Mission and Technology of a Gas Dynamic Trap Neutron Source for Fusion Material and Component Testing and Qualification

    SciTech Connect (OSTI)

    Ivanov, A; Kulcinski, J; Molvik, A; Ryutov, D; Santarius, J; Simonen, T; Wirth, B D; Ying, A

    2009-11-23

    The successful operation (with {beta} {le} 60%, classical ions and electrons with Te = 250 eV) of the Gas Dynamic Trap (GDT) device at the Budker Institute of Nuclear Physics (BINP) in Novosibirsk, Russia, extrapolates to a 2 MW/m{sup 2} Dynamic Trap Neutron Source (DTNS), which burns only {approx}100 g of tritium per full power year. The DTNS has no serious physics, engineering, or technology obstacles; the extension of neutral beam lines to steady state can use demonstrated engineering; and it supports near-term tokamaks and volume neutron sources. The DTNS provides a neutron spectrum similar to that of ITER and satisfies the missions specified by the materials community to test fusion materials (listed as one of the top grand challenges for engineering in the 21st century by the U.S. National Academy of Engineering) and subcomponents (including tritium-breeding blankets) needed to construct DEMO. The DTNS could serve as the first Fusion Nuclear Science Facility (FNSF), called for by ReNeW, and could provide the data necessary for licensing subsequent FSNFs.

  10. Qualification of the Lasentec M600P Particle Size Analyzer and the Red Valve Model 1151 Pressure Sensor

    SciTech Connect (OSTI)

    JR Bontha; NG Colton; EA Daymo; TD Hylton; CK Bayne; TH May

    2000-01-28

    The Lasentec M600 in-line particle size analyzer was installed at Oak Ridge National Laboratory (ORNL) in August 1998 to support retrieval of the Gunite and Associated Tanks (GAAT). Before installation at ORNL, the sensor underwent validation testing at the Pacific Northwest National Laboratory (PNNL) Instrument Validation facility. Mechanically, the instrument worked well during validation testing and met all expectations. Operationally, much was learned about optimum ways to display and interpret the data. Slurry samples taken during the in-line tests at PNNL were shipped to the vendor for analysis with a benchtop Lasentec sensor. These experiments were performed to determine if off-line analyses yield particle size distributions similar to those generated by the in-line sensor. It was determined that the Lasentec sensor measures repeatable chord lengths as long as particles are ''presenter'' to the sensor window the same way. After the initial non-radioactive simulant testing at PNNL, the instrument was shipped for radioactive validation and acceptance testing in the Slurry Monitoring Test System (SMTS) connected to the Tank W-9 of the GAATs at ORNL. For all acceptance tests conducted at ORNL, the variation in the chord length distribution and the total particle count corresponded very well with the slurry density data as determined using an in-line Promass 63M Coriolis meter. Based on the performance results obtained, the Lasentec M600P FBRM is expected to meet the requirements for measuring the particle size distribution during the slurry transfer operations at Hanford and the Oak Ridge GAAT remediation project. The Red Valve pressure sensor was endorsed at the Hanford Site following instrument validation tests at PNNL and is currently in operation in the Tank 241-C-106 pump pit. While this instrument measures pressure within a transfer line, this type of pressure sensor could be configured to measure pressure drop over time. In turn, the status of a slurry transfer could be inferred from the pressure-drop measurement. In 1998, four Red Valve pressure sensors (with Sensotech Model AE-213 pressure transducers) were installed before and after the booster pumps of the 4-in. slurry (SL-200) and supernatant (SN-200) transfer lines between Tank 241-C-106 and Tank 241-AY-1 02. These pressure sensors have been in operation for over 1 year, and to date, the sensors have been trouble-flee according to the operators involved with slurry and supernatant transfer operations. Based on these observations, it is apparent that the Red Valve pressure sensors could be installed at the end of the slurry transfer lines and used to measure the pressure drop in the system.

  11. Qualification and initial characterization of a high-purity 233U spike for use in uranium analyses

    SciTech Connect (OSTI)

    Mathew, K. J.; Canaan, R. D.; Hexel, C.; Giaquinto, J.; Krichinsky, A. M.

    2015-08-20

    Several high-purity 233U items potentially useful as isotope dilution mass spectrometry standards for safeguards, non-proliferation, and nuclear forensics measurements are identified and rescued from downblending. By preserving the supply of 233U materials of different pedigree for use as source materials for certified reference materials (CRMs), it is ensured that the safeguards community has high quality uranium isotopic standards required for calibration of the analytical instruments. One of the items identified as a source material for a high-purity CRM is characterized for the uranium isotope-amount ratios using thermal ionization mass spectrometry (TIMS). Additional verification measurements on this material using quadrupole inductively coupled plasma mass spectrometry (ICPMS) are also performed. As a result, the comparison of the ICPMS uranium isotope-amount ratios with the TIMS data, with much smaller uncertainties, validated the ICPMS measurement practices. ICPMS is proposed for the initial screening of the purity of items in the rescue campaign.

  12. Evaporator Feed Qualification Analysis Of Tank 38H And 43H Samples: January 2010 Through April 2013

    SciTech Connect (OSTI)

    Martino, C. J.; Coleman, C. J.

    2013-08-21

    This report provides the results of analyses that focused on the chemical species that pertain to the sodium aluminosilicate formation potential for archived Tank 38H and 43H subsurface samples from January 2010 through April 2013. Analyses included warm acid strike preparation followed by analysis of silicon, aluminum, and sodium and water dilution preparation followed by analysis for anions. The Tank 43H and 38H supernatant liquid silicon measurements for the January 2010 through April 2013 time period exhibit a slight increasing trend. Over this time period, the silicon concentration in the Tank 43H and Tank 38H samples averaged 179 mg/L and 235 mg/L, respectively. Comparison of Tank 43H sample results from 2005 through April 2013 to the previously developed process control models indicates that the current formation of sodium aluminosilicate in the 2H system is due to the seeded direct precipitation of cancrinite and sodalite.

  13. IDENTIFICATION OF APPROPRIATE QUALIFICATION TESTING AND END-OF-LIFE WASTE STORAGE CONSIDERATIONS FOR DEEP BED SAND FILTERS

    SciTech Connect (OSTI)

    Matthews, K.

    2010-06-02

    Deep bed sand (DBS) filters have filtered radioactive particulates at two United States Department of Energy (DOE) sites since 1948. Some early DBS filters experienced issues with chemical attack on support tiles, requiring significant repairs. Designs of DBS filters constructed since 1970 paid greater attention to chemical compatibility, resulting in decades of reliable performance since 1975.

  14. Welding procedure specification. Supplement 1. Records of procedure qualification tests. Gas tungsten arc welding of nickel to nickel-copper

    SciTech Connect (OSTI)

    Wodtke, C.H.; Frizzell, D.R.; Plunkett, W.A.

    1986-06-01

    Procedure WPS-2301-ASME-3 is qualified under Section IX of the ASME Boiler and Pressure Vessel Code for gas tungsten arc welding of nickel, NO2200 or NO2201 (P-41) to nickel-copper NO4400 (P-42), in thickness range 0.035 to 0.432 inch; filler metal is ERNiCu-7 (F-42); shielding gas is argon.

  15. Welding procedure specification. Supplement 1. Records of procedure qualification tests. Gas tungsten arc welding of nickel-copper

    SciTech Connect (OSTI)

    Wodtke, C.H.; Frizzell, D.R.; Plunkett, W.A.

    1986-06-01

    Procedure WPS-1302-ASME-3 is qualified under Section IX of the ASME Boiler and Pressure Vessel Code for gas tungsten arc welding of nickel-copper NO4400 (P-42), in thickness range 0.035 to 0.432 inch; filler metal is ERNiCu-7 (F-42); shielding gas is argon.

  16. Risk Informed Safety Margin Characterization Case Study: Selection of Electrical Equipment To Be Subjected to Environmental Qualification

    Broader source: Energy.gov [DOE]

    Reference 1 discussed key elements of the process for developing a margins-based “safety case” to support safe and efficient operation for an extended period. The present report documents (in...

  17. DOE-STD-1176-2004 | Department of Energy

    Broader source: Energy.gov (indexed) [DOE]

    January 16, 2004 Chemical Processing Functional Area Qualification Standard Replaced by DOE-STD-1176-2010 The Chemical Processing Functional Area Qualification Standard establishes ...

  18. DOE-HDBK-1002-96 | Department of Energy

    Broader source: Energy.gov (indexed) [DOE]

    and Qualification of Chemical Operators Canceled, Effective February 2016 The purpose of the Guide to Good Practices for Training and Qualification of Chemical Operators is to ...

  19. DOE-HDBK-1002-96; Guide to Good Practices for Training and Qualificati...

    Energy Savers [EERE]

    GUIDE TO GOOD PRACTICES FOR TRAINING AND QUALIFICATION OF CHEMICAL OPERATORS U.S. ... The purpose of the Guide to Good Practices for Training and Qualification of Chemical ...

  20. DOE-STD-1182-2014 | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    DOE-STD-1182-2014 October 2014 CivilStructural Engineering Functional Area Qualification Standard The CivilStructural Engineering Functional Area Qualification Standard (FAQS) ...

  1. EM Quality Assurance Program (EM-QA-001 Revision 0)

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    ... activities with EM HQ. L i e s of communication, feedback mechanisms, and interfaces ... qualification requirements, NQA-1 Lead Auditor qualification, etc.) or within a ...

  2. DOE-STD-1159-2003; DOE Standard Waste Management Functional Area...

    Office of Environmental Management (EM)

    59-2003 January 2003 DOE STANDARD WASTE MANAGEMENT FUNCTIONAL AREA QUALIFICATION STANDARD ... Environmental Management is the Sponsor for the Waste Management Qualification Standard. ...

  3. DOE-HDBK-1080-97; Guide to Good Practices for Oral Examinations

    Office of Environmental Management (EM)

    ... Within this handbook the terms "qualification" and ... the knowledge to enter a higher level of qualification. ... may be inclined to search for hidden meanings in ...

  4. DOE-STD-1162-2003 | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    DOE-STD-1162-2003 June 17, 2003 Instrumentation and Control Functional Area Qualification Standard The Instrumentation and Control Functional Area Qualification Standard ...

  5. DOE-STD-1179-2004 | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    PDF icon DOE-STD-1179-2004, Technical Training Functional Area Qualification Standard More Documents & Publications FAQS Gap Analysis Qualification Card - Technical Training All ...

  6. Xcel Energy (Gas)- Business Energy Efficiency Rebate Programs

    Broader source: Energy.gov [DOE]

    For more information, including equipment qualifications, eligibility and applications, see the program web site.

  7. Construction, Qualification, and Low Rate Production Start‐up of a DC Bus Capacitor High Volume Manufacturing Facility with Capacity to Support 100,000 Electric Drive Vehicles

    Broader source: Energy.gov [DOE]

    2010 DOE Vehicle Technologies and Hydrogen Programs Annual Merit Review and Peer Evaluation Meeting, June 7-11, 2010 -- Washington D.C.

  8. Development and Qualification of Advancements in Submersible Transfer Pump Performance and Life, and Implications for Advancing and Supporting Processing Options - 13343

    SciTech Connect (OSTI)

    Stover, David L.; Bryan, Wes; Kelly, James

    2013-07-01

    From the 1950's through the 1990's, relatively inexpensive, 'off-the-shelf' type, vertical turbine pumps (VTP) were used to transfer Hanford waste. The technology of those pumps was rooted primarily in the mining and agricultural (irrigation) industries. HNF-3218, Double Shell Tank (DST) Transfer Pump History and Reliability Report, 1998, provides a summary of Hanford DST pump history to that date. Such pumps operated in the Hanford radioactive waste environment for an average of only 400 hours before failure. However, at that time, operating life was not a driving criteria within the Department of Energy (DOE) complex, as the failure of transfer pumps represented a relatively low replacement and disposal cost. The Environmental Protection Agency (EPA) issuance of the 'Debris Rule' in 1992, which mandated that mixed radioactive waste contaminated equipment be decontaminated to a 'low level waste' category prior to burial, elevated the significance of transfer pump reliability and decontamination capability as life-cycle cost criteria. Minimizing the frequency of transfer pump failures and design for decontamination became significantly important and served to drive the need toward specific, designed for application pumps to meet this challenge. To this end, Washington River Protection Solutions (WRPS) and the supplier, Curtiss-Wright EMD (EMD), have recently collaborated on an intense program to further transfer pump technology and performance. (authors)

  9. Notice of Intent to Revise Department of Energy Order 426.2 Change 1, Personnel Selection, Training, Qualification and Certification Requirements for DOE Nuclear Facilities

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2015-02-19

    The Office of Nuclear Safety consulted field and Headquarters (HQ) offices on whether or not a revision is warranted for DOE O 426.2. As a result, certain aspects of DOE O 426.2 were identified as needing clarification and revision. Based on this feedback, the revision is intended to clarify educational requirements, certification requirements, and applicability. Addressing these concerns should improve operating training programs, and result in less time focused on managing ambiguous or possibly unnecessary requirements.

  10. Notice of Intent to Revise Department of Energy Order 426.2 Change 1, Personnel Selection, Training, Qualification and Certification Requirements for DOE Nuclear Facilities

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    The Office of Nuclear Safety consulted field and Headquarters (HQ) offices on whether or not a revision is warranted for DOE O 426.2. As a result, certain aspects of DOE O 426.2 were identified as needing clarification and revision. Based on this feedback, the revision is intended to clarify educational requirements, certification requirements, and applicability. Addressing these concerns should improve operating training programs, and result in less time focused on managing ambiguous or possibly unnecessary requirements.

  11. Welding procedure specification. Supplement 1. Records of procedure qualification tests. Gas tungsten arc welding of chromium-nickel steel to nickel-copper

    SciTech Connect (OSTI)

    Wodtke, C.H.; Frizzell, D.R.; Plunkett, W.A.

    1986-06-01

    Procedure WPS-2602-ASME-3 is qualified under Section IX of the ASME Boiler and Pressure Vessel Code for gas tungsten arc welding of 300 series Cr-Ni steels (P-8-1) to nickel-copper N04400 (P-42), in thickness range 0.035 to 0.432 inch; filler metal is ERNiCu-7 (F-42); shielding gas is argon.

  12. Welding procedure specification: gas tungsten arc welding of nickel-copper to nickel-chromium-iron. Supplement 1. Records of procedure qualification tests

    SciTech Connect (OSTI)

    Wodtke, C.H.; Frizzell, D.R.; Plunkett, W.A.

    1986-06-01

    Procedure WPS-2303-ASME-3 is qualified under Section IX of the ASME Boiler and Pressure Vessel Code for gas tungsten arc welding of nickel-copper N04400 (P-42) to nickel-chromium-iron N06600 (P-43), in thickness range of 0.035 to 0.432 inch; filler metal is ERNiCu-7 (F-42); shielding gas is argon.

  13. Project W420 Air Sampler Probe Placement Qualification Tests for Four 6-Inch Diameter Stacks: 296-A-25, 296-B-28, 296-S-22, and 296-T-18

    SciTech Connect (OSTI)

    Maughan, A.D.; Glissmeyer, J.A.

    1998-09-30

    The W420 project covers the upgrading of effluent monitoring systems at six ventilation exhaust stacks in tank-farm facilities at the U.S. Department of Energy's Hanford Site. The discharge stacks of five of the six systems will be completely replaced. Four of these (296-A-25, 296-B-28, 296-S-22, and 296-T-18) will be of the same size, 6-inches in diameter and about 12-ft high. This report documents tests that were conducted to verify that these four stacks meet the applicable regulatory criteria regarding the placement of the air sampling probe. These criteria ensure that the contaminants in the stack are well mixed with the airflow at the location of the probe such that the extracted sample represents the whole. There are also criteria addressing the transport of the sample to the collection device. These are not covered in this report, but will need to be addressed later. These tests were conducted by Pacific Northwest National Laboratory on a full-scale model of the 6-inch stick. The sequence of tests addresses the acceptability of the flow angle relative to the probe and the uniformity of air velocity and gaseous and particle tracers in the cross section of the stack. All tests were successful, and all acceptance criteria were met.

  14. DOE-STD-1150-2013

    Broader source: Energy.gov [DOE]

    Quality Assurance Functional Area Qualification Standard The Quality Assurance (QA) Functional Area Qualification Standard (FAQS) establishes common functional area competency requirements for all DOE QA personnel who provide assistance,

  15. DOE-STD-1146-2001 | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    DOE-STD-1146-2001 November 07, 2001 General Technical Base Qualification Standard Replaced by DOE-STD-1146-2001 The General Technical Base Qualification Standard establishes common ...

  16. DOE-STD-1137-2000 | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    DOE-STD-1137-2000 July 25, 2000 Fire Protection Engineering Functional Area Qualification ... PDF icon DOE-STD-1137-2000, Fire Protection Engineering Functional Area Qualification ...

  17. DOE-STD-1162-2013 | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    DOE-STD-1162-2013 July 19, 2013 Instrumentation and Control Functional Area Qualification ... PDF icon DOE-STD-1162-2013, Instrumentation and Control Functional Area Qualification ...

  18. FAQs: Copyrighted Images and Text on the Website | Department of Energy

    Energy Savers [EERE]

    Qualification Card - Occupational Safety FAQS Qualification Card - Occupational Safety A key element for the Department's Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA). For each functional area,

  19. Tax Credits, Rebates & Savings | Department of Energy

    Broader source: Energy.gov (indexed) [DOE]

    Business Energy Efficiency Rebate Programs For more information, including equipment qualifications, eligibility and applications, see the program web site. Eligibility:...

  20. Tax Credits, Rebates & Savings | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Food Service Equipment, Vending Machine Controls, LED Lighting, Commercial Refrigeration Equipment Michigan Saves- Business Energy Financing Pre-qualification application...

  1. Tax Credits, Rebates & Savings | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Personal Computing Equipment, Pool Pumps, LED Lighting, Commercial Refrigeration Equipment Michigan Saves- Business Energy Financing Pre-qualification application...

  2. Tax Credits, Rebates & Savings | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    (Small), Fuel Cells using Renewable Fuels, LED Lighting, Commercial Refrigeration Equipment Michigan Saves- Business Energy Financing Pre-qualification application...

  3. Tax Credits, Rebates & Savings | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    approval, Food Service Equipment, Vending Machine Controls, Commercial Refrigeration Equipment Michigan Saves- Business Energy Financing Pre-qualification application...

  4. I Mr. J. C. Delaney

    Office of Legacy Management (LM)

    FINANCIAL QUALIFICATIONS ...... 6 VI. INSURANCE ... 3. in chemical engineering and H. 5, in gas technology from Illinois Institute of ...

  5. November 3-5, 2015, Federal Technical Capability Program Face...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    STSM Requalification vs. Continuing Training Advantages Disadvantages of Requalification Advantages * Familiar Process * Covers "GAP" since previous qualification * Provides...

  6. DOE-STD-1151-2002 | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    02 DOE-STD-1151-2002 May 08, 2002 Facility Representative Functional Area Qualification Standard Replaced by DOE-STD-1151-2010 The Facility Representative Functional Area Qualification Standard has been developed as a tool to assist DOE Program and Field offices in the development and implementation of the Technical Qualification Program in their organization. PDF icon DOE-STD-1151-2002, Facility Representative Functional Area Qualification Standard More Documents & Publications

  7. DOE-STD-1160-2003 | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    60-2003 DOE-STD-1160-2003 March 11, 2003 Occupational Safety Functional Area Qualification Standard Replaced by DOE-STD-1160-2011 The Occupational Safety Functional Area Qualification Standard is not intended to replace the OPM Qualification Standards or other DOE personnel standards, rules, plans, or processes. The primary purpose of the Technical Qualification Program is to ensure that employees have the requisite technical competency to support the DOE mission. PDF icon DOE-STD-1160-2003,

  8. DOE-HDBK-1001-96; Guide to Good Practices for Training and Qualificati...

    Energy Savers [EERE]

    ... for the facility technical and applied fundamentals information (including simulator, if ... Trainees Subjects Taught Instructor Qualifications Technicians Fundamentals and ...

  9. DOE-STD-1180-2004; Construction Management Functional Area Qualificati...

    Office of Environmental Management (EM)

    ... Management's Qualification Standards Handbook establishes minimum education, training, ... shall demonstrate a familiarity level knowledge of the chemical fundamentals of corrosion. ...

  10. FTCP Site Specific Information- Carlsbad Field Office

    Broader source: Energy.gov [DOE]

    Site Specific Information including Contact Information, Annual Workforce Analysis & Staffing Plan Reports, and Technical Qualification Program (TQP) Self-Assessment.

  11. FTCP Site Specific Information – Office of River Protection

    Broader source: Energy.gov [DOE]

    Site Specific Information including Annual Workforce Analysis and Staffing Plan Reports, and Technical Qualification Program (TQP) Self-Assessment.

  12. FTCP Site Specific Information – Idaho Operations Office

    Broader source: Energy.gov [DOE]

    Site Specific Information including Annual Workforce Analysis and Staffing Plan Reports, and Technical Qualification Program (TQP) Self-Assessment.

  13. FTCP Site Specific Information – Pacific Northwest Site Office

    Broader source: Energy.gov [DOE]

    Site Specific Information including Contact Information, Annual Workforce Analysis & Staffing Plan Reports, and Technical Qualification Program (TQP) Self-Assessment

  14. FTCP Site Specific Information – Office of Science

    Broader source: Energy.gov [DOE]

    Site Specific Information includes Annual Workforce Analysis and Staffing Plan Reports, and Technical Qualification Program (TQP) Self-Assessment.

  15. FTCP Site Specific Information – Savannah River Operations Office

    Broader source: Energy.gov [DOE]

    Site Specific Information including Contact Information, Annual Workforce Analysis & Staffing Plan Reports, and Technical Qualification Program (TQP) Self-Assessment.

  16. November 3-5, 2015, Federal Technical Capability Program Face...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Background Currently 34 TQP qualifications standards Recommendations: Retain standards that are directly related to nuclear facility operations STSMFRNSSS&S...

  17. PROJECT MANGEMENT PLAN EXAMPLES Prepare Project Support Plans and

    Office of Environmental Management (EM)

    Training and Qualification Plan Examples Example 66 8.2.2 Personnel Training and Qualification The Personnel Training and Qualification program is being established as defined by laws, DOE Orders, and company directives to ensure that personnel are trained and qualified to perform assigned tasks. The training and qualification program develops personnel proficiency commensurate with the scope, complexity, and nature of an assigned activity. Management is responsible for developing staff position

  18. FTCP Site Specific Information – Los Alamos Field Office

    Broader source: Energy.gov [DOE]

    Site Specific Information including Contact Information, Annual Workforce Analysis & Staffing Plan Reports, and Technical Qualification Program (TQP) Self-Assessments.

  19. FTCP Site Specific Information – Livermore Field Office

    Broader source: Energy.gov [DOE]

    Site Specific Information including Contact Information, Annual Workforce Analysis & Staffing Plan Reports, and Technical Qualification Program (TQP) Self-Assessment.

  20. FTCP Site Specific Information – Savannah River Field Office

    Broader source: Energy.gov [DOE]

    Site Specific Information including Contact Information, Annual Workforce Analysis & Staffing Plan Reports, and Technical Qualification Program (TQP) Self-Assessment.

  1. Interconnection Standards

    Broader source: Energy.gov [DOE]

    West Virginia's interconnection standards include two levels of review. The qualifications and application fees for each level are as follows:...

  2. FTCP Quarterly Report on Federal Technical Capability, November 20, 2012

    Broader source: Energy.gov [DOE]

    This Quarterly Report on the Federal Technical Capability Program (FTCP) contains information on the status of qualifications in the Technical Qualification Program (TQP) and technical skill gaps, on a quarterly basis. Report also displays trend data for overall TQP qualification and staffing shortfalls.

  3. FTCP Quarterly Report on Federal Technical Capability, February 20, 2013

    Broader source: Energy.gov [DOE]

    This Quarterly Report on the Federal Technical Capability Program (FTCP) contains information on the status of qualifications in the Technical Qualification Program (TQP) and technical skill gaps, on a quarterly basis. Report also displays trend data for overall TQP qualification and staffing shortfalls.

  4. FTCP Quarterly Report on Federal Technical Capability, May 30, 2012

    Broader source: Energy.gov [DOE]

    This Quarterly Report on the Federal Technical Capability Program (FTCP) contains information on the status of qualifications in the Technical Qualification Program (TQP) and technical skill gaps, on a quarterly basis. Report also displays trend data for overall TQP qualification and staffing shortfalls.

  5. FTCP Quarterly Report on Federal Technical Capability, June 5, 2013

    Office of Energy Efficiency and Renewable Energy (EERE)

    This Quarterly Report on the Federal Technical Capability Program (FTCP) contains information on the status of qualifications in the Technical Qualification Program (TQP) and technical skill gaps, on a quarterly basis. Report also displays trend data for overall TQP qualification and staffing shortfalls.

  6. FTCP Quarterly Report on Federal Technical Capability, August 16, 2010

    Office of Energy Efficiency and Renewable Energy (EERE)

    This Quarterly Report on the Federal Technical Capability Program (FTCP) contains information on the status of qualifications in the Technical Qualification Program (TQP) and technical skill gaps, on a quarterly basis. Report also displays trend data for overall TQP qualification and staffing shortfalls.

  7. FTCP Quarterly Report on Federal Technical Capability, February 24, 2014

    Office of Energy Efficiency and Renewable Energy (EERE)

    This Quarterly Report on the Federal Technical Capability Program (FTCP) contains information on the status of qualifications in the Technical Qualification Program (TQP) and technical skill gaps, on a quarterly basis. Report also displays trend data for overall TQP qualification and staffing shortfalls.

  8. FTCP Quarterly Report on Federal Technical Capability, November 20, 2013

    Office of Energy Efficiency and Renewable Energy (EERE)

    This Quarterly Report on the Federal Technical Capability Program (FTCP) contains information on the status of qualifications in the Technical Qualification Program (TQP) and technical skill gaps, on a quarterly basis. Report also displays trend data for overall TQP qualification and staffing shortfalls.

  9. FTCP Quarterly Report on Federal Technical Capability, July 3, 2014

    Office of Energy Efficiency and Renewable Energy (EERE)

    This Quarterly Report on the Federal Technical Capability Program (FTCP) contains information on the status of qualifications in the Technical Qualification Program (TQP) and technical skill gaps, on a quarterly basis. Report also displays trend data for overall TQP qualification and staffing shortfalls.

  10. FTCP Quarterly Report on Federal Technical Capability, February 23, 2011

    Office of Energy Efficiency and Renewable Energy (EERE)

    This Quarterly Report on the Federal Technical Capability Program (FTCP) contains information on the status of qualifications in the Technical Qualification Program (TQP) and technical skill gaps, on a quarterly basis. Report also displays trend data for overall TQP qualification and staffing shortfalls.

  11. FTCP Quarterly Report on Federal Technical Capability, September 2, 2014

    Office of Energy Efficiency and Renewable Energy (EERE)

    This Quarterly Report on the Federal Technical Capability Program (FTCP) contains information on the status of qualifications in the Technical Qualification Program (TQP) and technical skill gaps, on a quarterly basis. Report also displays trend data for overall TQP qualification and staffing shortfalls.

  12. FTCP Quarterly Report on Federal Technical Capability, March 6, 2012

    Office of Energy Efficiency and Renewable Energy (EERE)

    This Quarterly Report on the Federal Technical Capability Program (FTCP) contains information on the status of qualifications in the Technical Qualification Program (TQP) and technical skill gaps, on a quarterly basis. Report also displays trend data for overall TQP qualification and staffing shortfalls.

  13. FTCP Quarterly Report on Federal Technical Capability, December 15, 2014

    Office of Energy Efficiency and Renewable Energy (EERE)

    This Quarterly Report on the Federal Technical Capability Program (FTCP) contains information on the status of qualifications in the Technical Qualification Program (TQP) and technical skill gaps, on a quarterly basis. Report also displays trend data for overall TQP qualification and staffing shortfalls.

  14. FTCP Quarterly Report on Federal Technical Capability, April 3, 2015

    Office of Energy Efficiency and Renewable Energy (EERE)

    This Quarterly Report on the Federal Technical Capability Program (FTCP) contains information on the status of qualifications in the Technical Qualification Program (TQP) and technical skill gaps, on a quarterly basis. Report also displays trend data for overall TQP qualification and staffing shortfalls.

  15. FRIED399.pdf

    Energy Savers [EERE]

    FPL Energy Services ESCO Qualification Sheet FPL Energy Services ESCO Qualification Sheet Document outlines the energy service company (ESCO) qualifications for FPL Energy Services in relation to the U.S. Department of Energy's (DOEs) energy savings performance contract (ESPC). PDF icon fpl_escoqual.pdf

  16. FTCP Quarterly Report on Federal Technical Capability, August 8, 2012

    Broader source: Energy.gov [DOE]

    This Quarterly Report on the Federal Technical Capability Program (FTCP) contains information on the status of qualifications in the Technical Qualification Program (TQP) and technical skill gaps, on a quarterly basis. Report also displays trend data for overall TQP qualification and staffing shortfalls.

  17. MaRIE 1.0 -- The Matter-Radiation Interactions in Extremes Project:

    Office of Scientific and Technical Information (OSTI)

    Accelerating Qualification, Certification, and Assessment (Technical Report) | SciTech Connect MaRIE 1.0 -- The Matter-Radiation Interactions in Extremes Project: Accelerating Qualification, Certification, and Assessment Citation Details In-Document Search Title: MaRIE 1.0 -- The Matter-Radiation Interactions in Extremes Project: Accelerating Qualification, Certification, and Assessment Authors: Barnes, Cris William [1] + Show Author Affiliations Los Alamos National Laboratory Publication

  18. FTCP Quarterly Report on Federal Technical Capability, March 2, 2016 |

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Department of Energy Quarterly Report on Federal Technical Capability, March 2, 2016 FTCP Quarterly Report on Federal Technical Capability, March 2, 2016 This Quarterly Report on the Federal Technical Capability Program (FTCP) contains information on the status of qualifications in the Technical Qualification Program (TQP) and technical skill gaps, on a quarterly basis. Report also displays trend data for overall TQP qualification and staffing shortfalls. PDF icon Quarterly Report on Federal

  19. America's Home Energy Education Challenge Poster Contest | Department of

    Energy Savers [EERE]

    Ameresco ESCO Qualification Sheet Ameresco ESCO Qualification Sheet Document outlines the energy service company (ESCO) qualifications for Ameresco in relation to the U.S. Department of Energy's (DOEs) energy savings performance contracts (ESPC). PDF icon ameresco_escoqual.pdf

    Clean, Efficient Fleets: An Infographic America's Clean, Efficient Fleets: An Infographic March 19, 2012 - 3:24pm Addthis 1 of 4 Image: Infographic by Hantz Leger (DOE). Date taken: 2012-03-19 15:57 2 of 4 Image:

  20. Join Us: 2013 National Clean Energy Business Plan Competition Finals |

    Energy Savers [EERE]

    P. Holdren and Nancy Sutley About Us John P. Holdren and Nancy Sutley Most Recent Green Button Giving Millions of Americans Better Handle on Energy Costs March 22

    Johnson Controls ESCO Qualification Sheet Johnson Controls ESCO Qualification Sheet Document outlines the energy service company (ESCO) qualifications for Johnson Controls in relation to the U.S. Department of Energy's (DOEs) energy savings performance contracts (ESPC). PDF icon johnsoncontrols_escoqual.pdf

    Energy.gov at the

  1. Enhanced Driver Requirements for WIPP Shipments - Fact Sheet

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    . a critical step toward solving the nation's nuclear waste disposal problem Enhanced Driver Requirements for WIPP Shipments Waste Isolation Pilot Plant (WIPP), Driver Hiring Qualifications and Requirements WIPP drivers must meet very stringent requirements. To be hired, drivers: * Shall meet or exceed licensing, training, and physical qualification for set forth in the Code of Federal Regulations (CFR): "Qualifications of Drivers" 49 CFR 391; and the Commercial Motor Vehicle Safety

  2. DOE-STD-1155-2002

    Broader source: Energy.gov [DOE]

    Transportation and Traffic Management Functional Area Qualification The Office of Environmental Management is the Sponsor for the Transportation and Traffic Management Qualification Standard. The Sponsor is responsible for coordinating the development and/or review of the Functional Area Qualification Standard by subject matter experts to ensure that the technical content of the standard is accurate and adequate for Department-wide application for those involved in the Transportation and Traffic Management Program.

  3. DOE-HDBK-1003-96 | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    3-96 DOE-HDBK-1003-96 May 15, 1996 Guide to Good Practices for Training and Qualification of Maintenance Personnel Canceled, Effective February 2016 This guide provides recommended education, experience, and training for maintenance personnel. Training and qualification programs based on the content of this guide should provide assurance that maintenance personnel perform their jobs safely and competently. PDF icon DOE-HDBK-1003-96, Guide to Good Practices for Training and Qualification of

  4. DOE-STD-1123-2009 | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    3-2009 DOE-STD-1123-2009 August 12, 2009 Safeguards and Security General Technical Base Qualification Standard The Safeguards and Security General Technical Base Qualification Standard is intended to ensure that all safeguards and security employees in the TQP have a common level of core technical knowledge. The Safeguards and Security Functional Area Qualification Standard builds on this base knowledge to provide greater knowledge and skills. PDF icon DOE-STD-1123-2009, Safeguards and Security

  5. DOE-STD-1151-2010 | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    10 DOE-STD-1151-2010 October 12, 2010 Facility Representative Functional Area Qualification Standard FACILITY REPRESENTATIVE DOE O 426.1, Federal Technical Capabilities, commits the Department to continuously strive for technical excellence. The Technical Qualification Program (TQP), along with the supporting technical qualification standards, complements the personnel processes that support the Department's drive for technical excellence. PDF icon DOE-STD-1151-2010, Facility Representative

  6. DOE-STD-1185-2007 | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    September 25, 2007 Nuclear Explosive Safety Study Functional Area Qualification Standard The technical FAQS has been developed as a tool to assist DOE program and field offices in the development and implementation of the TQP in their organization. For ease of transportability of qualifications between DOE elements, program and field offices are expected to use this technical FAQS without modification. PDF icon DOE-STD-1185-2007, Nuclear Explosive Safety Study Functional Area Qualification

  7. FAQS Reference Guide - Senior Technical Safety Manager | Department of

    Energy Savers [EERE]

    Energy Senior Technical Safety Manager FAQS Reference Guide - Senior Technical Safety Manager This reference guide has been developed to address the competency statements in the March 2013 edition of DOE-Standard (STD)-1175-2013, Senior Technical Safety Manager Functional Area Qualification Standard. PDF icon Senior Technical Safety Manager Qualification Standard Reference Guide, October 2013 More Documents & Publications FAQS Gap Analysis Qualification Card - Senior Technical Safety

  8. FAQS Reference Guide - Weapon Quality Assurance | Department of Energy

    Energy Savers [EERE]

    Weapon Quality Assurance FAQS Reference Guide - Weapon Quality Assurance This reference guide addresses the competency statements in the August 2008 edition of DOE-STD-1025-2008, Weapon Quality Assurance Functional Area Qualification Standard. PDF icon Weapon Quality Assurance Qualification Standard Reference Guide, August 2009 More Documents & Publications FAQS Qualification Card - Weapon Quality Assurance DOE-STD-1025-2008 FAQS Job Task Analyses - Weapons Quality Assurance

  9. FTCP Quarterly Report on Federal Technical Capability, August 18, 2015 |

    Energy Savers [EERE]

    Department of Energy 8, 2015 FTCP Quarterly Report on Federal Technical Capability, August 18, 2015 This Quarterly Report on the Federal Technical Capability Program (FTCP) contains information on the status of qualifications in the Technical Qualification Program (TQP) and technical skill gaps, on a quarterly basis. Report also displays trend data for overall TQP qualification and staffing shortfalls. PDF icon Quarterly Report on Federal Technical Capability 8-18-2015 More Documents &

  10. FTCP Quarterly Report on Federal Technical Capability, December 7, 2015 |

    Energy Savers [EERE]

    Department of Energy 7, 2015 FTCP Quarterly Report on Federal Technical Capability, December 7, 2015 This Quarterly Report on the Federal Technical Capability Program (FTCP) contains information on the status of qualifications in the Technical Qualification Program (TQP) and technical skill gaps, on a quarterly basis. Report also displays trend data for overall TQP qualification and staffing shortfalls. PDF icon Quarterly Report on Federal Technical Capability 12-7-2015

  11. FTCP Quarterly Report on Federal Technical Capability, May 29, 2015 |

    Energy Savers [EERE]

    Department of Energy 29, 2015 FTCP Quarterly Report on Federal Technical Capability, May 29, 2015 This Quarterly Report on the Federal Technical Capability Program (FTCP) contains information on the status of qualifications in the Technical Qualification Program (TQP) and technical skill gaps, on a quarterly basis. Report also displays trend data for overall TQP qualification and staffing shortfalls. PDF icon Quarterly Report on Federal Technical Capability 5-29-2015

  12. FTCP Quarterly Report on Federal Technical Capability, November 10, 2011 |

    Energy Savers [EERE]

    Department of Energy 10, 2011 FTCP Quarterly Report on Federal Technical Capability, November 10, 2011 This Quarterly Report on the Federal Technical Capability Program (FTCP) contains information on the status of qualifications in the Technical Qualification Program (TQP) and technical skill gaps, on a quarterly basis. Report also displays trend data for overall TQP qualification and staffing shortfalls. PDF icon Quarterly Report on Federal Technical Capability 11-10-2011 More Documents

  13. FTCP-09-003, Establishment of Record Keeping Requirements | Department of

    Energy Savers [EERE]

    Energy 3, Establishment of Record Keeping Requirements FTCP-09-003, Establishment of Record Keeping Requirements FTCP Issue Paper: FTCP-09-003 Approved by FTCP Chair, November 12, 2009 PDF icon FTCP-09-003 Record Keeping Requirements More Documents & Publications Technical Qualification Program Accreditation Report - Sandia Site Office Technical Qualification Program Accreditation Report - Nevada Site Office Technical Qualification Program Self-Assessment Report - Los Alamos Site Office

  14. FTCP-12-003, Supplemental Competencies | Department of Energy

    Energy Savers [EERE]

    3, Supplemental Competencies FTCP-12-003, Supplemental Competencies FTCP Issue Paper: FTCP-12-003 Approved by FTCP Chair, December 19, 2012 PDF icon FTCP-12-003 Supplemental Competencies File Supplemental-Competencies-Template More Documents & Publications Functional Area Qualification Standards Template FTCP-08-002, Technical Qualification Program Requalification FTCP-12-001, Use of "Expert Level" in Qualification Path Forward

  15. DOE-HDBK-1119-99

    Broader source: Energy.gov [DOE]

    Guide to Good Practices for the Selection, Training, and Qualification of Shift Supervisors Canceled, Effective February 2016 | Superseding DOE-STD-1061-93 (February 1993) This guide, used in conjunction with a facility-specific job analysis, provides a framework for the selection, training, qualification, and professional development of reactor facility and non-reactor nuclear facility shift supervisors. Training and qualification programs based on this guide should provide assurance that shift supervisors perform their jobs safely and competently.

  16. UNITED STATES GOVERNMENT DEPARTMENT OF ENERGY

    Office of Environmental Management (EM)

    Los Alamos Field Office Technical Qualifications and Federal Technical Capabilities Program Self-Assessment Report Geoffrey Beausoleil, Acting Manager, Los Alamos Field Office ...

  17. Microsoft Word - TQP 1 31 Final w signatures.docx

    Office of Environmental Management (EM)

    Los Alamos Site Office Technical Qualification Program Self-Assessment Report U.S. Department of Energy National Nuclear Security Administration January 10-13, 2011 This page ...

  18. DOE-STD-1138-2007 | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    7 DOE-STD-1138-2007 November 15, 2007 Industrial Hygiene Functional Area Qualification Standard The Industrial Hygiene FAQS establishes common functional area competency ...

  19. DOE-STD-1138-2000 | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    The Industrial Hygiene Functional Area Qualification Standard establishes common functional area competency requirements for Department of Energy industrial hygiene personnel who ...

  20. The Center for Climate Strategies (CCS) | Open Energy Information

    Open Energy Info (EERE)

    members have extensive qualifications in environmental science, public policy, economics, management, business, law, education, communications, and finance. Many have experience as...